ML20032B768

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Summary of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups,Respectively,In Bethesda,Md Re Pressurized Thermal Shock to Reactor Pressure Vessels.Attendee List, Agenda & Viewgraphs Encl
ML20032B768
Person / Time
Issue date: 08/14/1981
From: Rachel Johnson, Vissing G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TASK-2.K.2.13, TASK-TM TAC-45202, TAC-46890, TAC-46893, NUDOCS 8111060283
Download: ML20032B768 (92)
v • d • e


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8 uNeTED STATES 1

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'0CT191981 Docket No. (All Operating PWRs)

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N Licensees: B&W, Westinahouse & CE Owne'rs Groups 3

SUBJECT:

SUMMARY

OF MEETINGS WIIH THE BABC0CK & WILCOX,-WE ItfB 0 AND COMBUSTION ENGINEERING OWNERS GROUPS ON JULY 28, 29 AND 30,1981.

RESPECTIVELY, CONCERNING PRESSURIZED THERMAL SHOCK TO REACTOR PRESSURE VESSELS (RPV).

Introduction The meetings were held in Bethesda, MD at the request.of th; _NRC s_taff in order to

1) present, briefly, the staff's analysis of the problem and the actions the staff intends to take and 2) to hear,from the PWR owners groups, the results of their analyses to date and their proposed actions concerning the problem. The meeting followed the published agenda,.

The attendees for each meeting are identified in Enclosure 2.

Vis'ual aids for the staff's presentation are included in Enclosure 3.

~ Visual aids for the owners groups' presentations are included in Enclosura 4 (B&W), Enclosure 5 (Westinghouse), and Enclosure 6 (CE).

~E Summary of the Staffs Presentation The staff has reviewed the owners groups responses of f>y 15 and the licensees' responses of May 22, 1981 to our letter dated April 20 1981 concerning the issues.

As a result of these reviews and the staff's independent review of the concern, the-staff has concluded that:

1. Efforts should continue to reduce the probr$111ty and severity of overcooling transients.
2. Reliance on operator action to prevent repressurization is not an acceptable long term resolution.

f r continued operation.

3. An upper limit should be established for RTNOT The staff also has concluded that, for plants where the reactor pressure vessels have reached or are approaching the threshold referenced temperature stated in 10 CFR 50... Appendix.GH C, action is needed now to begin resolving the long term problems. The plants involved include the six plants which have the highest RT V

This conclusion is based in part on the fact that any M_os.alues.

ed corrective action must allow adequate lead time for planning, review, approval an_d procurenent.

Accordingly, the staff intends to request appropriate action by the six._.

plants and the staff expects the owners group participation fit the resolution of these concerns.

OgNN DR C

7/23-30, 1981.

The NRC takes the position that there is a need now to take prompt positive action toward defining specific acti~ons designed to prevent the potentially dcmaging transients or mitigate their effects. To ensure that such action is initiated, at least with respect to the most vulnerable plants, a draft letter has t,een prepared requesting submittal of plans for resolution.

At each meeting the Owners Group representatives were given draft copies for review and coment..

Summary and Conclusion of Meetinc with B5W Odiers Group The B&W Owners" Group has continued on the program defined in ;the May 1.5, 1981, The Small Break LOCA (SBLOCA) is the, bounding transient of concern.

Plant response.

specific analyses will be provided.. -Assu=ptiens used in the analyses will be

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bas'ed on realistic assumptions.

Using realistic assumptions, preliminary analysis for Oconee l'.shows a vessel lifetime of 32 Effective Full Power Years (EFPY) for SBLOCA.

This assunes operator action within 30 minutes to control subcooling.

The staff has concerns on the acceptance criteria of the 32 EFPY, the clarity of procedures and the adequacy of the operator training.

The B&U Owners Group is not considering annealing or removing fuel assemblies.

The path tMat is being followed is realistic analyses in plant specific analyses.

The schedule for conpletion of these analyses is as fellows:

(1) Oconee 1, December 31, 1931; (2) Rancho Seco, March 1, 1982; (3) others, later in 1982.

The staff discussed Item III of the agenda which ar,pssubjects which the staff,'

wishes to see addressed in the reports. The B&W Owners Group committed to' have their Material Subcommittee neet with'the staff to appraise the staff of their progress.

This meeting will address the systns concerns also.,

Sumary and Conclusions of Meetinc with Westinchouse Owners Group The discussion was directed toward the efforts underway to provide a generic

- solution; plant specific comments did not go into detail. The Owners Group plan goes further than the scope.cf the May 15th letter.

A committee (" Utility Task Force") has been formed to deal with the issue which they agree is a problem demanding near-term acti.on.

They have an orderly generic program in place with c planned transition into plant-specific efforts.

The accident sequences were described with emphasis on the operator instructions and actions.

The Westing-house guidelines assume that operators will take action in transients so the instructions are aimed to minimize operator error.

The result has been to nininize operator actions but in a large steam line break (SLB) termination of safety injection (SI) and auxiliary feedwater (AFW) depends on operator action.

The fracture mechanics calculations of crack initiation and arrest were reviewed.

Remedial actions are being considered and were discussed.

They believe that all Westinghouse operational transients are bounded by the small SLB and, since their EPVs can get through that accident without operator action, no operator action would be needed for operational transients.

The Owners Group took the position that a request to provide plant specific analyses in 90 days would be an impediment to the generic program.

Sumarv and Conclusions of Meetino with CE Owners Group The presentation was generic and the Owners Group requested that plant specific questions be directed to the appropriate licensee. Work has been going on 1

under the direction of the Analysis and Operations Sub-Committee of the Owners Group and results to date indicate that no action is required for the most

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L 7/28-30/81.

limiting plant for the next five EFPY. CE stated that they prefer to use fracture mechanics in the analysis rather than RT data No engineering analyses have yet been performed to assay any of ESI sugge.sted (or any other) remedial measures but CE will provide solutions within the 5 EFPY margin they have established.

Currently, operators are instructed to achieve 50*F sub-cooling in a LOCA event and they may discontinue HPI under guidelines pro-vided. The statements found in some CE submittals that "no operat action" is expected in some emergencies was,valified to mean:

none beyond prescribed procedures. The most limiting evenu for CE plants is the SLB as was stated in the April URC meeting. The analyses aim at both crack initiation and arrest with the final condition of cracked with no RPV wall penetration, preserving vessel integrity, being judged acceptable. The fracture mechanics analyses follow essentially the same method as is used by ORNL and the NRC staff except that the computer program calculates the J-integral rather than the stress intensity factor.

It was agreed that a meeting will' be held in September or October,1981, to update the NRC on the technical progress in the CE program and that the Owners Group will review and comment on the draft NRC letter to licensees.

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.- D.

s-C Vissing, Pro ect ianager Operating Reactors anch #4 Division of Licensing

Enclosures:

4) ]> f I( Aw w As Stated b

Richard E. Johnson,'USI Task tianager cc w/ enclosures:

Generic Issues Branch See next page Division of Safety Technology 9

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1 MEETING

SUMMARY

DISTRIBUTION Licensee:

B&W, Westinghouse & CE Owners Groups

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Copies also sent to those p'eople on1 service (cc) list for subject plant (s).

Docket File NRC PDR L PDR-i ORBi4 Rdg TNovak JStolz Project flanagers (31).

Licensing Assistants (5)

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Meeting' Sumary File-0RB!4 j

RFraley, ACRS-10 Program Support Branch DL Branch Chiefs (4) 4 J01shinski BGrimes, DEP SSchwartz, DEP SRamos, EPD3 FPagano, EPLB l

R. E. Johnson F. Ashe W. Lanning T.11urley T. Marsh D. Eisenhut E. Throm F. Shroeder G. Lainas (2)

L. Lois B. D. Liaw R. Vollmer W. Hazelton H. Denton R. Mattson B. W. Klecker II. Vagins T. Speis J. Pellet D. L. Basdekas S. Hanauer E. J. Brown P. N. Randall L. Shao

'E. Abbott J. H. Austin R. Bernero H. Ornstein W. Bock I. Igne R. Crouse 2

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July 20,1981

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Docketi (All Operating PWR's)

MEMORANDUM FOR: Thomas Novak, Assistant Director for Operating Reactors, DL e

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1 FROM:

Guy Vissing, Project Manager Operating Reactors Branch #4, DL

SUBJECT:

FORTHCOMING MEETING WITH THE BABC0CK & WILC0X, C0f18USTION ENGINEER, AND WESTINGHOUSE NSSS OWNERS GROUPS CONCERNING THE THERMAL SH0CK TO RPV ISSUE Time & Date:

According to following schedule B&W Group Westinghouse Group CE Group July 28.T981 July 29, 1981 July 30,1981 1 :00-4:15pm 1 :00-4 :15pm 1 :00-4:15pm Location:

P ll8 P-l l8 P-ll8 Phillips Building Phillips Building Phillips Building Bethesda, MD Bethesda,-g Bethesda,f1D

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Purpose:

To discuss the Thermal Shock to Reactor Pressure Vessel Issue according to the attached agenda.

Requested i

Participants:

NRC l

T. Murley, et. al.

B&W Owners Group John Mattimoe, Chairman B&W Representatives Operating Plant Owners Group Representatives Westinghouse Ow'ners Group Robert Jurgensen, Chairman Westinghouse Re~presentatives Operating Plant Owne'rs Group Representatives Combustion Engineers Group Ken Ibrris, Vice Chairman l

CE Representatives Operating Plant Owners Group Representatives p

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Gu issing, Project Mp ager Operating Reactors Branch !4 Division of Licensing Phone (301) 492-8136 cc: See next page

7/20/81

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AGEtiDA

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Meetinas with PWR Owners' Group Representatives and Vendor Recresentatives

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Pressurized Thermal Shock I.

Introduction - NRR 15 min.

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- Purpose of Meeting

- Summary of NRC Activities

- NRC Plans 60 min.

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Owners' Group Representatives

- Summarize Current and Planned Activities

- Specific Questions

- What is each plant's current RT and what is the expected yearly change over next 10 yearkI g

- What are each licensee's instructions to operators for operation of HPI after automatic initiation?

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- What are the estimated costs and benefits for

- removing outer fuel assemblies?

- raising temperature of ECC water?

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- in-place annealing?

- other potential fixes?

III.

Detailed Technical Discussions 120 min.

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- Bounding Overcooling Transients i

- Estimated Probab.ility of Bounding Transients

- Systems Response

- Assumed Operator Response

- Systems Analytical Medel (Computer Codes Used)

- Verification of Systems Model l

- Mixing Assumptions

- Downcomer Pressure / Temperature vs. Time for Selected Transients

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(Symmetric / Asymmetric?)

- Heat Transfer Assumptions

- Treatment of Clad Effects on Relatively Small Cracks

- Material Properties Used (Temperature Dependence?)

- Initial Crack Size / Shape Assumptions

- Temperature / Stress /LEFM Algorithms

- Treatment of Upper Shelf

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t MEETING ON THERMAL SHOCK TO RPV FOR B&W PLANTS 7/28/81 ATTENDENCE LIST Name Organization Richard E. Johnson NRC (Generic Issues Branch)-

Tom Murley NRC-DST

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William A. Cross I

FLA Power Corp.

J. H. Roy B&W B. J. Short B&W '

John Mattimoe SMUD' Robert Dieterich

'SMUD-Edward D. Throm NRC/RSB Lambros Lois NRC/CPB Warren S. Hazelton NRC'/DE Guy T. Vissing NRC/DL/ ORB &

John F. Stolz NRC/DL B. W. Klecker NRC/DE T. M. Novak h.2/DL l

Don K. Croneberger GPU Harvey W. Slager CPLo Daniel F. Spond Arkansas P&L

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Larry D. Young Arkansas P&L Ted J. Myers Toledo Edison Co.

Frank Walters B&W Louis Redd B&W John Bohard B&W 1

Robert Gill Duke Power Robert Borsum B&W ww-,

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Name Organization John Pellet NRC/AE0D Earl'J. Brown NRC/AEOD E. T. Murphy Westinghouse Lynn Connor Doc-Search Associates Ed. Abbott

.ACRS/NRC Hal Ornstein NRC/AEOD Pa'ulette Tremblay NUS for NSAC/EPRI

, Philip C. Wagner NRC/DL/0}B!4 Daniel Garner NRC/DL/0RBf4

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Frank Ashe AE0D/NRC Joanne Donn McGray-Hill Tad Marsh NRC/0CM

' Frank Schroeder NRR

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Milton Vagins NRC/RES G

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o NRC Meeting of July 30, 1981

SUBJECT:

RPV THERMAL SHOCK PROBLEM IN CE PLANTS Name Orcaniz'ati'on Edward D. Throm NRC/RSB R. K. Mattu I

NUS. Corp.

D. L. Basdekas NRC/RES Lambros Lo'is NRC/CPB P. N. Randall NRC/IE T. Murley NRC/ DST ' '

R. E. Johnson NRC/ DST R. W. Klecker.

NRC/DE W. S. Hazel ton NRC'/DE'

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K. J. Morris OPPD

~4 J. K. Gasper OPPD William E. Burchill C-E Dan Peck C-E S. K. Mathavan Fla Power & Light Vernon T. Carson Fla Power & Light M. D. Patterson Baltimore Gas & Electric Co.

D. R. Howard Arkansas Power & Light David L. Schreder Arkansas Power & Light David J. Ayres C-E Fred L. Carpentino C-E T. M. Novak NRC/DL B. D. Liaw NRC/0CM Earl J. Brown NRC/AE0D F. Schroeder NRR/ DST

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Name Orcanization

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-Joe Longo C-E I

Robert A. Clark NRC/DL/0RBf3

' Monte Conner NRC/DL/0RBf3 i

Vincent Callaghan C-E Robert Jewell C-E

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1 Jake Westhoven

~ C-E Mike Keller WPPSS -Washington Public Power Supply System Jom Pfeifer C-E j

Dave Earles C-E

. Paul Bergeron Yankee A~ttg$c.

Roger Huston Consumers Power -

i Lynn Connor Doc-Search Associates Robert Borsum B&W William Bock ACRS John Garrity Maine Yankee Robert Shore MY John F. Hoffman Yankee Atomic (MY)

George M. Solan YAEC Eric C. Biemiller Yankee Atomic Elec. Co./ Maine Yankee Thomas F. Starr Jr.

Northeast Utilities. (Millstone 2)

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Name Oroanization Jan S. Teraszkiewicz PASNY IP-3 Joseph P. DeRoy PASNY Robert Borsum 1

B&W Lynn Connor Doc-Search M. B. S h el to r, VEPC0 D. W. Lippard VEPC0

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William Bock ACRS Fel~ow Wayne Lanning NRC/AEOD

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T. N. Tayl o r Public Service E&G'Co.

z J. E. McEwen Jr.

Portland-Qpge:2,1 Electric

-r Pres Rahe NuclearS{ Espy

Bruce King WestinghouEE.

Daniel M. Spayer West. Owners Group D. L. Basdekas NRC/RES R. C.

Mecredy Rochester Gas & Electric

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D. G. Maire Westinghouse E. T. Murphy Westinghouse-Bethesda W. J. Johnson Westinghouse B. S. Monty Westinghouse S. S. Ptlusamy Westinghouse J. T. Crane Westinghouse G. E. Campbell Westinghouse

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C. A. Schrock Wisconsin Public Service Corp.

R. K. Mattie NUS Corp.

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2-Name Organization R. E. Johnson NRC/ DST i

T. Murley NRC/ DST'

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S. L. Anderson

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W. S. Hazelton NRC/DE r

T. A. Meyer NTD t

i R. L. Kinsaul SCS/APC S. K. Mathavan Fla Power & Light Frank Gilman CP&L dward D. Throm NRC/RSB

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M. Kupinski Northeast Utilities D. Rawlins Westinghous,e i

F. Schroeder NRR/ DST Earl J. Brown NRC/AEOD 4

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SUMMARY

OF THE PROBLEM e

SEVERE OVERCCOLING TRAtlSIENTS CAli RODUCE HIGil TilERMAL STRESSES IN TliE VESSEL.

e CRACK INITIATION CAN OCCUR IF A FLAW EXISTS AND IF Tile FRACTURE TOUGilNESS tlAS BEEN REDUCED BY NEUTRON 1RRADIAT10N.

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e REPRE'SSURIZATION DURING Tile TRANSIENT CAN CAUSE A CRACK TO PROPAGATE TilROUGil Tile WALL.

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e SOME PWR VESSELS ARE APPROACilING llIGil RTHDT' LEVELS WilERE REDUCED FRACTURE TOUGilNESS BEGlHS TO BE OF CONCERN. '

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RRADIATED TEMPERATURE

POSSIBlFl0RRECTIVE ACTI0tLS 1

REDilCE Tile PROBABILITY 07 OVERC00 LING TRANSIENTS i

(E.G., MORE REl.IABLE CONTROL SYSTEM)

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REDUCE Tile SEVERITY OF OVERC00 LING TRANSIENTS

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(E.G., RAISE TEMPERATllRE OF ECC llATER) l 3.

REDUCE Tile LIKELIll00D OF REPRESSURIZATION (E.G., OPERATOR PROCEDURES OR CONTROL SYSTEM MODIFICATIONS) 4.

MAINTAIN 111G11FRACTURETOUGilNEySOF, VESSEL.

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(E.G., REMOVE OUTER FUEL lIs 'R$D'llCE FLijX 'AT VESSEL) 5.

REGAIN FRACTURE TOUGilNESS OF VESSEL (E.G., IN-PLACE ANNEALI!!G)' '

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7 REFERENCE TEF ~.RATURE FOR THE PWR i

VESSELS OF INlEREST, ADJUSTED FOR RADIATI0rl DAMAGE TO DATE VEh=T RTNDT*

( F) i PLANT NSSS 280 FORT CALHoUN CE CE 250 280 RosINsoN 2 H

CE 250 san ONoFRE H

CE 250 280 230 MAINE YANKEE CE CE 200 ALISADES CE 190 220 J

YANKEE Rows H

BaW 180 210 190 OCCNEE 1 B&W E8'd 160 ZION 1 E

BaW 150 180 180 ARKANSAS ANO-1 B8W B&W 150 180 INDIAN POINT 2 H

CE 150 TMI-1 B&W B&W 190 170 160 RANCHO SEco B&W B8'd 130 150 SURRY 1 H

B&W 120 140 CRYSTAL RIVER 3 3&W LcW 110

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BACKGROUND.

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MAY 15519811.ETTER REPORT ACTIONS IDENTIFIED e

B&WOWNERSPLANTSPECIFICPROGRAM(ONGO[NG) e c-SCOPE ASSUMPTIONS EXPECTATIONS

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SCHEDULE I

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BACKGROUND e

ITEM ll.K.2.13 0F NUREG-0737, SBLOCA

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GENERIC, CONSERVATIVE ANALYSIS - BAW-1648

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e CO.NCLUDED:

LEAD B8W PLANT (RANCHO SECI) OK INTO 1983 c=

e NRC REQUESTS OF MARCH 31, 1981, AND APRIL 29, 1981, TO. ASSESS OVERC00 LING /REPRESSURIZATION e

MAY 15, 1981 LETTER REPORT CONCLUDED IHE PREVIOUS ANALYSIS WAS BOUNDING e

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MAY15,"1981," LETTER" REP 05 ACTIONS IDENTIFIED

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COMPLETED 1.

ICS/NN.I AND EPd SYSTEMS UPGRADES 1

2.

REVISED SBLOCA OPERATING GUIDELINES ISSUED 3

RECOMMENDATIONTOMAINTAINENSIThMPERATURE N-HIGHER IHAN TECHNICAL SPECIFICATION MINIMUM 4'.

ATOG CONSIDERATION OF PROBLEM 5.

0WNERS GROUP DOCUMENT ON R.V. MATERIALS (3AW-1511P)

B.

CURRENTLY UNDERWAY 1.

DWNERSGROUPPJ.V'.MATERIALSPROGRAM

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SURVEILLANCE PROGRAMS (APPEND g H OF 10CFT50)

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C.

IMMEDIATE FUTURE 1.

PLANT SPECIFIC EVALUATIONS 2.

2-D VESSEL HEAT CONDUCTION EVALUATIONS

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3.

NON-LOCA EVENTS EVALUATION D.

LONG,IERM 1.

CONSIDER IHERMAL MIXING IEST

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CONSIDERENHANCEDINSERVIbEINSPEC1 ION

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EVALUATEIN-PLACER.Y.THERMALANNEALING 4 '.

INVESTIGATE iMPROVhDDOSIMETRYANDFLUENCECAlbul e

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SBLOCA ANALYSIS.

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M'IxiNG

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FRAbTUREF.EbHANIbS

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OVERC00 LING /REPRESSURIZATION A'.

SELECTION OF IRA!!SIENT B.

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MORE REALISTIC HP! FLOW (PREVIOUS ANALYSIS ASSUMED BOUNDING FLOW)

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EXPANDED MIXING ANALYSIS (PREVIOUS ANALYSIS WAS BASED ON L'IMITED EVALUATION)

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ASME CODE LINEAR ELASTIC FRACTURE MECHANICS ANALYSIS WITH CREDIT FOR WARM PRESTRESSIffG@HERE APPLICABLE.-

(PREVIOUSLY NO CREDIT TAKEN FOR WARM FRESTRESSING) 6.*

2-DIMENSIONAL HEAT CONDUCTION IN VESSEL (PREVIOUSLY ASSUMED l-D HEAT CONDITION) 7.'

PLANT-SPECIFIC UPDATED MATERIAL CHEMISTRY AND FLUENCES (PREVIOUSLY USED BOUNDING VALUES) e

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OTHER ASSUMPTIONS ARE SIMILAR TO PREVIOUS ANALYS.S BUT BEING EVALUATED (E.G. OPERATOR ACTION) l

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NUCLEAR ENEHGY SYSTEMS

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< Revision No.

NUCLEAR ENERGY SYSTEMS to 1.3 p.g.

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CE. Owners Group Presentation I

PRESSURIZEIfTHERMALSHOCK TRANSIENTS ANALYSES

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MATERIAL PROPERTIES

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4

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