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Summary of 930609 Meeting W/Util in Rockville,Md Re Discussion of Pressurized Thermal Shock Issues for Plant
	ML20045E882
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	06/23/1993
From:	Shiraki C; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 9307060176
	Download: ML20045E882 (33)
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June 23,1993 Docket No. 50-295 LICENSEE:

Commonwealth Edison Company FACILITY:

Zion Nuclear Power Station, Unit 1

SUBJECT:

MEETING

SUMMARY

- DISCUSSIONS OF PRESSURIZED THERMAL SHOCK ISSUES AS THEY APPLY TO ZION NUCLEAR POWER STATION, UNIT 1 On June 9, 1993 a meeting was held at NRC Headquarters in Rockville, Maryland, to discuss the pressurized thermal shock issue for Zion Nuclear Power Station, Unit 1.

A list of attendees is provided in Enclosure 1.

The handout used by the licensee in its presentation is provided in Enclosure 2.

The licensee gave a brief summary of its initial proposal for determining the unirradiated reference temperature (RT,) and the increase in reference temperature (ART,) resulting from neutron irradiation.

In the initial proposal, the unirradiated RT"uSed.was determined from Charpy test data with high stress relief times excl However, no mechanistic basis was given for this exclusion. The ART, resulting from neutron irradiation was determinedfromsurveillanceNatafromZionandotherBabcockandWilcox(B&W) fabricated and designed reactor vessels.

Although all the surveillance data were from weld metal fabricated using the same heat of weld wire used to fabricate the limiting Zion beltline welds, the data indicated that the rate ai w ittlement was greater in Zion than in the other B&W fabricated and designed reactor vessels.

Hence, including the data from the other B&W iabritated and designed reactor vessels would be nonconservative for Zion.

The licensee's new proposal would use only Zion surveillance data to determine the ART, resulting from neutron irradiation.

The licensee also proposed an alternate method to the ASME Code for determining the unirradiated reference temperature (RT,33).

This proposal was to use fracture toughness data from unirradiated compact test specimens to determine the unirradiated RT,.

The staff felt this methodology had merit, and encouraged the licensee to pursue it to completion.

The staff also indicated that the licensee should consider the effect of test specimen constraint adjustments and strain rate effects.

The data should be compared to the ASME Code plane strain fracture toughness (Kg) and crack arrest fracture toughness (K ) curves.

The staff also recommended that test data y

from other reactor pressure vessel (RPV) materials be compared to the Zion data to justify the alteraate method.

The licensee committed to a submittal in September 1993.

This supports the staff's target date for resolution of this issue for Zion before the end of December 1993.

The licensee stated they might have some difficulty obtaining sufficient test specimens because there are only limited specimens available 0k

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The staff said that if this became a problem, it might be able to assist in obtaining additional specimen material. The licensee stated that the static test data would be included in the September 1993 submittal, but that the dynamic test data would probably follow at a later date. This was satisfactory to the staff.

The staff reiterated that the licensee must show that the alternate approach using fracture toughness data gives RT values that are as conservative as j

n3 those required by 10 CFR 50.61.

i n

p Clyde Y. Shiraki, Sr. Project Manager Project Directorate Ill-2 Division of Reactor Projects III/IV/V Office et Nuclear Reactor Regulation

Enclosures:

i 1.

Attendance List 2.

Licensee Handout cc w/ enclosure:

See next nace l

.y Zion Nuclear Power Station Unit Nos. I and 2 cc:

Michael I. Miller, Esquire Mr. D. L. Farrar Sidley and Austin Manager, Nuclear Regulatory Services One First National Plaza Commonwealth Edison Company Chicago, Illinois 60603 Executive Towers West III, Suite 500 1400 OPUS Place Dr. Cecil Lue-Hing Downers Grove, Illinois 60515 Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 t

Mayor of Zion Zion, Illinois 60099 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 10'E quirr a:rk Frive 3pringfield, ii '

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U.S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shiloh Blvd.

Zion, Illinois 60099 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60001 l

1 i

1

s 1

ENCLOSURE'1 i

LIST OF ATTENDEES Name Organization Russ Tamminga Commonwealth Edison Company, Engineering George Galanes Commonwealth Edison Company, Metallurgy Terrence Simpkin Commonwealth Edison Company, Nuclear Licensing l

Tom Spry Commonwealth Edison Company, Mechanical and Structural Engineering Marvin Lohman Commonwealth Edison Company, Site Engineering and Construction Manager Terence Schuster Commonwealth Edison Company, Licensing Operations Director Alex Panagos Commonwealth Edison Company, Nuclear Engineering Stephen Stimac Commonwealth Edison Company, Nuclear Licensing Ed Hackett NRC/NRR/ Materials and Chemical Engineering Branch Allen Hiser NRC/RES/ Materials Engineering Branch James Dyer NRC/NRR/ Project Director, Project Directorate III-2 Carolyn Fairbanks NRC/NRR/ Materials and Chemical Engineering Branch Maudette Griggs NRC/NRR/ Materials and Chemical Engineering Branch B. D. Liaw NRC/NRR/ Deputy Director, Division of Engineering Jack Strosnider NRC/NRR/ Materials and Chemical Engineering Branch Keith Wichman NRC/NRR/ Materials and Chemical Engineering Branch l

Bari) Elliot NRC/NRR/ Materials and Chemical Engineering Branch Clyde-Shiraki-NRC/NRR/ Project Directorate III-2, Zion Project Manager Ken Yoon Babcock and Wilcox, Nuclear Technologies Dave Miskiewicz Florida Power Corporation Warren Bamford Westinghouse Energy Systems Don Howell Babcock and Wilcox, Nuclear Technologies l

Ken Moore Babcock and Wilcox, Nuclear Technologies Stephen Collard Florida Power and Light, Babcock and Wilcox Owners' Group Lynn Connor Southern Technical Services Kurt Cozens NUMARC F

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ENCLOSURE 2

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COMMONWEALTH EDISON - NRC MEETING TO DISCUSS PRESSURIZED THERMAL SHOCK ISSUES JUNE 9,1993 ROCKVILLE, MARYLAND

3' AGENDA INTRODUCTION BACKGROUND ALTERNATIVE ANALYTICAL APPROACH

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I ACTION PLAN AND SCHEDULE a

SUMMARY

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BACKGROUND i

DECEMBER 1991 SUBMITTAL RG 1.99 Rev 2, Position 1 Screening limit exceeded at EOL (Zion 1 only) f i

Additional flux reductions MAY 1992 SUBMITTAL

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RG-1.99 Rev 2, Position 2 Data from B&WOG Integrated Reactor Vessel Surveillance Program Screening limits not exceeded at EOL (Zion 1 and 2) i

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'i BACKGROUND (CONT.)

DECEMBER 1992 NRC RAI ISSUED RTxn7:

Basis to exclude data >35 hours stress relief time.

Shift:

Combination of surveillance data from Westinghouse and B&W plants.

i JANUARY 1993 CECO RESPONSE TO RAI a

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s BASIS FOR MAY 1992 SUBMITTAL STRESS RELIEF TIME EFFECT:

INITIAL RT INCREASES WITH

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xor INCREASING STRESS RELIEF TIME Observed by W and B&W B&WOG data WRC Bulletin 322 MECHANISM

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Carbide coarsening (WRC Bulletin 322) 1 CONCLUSION-

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Data >35 hours stress relief excluded Maximum stress relief times:

Zion 1 (23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months )

Zion 2 (31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months )

BASIS FOR MAY 1992 SUBMITTAL (CONT.)

CREDIBILITY OF IRRADIATED SHIFTS RG 1.99 REV 2, POSITION 2 Data sets from one reactor Scatter normally less than 28 F for welds i

No guidance on integrated programs B&WOG INTEGRATED PROGRAM 14 Data sets from 5 reactors Consistently uses all data CONCLUSION:

ALL WELD WIRE HEAT

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72105 DATA UTILIZED i

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s CURRENT STATUS ISSUES ORNL data ( NUREG / CR-5914)

Combination of Westinghouse and B&W irradiated data Wide scatter and high mean initial RT of xor B&WOG and ORNL data CECO RESPONSE TO ISSUES ORNL data to be included in evaluation Chemistry factor of 198 from Westinghouse irradiated data Alternative approach developed to determine initial RTxor

u ALTERNATIVE ANALYTICAL APPROACH DETERMINATION OF INITIAL RTuor : MEMT METHOD NB-2331

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ALTERNATIVE APPROACH FOR INITIAL RTmyr DETERMINATION B&WOG DYNA.MIC FRACTURE

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TOUGHNESS TEST DATA B&WOG performed a dynamic fracture testing of WF-70 and reported the results in BAW-2100 Data tend to fall into three groups, based on NDT All three groups of WF-70 data were analyzed according to the proposed ASTM Standard for Test Practice for Fracture Toughness in the Transition Range A total of 30 dynamic K;c data points were assessed for this evaluation According to this data set initial RTNor = T is xor a more accurate method of correlating the data Mean Tsor for WF-70 welds is - 56 F.

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TRANSITION RANGE STATIC

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FRACTURE TOUGHNESS DATA There are only three unirradiated static KJc points in the high transition range from the B&WOG data base Testing is planned to gather additional data consistent with the proposed ASTM Standard t

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DRAFT 5 Rev. 3-3 93 TEST PRACTICE (METHOD) FOR FRACTURE TOUGHNESS IN THE TRANSITION RANGE THIS DOCUMENT IS NOT AN ASTM STANDARD:IT IS UNDER CONSIDERATION WITHIN COMMITTEE BUT HAS NOT RECENED ALL APPROVALS REQUIRED TO BECOME AN AS SHALL NOT BE REPRODUCED OR CIRCULATED OR QUOTED, IN WHOLE OR IN PART, OUTSIDE OF ASTM COMMITTEE ACTIVITIES EXCEPT WITH THE APPROVAL OF THE CHAIRMAN OF THE CO JURISDICTION AND THE PRESIDENT OF THE SOCIETY.

COPYRGHT ASTM, 1916 RAM STREET, PHilADELPHM, PA 19101 Al.L IUGHTS RESERVED.

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CONCLUSIONS A LARGE DATABASE OF FRACTURE TOUGHNESS EXISTS FOR WF-70 WELDS ALTERNATIVE METHOD TO DETERMINE a

INITIAL RTsor HAS BEEN DEVELOPED DYNAMIC FRACTURE TOUGHNESS DATA CAN BE USED TO OBTAIN INITIAL RTxor = Tsor (Use of T is consistent with development of KIR curve) xor CURRENTLY AVAILABLE DATA IS LIMITED ADDITIONAL STATIC AND DYNAMIC l

FRACTURE TOUGHNESS TESTING WILL BE PERFORMED ABSENT ADDITIONAL DATA, A CONSERVATIVE VALUE OF INITIAL RTsor (0 F) WILL BE APPLIED

- This incorporates a margin of approximately 50 F over the best estimate of initial RTxor based on Tsor

ACTION PLAN s

REANALYZE AND SUBMIT ZION PTS a

EVALUATION ZION 1 and 2 RVSP Data Initial RT,s.or based on alternative approach COMPLETE ADDITIONAL FRACTURE a

TOUGHNESS TESTING EVALUATE ORNL IRRADIATION OF MIDLAND

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WF-70 MATERIAL AT THE FORD NUC. LEAR REACTOR COMPARE WF-70 MATERIAL IRRADIATED IN W

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AND B&W REACTORS

1 3 *4 ACTION PLAN (CONT.)

i SCHEDULE REANALYZE. AND SUBMIT 9/93

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ZION PTS EVALUATION COMPLETE ADDITIONAL l

FRACTURE TOUGHNESS TESTING UNIRRADIATED TESTING 9/93 j

IRRADIATED TESTING To Be l

Determined-MONITOR FUTURE

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WF-70 RVSP CAPSULE DATA Ongamg j

i EVALUATE ORNL

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IRRADIATION OF MIDLAND l

WF-70 MATERIAL AT THE FNR Ongoing 1

COMPARISON OF WF-70

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MATERIAL IRRADIATED IN W AND B&W REACTORS Ongoing l

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SUMMARY

TECHNICAL BASIS FOR MAY 1992 SUBMITTAL J

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WAS REVIEWED IN LIGHT OF ORNL DATA AND NRC QUESTIONS AN ALTERNATIVE TECIINICAL APPROACH FOR DETERMINING INITIAL RTm HAS BEEN DEVELOPED AVAILABLE FRACTURE TOUGIINESS DATA

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SHOW ZION DOES NOT HAVE AN IMMEDIATE PTS CONCERN ADDITIONAL TESTING IS PLANNED CECO REMAINS COMMITTED TO ONGOING

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PARTICIPATION IN B&WOG RVIP

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.Otp %

i at the Oak Ridge National Laboratory (ORNL). The staff said that if this became a problem, it might be able to assist in obtaining additional specimen material.

The licensee stated that the static test data would be included in I'

the September 1993 submittal, but that the dynamic test data would probably-follow at a later date.

This was satisfactory to the staff.

The staff reiterated that the licensee must show that the alternate approach using fracture toughness data gives RT,3 values that are as conservative as p

those required by 10 CFR 50.61.

t r

Of5 fMdSICw]Q 9

Clyde Y. Shiraki, Sr. Project Manager Project Directorate III-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation l

Enclosures:

l.

Attendance List 2.

Licensee Handout cc w/ enclosure:

See next page DISTRIBUTION

[

Docket File NRC & Local PDRs PDIll-2 r/f l

1Murley/FMiraglia JPartlow JRoe JZwolinski JDyer CShiraki CMoore OGC EJordan ACRS(10)

BClayton, RIII EHackett AHiser CFairbanks MGriggs BDLiaw JStrosnider KWichman BElliot

)

Pd [1 -

PM/PDII -2 D/PD) d /

CMoors CShiraki:rc JDyer h/C/93 g g /93 y/

93

.

ML20045E882

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