ML17341A593

Forwards Corrected Page 1 to Attachment to Util 811021 Ltr Responding to NRC 810821 Ltr Re Pressurized Thermal Shock to Reactor Pressure Vessels

ML17341A593
Person / Time
Site:	Turkey Point
Issue date:	10/23/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-81-465, NUDOCS 8111020285
Download: ML17341A593 (17)

Text

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UHR IG R ~ E'~ Flor>>i de>> Power L L.igh,t C'o.

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FLORIDA POWER 8( LIGHT COMPANY October 23, 1981 L-81-465 Office of Nuclear 'Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: FPL Letter L-81-462 Dated October 21, 1981 ATTACHMENT CORRECTION By our letter referenced above, we responded to questions of your letter dated August 21, 1981 regarding Turkey Point Units 3 8 4 relating to pressurize'd thermal shock to reactor pressure vessels.

The attached corrected page replaces Attachment Page 1 of our letter referenced above.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU:DAC:cf Attachment cc: Mr. James P. O'Reilly, Region II Mr. Harold F. Reis, Esquire f$ pic 8.% 1 0 2 0 g .

PEOPLE... SERVING PEOPLE

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Pressurized Thermal Shock to Reactor Pressure Vessel's uesti on 1):

Provide the RTNDT Values of the critical welds and;plates (or forgi ngs) in, your vessel for:

(a) Initial (as built)'onditions and ocati.on (e.g. 1/4T) and 1

(b) current conditions (include fluence level') at the RPV inside carbon steel surface.

Response 1):

Ini ti al Current Materi al ~RT gQ ~RT I1j ~RT ~

(a) Intermedi.ate Inner 123P481VA1 +50 F +35F +85F Forging*

Ci rcumf erenti al (Girth): Weld** SA 1101 +3 F +190 F +193F Lower Forging* 122S180VA1 +40 F +35F +75F

• 1/4 T

• • Inner wall. The current RTNnT (1/4 T) = +168 F. Value is based on Unit 3 data .which has been sfiown to be more representative of Unit 4 than surveillance capsule removed fran Unit 4 (L-77-113, dated April

+

ll, 1977 and L-77-326, dated October 21, 1977).

Based on the slo e of prediction curves presented in proposed ASTM Standards "Pre icting Neutron Radiation Damage To Reactor Vessel Materi al."

(b) There have been 5.61 Effective Ful,l:Power Years (EFPY) of operation as of September 30, 1981 at Turkey Point Unit 4.

The total fluence on the inner wall is 1.1 X 10 9 n/cm2 and 6.6 X 1018 n/cm2 at 1/4 T.

(jues~tion 2:

At what rate is 'RTNDT increasing for these welds and plate material?

Res onse 2 :

RTNDT is increasing at the rate of 7'F/EFPY for the next 10 years;. for the remainder of life, 5'F/EFPY. The rate of change for the forgings i's 30F for the remaining design life of the vessel. These are based on the slo e of prediction curves presented in proposed ASTM Standards ".Predicti.ng eutron Radiation Damage To Reactor Vessel Material."

uestion 5:

Provide a listing, of operator actions which are required for your plant to prevent pressurized thermal shock and to ensure vessel integrity. Include a

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LEHIGH UNIVERSITY

)nsthu(e of Frac)use anC Solid Mechanics PacLard Lab. B}d8. N)9 BETHLEHEM, PEA.'CSYLVANIA,l8015 Telex Yo. Lehigh Univ. UD 7)0-670-)066 g ['(') fj):.

, w G. C. Sih Di:ecto.'ctober l(~.

198'ttorney Yiartin H. Hodder 1131 N.E. 86th Street Niami, Florida 33138 RE: Turkey Point Nuclear Power Plant Unit No.': Reactor Vessel Lmbrittlement and Surveillance Program

Dear Attorney Hodder:

In response to your letter da.ed August 29, 1985 and the abnve referenced subject matter, I have read the package of documents on th<< RPV e::;t>.-i:tlement program at Turkey Point Unit No. 4. A number of supporting argu>>ants with ref-erence to the calculation of bRTNDT ale questionable If not invalid from the scientific view point. In what follows, the SMRI report and the FPL setter shall be referred to as $ 1]* and t2j**, respectively.

Prediction t'1 (1} Sn%I Based on the RPV material surveillance methodology, SM-.:! fl: estimated the shift in RTN>- for Turkey Point Unit No. 4. The results per;a'.):i:.'o wall ND) loca.ion 1/4T based on the data of Capsule T -in terms of L'FPY a. e sum= -ized graprically on the sheet attached to this letter. The shift in R;,,. ': found tc be*a -.oximately 324'F at 8 EFPY. This is beyond the NRC screef.',:" ialue of 300eF.

E. B. Norris, "Reactor Vessel Material Surveillance Prooram fo y Point Unit Nc. 4: Aralysis of "apsule T", Southwest Research Institute ;ical Re-port Nc. 02-4221, June 1976.

+*

Le ter, Ul io, FPL, to Eie,".l'ut, "Re: Turkey P .in. Unit <, Docs.~ :.s. 50-251, P:S to Reactor Pressure Vessels", January 21, 1982.

'2-(2) FPL Res onse 2 Mith reference to the material in Docket No. 50-:'51 on P1S of RPV as stated in [23, a lower aRTNDT value of 211'F was obtained for Unit No. 4. This result,'.however, was obtained by application of the survei'.lance data taken from Turkey Point Unit No. 3. The, justification was that the n~t".llurgica1 Properties of the beltline welds of the Turkey .Points Units No. 3 ard t'o. 4 are the same and that data on Unit No. 4 are not sufficient.

,(3) Comments The rate at which the beltline weld material deteriorates and/or em-brittles depends on the eomMned effects of irradiation and pressurized thermal shock. 'It is plant-specific in the sense that the influence differs inherently from one unit to another. In other words, the metallurgical properties alone

.. cannot determine the damage behavior of the welds. The ZocAno k'~.<one plays <

major role. Unless the rates of irradiation, fluctuations in thermal gradients and time variation in pressure are exactly the same for both Units No. 3 and No. 4, one is not justified to assume that data collected in Unit No. 3 could be applied to predict the behavior of Unit No. 4. Hence, conclusions drawn on tRTNDT for Unit No. 4 based on the da.a of Unit No. 3 cannot be considered valid.

I will not delve into the other details concerning the actual calculation of aRTNDT as they are beyond the scope o our imnediate concern.

Very sincerely vours,

'George C. Sih Professor of tiechanics GCS:bd *'='.

Enclosure

Oata Reproduced. from Table on Page 3 at Mall Los<<tion 1/4T, Report by E. B. Norris, "Reactor Vessel Naterial ."urveillance Program for Turkey Point Unit No. 4: Analysis u< Capsule T",

Southwest Research institute Technical Report Nn. 02-4221, June 1976, 500 400

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tg 350 324'F 300 NPC Screening Criterion I

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I 250 I I

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t 8 10 15 . 20 E ect'.ve Full Po~er Year (EFPY)

r oc Dr. Geo. oe C. M. Sih Professor of Mechanics and Director of the Institute o Fracture and Solid Mecharics

~

Dr.. Si' . vrrently Professor of Mechanics and Director of the Institute of Fractur- a';"'olid Mechanics at Lehigh University, Bethlehem, Pennsylvania.

h{ lds the appoir.ment'of Adjunct Professor at The Hahnemann Medical Col-lege and H-.,spital of Philadelphia since 1972. He received his B.S. at the Uni-versity of Por'land; Oregon, 1953; .his M.S. at New York University, 1957; and ph.D. at Lehigh University, 1960; all of thee degrees in Mechanical Engineering.

Dr. Sih has engaoed in research in the in.eraction of mechanical deforma.ion and heat flow (1960) supported by the Koppers Foundation, in Fracture Mechanics (1950 and 1961) for the Boeing Company Transport Division and (1962 to 1965) for the -National Science Foundation, and as a member of the Technical Staff, Bell Te'.ephone Laboratory (Surfer 1961). He has been engaoed as Principal Investigator in more than fifty projects at Lehigh University sponsored by the Office of Naval Research, Naval Research Laboratorv, the National Aeronautics and Space Adminis-tration, the Air Force, the Arry, etc.,'ll of which are concerned with opti-mizing the use of high performance material with design, a discipline that has r

beer freq~e:tl.> referred to as "Fracture Mechanics". 'Much of his work has been concerned with es:imating the remaining life of material and structural components dar aged by yielding ar.".or fracture. He specializes in developing co:@uter soft-ware for predicting th~ mecI arical behavior of structures and the stability of objects moving through fluid media. his more recent activities are concerned'ith the influence of moisture and te >perature ln co;.-,osite ma ellals laser glazing tech;iques a~d no."-destru tive testing methods involving higt'-voltage electrophotography.

.0 Fror.: 1953 to 1957, Dr. Sih was e-. ioyed by

~

Pa"io Corporation O'. America as a project and re:eiirch engineer. He worked on the research ard developnent of input and output d..vices for the first generation "Bizmark" computer system.

Among 1..

2.

Adju~

.Autor h

the sigr<i'.'cant patents he obtained were:

optical system for line printing.

'.:: " 'gnetic disc printing device for the 0

Xerox process.

In 1957 ~-." 19'. 8, Dr. Sih returned to the academic life and served at the City College of Ne~ York as Lecturer in Mechanical Engineering. He came to Lehi gh Uni vers i ty in 195B as In..tructor in Engineering Mechanics and was appointed Assistant Prc '.e's-. af er comp'c tion of his doctorate. From 1965 to 1966, Dr.. Sih held the positior of Visiting Professor in Aeronautics at the California Institu'e of Technology and participated in an Air Force research project on the dyramics of crack propagation and size effects in the fracture of plates.

Dr.:Sih assumed in 1970 the du"..es of Regio'nal Editor, International Journal of Fracture Mechanics, a~ d the responsibilities of soliciting and reviewing papers in the field of fracture Mechanics. From 1971 to 1975, he served as an Associate Editor .of the ASM: Journal of Applied Mechanics. 'He is also on the Editorial Ad-visory Board of the Journal of Engineering Fracture Mechanics. He is also Ed~tor-in-Chief of an Interrati~'l Journal of Theoretical and Applied Fracture Mechanics.

Dr. Sih is a Fe'ow of tie American Society of Mechanical Engineers and Honorary Fellow""of the Internatir>> al Congress of Fracture. He is also a foundino member of the Ir+erra',ional C:::, era+ive Fracture Institute, an organization established to promote the interc~.'e of ideas and information among active researchers in

'fracture m chanics.

i Dr.. Sih is'lso a me".; of the fol'oi irig societies:

1 ~ Society of Signa Xi

2. AS'on-..ittee E-24 on Fracture Testing of Y<a+erials

3. International Society of Engineering Science

4. American Society of Civil Engineering

5. American Society of Hechanical Engineering

6. Interriatioral Society for the Interaction of He;! anics aric'. 1'<1hematics Dr. Sih is the Editor of three book series. Seven volumes on thr <echanics of Fracture series have been or are about to be published:

Volume I - Methods of knalysis and Solutions to Cra~k Problems, 1973 Volume II - Three-Dimensiorial Crack Problems, 1974 Volume III - Plates ard Shells with Cracks, 1976 Volume IV - Elas+odynamic Crack Problems, 1976 Volume V - Stress kralysis of Notch Problems, 1976 Volume VI - Cracks in Composite Yiaterials, 1980 Volume VII - Experimenal Evaluation of Stress Corcentration and Intensity Factors, 1980 The two other series are Fati ue and Fracture:

Volume I - Fatigue and Fracture, S. Kocanda, 1978 Volume II - Fracture t'icromechanics of Polymer Na:erials, V. 5. >:i:,shenko and V. P. Tamuzh, 1980 and Enoineerinri k" lication of Fracture He Ianics:

Vol um I - Fracture %chanics Yiethodol ogv: Eve 1 ua. ion of St i.u:; ural lo:-:~:

nents Integrity, edited by G. C. Sih a-d L. Faria

,.-~c II

~

MsxeC Miode Crack Enter sior

~

by E. E. Gdouto.

-- III - Fracture Nechanics of Concrete: Material Characterization and Testing, edi ted by A. Carpinteri and A. Ingra ffea Volure IV Fracture Mechanics'f Concrete: Numeric~1 Analysis and Struc.ural Application by G. C. Sih anC Ii. DiTommaso Volume V Bonded Repair of Aircraft Structure by I b. Balt r arid R. Jor es Volume YI Crack Grouch and Material Damage iri Coi <

i < tc'. Lin:i'. Load arid Bri t tl e Frac ture by A. Ca r pinteri Dr. Sih has also served as principal organizer and editor of proceedings of several conferences:

1. International Conference on "Dyniamic Crack Prop,<;ation", (1972), Lehigh University

2. Internatiorial Corference on "Prospects of Fracture Mechaf lies", (1974';,

The Netherlands 3.. Conference on "Linear Fracture Mechanics", (1975), Lehigh University 4; Interriational Corference on "Fracture Mechanics and Technology", (1976),

Hong Kong 5.=" 14th Annual Meeting of the Society of Engir merino Science, (l977), '.e-high University 6; First USA-USSR Symposium on "Fracture of Composite Match la s', (1975'),

USSR

7. International Conference on "Fracture Mechanics in Engii .-:

"' " Applica-tions", (1979), India

8. International Coriference ori "Analytical and Experimen+a ~ fi~cture N=-

chanics", (1980), Italy

9. International Con.erence on Defects arid Fractu e", (.9;-'.:), Po'.and

10. International Conference on "Yixed Yiode Crack I'ropagation", (1980),

Greece

11. International Conference on "Absorbed Energy arid/or Specific Strall'i En-ergy Density Cri ter ion", (1980), Hungary

12. International Coriference on "Defects, Fractur~ and Fatigue", (1982),

Cariada

13. International Conference on "Fracture Yiechanics 7echnnlogy Applied to Yaterial Evaluatiori and Structure Design", (1982), Australia

14. International Conference on "Application of Fracture Hechanics to Na-terials and Structures", (1983), Germany Dr. Sih has approximately two hundred publications principally in the area of solid and fracture mechanics. He has authored and co-authored a total of three books.

Handbook of Stress Intensity Factors, 1973

2. Three Dimensional Crack Problems (with Yi. K. Kassir), 1974

3. Cracks in Composite ¹terials (v ith E. P. Chen), 1980 Dr. Sih received the 1975 Achievement Award from the Chinese Institute of Engineers in the United States and the 1984 Achievement Award from the Chinese Engineers and Scientists Association of Southern California for his accomplishments ir research and teaching in fracture and solid mechariics.

Dr. Sih has also beer active in serving as members of riatic ~

=.':~ittees.

Among ther are the National Yiaterials Advisory Board conicernina ~ .i the Dyraric Response of Y~terials Subjected to High Strair Rate koadira; Shii t'~!erials Fab-ri:ation arid Inspection; and other cow;ittees concerrinc Nu lear hf'c:ctor Compo-nf nts Cf A Cox Newspaper Friday Afternoon. October 25. 19ffb 40 Pages Make I eectcr vv alms CBllled 'embff'ittted't TUrkey Point Srn said he could not discuss KI.LEM HAMPTON whether Unit Four ls potentially Snulhwcst Rci<<iirch Industries AW+4 items 8 eeettor dangerous because of the many filrd an ad<lllin>>al riliort fn 1979 factors that contribute to safety at equaling sevr>> rf f<<c rive full pow-A metals engineer who re- a nuclear power plant. But he safd er years at Turkry Point to 10 cal-viewed a 1976 Florida Power & the information in the FP&L re- endar years. It suggested that an-Bght Co. report on two nuclear port called for further study. other brittleness test be conducted reactors at Turkey Point maintains "They should seriously re-evalu- in seven full-power years. Unit that the walls of one of the reac- ate the situation," Sih said. "Ac- Four, currently in ils eighth full tors has "..gone Into embrlttle- cording to their assessmertt, it has power year. was scheduled tor a inent" and should be promptly ln- passed beyond the limits. The pub- brittleness inspection this year.

pected. lic deserves an answer on that ba- But FPgiL requested permlssfon But an FP&L spokesman said the sis from the NRC to delay the teston conditions of the reactor walls are Brittle walls can become dan- its request, FP&L said ft wanted to within federally set safety stan- gerous during sudden changes ot begin an integrated program of 4ar'ds and do not warrant immedi- testing between Unit Three and ate inspection. an assessment the temperature. If a minor accident Unit Four, thus reducing employee Nuclear Regulatory Commission were to occur and Unit Four had exposure to radiation and avoiding agrees with, aa NRC spokesman to be cooled down quickly with possible power outages.

said. water, the walls could shatter. A

'he fssue of the reactor's em-cracked reactor would result in a meltdown, Lorion said, and NRC The NRC approved the delay and FP&L's plan to test material brittlement, or lack of ductility sdentlsts agree. from Unit Three to evaluate condi-pliability) caused by age and And a meltdown at Turkey tions in Unit Four based on several etress, was raised at a press con- Pofnt, according to a report by criteria. Among them, the NRC ference yesterday by Joette Lo- Sandia Labs for the NRC, could be said, the units must be "sufHcient-rioa, a freelance writer-researcher expected to cause immediate death ly similar to permit accurate com-who founded and serves as the to anyone within a 20-mile radius parisons" and there must be "sub-sole member of, the Miami-based of the plant and radioactive con-, stantial advantages" to personnel Center for Nuclear Responsibility, and power clients in reduced radi-

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a nuclear watchdog group.

tamination to a 70-mile radius.. ation exposure and outages.

Lorioa obtained the FP&L report Turkey Point's just north of FP&L responded that Units Homestead in deep South Dade., Three and Four are identical in de-the NRC Ia August and sent 'rom Wolverton said that Unit Four I

ft to Dr. George Sih, director of the walls have not become dangerous- sign. modifications and materiel Institute of Fracture and Solid Me- ly embrittled. He said there is l and are operated under the same chanics at Lehigh University in embrittlement of the walls, 'ome conditions. FP&l. acknowledged a Ifethfehem, Pa., for analysis. but that lt has not exdeeded feder- difference in emb..':llement be-Sih said fn a telephone intervfew al safety standards. tween the two units r>>d attributed that after reviewing the FP&L re- "We contend that the plant is it to different lev<<ls of usage.

port, he concluded that the walls sate or we wouldn't run it," Wol- The Southwest Rrscarch Indus-on the Unit Four reactor at Turkey verton said. tries Inc. tests shnwrd considera-Point reached a condition ot em- . bly lower ernbririlrr cnt levels for brfttlement in 1981. NRC spokesman Frank Ingram Unit Three than .'i "nit Four, Sih "According to the report. the arateriaf has gone fnto embrittle-rnent," Sih said. ~

aafd his agency had studied the po-tential for embrittlement at Tur-key Point and was satisfied that not expectc ':i said. Unit Thirr. li r example, was

~ ceed federal safety standaiui r.i '. after 10 full Sih. who was named a feBow of "embrlttlement would not be a power years.

the American Society of Mechani- problem for either reactor for Martin Hod:;i; i "orney for Lo-cal Engineers in 1973 for distin- some time, possibly even up to the rion's group, s:.i', i'.~t with the ap-guished work, said he pioneered end of its 40-year life span. proved delay i:.:irittlement of said the NRC currently fs re- Unit.Four's vi >>lli ~ ould not be ex-

'e the field of assessing the life span wrrd strength ot metals and has viewing FP&L's 1976 report as amined for arii".l i l4 years. Wol-

~

conducted many assessments on part ot a hearing request by Lo- verton said lir i "uldn't say how nuclear plants nationwide in the rion's group on the embrfttfemi;nt long the ext'>>."i >> is for iri re-past decade. issue. Thc report, based on a 1975 quired testing FP&L spokesman Dave Wolver- test by Southv, est Research Indus- Litigation 1!i i<>cli nr Responsibility and "we have found his assess- Four would exceed federally set began in 198'. << lien Lorior. co~-

ment was a limited assessment safety standards for brittleness be- plained to tl. NRC about Turkey with a lin:ited "amount of informa- tween its fifth and tenth "effective Point.

tion. Some of it in fact was old. It full power year," which is mea-was not a comprehensive study of sured in time at full operating the u:hole situation." power. ~