ML19260C444

Provides Summary of Status of Task Action Plans A-3,A-4 & A-5 Re Westinghouse,C-E & B&W-designed Steam Generator Integrity

ML19260C444
Person / Time
Issue date:	03/23/1979
From:	Noonan V Office of Nuclear Reactor Regulation
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-03, REF-GTECI-A-04, REF-GTECI-A-05, REF-GTECI-SG, TASK-A-03, TASK-A-04, TASK-A-05, TASK-A-3, TASK-A-4, TASK-A-5, TASK-OR NUDOCS 8001030380
Download: ML19260C444 (20)

Text

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- Th g man z 31979 MEMORANDUM FOR:

D. G. Eisenhut, Deputy Dir Division of Operating ctors FROM:

V. S. Noonan, Chief. Engineering Branch Division of Operating Reactors THRU:

B. K. Grimes, Assistant Director for Engineering & P

-/

Division of Operating Reactors

SUMMARY

AND STATUS OF TAP'S A-3, A-4, AND A-5 During the past two months there have been several activities relative to establishing the status and schedules for Task Action Plans (TAPS)

A-3, A-4, and A-5 regarding Westinghouse, Combustion Engineering, and Babcock and Wilcox designed, steam generator integrity, respectively.

The attached enclosures summarize the activities involved in the TAPS, define their interrelations, report their current status and define the new schedule for action. The enclosures are also intended to provide an overview of the TAPS for the Branches and technical re-viewers involved in the programs.

1 -

,/ ' iyer.,

Vincent S. Noonan, Chief Engineering Branch Division of Operating Reactors Contacts:

R. G. LaGrange F. M. Almeter J. R. Strosnider 49-28060 cc:

See next page 8 0010 3$

1700 322

MAD 2 31979 D. G. Eisenhut cc w/ encl:

V. Stello, Jr.

R. Mattson B. Grimes R. Vollmer J. P. Knight M. Aycock R. DeYoung R. Boyd W. F. Anderson P. Check G. Lainas G. Knighton Z. Rosztoczy R. Bosnak S. Pawlicki V. Noonan T. Telford C. Serpan, RES W. Russell B. D. Liaw W. Hazelton J. Muscara, RES R. LaGrange F. Almeter J. Strosnider L. Frank N. Economos, Region II 1700 323 e

ENCLOSURE I TASK ACTION PLANS A-3, A-4, AND A-5 PWP STEAM GENERATOR TUBE INTEGRITY I.

SUMMARY

OF ACTIVITIES l.ND THEIR INTERRELATIONS The TAP's regarding steam generator tube integrity consist of three main areas (1) tube integrity, (2) consequence analyses and (3) inservice inspection (ISI).

A.

TUBE INTEGRITY The tube integrity portion of the TAP's is concerned with the ability of the steam generator tubes to withstand the loadings imposed on them during the full range of normal operating and postulated accident conditions.

Two major confinnatory research programs are underway to address the subject of tube integrity.

A laboratory research program to investigate the failure mode of artificially defected steam generator tubes is underway at the Pacific Northwest Laboratory (PNL). These tubes are representative of those found in pressurized water raattor (PWR) steam generators.

The program has several primary objectives.

A selected number of burst and collapse tests are being carried out on baseline and artificially defected tubes.

Controlled defects, similar to those found in PWR steam generators, have been created and fully characterized by the use of replication and eddy current and/or other nondestructive testing methodology. Margins-of-safety for burst and collapse pressures are being developed as a function of flaw geometry, tube size, and operating conditions.

Finally, criteria for estimating margins-of-safety are to be developed for 9pplication in the evaluation of service tubes with flaw indications.

A second experimental program to investigate the susceptibility of Inconel tubing to stress corrosion cracking (SCC) is underway at Brookhaven National Laboratory.

The objective of the program is to determine the parametric relation of strain, strain rate, temperature, environment and time to stress corrosion cracking in Inconel tubing subject to various heat treatments.

The results of these programs will be used to establish tube plugging criteria for tubes degraded in service by either wall thinning, cracking, or denting.

I NUREG/CR-0277, " Steam Generator Tube Integrity Program" - Annual Progress Report January 1 - December 31, 1977, M. Vagin and others.

1700 324

2 B.

INSERVICE INSPECTION The inservice inspection portion of the TAP's is concerned with evaluating the effectiveness of eddy current testing (ECT) techniques and ISI programs. The current licensing basis does not require postulated steam generator tube failures concurrent with postulated accidents (MSLB and LOCA). Thus, inservice inspection and plugging of defective tubes must guarantee tube integrity durih; these postulated events.

Several programs are underway to evaluate the effectiveness and to improve the techniques of ECT.

EPRI, the industry and NRC are all funding ECT development or evaluation programs.

It is an extremely dynamic area of research which requires continual review. Of prime interest are the development of multitreguency ECT probes with the ability to eliminate extraneous signals and the development of mini computer ECT signal evaluation. Mini computer ECT signal interpretation will eliminate human errors in interpretation and allow ECT signals to be compared against a number of standard calibration curves developed for specific flaw types, thus increasing accuracy, and will allow real time ECT signal interpretation. The ability to perfonn real time ECT signal interpretation will be extremely significant in the event that larger inservice inspection samples are found to be necessary.

The most comprehensive and quantitative evaluation of ECT testing and ISI programs is being conducted through an NRC, D0R technical assistance program at Sandia National Laboratory.

Through this program statistical evaluations are being made of all the ECT data available.

This evaluotion includes the large (500-600 data points) data base established by ECT testing of all the tube burst and collapse specimens tested in the PNL Tube Integrity Program.

Error distributions which determine the likelihood of not detecting defective tubes or plugging undefective tubes are being established.

These results are imperative in establishing tube plugging limits and establishing and scoping effective ISI programs to minimize tube leaks and limit consequences of postulated accidents to an acceptable level.

C.

CONSEQUENCE ANALYSES The consequence analyses portion of the TAP's is concerned with the effects of steam generator tube failures on systems response and possible radiological releases during postulated accident conditions.

The objective of the consequence analyces, most simply stated, is to define the tolerable number of tube failures concurrent with postulated accident conditions.

The ISI and tube plugging require-ments must assure with reasonable confidence that the tolerable number of tube failures will not be exceeded. This will assure that the current licensing design basis is adequate.

1700 325

. The consequence analyses portion of the TAP's requires a complex systems analyses.

Several coordination and working groups meetings have been held with the technical review Branches involved in the consequence analyses. As a result of these meetings the PERT charts in Enclosure II have been developed for the consequence analyses portions of the three TAP's. The PERT charts indicate six tasks and the necessary sequence they must be perfomed in to evaluate the consequence of LOCA and MSLB concurrent with steam generator tube failures. These tasks will parametrically address four main concerns (1) containment response during MSLB inside containment, (2) radiological releases during MSLB outside contain-ment, (3) containment response during LOCA and (4) ECCS perfomance during LOCA. These analyses will include consideration of fuel failure during MSLB and Hydrogen generati_on and steam binding during LOCA.

Parametric studies will define amounts of tolerable inleakage and out-leakage during accidents.

Leakage rate data for various forms of tube failure will then be used to define the tolerable number of tube failures. This information will provide input to the ISI portion of the program to provide a statistically sound ISI program.

II. STATUS AND SCHEDULE The tube integrity and ISI portions of the TAP's are progressing on schedule. The PNL tube integrity test program is on schedule.

Results from mechanically defected tube burst and col. lapse tests are available and results from chemically defected tube tests and leak rate tests should be available by April 1979. The stress corrosion cracking program at BNL is progressing on schedule. However, due to the long time periods involved in conducting SCC experiments for production grade Inconel tubing, generic criteria developed in the TAP's may have to rely on accelerated corrosion tests and field data with confirmation from long term tests of the production grade tubing to follow.

As mentioned earlier ECT technology is rapidly developing and many new innovations will take place in this area before completion of the TAP's.

State-of-the-art commercial ECT will be used in developing criteria at the completion of the TAP's. This will be possible since the statistical analysis at Sandia is being performed parametrically and the model for developing ISI programs will easily incorporate eddy current testing characteristics once they are defined.

The statistical analysis is progressing on schedule and the criteria for selecting ISI programs will be developed by the end of this fiscal year.

The status of the consequence analyses of the TAP's is more complicated and requires specific evaluation for each PWR system design. The status of these analyses is discussed below.

7g 3g

. WESTINGHOUSE:

The computer codes for evaluating the systems response due to S.G. tube failures concurrent with MSLB and LOCA have been developed at BNL and INEL, respectively. As indicated by the A-3 PERT chart, the actual parametric stuaies for the proposed lead plants, Surry and Prairie Island, must start as soon as possible in order to meet the proposed schedule.

The MSLB parametric studies (activity 1-3 on the PERT chart) are to be conducted by the Analysis Branch, DSS; however, the LOCA parametric study (activity 2-4) requires placing a technical assistance contract at INEL in FY 79.

Reactor Safety Branch, D0R will determine the number of failed fuel pins during MSLB (activity 3d5) in house.

Plant Systems Branch, D0R is responsible for determining containment response during MSLB and LOCA (activities 3-6 and 4-5) and has indicated that $36K of technical assistance will be necessary in FY 79.

INEL is the proposed contractor.

The Environmental Evaluation Branch (EEB) can perform their task in-house if the necessary manpower is available.

The cost of going to a laboratory for technical assistance would be approximately

$30K.

The time for completion of each of the above activities and the cor-responding start and completion dates are indicated on the PERT chart.

COMBUSTION ENGINEERING:

The computer code for evaluating the systems response due to S.G. tube failures concurrent with MSLB have been developed.

The parametric studies for the proposed lead plant, Calvert Cliffs, are to be performed in-house by the Analysis Branch, DSS. The computer code for evaluating systems response due to LOCA has not been developed and a technical assistance program for $50K is necessary to develop the code ar.d to perform the necessary parametric studies.

INEL is the proposed contractor. As indicated in the CE PERT chart, this program (activity 2-4) has been scheduled to start at the beginning of FY 1980.

The remaining tasks are the same as those required in the Westinghouse TAP except the schedules have been changed as indicated on the PERT chart.

BABC0CK AND WILC0X:

Neither of the computer codes for evaluating the systems response due to MSLB or LOCA have been developed. Analysis Branch, DSS is in the process of establishing a $100K technical assistance program at BNL to develop the MSLB code. As indicated on the A-5 PERT chart, the development of the LOCA code and the parametric calculations (Task 2-4) am scheduled to begin in FY 1980.

INEL is the proposed contractor for the program which will cost approximately $50K. The remaining tasks are the same as those required in the Westinghouse TAP except the schedules have been changed as indicated on the PERT chart.

The necessary manpower estimates and schedules and the required technical assistance programs to complete the three task action plans on schedule are 1700 327

. indicated in Enclosure III.

The schedule for placing the technical assistance contracts is indicated in the PERT charts.

1700 328

ENCLOSURE II TAP A-3, A-4, AND A-5 CONSEQUENCE ANALYSES PERT CHARTS 1700 329

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ENCLOSURE III TASK ACTION PLAN RE5OURCES PLANNING AND FORECASTING CHWTS 1700 333

i I Hi lli'.lflil :l I A'.X Al.Il0N l'l AN llLS0lltCL l'LANNING ANI) 1:Olli.CAsilNG CllAlli

(.I NiltAI. INI ORMAT ION l.ead (Cognizant) Divi.sf on:

non TAP

Title:

Westinnhouse Steam Generator Tube Intecrity TAP #:

A1 Task Manager:

R. C. LaGranne b

l. cad Supervisor: D. C. Eisen1mr CognlZant Supervisor (if appl.):

Target completion date:

TfFO Total man-months (man-years):

14 1 ( 7. ) )

Total dollars: M 4 3.3 k II. HANI'0WfR RESOURCES (in technical man-months)

FY79 FY80 FY81 Div/llr.

' Reviewer Sub-task IQtr 2Qtr 3Qtr 4Qtr IQtr 20tr 3Qtr 4Qtr 1Qtr 2Qtr 30tr 40tr Tot.tl Notes 1.M 3.K

(, o DOR /EB LaGrange Overall Direction

• T 61T i

t DOR /EP Evaluate Tube Integrity (ISI, PNL program, BNL 110 chemistry program, and 2

N R.C. 1.121 Revision)

I*

DOR /EB Evaluate statistical

.a J

(

samplirg plans from SANDIA (R.C. 1.83 Revision)

DSS /HTEB Evaluate Tube Integrity 8

(Water chemistry, ISI, materials in new generatoro SRP Revisions)

TOTAL

• 111. FISCAL RFSOURCES (in thousand dollars)

DMit r Contractor Title (FIN)

IQtr 20tr 3Qtr 4Qtr IQtr 20tr 3Qtr 4Qtr IQtr 2Qtr 3Qtr 4Qtr Total DOR /EB SANDIA STATISTICAL ASSESSitENT OF 1.3 4

4 7

2*

18.3 S.G. TilBE DECRADATION (A1108);

1I 0 CllEMISTRY, CORROSIION 4

7 10 14.0 IKIR/ Eli BNI.

• Tiu se funds i ot al oca t. d

t l A'.K ACll0N l'l AN RL50tXtLE l't.ANNING ANU FORLCASilNG CllART

-~

Lead (Cognizant) Division:

D0n 1.

l.1NIHAL INIORMA110N IAl' li tie:

Westinghouse Steam Cencrator Tube Integrity TAP #:

A_3 Task lianager:

R. G. 1.aGrange lead Supervisor: D. G. Eisenhut Cognizant Supervisor (if appl.):

Target completion date:

Total man-months (man-years):

Total dollars:

11. MANI'0WER Rf SOURCES (in technical man-months)

FY79 FY80 FY81 Div/hr.

Reviewer Sub-task IQtr 2Qtr 30tr 40tr IQtr 20tr 30tr 40tr 10tr 20tr 30tr 40tr Total Notes l'O

'8 l **

i DSS /MEB Evaluate Tube Integrity (and New Steam Gen. Designn)

O.f OI Evaluate Effects of Tubi 3

i DSS /AB Failures Concurrent With Na ftSLl!

DOR /EEll Evaluate Effccts of Tube

__f

_ 2K 2,$

O U

Failures Concurrent With MSLB and LOCA I'

2.0 a

s imR/PSil Evaluate Effects of Tube Failures Concurrent With MSI.B and LOCA TOIAI

• TENTATIVE (funds not allocated) 111.

fl'. cal Itrstil!HCES (in thousand dollars)

Is e s/llr Contrac tor litle (FIN)

IQtr 2Qtr 3Qtr 4Qtr 10tr 20tr 3Qtr 4Qtr IQtr 20tr 3Qtr 40tr Total 25.0 DOR /kSil INEL*

EFFECT OF PRIMARY TO 25

~

SECONDARY 1.EAKAGE ON CORE DURING 1.0CA (funds not availabic)

).

TASK ACil0N l'LAN RESOUllCE PLANNING AND FultECASTING CllART l.

1.l HiltAl. INi uttHAll0N Lead (Cognizant) Division:

DOR TAP #:

A-3 IAl' Ti tie:

Wens..Inglionne steam Genernror Tube intentttv Task Handeler:

1. C.

f.aGranne lead Supervisor: D. C. Eisenhut CognlZant Supervisor (if appl.):

Target cinpletion date:

Total man-months (man-years):

Total dollars:

11. HANI'0Wl R RESOURCI.S (in technical man-months)

FY79 FY80 FY81 Div /llr.

Reviewer Sub-task l1Qtr 20tr 30tr 40tr IQtr 20tr lQtr 40tr IQtr 20tr 30tr' 40tr Total Notes 20 1.0 DOR /RSB Evaluate Effects of Tube Failures Concurrent With I,

MSI.B and I.0CA N

C~D cD Vw.

O' lID I 25 7 TOIAL

• 111.

Q', CAL Id. SOURCES (in thousand dollars)

• TENTATIVE (funds not allocated) his/Itr runtractor Title (FIN)

IQtr 20tr 3Qtr'4Qtr l1Qtr 20tr 3Qtr 4Qtr IQtr 20tr lgtr 4gtr Total lH Ht/l'Sil EGhG*

CONTAINMENT REPONSE TO 36 36,0 1.0CA/MSI B CONCIIRRENT WITil b3. 3 TilnE FAII.IIRES (funds not ava i l abl,c)

I

l l A?,K M.IION l'1 AN ItES0lXtCL l>LANNING ANil FUltLCASilNG CllART 1.

I,1 Ni ll Al INi ilitMA110N Lead (Cognizant) Division:

now TAP i:

A-4 I Al' i n tl e :

___r.umliin a r t nn rnetneerine '; rom Generritor Tnho intoorrty lask Manager:

1.

M. Almeter lead Supervisor: n_ G. "fscabut Cognizant Supervisor (if appl.):

Target completion date:

Total man-months (man-years):

Total dollars:

lI. - ~~MANI'0Will 111 S0ll11015 (in technical man-months)

FY79 FY80 FY81 D i v/llr.

Iteviewer _ Sub-task IQtr 2iltr 3Qtr 4Qtr 10tr 20tr -.TQ tr' 4Qtr IQtr 2Qtr 39tr 40tr Total Notes DSS /AB Evaluation of Tube Failures 08,

.7 Current witti itSt.B b

I

'Y.

l.5 ( g IXHt/I'Sil Evaluation of Effect of

~

Tulse Failure Current Witti I.OCA & MSLB m

N

( Y O

@w O

V

=a u

,Q N

359 J

7.(

10,)

I'l. 2.

lul Al 111.

1l'il.Al Ill ? nultti s (in thousand dollars)

• Funds not allocated b i s /lt r Contractor' Title (FIN)

IQtr 2Qtr 3Qtr 4Qtr IQtr 20tr 3Qtr 4Qtr IQtr 20tr 39tr 40tr Total n

DOR /En SANDIA STATISTICAL ASSESSMENT OF 1.3K 4K 4K 7K 2K 18.3K S.G. TUNE DEGRADATION Isoft/i:SI, IM.G r0NTAINMENT RESI*ONSE TO 1.0CA 18K*

18. K

/MSI.ll ro,NCURRENT WITil TUHF.

FAIL.IIRES ll f oi :.b

TASK ACTION PLAN RESOURCE PLANNING AND FORECASTING CHART 1.

GENERAL INftlRMATION Lei.d (Cognizant) Division:

DOR 1AP Iitje:

B&W Once-Through Steam Generator Tube Integrity TAP #:

A-5 Task Manager:

J. Strosnider N' d5 Lead Supervisor:

D. G. Eisenhut Cognizant Supervisor ( i f appl.):

Target completion date: M Total man-months (man-years):

' S J

l' ToQ1 dollars: S IBb.3k 8/6'o

/6. ? (t. 4 )

~

11. MANPOWl R RI SullRCES (in tecnnical man-months)

FY19 FY80 FYbl D i v/llr.

Reviewer Sub-task IQtr 2Qtr 30tr 4Qtr 1Qtr 20tr -T0tr 40tr IQtr 20tr 30tr 4Qtr Total Noti 2.2r 2.U gg DOR /EB Strosnider Overall Direction DOR /EB Evaluating Tube Integrity

.25

/O

/2f DOR /EB Evaluation of Statistical

.7f

",,g Sampling Plans DOR /RSB Evaluation of Tube Failures

'73

/. 2f Concurrent With LOCA and MSLB DOR /EEB Evaluation of Tube Failure

~25

' '2#

a Concurrent LOCA and MSLB gg DSS /MER Evaluating Tube Integrity pg g

jg 101AL - _ _ _

Ill.

fl'.I'.AL Hl:SullRCES (in thousand dollars)

• TENTATIVE (funds not allocated) s

-~

y c) Div/Br Contractor Title (FIN)

IQtr 20tr 3Qtr 4Qtr IQtr 2Qtr 3Qtr 4Qtr IQtr 20tr 30tr 4Qtr Total DOR /EB SANDIA STATISTICAL ASSESSMENT OF

/. 3N #f

1. N 7N 2F

/g.3 N (7,

u S.G. TUBE DEGRADATION (A1108 DOR /RSB INEL*

EFFECT OF PRIMARY TO SECON-

/7" /8

/f#

SOi #

OARY LEAKAGE ON CORE DURINO l.0CA (funds not available)

TASK ACTION PLAN

~

RES0lMCE PLANNING AND FORECASTING CHART l.

GI Ni l' Al. I hl~tJRMA l l tlN Lead (Cognizant) Division:

DOR I AP Ii tle-B.'.W Once-Tlirougli Steam Generator Tube Integrity TAP #:

A-5 l a ?.k flasia<ier :

1, j;t r.osn_ide.r lead. Supervisor: D. Eisenhut Corinizant Supervisor ( i f appl.):

Iartlet ctattlil ef lun d.ite:

Total siian-months (man-years):

Total dollars:

N

.&.W

-M I1.

MANPtml R HI '.ollra f '. (in technical man-months)

FY79 FY80 FY81' lii v/lt r.

Iteviewer

'.ub-task IQtr 20tr 30tr 4Qtr IQtr 20tr 30tr 40tr 1Qtr 20tr 30tr 4Qtr Total Notes DSS /MTEB Evaluating Tube Integrity,

,g g

g Water Chemistry and ISI DSS /AB F. valuation of Tube Failures Concurrent with MSI.B M

,8 g

6 9

b b

00R/I'SY B Evaluation of Tube Failures Cinienrrent with MSI.B and

~f

, ~75 M

l0CA

/. 2 f CD cp 9

$3'50 w

U

_Y_.

e Mk

$'S WI b*

lulm 1

iiI. I l'.i At til %IlllPt I '. (in thousand dollars)

• TENTATIvc ( runits suit alliscate<I)

l i v/ll r I.ont rat ten lille (FIN)

IQtr 20tr 3Qtr 40tr IQtr 20tr 3Qtr 40tr IQtr 20tr 30tr 4Qtr Total USS/All BNI.*

{MVI:1.01'ilENT OF COMPilTER CODE 33K 33K 34K 100. K

())

'Fol: l'.VAI.IIATING TURE FATLURES t :' L H :ll::RI:HT WITil LOCA & MSI,B liOR /I' Sit F.GI.Gi i.-

~tr.NT RESPONSE TO 18K K__

1.0::A/M3!.1, CONCliRRENT WITil i 181:1-: FA I l.1i:UN l

~

TOOT. NOTES 1

(1) This nt t ha not b pla and uj to prailabi ty,

manpo'

'EL. p me.s.

4entract is placed by. rch 79.

Indicated cost is 1/3 of total required funds.

1/3 for each A-3, A-4, and A-5 e

O 9

1700 340

m,,

I NCI fl';tilti I 1 A.X Al.1 I)N l'l AN HUilllillCl. I'l ANNIN(i ANI) I tiltlCASIIN(i CllAlli

[

i.I NI It At INIURMAIION Lead (Cognizant) Division:

DOR c)

TAP Titie:

CombusNon Engineering Steam Generator Tube Integrity TAP f:

A-4 u

Task Manager:

F. M. Almeter rJ./ JM Lead Supervisor: D. G. Eisenhut Cognizant Supervisor (if appl.):

Target completion date:

'}[ FO Total man-months (man-years):

l l.'2

[fh Total dollars:I 100.3 k II.

MANP0ld R It[50tlRCES (in technical man-months)

FY79 FY80 FY81 Div/Dr.

Review >r Sub-task IQtr 2Qt730tr 40tr IQtr 20tr lQtr 40tr IQtr 2Qtr 30tr 40tr Total Notes

'I M 3I 5.17 DOR /EB F. Almeter

. Task Management

_____.._i i

Evaluation Tube Integrity

.M 10

g. u

_a Evaluation Statistical

'T 1M Sampling Plan (It.G. 1.83)

DOR /RSB Evaluation of Tube Failures

• T

• f i

i n

Concurrent with I.0CA 6 MSI.B

(

)

DOR /EEB Consequence of Tube

[

18 Failures linder I.0CA & MSI.B i

00

• 1 1

DSS /MER Tube Integrity Evaluation a

a

( M DSS /MTEB Tube Integrity, Water Ib

7. 4 l 3g)

Chemistry ISI Sample Plan

$52D

{

TOTAL

=

LD i

I F= =

111. Fl5 cal. Ill hilllRCf S (in thousand dollars)

• Funds not allocated D. < /lt r Contrac tor Title (FIN)

IQtr 2Qtr 3Qtr 4_9 tr IQtr 2Qtr' 3Qtr 4Qtr IQtr 2Qtr 3Qtr 40tr Total l

DOR /En HNI.

WATER CllEMISTRY, CORROSION 4K 10K 14K DOR /RSil I N El.*

EFFECT OF PRIMARY TO lord 50K SECONDARY LEAKAGE ON CORE DilRING LOCA

_