ML17262A759

Forwards Westinghouse Reassessment of Ieb 88-002. Re-evaluation Determined That Two Addl Tubes in S/G-A & Two Addl Tubes in S/G-B Should Be Taken Out of Svc.Tubes to Be Stabilized & Plugged During 1992 Refueling Oytage

ML17262A759
Person / Time
Site:	Ginna
Issue date:	03/02/1992
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson Office of Nuclear Reactor Regulation
References
IEB-88-002, IEB-88-2, NUDOCS 9203110362
Download: ML17262A759 (26)

Text

ACCELERATED DISTRIBUTION DEMONSTIWTION SYSTEM REGULATLO INFORMATION DISTRIBUTIOIOZSTEM (RIDE)

ACCESSION NBR:9203110362 DOC.DATE: 92/03/02 NOTARIZED:

NO FACIAL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3 DOCKET ¹ 05000244

SUBJECT:

Forwards Westinghouse reassessment of IEB 88-002, Re-evaluation determined that two addi tubes in S/G-A

& two addi tubes in S/G-B should be taken out of svc.Tubes to be stabilized

& plugged during 1992 refueling oytage.

co o:

g Q

I TITLE: Bulletin Response, 88-02 Rapidly Propagating Fatigue Cracks in Steam NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244

/

RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR MURPHY,E NRR/DOEA/OGCBll NR S

8E2 REG FILE 02 G

FILE Ol EXTERNAL: NRC PDR COPIES LTTR ENCL 1

0 1

1 1

1 1

'1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD1-3 PD NRR WILLIAMSFF.

NRR/DREP/PEPB9D NRR/PMAS/ILRB12 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1

1 1

1, 1

1 1

1 1

1 1

1

~o F798'f 7da~s D

NOTE TO ALL"RIDS" RECIPIENTS:

D D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 14 ENCL 13

ROCHESTER GAS ANO ELECTRIC CORPORATION I 89 EAST AVENUE, ROCHESTER MY. 14649.0001 10Ic cT*cc ROBE R1 0, wSECRf Dh Vice Pyc suIe c; Ginna Nuc'ic sf hoduc cion March 2,.1992 TELERcOl)E ARE*COOE.~1E 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Transmittal of Westinghouse Reassessment of IEB 88-02 for R.E.

Ginna R;E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In your letter dated July

" 10,

1990,

Subject:

Westinghouse Reassessment of IEB 88-02 for R.E. Ginna, you requested that RGGE submit the Westinghouse reassessment to the NRC when it was received.

The reassessment has been completed and a copy of the non-proprietary version is attached.

The re-evaluation process has determined that two additional tubes in S/G-A and two additional tubes in S/G-B should be taken out of service.

These tubes will be stabilized and plugged during the 1992 refueling outage.

Very truly yours, Robert C. Mecr dy SCK/207 Attachment xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9203ii0362 920302 PDR

• DOCY 05000244 PDR

I

ATTACHMENT WESTINGHOUSE PROPRIETARY CLASS 3

Subject:

'88-02'eevaluation of R.E.

Ginna SG's Ref:

1)

W. J.

Johnson ltr. NS-NRC-90-3498,

"..Tube Fatigue Evaluations Update",

March 27, 1990 2)

WCAP-11802, WCAP-11803, "R.

E.

Ginna Evaluation for Tube Vibration Induced Tube Fatigue", April 1988 3)

WCAP-12409, Evaluation of the Effect of Reduced Steam Pressure and End-of-Cycle Coastdowns on Steam Generator Tube Fatigue at R.E.

Ginna", October 1989 Please convey the following evaluation to Rochester Gas

& Electric Corporation.

Reference 1 lists R.

E.

Ginna as a 'category 6'lant, requiring reevaluation of the-eddy current test data and the flow peaking interpretation of the same.

The reevaluation process has been completed, with the conclusion that two additional tubes in SG A and two additional tubes in SG B should be taken out of service.

Published in April of 1988, the Tube Fatigue Evaluation performed for R.

E.

Ginna "(reference

2) preceded the most recent eddy current interpretation of [

] a,c The AVB data for R.

E. Ginna has been reviewed to evaluate the possibility that the more recent methods would lead to different AVB placement (with different flow peaking and tube fatigue results) than were reported in the original WCAP reports.

In this review process, detailed AVB signal maps have been made for approximately 650 of the 1850 tubes originally considered, and the eddy current evaluation has been repeated for approximately 300 tubes.

• The interpretation of AVB positioning when'[

]a,c In the R.

E. Ginna SG's, this condition appears to be unrelated to columnar location.

The most significant result of this change in AVB insertion distance is an increase in flow peaking for tubes in proximity to the AVB's involved.

The revised AVB placement maps are attached as Figures 1 and 2.

Examples of the result of the updated AVB mapping technique in SG A are the relocation of the AVB's in the region between columns 9 and 15.

A large scale map of this region is shown in Figure 3.

Reevaluation of the EC data for this region resulted in the 'withdrawal'f the AVB's on both sides of column ll and the AVB shared by columns 13 and 14.

The data indicates that support can not be verified for tubes R12C11, or R13Cll.

The resulting combination of flow peaking and stress ratios for these tubes is high enough (see Tables 1

and 2) that they should be taken out of service.

Conversely,

'withdrawal',of the AVB shared by columns 13 and 14 does not modify support conditions or appreciably effect flow peaking for tubes in that region.

2808A

l I

WESTINGHOUSE PROPRIETARY CLASS 3 Examples of the result of the updated AVB mapping technique in SG B are the relocation of the AVB's in the region between columns 44 and 51.,

A large scale map of this region is sh'own in Figure 4.

Reevaluation of the EC data'for this region resulted in the 'withdrawal'f the AVB's on both sides of column 46 and the AVB shared by columns 50 and 51.

The data indicates that support can not be verified for tube R12C46; and the resulting combination of flow peaking and stress ratios for that tube is high enough (see Tables 1

and

2) that it should be taken out of service.

Additiorially, support cannot be verified for R13C89, which should also be taken out of service.

Conversely, 'withdrawal'f the AVB shared by columns 50 and 51 had no significant effect on support or flow peaking for tubes in that regions The flow peaking models used are shown pictorially in Figure 5, and flow peaking interpretation in Table 1.

The resulting stress ratio values're listed in Table 2 and the stress ratio plots in Figure 6.

These figures and tables supersede those originally supplied as a part of the 'WCAP'eports listed in reference 2.

In conclusion:

In SG A, in addition to tubes R13C5 and R13C6 previously identified; tubes R12C11 and R13Cll also require action.

In SG B, in addition to tube R11C73 previously identified; tubes R11C46,,

and R13C89 require action.

All other tubes identified as being unsupported are judged to have acceptable

.flow peaking values.

The evaluation documented herein is based on the full power operating conditions of 3,240,000 0/hr steam flow at 736 psia, used as analytical input to the referenced

'WCAP'eports.

Operation at a lower pressure or a higher power level may make these tube fatigue assessments non-conservative and is contingent on meeting the criteria identified below.

As described in reference 3, future full power operation at reduced steady state pressures, together with end-of-cycle coastdowns will produce SG U-bend conditions of higher velocity and lower damping than the values "used in the analyses of reference 2.

Analyses of these lower pressure conditions can lead to the identification of additional tubes which do not meet the stress ratio and fatigue usage criteria for acceptance.

The R.

E.

Ginna steam generators may be operated at full power steady-state pressures as low as 675 psia, together with end-of-cycle coastdowns as defined, with no additional tubes requiring actions other than the seven tubes previously identified.

However, if the steady-state pressure is reduced to 650 psia, two additional tubes in SG B; RIOC41 and RIOC67 must be taken out of service.

If the steady-state pressure is further reduced to 625 psia, tube RIOC79 must be taken out of service in SG A, and tube RIOC73 must be taken out of service in SG B, Operation at steady-state pressures lower than 625 psia has not been evaluated.

A summary of effected tubes, and 'limiting'ubes is provi'ded in Table 3.

The reduced pressure analyses are based on tube-specific fatigue usage calculations composed of three components:

l) usage accumulated during past operation, with an accounting for cycle to cycle variations in operating conditions; 2) usage associated with future operation at reduced steady-state steam pressures and;

3) the incremental usage associated with 19 future end-of-cycle coastdowns, assuming there is an "enveloping coastdown" cycle at the end of each.

See reference 3 for details of the calculational methodology 280BA

12 IO QQQ 000 OROR OOOOR 8080 00II Oa O4 Q0 0*

OR OR 00 Q.

Q4 Q4 OQ OO O0*

Q4 00 Q'

Q0 OR OR 00I 08888 QR 0

O ORI 80 Q0*

Q4 QO OO O0*

8 OR OQ OOI O*

0*

0*

$ 0280 020208 G>>" IOOI 0800 OR 0

0'$$ 8$ 8688$ $ 8 91 00 60 68 dl 85 5$

84 83 82 81 60 70 78 ll 78 7S 74 73 72 71 70 d0 88 dl e5 55 ProIoctbn 10.0 0.1 0.4 0.1 80 7.0 7.7 7.8 8.4 8.8 8.0 10.7 IO.S 10.3 0.0 0.0 0 1 10.4 10.3 10.8 10.7 10.1 10.7 11.1 11.1 109 10.4 10.3 9A 0.0 7.0 4.5 10.8 10.8 IOA 10.8 10.8 1.8 'Il.d 10.8 I2I (77a r-C I

(D 0

0 la 10 0'

8 02 8'4 0

Qe Q4 Q4 0802 0

OR Oe OR 8QR 03$

O8ORO*

00202 I QR QR Q*

QR

. (g

~ g O.*$$ $

00000000 1

0 4

~

4 I

4 I

I 0

Q QI 0*

OR OO O4 Q4 Q4 Qe OQ g

$0 I

'I I

I I

00 Qe 1

2 8 $ 0800008804 0 008800400088 008 Qa QR QQ QO QR QR OR OR OO

~bn(~

10.7 10.1 0.0 IO.S 11.4 I2.3 2.3 11.0 11.4 11A 11A 11.5 0.8 10.3 10 00 0'R OOR0 8 00200 OQQS 0*

OR 0*

Q*

08018 SO SO*

8$

038 801 2

Qe QR

@QR Qe 08 0*

Qe Q

4 Qe

• 8 3

Oa d

Os 2

Qi 02 Q(Q

~

Q2[Q2 2

Q2 Q2+2Q2[QI Q2 QQ2 2

3 Q1 2

Q1 01Of2 O8Q1 Q oo eoooooeeee 2

~080800000000000 0000008000080000 OQ 1

1 1

1 1

0 Oobmn 3'I 30 20 28 21 25 25 24 23 22 2'I 20 10 18 ll 15 15 14 13 12 11 10 0

5 1

8 S

4 3

ProI4dbn 10.3 10.

10.0 10.2 IO.S 10.3 0.0 10.2 10.1 10.2 IOA 10.4 10.5 10.5 10.5 10.4 11.0 ll.l 12.'I 12.0 13.1 2A I2.2 12.8 12.8 13.4 Ia.e 12.9 13.0 62 el eo se se s

se 5

sa s2 51 50 40 48 41 48 4

44 4

42 40 30 38 3

38 as 34 aa 32 Pro)octbn 10.2 10.2 0.7 0.8 0 5 10.2 10.8 10.d 1.2 11.5 11.5 IIA 11.2 11.2 11.1 10.8 10.8 10.8 10.0 I'1.0 11.0 11.0 10.8 10.8 10.5 I0.3 0.8 0.5 0A 10.3 10.2 I

tort 2+

0 GI

'tt rt0'0 I.Ift tutt

~(

PrcIoctbn \\uPPorI 10.3 10.4 10.5 IOA 11.2 11.2 11.'I 11.

10.7 3.7 13.0 13.2 13A 13.1 IIOTES:

Hwnbors hdtctso vtsb4f AVEs 8 no number is dtvon. no drsa exists PrcPctbrrt are booed on coraorttne cN AVBrotct2o to corsoryno oiabo 9

Tube hspoctod end bund to be dorsod wih dotcrrnattcn at uppor TSP Tube Ptuddod br reasons other 62an suscoptbliy to%noh Anne'ype tube bttguo O

IIontesnond tube bo ptug0od br suscopt blry to 'Ilonh Anna'ypo tube 1sttduo tnnw Nohy data. hcondustre drsa

12 10 68080 6

~ 0 01.

0*

I 8 00 Qb Qt

$ $ 888 9880888 0

Qs 02 Qi Qi QZ Q2 OS 802 IO*

080 0280 0280'8$

88800 8$ 888$ 88 00 OO Os 04 O1 01 0

Qi Qi Q*

Qi Q

Ql 0

Qi Qi 028802 00 OO 02 Qs 2

Qs 020 0

0 0

~ 0 04 2

04 Qs 1

Qs 02 00 0*

0 0'

02 00 3 8 01 91 00 89 bb 87 88 05 04 83 82 81 80 79 78 77 78 7S 74 73 72 71 70 89 88 87 58 bS 84 83 Pmjoalon lSA 12.Q 2.8 11.7 11.8 11.7 11.7 10.7 10.8 11.5 11A 11.1 10 10.1 9.8 9.8 11.2 107 QA 95

'9.8 Qy 10.7 9.2 9.3 10.1 10.3 12.9 12.4 12.$ 11.5 11.8 11.1 10.3 10.3 11.2 12.1 2.1 0.7 9.9 11.0 11.3 99 10.3 D

10 000 QOOS 0*

0.

Qs 02803 01002 04 2

Qi 2

Qi 04 Os 0*

OO 80*

0201 01 01 02800 0280 02 Ol 01 02 02[02 0* 0202 0* 0*0*

0*

04 0 0*2 QO 0'80*8 Qs Os Os Qs Ol 000101019002 Qs Qs 0

Os Qi Qi Qi Qi Qi 90 Qi Qi 0

n I

4 4

08$ $ $ 0800$ 0000000 8

QQ~

0 0

QO Q42 2 QS QZQ2

$ 888808 82 81 50 SQ 8

S

$8 54 53

$2 1

50 49 48 47 48 4$

44 43 42 40 39 38 37 38 3$

34 33 32

~tont~

tOA 9.8 10.5 t0.7 tt.t tt.s 11.0 11A 11.0 lb.S 1S.S 11 7 11.8 12A 11.3 10.5 1.7 11.8 11.0 103 10.3 10.2 D

13 10 000 000 02802 01 01 01 O2 O4] 2 O2 O2PI 020>>

010100 888QISI Qe eS

~

SS2 008 000 0308 Oi 01 0 Qi 0

4 Qi 2

02 0000 00400 0*80'8 0204 Os 8 80001 008 Ql 0200 0200 SSQ'*

0*

02 02 4

02 0,

026899888$

800080188018888$ 080000000 31 30 20 20 27 28 25 24 23 22 21 20 19 18 17 lb 15 14 13 12 11 10 9

8 7

8 5

4 3

2 Pmj4alon lb.2 to.

10.2 10.1 10.0 10.3 10.1 10A 10.0 10.0 10.7 lb.S 10.4 10A lb.1 10.2 10.9 lb.Q lb.0 10.1 10.8 11A 11.5 11.8 12.1 12.2 12.9 12.9 13,3 Prt4eaton lb.2 9.8 9.2 Q.2 108 10.7 10.7 10.7 10.8 10.7 lb.7 100 ttk 11.4 ttd ttd 12.3 11.2 10A 10.2 101 11.0103 Qs 94 10.3 103 10.2 Q.Q 10.1 10.1 CD Cn Ct tl 0

C coI

'llIt0'0 CD It

'C 10.7 10.0 10.5 11A 11.3 10.7 108 09 10.8 11.4 tss 138 tube tnspoaod ond bund to bo dersed otto debrrnsdcn ot uppec 75P NOTES:

Numbers tndtc¹o 'utsRSo'VEs IIno nufnbsr ls gyron, no deco elhts

~lone ero hosed on eeseettSno ot AVBr¹sttro lo corssrttno ol tube Qnd 8

Tube pbgged bc reosons aber thon cuscopttbtttty lo Nonh Anne'ube tube tettguo Notsy dree: hconausho choo Aeconunond tube bo pbggod ior suscoptbtty to 'North Anne'ypo tubo tetrguo

t 5 tQ IS.I ILS l~

II IO

%lcd-A B

7 Is.o ILe ILI IZ:L It.'L V)S I.

0 O0 r-II5 4J w.1 50 $

I

.0 sP IL'55 C50

~0 55, O

55

'C IO fg0 5Q

55 PRE)

(

'I ("'I

(."I < l fb R

HI

(

'I (

'I I'.)

(H I' i'i II'I('ll'I R

55

':) tel I'I (R~

<W~ i~R.

(~l (~i ~l

(~f gg Q

le) I' (m<

~<~) g (C5$

pt%)

('nn (~) gg (el l'

TYPE OF AVB PEAKING INSERTION FACTOR TYPE OF AVB INSERTION PEAKING FACTOR TYPE OF AVB PEAKING INSERTION FACTOR Figure 5

Flow Peaking Models Used in Analysis

Mes"'.".@souse P"op='e" a "y Cl 3

i R.

E. Ginna Plots of Stress Ratio

Steam Generator Row No Column No Type of AVB Configuration Peaking Factor Peaking Ratio 79 60 2?

11 53 12 11 13 6

5 All of the remaining 10 10 73 72 67 41 24 21 11 79 73 46 All of the remaining

-4d, -4r 4a 4b

-1w

-4w

<<5j

-4e

<4d

<8a

-1a, -4f

-1a, <<8k

-1w

-4a, -4w

-1n, <1y

<1s

-1a Table 1

Velocity Peaking Factors and Peaking Ratios R. E. Ginna U-bend Flow 10

~ >>

~

~ 6

~

~

I

~

~

I

~

I I I'

~ ~

I I ~

I

~

~ I'

~ ~

I I

~ ~ ~

I I

I

~

I

~

I I

I

~

~

I I

I I

I '

I

~ ~

~ ~

I ~

Evaluated Nominal Enveloped Accumulated Tube Stress Ratio Tubes Fatigue Usage SGB: R10C41 0.77 SGB: R10C67 0.084 Pressure 700 675 650 625 Future Steady State Coastdown 0.296 0.024 0.503 0.045 0.938 0.1 43 2.221 0.546 Total 0.404 0.632

'1.165'.831'GA:

R10C79 Q.71 0.059 700 675 650 625 0.204 0.344 0.637 1.206 0.016 0.03 0.073 0.27 0.279 0.433 0.769

-'1.535'GB:

R10C73 0.69 SGB: R10C21 0.27 SGA; R11C53 R10C60 R10C27 SGB: R11C?9 R10C72 R10C24 0.052 0.001 700 675 650 625 7QO 675 650 625 0.179 0.301 0.556 1.05 O.Q04 0.005 0.009 0.015 0,014 0.027 0.054 0.2

<0.001 (0.001 0,001 0.001 0.245 0.38 0.662

'1.302 0.005 0.006 0.011 0.017 Table 3

Tubes Effected by Operation at Low Pressure and 'Coastdown'peration 12