27
' , . , , ., . - . . October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission Washington, D.C. 20555 Subject: Dresden Nuclear Power Station Unit 2 Supplement to the Intergranular Stress Corrosion Cracking (IGSCC) Program (Generic Letter 88-01) Refuel Outage Examination Plan NRC_Qoch1Jiom52-237. Reference: (a) P. Piet memo to T. Murley, dated October 14, 1992. Dear Dr. Hurley: During the transmittal of the Reference (a) letter, Attachment A was inadvertently omitted. Commonwealth Edison (Ceco) apologizes for any inconvenience this omission may have caused the NRC Staff. The omitted z information is provided as an attachment to this letter. Please update your copy of the Reference (a) letter accordingly. If there are any questions, please contact me at (708) 515-7286. _ Sincerely, j/ G [ I 4 ' Peter L. Piet Nuclear Licensing Administrator Attachment | ! |- L: l' tirain2/268/ -9211030244 921014 |_ - PDR ADOCK 05000237 P . peg

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Page 1: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

', . , , .,

.

-.

.

October 27, 1992

Dr. Thomas E. HurleyOffice of Nuclear Reactor kegulationNucli.ar Regulatory CommissionWashington, D.C. 20555

Subject: Dresden Nuclear Power Station Unit 2Supplement to the Intergranular Stress Corrosion Cracking(IGSCC) Program (Generic Letter 88-01) Refuel OutageExamination PlanNRC_Qoch1Jiom52-237.

Reference: (a) P. Piet memo to T. Murley, dated October 14, 1992.

Dear Dr. Hurley:

During the transmittal of the Reference (a) letter, Attachment A wasinadvertently omitted. Commonwealth Edison (Ceco) apologizes for anyinconvenience this omission may have caused the NRC Staff. The omitted zinformation is provided as an attachment to this letter. Please update yourcopy of the Reference (a) letter accordingly.

If there are any questions, please contact me at (708) 515-7286.

_

Sincerely,

j/ G [ I4

' Peter L. PietNuclear Licensing Administrator

Attachment

|

!

|-

L:l'

tirain2/268/

-9211030244 921014|_ - PDR ADOCK 05000237

P . peg

Page 2: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

h 'T h(_hk Mbbk ['

4

Appendix C

EMS.TAl.11ED STRESSES AT yliFLAWEDWELD LOCATJ_Qlig

"U2b).e lig_,_ System pggg

REACTOR RECIRCULATIOll:

C-1 4" Bypans Piping P.1C-2 12" Risors at Nozzles ll2A, H2B, C.3

112 C , N2D, and N2EC-3 12" Risors at tiozzles N2F, N2G, C.5

N2H, N2J, and N2KC-4 22" Header Piping C.7C-5 28" Pump Suction & Discharge Piping C.9

C-6 SHUTDOWN COOLINO C.11

RESIDUAL HEAT REMOVAL:

C-7 LPCI Loop "A" C.13C-8 LPCI Loop "B" C.15

ISOLATION C0!iDENSER:

C-9 Steam Supply C.17C-10 Condensate Return C.19

C-11 CONTROL ROD DRIVE C.21

C-12 RESCTOR WATER CLEAN-UP C.23

|

XCE-53-102 C.0 NUTECHRev!sion 3 El4GNEERS

Page 3: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

4.. . .,

. 4

Table C-1

DRESDE11 Uf11T 2SUSTAIRED SIRESSES

REACTOR RECIRCULATIO!1 SYSTG4" BYPASS PIPIlLQ

" e w~i,ra k im m w66struts (q s rpt as (7) sist sa m siff ES A

W1 L D en (t)(pei) (ps0 (peQ (pe4

4 X-1/SPM-4 5-7 4 173 4 051 37 328

SPM-4b6 4.173 222 6 43

S PM-45-5 4.173 747 1e 105

SPtJ-4 5-4 4.173 1.240 16 135

SPM-4 5-3 4.173 1.520 4 85

SPM-4b2 4 173 126 0 0

SPM-4 5-23 4.173 1.253 17 72

4 X-2/SPM-4 5- 2 5 #173 3 914 56 298

4 X-3/SPM-4 5-18 4 173 862 12 34

SPM-45-26 4.173 4E2 12 38

SPl.1-4 b17 4 173 184 8 12

SPM-4 5-16 4.173 ! 70 17 14

SPM-4bl5 4.173 477 51 194

SPM-4bl4 4.173 1,2W8 $1 196

S PM-4 5- 13 4.173 126 0 0

SPM-4b24 4 173 1.060 46 175

4 X-4/SPM-45- 19 4 173 1.024 9 22

NOTES.(t) P = (IP u OD)/|4 a Op)|(i) DW. TH. and WCS (F/A) + |(SQRT[(Mx'2) + /My' *2)) 12 in th )/S]

|4iNRR3 WK,/ AltkD2) (Pg 1 of 2)

XCE-53-102 C.1 NUTEEHRevision 3 ENONEERS

Page 4: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

. .

., , .,

. .

Tcble C-1

QRESDEli UNIT 2SNETliINED STRERSIS

REACTOR RECIRCULbTIOli SYSTEli1"_ BYPASS PIE 11LQ

(Concluded)

F.im. b"~

T H. M M4 |1) totVA L D NO 4e9 Wef) r!)

4 X-1/SPM-4 5-7 8 589 16 950 0 $1

SPM-45 6 4 444 16 950 0 26

SPM-4 5- 5 5041 16.950 0 30

S PM-45-4 5 572 to er* 0 33

SPM-4 5-3 5.741 16 950 0 34

SPM-4 5-2 4199 16.950 0 25

SPM-4 5-23 5 515 16 910 0 33

4 x-2/SPM-45-25 8 445 16 950 0 50

4 X-3/S PM-4 5-18 5064 16 950 0 30

SPM-4 5-26 5 084 16 950 0 30

SPM 45-17 4.378 16 950 0 26

S PM-4 5-16 4.404 19.950 0 26

SPM-4 5-15 4 P95 16 950 0 29

SPM-4 5-14 5 716 16950 0 34

S PM-4 5-13 4 299 16 950 0 25

SPM-4 5-24 5454 16 950 0 32

4 x-4/SPM-4 5-19 5 227 16 950 0 31

i

NOTES(1) Srn = Allowat# e Dwaign Stress intensity for Type 3041

Stainless Steel at Design Temperature of575 degrees F frorr. ASME Section Hi

| 2) SR = (P + DW e TH + WOS)i SmAppend.1 Table 1-1.2

gi

|tesNRR3 WK1/ ALL)(D2l (Pg 2 of 7'

XCE-53-102 c.2 t4UTEEH. Revision 3 ENGt4EEP-:

|

Page 5: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

. - . _ ._

'' . ,*,, .. .

Table C-2

DRE5 PIN UllIT 2SUSTAI]1ED STRESSIf4

REACTOR RECIFCULATION SlgIEM1?" RISERS AT NOZZLES ff2L_N28, 112 C , 112 D , AllD 112.E

# w ssais s in his6f 8W Es (PJ Bf 6W AS (?) sitt $4 (7) stig as (tj

wuno o ne.4 _ v.4 w.o 9o

t42A J Dir9 171 369 924

PD4/201 1 6 600 390 422 1,455

PO4/L' S 400 1/2 1.946 4.137

N2D 3 999 83 4 30 3 601

PD6/201-1 6 600 188 966 6.424

PD6/L 1 6.800 462 1.372 2 821

N2C 3 999 114 336 4.233

PDC /201 1 6 800 212 794 7.201

PD6/L 1 6 400 600 1.664 3 887

N2D 3999 174 391 16.293

PD 1/201-1 6 800 396 897 27,781

N2E 3.999 IOS $34 ,906'

PD 1972r t .1 6 000 239 1.226 19 946

PD19/L2 6 600 419 2 008 2.748

f40TES(1) P e (IP a 00)/[4 m (ip))(2) DW, TH. and WOE = F/Al + |(LCRT[An* *2) , (My'?)| 12 m /ft )/S|

(12ildRAA3 WK1/ ALLKD2) (Pg 1 of 2)

XCE-53-102 C.3 NU T ED.Revision 3 EtKM4EERS

.

Page 6: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

._ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - _ . __ - __

'

. , . s'... .

.. n . .

ble C-2"

DA J1EN UNIT 2.: WFIJMED STRESSESi REACTOR PEUIRCULATION SljiT11'

@g f 12" RlSEBSJ,T NOZZLES N2A, _N2B, U 2C, N2D, AND U2E,

?- (Concludad)

e. . % 7T H.WOH (1) | SH

wt1D wo. We en to

. Nis. 5.453 16.950 0 32*

7, PO4/201 1 4.467 16.950 0 50

PO4/L1 12.064 16,950 $ 71r

[kN2B 8.013 16.950 7

YPD5/201 1 13.397 16 950 1

POS/L1 10 4/ ' to 950 -

N2C 947 , 16.950 0 51,

PO6/201 14.ty * t 16.350 0 v3

PD6/L'. 1 ' 7ef 16.950 0 69

N2D 19F 16 950 1.17

PD1/201-1 34.873 16.950 2 Oc

N2E 13.544 16 950 0 to

PO10/20 t-1 24.211 16.950 1 43|

*

PO19/L2 10.974 i 16 950 t{NOTES-(1) Sm = Niowatde Design Strese intensity for Type 304

Stamiese Sit * at Design Temperature of>

57: oogrees F tw., ASME Section IllAppendia Table 1-12.

(2) SR = (P + DW + TH + WOS) / Sm-

(12tNRRA3 WK1/ ALLH02) (Pg 2 of 2)

-

)

XCE-53- 2 C.4 -

840TEEHRevision 4 ENEANEERS

Page 7: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

' *.

,, ,,

. .

Table C-3

DRESDEN UNIT 2SUSTAINED STRESSES

EEACTOR RECIRCULATION SYSTEMJ.2" RISERS AT NOZZLES N2F. N2G._li2H. N2J. ANpjgE

'~

Nd Mine DW~

1H YA)6

sTHESs e sitn'as pl sits as m sTHras (2)vd t t's+0. (t)(re0 (p*4 (Pe9 1780

fl2F 3,999 737 599 1,790

PD7/201 1 5.800 1.681 1,375 3 424

P07/L4 5800 281 2.371 2.481

N2O 3 999 281 608 2.444

POS/201 -1 5.800 592 1.164 3 481

PD8/L4 6 800 669 1.912 7.794

td2H 3.099 87 283 3 306

PO9/201-1 5 800 198 651 6.233

PO9/L4 5,000 323 1.548 3.202

N2) 3 999 154 '82 : 190

PD2/201-1 5 800 350 1,1C 1 2 Cri3

PD2/L5 5800 780 1,112 2 580

N2K 3 999 65 294 704

PC1'?01-1 5 800 147 674 1.467

Pol'L5 5 800 682 1.712 4.285

NOTES.(1) P = (IP x OOVl4 m (tp))(2) OW, TH. and WOS = (F/A) + [(SQRT|(Mx'2) + (My* 't!] x 12 n /tt )/S}

(121NRRB3 WKil ALLND2) (Pg 1 of 2)

l

{i

|

!

.

XCE-53-102 C.5 NUlEEHRevision 3 ENONEERS

~_ _ _ . _ _ __ ..

Page 8: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

.. - ~

'-;c , s ! .,,

+

Table C-3

DRESCEN UNIT 2SUSTAl1[ED STRESSES

BFhMOR RECIRCULATION SYSTEM12" RISERS AT !!OZZLES N2F, N2G<_lQH, N2J. Al{p_JGE

( Conc? "-led)

P.OW. smTH. Wort (1) SH

MADen (pen (pea mN2F 7,124 16,950 0 42PD 7,201-1 12.275 13.950 0 72

PD7/L4 10 933 16,950 0 64 '

N2G 7.212 16.950 0 43

PD8/201-1 11.019 16 950 0 65,

PD9/L4 16.174 16.950 0 95

N2H 7.675 16,950 0 45

PD9/221-1 12,881 16.950 0)6PO9/t 4 10.872 16.950 0 64

N2J L.426 16.950 0 34

g PD2!201-1 0.309 16.95') 0 55

PDal' 6 10,252 16,9A C.30,

N2K 5.062 '.6 950 0 30

PD3/201-1 8.087 16.950 0 48

PD3/L5 12.379 16 950 0 73

NOTES(1) Sm - Allowable D sign Strea intenoty los Type 304

Staintees Steel at Design Tempeiatuta of575 oogrees F trom ASME Section tilApren6u Table I-12

(2) SR e (P + JW , TH , WDS) / Set

(12iNAR83 WK1/ ALL)(D2) (Pg. 2 of 2)

XCE-53-102 C.6 NUTKHRevision 3 F_NGHEERS

Page 9: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

-.

/ ' *e*,.. .

c

Table C-4

DBESDEN UNIT 2SDSTAINED STRESSES

REACTOR RECIRCULATION SYSTEM2] " HEADER PIPING

~6i $Gl#( thy TH W3S(HL SS U7 STFESS ft) STFE&t (7) STFESS t>)

MLD NO. (1)(pag (pel) (pe4 (pe!)

1.1/L2 A,290 592 597 3754L2/D17A (290 117 $As 2 659

L2/202-6A 6.290 322 547 3.503

202-6A/L3 6.290 150 60'/ 3 252

202-60/L3 6.290 713 780 2.750

LS-06A 6290 140 528 1.300

L5/L4 6190 742 674 1.401

L 4/202-68 6.290 471 744 2.gNorES.(1) P = (IP x 00)/14 x (rp))(2) OW, TH. and WOS e (F/A) + [(SQRT|iMx "2) + (My'2)[ x 12 in a VL]

(22!NAR3 WK11 ALL)Q2) (Pg 1 of 2)

|

|

||

'

XCE-53-10? Cs7 NUTE[HRevision 3 ENGNEERS

Page 10: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

';, s*-. .

9

Table C-4

DRESDEN UNIT 2SUSTAIllED STRESSES

REACTOR RECIRC*JLATIOli SYSTEM22" HEADER __ PIPING

(Concluded)

' P.DW. $mTH.WOH (t) sq

Wt10 #40 (pei) (p.6, ga

L1/L2 11,234 16.950 0 66

L2/D l7 A 9.595 16.950 0 57

L2/202-6A 10.702 16.950 0 63

202-6A/L3 10.489 16 950 0 62

202-6BIL3 10.540 16 950 0 62

L5-D6A 8.257 16.W50 0 49

L5/L4 0,507 16. bio * 0 56

L4/202-68 9 621 16 950 0 57

NOTES:.'*) Gm = Allowable Desig7 Strese intenuty for Type 304

Stainless Siegt at Des gn Tempe.ature of$75 degrees 48 from ASME Osetion thAppe4x Tabi a l-1.2-

(2) SR . (P + DW + TH + WOS) / im

(22tNRR3 WK1/ ALL)(D2) 93 2 of 2p

.

l

.

XCE-53-102 C.8 84UTE[H.

Revision 3 ENGHEERS

Page 11: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

_ ---

P,..

Table C-5

DRESDEN UNIT 2SUSTAINED STRESSES

REACTOR RECIRCULATION SYSTEM28" PUMP SUCTION & DISCHARGE PIPING

PS h3VM OW TH WOS|

S T ESS (P) Pf 4SS (2) ST8E SS rj SifE SWCh '

wt L O NO C Hpen (pe4 (peQ (pe)_

NIA 6 439 486 230 1G1

P S t -2t201- 1 6 430 486 230 526

PS1-2 01 6439 378 212 372

PS1-2-02 6 439 336 245 1,181

PSI-2-03 6.439 3W 233 1,170

PSI-2/PS t -2 A 6.439 160 32 985

PSI-2 A/202 4A 6.439 501 37 745

202-4 A/ PSI A 6.439 ;,59 92 664

PS14/202-1 A 6 439 152 11 180

POlB/202-1 A 6.43G 382 129 362

; '2-5A/PO1 A 6.439 219 205 652

PO1A-015 6439 651 e43 893

PO1A/L2 6.439 597 153 891

L2-017 6439 , 100 ' 151 1,287

INIB 6439 300 ?14 136

PS2/201+1 6 439 300 214 133

PS2-C1 6.439 406 158 437

PS1/PS2 TEE 6 439 416 159 330

PS2 TEE!?o2-4B 6.439 89 77 555

202-48/PS2 A 6.439 141 25 512

PS2A-02 6.439 216 77 441

PS2A-03 6.439 181 88 275

PO1C/202-1 B 6.439 411 100 316

202-58/POIC 6 43; 310 127 119

202-58/PO ID 6 439 245 165 321

PO10-011 6 433 463 181 = 54

PO104312 6439 537 131 380

PO10/L5 2 430 494 114 127

L5-06 6.439 96 '20 290

NOTES.(1) P = CP x 001/14 x (1p11(2) OW TH and WOS = (F/A) + |{SORTi(Mx"2) + (My"2)] x 12 initt )/SJ

f(28iNAR3 WK11 ALL)(O2' (Pg 1 of 2)

i

|,

XCE-53-102 C.9 ggyggRevision 3 ENIANEERS

.

Page 12: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

;. .r* .s. .

Table C-5

DRESDEli UNIT 2SUSTAIllED STRESSES

REACTOR RECIRCULATION SYSTEM?_B." PUMP SUCTION & DISCHARGE PIPI!1Q

(Concluded)

P.DWT fwn

T HeWOf1 (1) SHML D NO (ps4 (pe0 CD

NIA 7.250 16 950 0 43

PS t-2/201- 1 7,681 16 950 0 45

PS t-2-01 7.431 16.950 0 44

PSt-2-02 8 201 16.950 0 48

PS t -2-03 4.195 16.950 0 48

PS t-2/ PSI-2 A 7 616 to 950 0 45

PSt 2A/202-4 7.722 16.950 0 46

202-4 A/PSt A 7,454 16 #53 0 44

Pe t A!202-1 A 6.788 16.950 0 40

"U18/202 .A 7.312 16 950 0 43

2C2 5A/ POI A 7,515 16.950 0 44

PO1A-015 8.125 16 950 0 48

PO1 A/L2 d.079 16 950 0 48

L2-017 7.986 16.950 0 47

N1B 7.088 16.950 0 42

PS2/201-1 7.0E6 16 950 0 42

PS2-01 7,469 16.950 0 44

PS1/PS2 TEE 7.393 16 950 0 44

|PS2 TEE /702- 7.160 to 950 0 42

202-48/PS2 A 7.117 16 950 0 42

PS2A-02 7,173 16.950 0 42

PS2A-03 6.982 to 950 0 41

PO1C/202-18 7.271 16 950 0 43

202-58/F 6 995 16.950 0 41

202-5BJPC - 7.169 16 950 0 42

P010-011 7.536 16 950 0 44

PO10!O12 7.486 16.950 0 44

PC 10!L5 7.174 16.950 0 42

L5-06 6 945 16.950 0 41

NOTES.(1) Sm Allowable Ossign Suvas intensity for Type 304

Stamiens Steel at Design Temperature of575 degrees F aom ASME Secte niAppendix Table 1-1.2.

(2) SR = (P + OW + TH + W"JS) / Sm

(;8tN RR3.W K11. ALL)(O2) (Pg 2 ol21

XCE-53-102 C.10 '

NUTE[HRevision 3 ENGNEERS

Page 13: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

- _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ -

'

|. e' ,

* *

h

Table C-6

'.RESDE!1 UllIT 2

SUSTAIJiEQ STRESSESS11UToowt1 cooLIf1G SYSTEM

est asure. DW 1H was6f15 as (19 situ ss (:r) stFtss (2) sistss(21

WEID No (1 Mesa (per) gen (p.a

LOOP *A"

10-11 6 925 275 1.362 1.006

16-10 6 925 352 1.998 679

LOOP'B' -

1645 6 925 1,014 2.334 S37

16-9 6 925 902 2.205 589,

16-10 6925 144 f,525 413

NOTES(1) P = (IP a OOM4 x (tp)1(2) OW, TH and WOS * (F/A) + [(SQRT[tMa* *2) + (My* *2)} x units)/S]

Y

(02 SOC 2 WK11 ALL)(C2) (Pg 1 of 2)

-r

a

s

XCE-53-102 C.11 NUTEEHRevision 3.

EMNEERS1

- - _ _ _ _ - _ _ _ _ _ _ _ - - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _

Page 14: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

*a'*%,o

*

I

Table C-6

DRESDEN UNIT 2SUSTAINED STRESSES

FHUTDOWN COOLING SYSTEM(Concluded)

e.uw. A16.Wtm (1) $ f fM.SR IMilO

v4 LO M) (paQ (poi (2)

LOOP'A*

16-11 9 569 16 950 0 56

16-10 9.954 18 950 0 59

LOOP'D'

16-- K 6 10 809 16.950 0 64

16-9 10.620 16.950 0 63

16-10 10.011 18 950 0 51

-

NOTES-(1) Gm a Alawable Design Stress truensity for Type 304

Stamiess heel at Design iemperature of$75 degrees F from ASME Section IIIApg endia Table I-1.2,

(2) SR = (P + DW + TH + WOS)/ bm

(00 SOC 2,WK1!. ALL)(D2p (Pg 2 of 2)

XCE-53-102 C.12 NUTEEH. .

Revision 3 ENCANEERS,,

Page 15: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

*

. ' . '' 4- .

Table C-7

DRESDEli UNII_2SUSTAINED STRESSES-

RHR SYSTEM - LPCI LOOP "A"

ne ssuse ow TH wasSiiW,SS (P) $IFW SS(2) ST YSS (2) ST Ft.SS (?)

)NL'L D NQ, { y (pei) (peQ (pt) (pgi)

821|16-15 6125 314 1,154 .

16-K10 6.9'S 291 1.634 292

16-14 6 W25 614 11 565 1,9A4

16-13 6925 546 5.046 1.879

16-12 6 925 389 3.594 1.860

16-K9 P.925 85 3.942 775

16-Ka 6.925 149 1,246 236

16-K7 6925 109 5729 1.05?

16-X6 6.925 172 8.520 106

16-11A 6.025 611 4.765 2.000

16-1$ 6.925 126 1,716 2.090

16-10 6925 435 m,734 2.991

16-K5 6 925 468 4 622 3 592

NOTES(e) P (IP x 00)14 x (rp)!(2) OW. TH. and WGS = (FIA) + l(Sr ~ Ti(Ms"li + (My"2)] a 15 m1ft 1/S1

f t PCIA3 WK11. ALL)(D2) (Pg 1 of 2)_

XCE-53-102 C.12 NUTEHRevision 3 Et4GNEERS -

Page 16: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

_ - _ _ _ _ .

*

|, e,.

.

Table C-7

PRESDEN U'IT 2fiUSTAINED STRESSES

El![i_ SYSTEM LPCI 100F "A"-

(Concludeo}

P etM. 8wn

TH+M N1 (1) STIE88 fMilOv410NO (peo 9m0 (2)

16 it 13.214 16.950 0 78

16-Kto 9.143 16 950 0 54

16-14 21.092 16.950 1 24

16-13 14.396 16.950 0 85

16-12 12,772 10 950 0 75 i

16-K9 11.726 16.950 0 69

16-K4 8.555 16,950 0 50

16-K7 1d $20 16 9 % 0 87

16-F1 15.723 1&ds0 0 93

16-11A 14 392 16.950 0 85

.6-11 to854 16.950 0 64

16-10 14.000 16 950 0 &J

16-K5 15.607 16,950 0 92

NOTES,

(1) Sm a Mowable Desion Stresa Intensity for Type 304Stainless Stee6 at Design Temre'ature of575 degrees F trom ASME Swtion illAppendix Table I-12.

(2) SR = /P + DW + TH + WOS)i Sm

(LPCIA3 WK1/ A8.L)(D2),

(Pg 2 o

XCE-53-102 C.14 NUTETHEcvie4.on 4 EN EERS

Page 17: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

.

-, . - ,-.

,,

Table C-8

DRESDEN UNIT 2SJ; STAINED STRESSX.S

RHFi SYSTEM - LPCI LOO P '' B ",

f Ptsssiit (m TH wossiitss (55 stiESS m sine SS A Gilt SS CT)

WELD NO (t) (pei) (peQ (p44 (pe4

18-12 6 925 304 4.749 1.070

16-K9 6.925 274 1.691 228

16-11 6.925 599 11.075 461

16-10 6915 541 4 8c0 836

16-K8 6 92f - 378 4 011 e 119

16-K7 6.92. 86 4 087 579

16-K6 8925 151 1.233 171

16-K5 6 925 107 6712 944

16-K4 6.925 183 8.066 409

16-4 6.925 117 1,776 788

16-8 0.925 457 3.831 1.551

16-K3A 1 6 925 502 5 321 2.256

NOTES.(1) P = ('P x 00)/[4 x (tp)).(2) DW, TH. and WOS = (F/A) + [(SCRTI'Ms"2) + (My"2)i a 12 in /ft 1/5;

(LPCIB3 WK1/ .LL)(D2) (Pg 1 of 2)

XCE-53-102 C.15 NUTEEHRevision 3 ENGNEERS

=. . . _ _ _ _ _ _ -. __.

Page 18: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

_ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - . . . _ _ _ _ _ _ _ _ .

' ~

|. :. e= e

v. .

Table C-8a

DFESDEN UNIT 2SUSTAINED STRFSSES

Ellit SYSTEM - LPCI LOOP "B"

(Concluded)

e

P.Dm MTWWOH (1) STTE ES M TIO

WW1D W (p+4 M GP _s6-12 13 044 16 950 0 77

16-K9 9.118 16.950 0 54

16-11 19 061 16.950 1 12~16-10 .1,111 14.950 0 77

16-K4 12 44 16.950 0 73

16-K7 11.677 16.950 0 69

16-K8 8,540 13.950 0 60

16-K5 14 693 16 950 0 87

16-K4 15.584 16 950 0 92'

g

16-9 9 606 16 950 - 0 57*

16-4 12,765 10.950 0 75

16-K3A 15 004 16.950 0 89_NOTES.

g (1) Sm = Allowable Design Stresa Intene4ty tw Type 304kain6eas Otaet at Dewgn Ts.nperature of676 degrees F froci AsME Section 11!Append n Table 8-1.2

(2) SR = (P + f1W + TH + WOS) / San

kLPCIS) WK11 ALLXOC) (Pg. 2 of 21

)_

<

4

XCE-53-102 C.16 NHYE[HRevision 4 ENGNEERS

.

_ _ _ _ _ _ _ - _ _ _ _ _ _ __ _ _ _ - _ _ _ _ _ _ .

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_ _ .

,- <*. ...

Table C-9

DRESDEN UNIT 2SilSTAIilED STRESS 13

LS2[ATIOll CONOPJEER SYSTEM - STEAM SUPPL 1

{ thitssue: tur 1H ] wog|

,

| sW Sa (P) 81 P".5 3 (7, s1 Fit'sa (7; site as (7)WT 1 O P40 ( t)W)__ (poi (pa.) (m2,

2 1102-t4* ItCtOE DA YWF',4N58 6.857 231 7,351 014-K1 8857 178 6 851 014->J 6.857 405 5 003 014-K3 9.857 912 9192 0.4-K4 6.857 634 . 10.553 014 2 6.857 829 10.555 0'4-2 8 857 178 11.254 C

14-K5 6 867 186 11.285 014-K6 6 857 1 217 1.945 0ti-3A 68571 1.217 1.945 014-4 6.857 I 314 8,1* 8 0.

14-5 6 857 251 7.t ae 014-5A 6.857 74 5 456 014-5N 6857- 4J 5.76# 0

2- t 302-14' OUTSIDE D AYWEU NOTE (3)14-6 E857 4.322 .i.692 014-64 68U 4.322 4 #2 , 0,

14-7 6 857 3.102 3.928 014- ' '57 1.42C 1.782 0-.

14-2 a E '7 S$1 5.743 014-3 6.657 253 3.892 0e4-4 0.857 99 1 1.269 0

it4-5 0 857 835 5 041 0

f14-6 0ff.857 727 4.34314-7 6 SS7 697 S.196 0*

314-8 6.857 100 5 696 014-0 8.857 310 5.476 C

?; * 102_A- 12'12-1 6%il 97 ,

NOTE (3)7.J41 0

12-1 0. 8 .1 EM 5.555 0-

5.100 f12-3 6.811 109 s;12-4 6 811 205- 5.127 C

[12-4A I

978|.6 811 g * 4 816 0

:12 5 6 811 | 4.701 0

f)2-0 0.811'' 1,101 5115 0i.2-7 6.811 1.183 5655 0

l; 2-13028 t?' NOTE (3;

{12-1 6,811 246 6,514 012-2 6 811 247 5 2Rli 012-3 6.811 458 6.210 012 3A 6.811 827 0.487 012-4 6 81 t 796 4.753 012-5 6.811 980 6.072 012-6 6 811 947 '7.b s6 0

INOTESfil' P = (!P x 00)/l4 m {tpy,

h2) DW.TH snd WO3 -(FIA) + [(SORT [(Me"2) +(M "2)| x 12 in /ft }/S)f

h3) ENVElnPE LOAO OF Fu t 660 lb. My=22.0?O h-Ib & Mud 550 ft-Idadded per ASU Cctculatan

I

h02tSCO3 WK1/ ALL fD2) (F g 1 of 2) .

XCE-53-102 C.17tG TEEHRevision 3 g;EIMEERS -

__ -

Page 20: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

__ _____ _ _____ ._ __- _

*. . . ..,* *

Tabic C-9

RBIfQEN UNIT 2SMSTAINED STRESSIS

ISOLATlQE CONDENSER SYSTEM - STEAM SUPPLY(concluded)-

P sowe ~S~t n.wost (1) tri4GSFMTC

VALDNO M4 (pe 6) (7)

2-1302-14' INSIOE D AYWEQN58 14 439 16 950 0 8514-K1 13487 16 DN 0 8214-K2 12.728 16 960 0 7514-K3 17.561 16.950 1 04

14-K4 18,245 16.950 1 04 -

14-2 18.242 16.950 1 04# 14-3 18 290 16.950 1.08 y

14-K$ 14.325 to 950 1 08 v14-K6 10.019 16 950 0 59 #

14-3A t 0.019 16.950 0 50e 14-4 15.310 18,9t0 0 90

} 14-6 14 295 18 950 0 84/ 14-5A 12.387 16 950 0 73

14-6H 12.6ad 16 950 0 75

h1302-14' OU.T Sg D AYWELL14-6 15 872 16.95%' 0 941441A 15.872 16)$0 n 9414-7 13.887 16 950 0 E214-1 12.000 16 950 0 7114-2 13.152 16 # 60 0 78

9 14-3 11.043 16 950 0 6514-4 10.225 16,950 0 6014-5 13 633 16 950 n 40

' 14-6 11.9.17 16.950 0 7014-7 13.750 16.250 0 8114-8 12.653 16.9f 3 0 7614-4 12.643 16 950 - 0.75

Q302 A-12*12 1 14.249 16.950 0 84

i12-2 13.220 - 18.950 0 78

f12-3 12,020 16.950 0 71112-4 12.143 10 960 0 72

{ t2-4 A 11.709 16.950 C P4

|12-5 12.400 16 950 0 74 -g;

|12-6 13 117 16.950 0 7712-7 13.649 16.950 0 41

2-1 M28-t2'12-1 13 47C 16.950 0 8212-2 12.346 16 950 0 7312-3 13,479 16 950 0 8012-3A 13.125 16 950 0 77 .

12-4 12.159 16 950 0 7312-5 13.864 18.950 0 2212-6 16 404 18 950 0 91

WCTE C~

(1) Sm = AWtswebte Demon Strese intensty w lype 304Stainless Steet at De*0n Temperature of -575 riegtses F trom ASHE Sechon 1HAcpec$2Tath M .2

12) SR = (P + DW + TM + WOT) / 2%

(#12| SCC 3 WK1/ ALLMD2) (Pg 2 of 2y

XCE,53-102 C 18. NUTEEH

Rev.is2on 4 ENHtER*ii.

-1|

Page 21: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

.

-.,g . . ,

.

Table C-10

DRESDE.'l UllIT 2SUSTAIllED STRESSES

JSOIJC7,Qfi COtlDE!1SEE SYSTEM - COtIDEtJSATJ RETURU

P5ELsuff (Nv TH vos

s f HESS (P) STFESS (2) SI TE SS (2) $1 Fess (2)!

! wtLDfC (1) (psi (pad (pea (pc 4

2-1303-12*lNSIDE ORYWEg'

12X-4 6.811 0.005 158

12-K7 64t1 167 6 910 137

12-11 6.811 7 /9 8.158 159

12-KSA 6,811 675 7,585 160

12-K3 8.L . ' ~ $56 - 7.58) 214

12-10 6.81 760 5.620 189

12-9 6.411 752 2.589 112

12-KI 6.811 703 3 701 63

12-8 6.811 264 5422 90

12-78 6.811 | 120 ,7 S74 '4

12-7N 8.h t i i 154 4.134 26

p.t 30.3 12aOUT $10E DAYWELL

'2-7A 6811 183 528 0

12-7 c.811 183 528 0

12-6 6 811 342 2087 0

'NOTED(1) P = (iP x 004/14 x (tp))(2) OW. TH. and WOS (F/A, + [(SCRT{{Mx"?) + (M '2)| w 12 in lft ytlf

;31 ENVELOPE LOAO OF Fu =1.600 Iti. My=22 050 R-lo. & Mied 550 It-Ibadded por ABB Calculatian

;C215003 WK1/ ALLKD2) (Pg 1 of 2; |

XCE--5 3 - 10 2 C.19 NU'TEHRevision 3 ENGMF.ERS -

Page 22: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

*:-cs* .

Table C-10

DRESDEli U?iIT 2SUSTAIt<ED STRESSES

ImTIori CorIDEtiSER _ SYSTEM - COfiDEllSATE RETURif(Concluded)

_

r .UW. Sm

TH.Woh (t) Sf HE SS nATIO

WELD NO (pad me) m

|2-1303-t:"INSIDE D AYWEL L

12X-4 13.219 16 950 0.78

12-K7 14.025 10.950 0 83

12-11 15 908 16=950 0 94

12-K3A 15.231 16.950 0 90

12-K3 15,162 16.950 0 SG

12-10 13.279 16.954 0.78

12-9 10,265 16.950 0 61

2-K1 10.778 16 950 0 64

12-8 12.591 18,950 0 74

12-7B 11.019 16.950 0 65

Iw-7N 11.125 iA950 0 66

2-1303-ir*OUTSIDE DRVWELL

12-7A 7.522 16.950 0 44

12-7 7,522 If ~30 0 44

12-6 9 240 ?O.950 0 55

llO TEF --

(1) Sm = Allowable Design Stress Intensity fcw Type 304Stamiese Steel at Design Temperature of$75 degrees F ham ASME Section ..

.

Append 4x Table |-f.2.i(2) SR = (P + DW + TH + WOS) / Sm

dD2|SCO3 WK1/ ALLHD2) (Pg. 2 of 2) ,

!

XCE-53-102 C.20 NUTEHRevision 3 ENGt4EERS

Page 23: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

.

es. **,,* e

4

-Table C-11

DRESDEN UNIT 2SUSTAINED STRESSES

COf1 TROL ROP DRIVE _ SYS'"fM

| reu.sauset ow TH vvussisu nsp*) st F(ss rz) stit.ss m sisu:ss rj

ut D NO O Hpe4 (pe4 @e4 (pe4

I4-6 4.173 133 1.125 0

4-5 4 173 1.010 2.742 0

4-4 4.173 426 2 070 0

4-3 4,173 278 1 960 0

4-2 4.173 1,167 1.744 0

4-1 4.173 1.257 1.663 0

|WOTEs,(t) P . (IP x OD)/i4 x (tp)](2) DW, TH. and WOS = (F/A) + {(SQRTI(Mx"2) + (My* '2)] x 12 in Itt )/S).

'020RC3 WK1/ ALL)(O2) (Pg 1 of 2)

XCE-53-102 C.21 NUTEEHRevision 3 ENGHEERS

Page 24: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

- _ - _-_-__--. - - - - - - -

*, e-.,

'.

.

Table C-11

DRESJEN UNIT 2_S3ES3'AIEED STRES_S1's

C_QRTROL POD DRIVE SYSTEM(Concluded)

f Pbw.~ w,1HMH (i)-" IU' L _.,,._ _ 5'4 etsuAs ruix)

;4 6|

____S'S

G15 431

SS 16.950 !;47 926

4-4 16 950 -o gr6 669

4-3 1e 9500 39

0.411A-2 16 950

0 337.084

41 te gio0 427,093

16 950 'o 42

ll0TE5 -(1) Sm = Allowable Destgr) Stress intensity b Type 304

Stamiese Steelat Dusgr Temperature of575 degrees F from ASME Secoon litAppendia Table i+1.2

(2) "A = (P + OW + TH + WOSlt Sm

{D2 CAD 3 WKII A_LLv02)(Pg 2 of 2)

t_

<

>

0

3-102 JTE[Hion 3 C.22 HaNEERSNUTEEHENGNEERSg

__ __ . _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - __ __ _ _ _ - _ _ - - - - - - - - - - - - - - - - - - - - - - - ~ ^ - ~ --_--- "_

Page 25: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

.___

... .

.

* .

*.

Table C-12

QFESDQi UNIT 2SUSTAINED STRESSES

REACTOR WATER CLEAN-UP SYSTEM,

(Concluded)

P.Dw. smT H4vot (t) sit

wt iD too tusi (p=0 (2)

8X.t 9.014 16.950 0 53

I

NOTES.(1) Sm = AllowaDie Design Stress Intensity for Type 304

Stainiese Steel at Desegn Temperature of575 degions F from ASME Section tilApperio u Table 1-1.2.

(;') ?9. (" + OW , TH + WOS) / Sm

(D2RWCt.13 WK11 ALLMD2) (Pg 2 of D

i.

XCE-53 - 102 C.24 NUTEEHRevisi - 3 ENGNEERS

Page 26: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

( -----

'g .,

- J

&T Conanonwealth Edison Co.

'

P.O. Box 767, Chicago, IL 60690 September 1990 Inservice InspectionUnit No. 2; National Board No. N-137,

Dresden Nuclear Power Station Commercial Service Date: 06-09-724-

R.R. No. 1, Morris, IL 60450 .

.

TABLE E INTRODUCTION

A reanalysAs of the Reactor Recirculation Piping was performed inOctober, 1990. The analysis was performed to asses the effe-ts ofRiser shrinkage caused by Weld Overlays.

The reanalyais resulted in the change of several spring can cold loadsetting tolerances on the Recirculation, Low Pressure CoolantInjection, Reactor Water Cleanup, Isolation Condenser, and ShutdownCooling systems. A special inspection was performed on the springcans in these systems that were not inspected during D2R11, and werenot part of the regularly scheduled ISI for D2R12.

Several of the spring cans inspected had cold load settings outsidethe new tolerance range. The cold loeds were reset within tolerancesand a baseline visual inspection was performed.

The attached Table summarizes the supports that received the specialinspections and the results of the baseline examinations followingany repairs.

.

- 56 -

IR17/202

.

- - -..e m. -- , . . . . ~ , , m

Page 27: Office of Nuclear Reactor kegulation Nucli.ar Regulatory Commission … · 2020. 5. 11. · October 27, 1992 Dr. Thomas E. Hurley Office of Nuclear Reactor kegulation Nucli.ar Regulatory

. . _ - .

,

; y,_,

.--w

s. ,

i Coamonwealth Edison Co. . septerber 1990 Inservice inspectica -.

P.O. Box 767 Chica90, IL 60690 O,it No. 2; National Board No. N-137Connercial Service DatS: 06-09-72

Dreiden Nuclear Power StationR.R. No. 1, Morris IL 60450

IABLE_f

Page 1 of f

RESULIS

CATEGORY ,MATERI AL/ LOC ATION METh00 EXTENT OF EXAMINATION I!jQ1LAT10N NO. SCAN TYPE.. . PERCENT CAC _.

EVALUATIONASHE COMPONENT

NRIF-C Recirc Line 0201A VT-3/4 M-Il57D-255

Class 1 DW 22" NRIVT-3/4 K-flu:u-2%7

NRIVT -3/4 M-Il57D-Z58

VRI' VT-3/4 M-1157D-258

NRIRecire Line 02013 Vi-3/4 M-1!570-256DW 22" NRI

VT-3/4 M-1157D-263

NRI J

VT-3/4 M-1157D-264NRI

'A' Recirc Pump VT-3/4 N-il57D-276DV NRI

'/T-3/4 M-1157C-277NRI

VT-3e4 H-1157D-278NRI

Recirc Line 0203A VT-3/4 M-1157D-265

DW 4" NRIVT-3/4 tb1157D-269

NRIRecire Line 02038 VT-3/4 H-1157D-2f5 .jDW 4"

NRISDC Line 1001A . VT-3/4 H-11590-259

DW 16"NRI

RwCU Line 1201 VT-3/4 H-11590-262

DW 8"

o

- 57 -ZR17/202 .

'

.

_

| - _ _ _ _ _,