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Forwards Summary of Analytical Results for Reassessment of Seismic re-evaluation of NSSS Piping.All Piping Stresses within ASME Code Allowable Values
	ML20052H310
Person / Time
Site:	Fermi
Issue date:	05/20/1982
From:	Heidel C; DETROIT EDISON CO.
To:	Kintner L; Office of Nuclear Reactor Regulation
References
	EF2-57-885, NUDOCS 8205200200
	Download: ML20052H310 (64)
	v • d • e

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Harry Tauber vice President Engrneenng and Construction MI Edison EiME ">>-

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EF2 - 57,885 Mr. L. L. Kintner U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555

Dear Mr. Kintner:

References:

(1)

Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 (2)

EF2-54,761 dated August 25, 1981 (3)

EF2-54,665 dated September 9, 1981

Subject:

Scismic Re-Evaluation of the NSSS Piping The seismic reassessment of the NSSS piping, as discussed in the referenced letters and the SSER, has essentially been completed.

A summary of the analyti-cal results of this reassessment is provided in Attachment I.

The results show that all piping stresses are within ASME Code allowable values and that the loads on pipe mounted equipment are within prescribed limits.

However, some snubbers have predicted loads that exceed their rated loads, and three recirculation discharge reactor pressure vessel nozzles have loads that exceed the allowable values.

Detroit Edison is in the process of upgrading these snubbers to accommodate the site-specific seismic loads and expects that the increased stiffnesa of these supports will result in acceptable loads at the reactor vessel nozzles.

{j OC)I s

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B205200200 820520 PDR ADOCK 05000341 P

PDR L

4 Mr. L. L. Kintner EF2 - 57,885 Page 2 It should be noted that the reactor water cleanup piping inside containment (not required for plant safe shutdown) was also originally analyzed using the center-of-gravity method for seismic response spectra selection. This piping system is currently being ana-lyzed for the final as-built condition using an accep-table response spectra selection method (envelope method).

Sincerely, C.M.

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k Attachment I to EF2-57,885 Contents: Appendix A: Mathematical Models - Recirculation Appendix B: Equation 9 Stress Summary - Recirculation Appendix C: Support and Equipment Loads - Recirculation Appendix D: Mathematical Model - Main Steam Appendix E: Equation 9 Stress Summary - Main Steam Appendix F: Support and Equipment Loads - Main Steam Appendix G: Seismic Analysis Input Summary l

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APPENDIX F - Pipe Mounted Equipment Loads Summary Table C-1 Pipe Mounted Equipment Loads Summary - Main Steam A Table C-2 Pipe Mounted Equipment Loads Summary - Main Steam B Table C-3 Pipe Mounted Equipment Loads Summary - Main Steam C Table C-4 Pipe Mounted Equipment Loads Summary - Main Steam D r
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,e 0322823 000000000000000000 SEMERAL*8 ELECTRIC COMPANY SPEC MO.
ftA7827 REV. MD.
O BOILIMO WATER REACTOR SYSTEMS DEPARTIENT PAGE NO.
SRV FLANGE MUMENT(MS-A) d I;
LEVEL D MDMENT RATIO EG.
108. 104.
377000. 0.4077 2
l 208. 204.
296848.
0.3198 2
5 308. 304.
243021. 0.262Y t
8 y
110. 111.
300120 0.0002 2
210. 211.
361193. 0.4363 2
0 310. 311.
227727.
0.3795 2
THE LOADIMS COMEIMATION USED FOR THE ANALYSI5 saFLeM eee ARE AS FOLLOW LEVL D 1 WT1
+ TE
+ SORT ((SSEI
+ SSEO last
+ t TSV 3sst
)
LEVL D 2 WT1
+ TE
+ SQRT((SSEI
+ SSED 3es2
+ t RV1 Iss2
)
l L
m, w
A p
0322^28 000000000000000000 i
SENERALsELECTRIC COMPANY SPEC HO.
22A7827 ItEV. HO.
0 BOILING WATER REACTOR SYSTEMS DEPARTMENT PAGE No.
4 RELIEF VALVE ACCEL (MS.A) o LEVEL 0 ACCEL RATIO EO.
108. 100.
AH 1.7782 0.2220 2
4 AV O.8444 0.1408 2
~
9 0
20s. 20s.
AM 2.2009 0.2759 2
AV 1.1282 0.1880 2
306. 304.
AH 1.9322 0.2415 2
AV 1.3086 0.2181 2
E l VALVE ACCEL (MS-Al e
~
LEVEL 0 ACCEL RATIO EG.
441. 443.
AN 0.4508 0.0901 2
AV O.3237 0.1079 2
443. 441.
AH 0.8185 0.1633 2
AV O.2297 0.0766 2
THE LOA 0f191 COPSIMATION USED FOR THE ANALYSIS eeVACC eae ARE AS FOLL(N LEVL 0 1 SORT ((SSEI test
+ t TSV post 3
LEVL D 2 SORT ((SSEE pas 2
+(
RV1 pes 2
)
s.
F b
g b3
^
p i
', 032Z 28 000000000000000000 GENER4LeELECTRIC 00MPANY SPEC MO.
22A7627 REV. NS.
0 90lLIMS WATER REACTOR SYSTEMS DEPART 7E9(T PAGE MD, MSlv BNLET/0UTLETEMS-A) d I
i LEVEL D MDE NT RATIO EO.
043. 045.
FA 37477 0.0104 1
TOR 885025.
c.0154 2
(
MOM 1706154.
0.0594 2
)
L
)
051. 060.
3 FA 18812. 0.0047 1
I' 5
TOR 184340.
0.0027 2
9 MON 1466386.
0.0510 2
I' I-
.I I!il
)
MSIV BOMMET(MS-A)
'i LEVEL 0 MDMENT RATIO EO.
o, 047. 049.
~~i FA 2363.~~
0.0873 2
i TOR 0.
O.0000 2
{
MON 313910.
O.1975 2
!l Il lI e
)
THE LOADIMS COMBIMATION USED FOR THE ANALYSIS eoMSIy see ARE AS FOLLOW 5
LEVL D 1 WT1
+ TE
+ SORT ((SSEI
+ SSEO Inst
+(
TSV iss2 3
LEVL D 2 WT1
+ TE
+ SORT ((SSEI
+ SSED pas 2
+ ( RVI Iss2
)
1 r'
-t.
^"
^._
m
,m
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22A7927 NEV. NO.
O 90lLIMO WATER'REACTOP SYSTEPts DEPART M T PAGE No.
MCZ2LE(MS-Al 4
LOCATION FORCE RATIO NO. COPW MOMENT RATIO NO. COPS 003.
002.
LEVL D 3s173.
O.1699' f
1286987.
O.2894 1
.)
'?
i s'l l
'I THE LOAO'IMO COPCINATIER DSED FOR THE ANALYSIS saMOZL esa ARE AS FOLLOW j
IEVL D 1 WT1
+ SORT ((SSEI test
+ ( TSV pseg
)
LEVL D 2 WT1
+ SORT ((SSEE pas 2
+(
RVI 1se2
)
5 L
I
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0322828 000000000000000000 OEMERAL fLECTRIC COMPANY SPEC No.
22A7628 REV. No.
0 DOILING WATER REACTOR SYSTEMS OEPARTMENT PAGE No.
SRV FLAMGE MOMENT (MS-Bi LEVEL D MOMENT RATIS EO.
106. 104.
455232. O.4921 2
206. 204.
467651.
0.5056 2
1 306. 304.
393690. 0.4256 2
j 406. 404.
262661. 0.2642 2
506. 504.
360276. O.4111 2
110. 111.
424756. 0.7079 2
210. 211.
457033. 0.7617 2
310. 311.
375050.
0.6251 2
410. 411.
262464.
0.4706 2
e e
[
510. 511.
317673.
0.5300 2
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22A7828 REV. NO.
0 90lLING WATER REACTOR SYSTEMS DEPARTMENT PAGE NO.
4 NOZZLEtMS-81 LOCATION FORCE RATIO NO. Cope MONENT RATIO NO. COPB
~~003, 002.~~
LEVL D 45600.
O.2030 1
1731998.
O.3895 1
1 I
l l
i 4
l 1
l
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4 0.
Oo NN
.E VG.
EA.
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n'
^
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7 A
2 2
O N
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M.
T.
2 2 2 2 2 2 2 2 2 2 R
O AP.
E EO 0 O Y
9 7 7 0 5 5 9 2 9
)
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RT NS.
8 2 2 4 i
I 1
f 8 7 5 0 AM 7 5 2 0 0 5 0 6 9 0 O
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5 A
S 0
MT OS M 0
L O 0 0 0 0 0 0 0 0 0
(
0 CY.T 0
. N 0
CS.E 0
. M T
8 7 7 3 4
7 4 3 9 3 IR.S N
0 RO.
1 2 8 7 3 8 1
3 4 5 0
7T.M E
2 9 4 3 9 8 1
7 1
5 0
CC.
M 2
8 8 4
0 3 5 0 7 0 0
D 4
1 9 7 7 5 8 0 9 0 EA.E M
4 4 2 3 3 4 3 2 2 3 0
LE.NG 00 ER.A 0
LR.L 0
AE.F 0
RT 0
EA.V 4 4 4
4 4 1
1 1
1 1
NW.R 0 0 0 0 0 1
1 1
1 1
m-E 1
2 3 4 5 1
2 3 4 5 OG S 4
N.
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1 1
1 1
2 2 3 4 5 1
2 3 4 5 I
1 2
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0 I
Bell. LNG WATER REACTOR SYSTEMS DEPARTMENT PAGE NO.
1 RELIEF VALVE ACCEL (MS-C)
LEVEL D ACCEL RATIO EO.
ls 1
106. 108.
AM 2.4889 0.3111 2
AV 1.0007 0.1668 2
.i i!
)
208, 208.
AM 2.5472 0.3234 2
AV 1.0307 0.1718 2
k 306. 308.
AM 2.4579 0.3072 2
i AV 1.1465 0.1911 2
ii 406, 408.
AH 2.6980 0.3373 2
{
AV 0.8908 0.1485 2
i 506. 508.
AM 1.7788 0.2224 2
AV 0.8075 0.1346 2
y f:
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0 PAGE No.
80lLING W4TER REACTOR SYSTEMS OCPARTMENT 4
MSIV INLET /0UTLET(MS-C)
[
l LEVEL C MOMENT RATIS EG.
052. 051.
FA 34715.
0.0096 1
TOR 54004.
0.0009 1
M01 7550402.
O.0539 1
059. 060.
FA 36761.
0.0102 1
TOR 56853.
0.0010 1
MON 1938547.
0.0396 1
MSIV BONMETIMS-C)
LEVEL 0 MOMENT RATIS EQ.
055. 057.
FA 2189.
0.0531 2.
TSR 0.
0.0000 1
MON 198193.
O.1247 2
L
^
m O
0322628 00000000000G000000 GENERAL ELECTRIC COMPAPff SPEC No. 22A787829 REV. No.
O BOILING WATER REACTOR SYSTEMS DEPARTMENT PAGE No.
NOZZLEtMS-C)
LOCATION FORCE RATIS No. COPW MOMENT RATIO No. COPS 003.
002.
LEVL D 43367.
0.1931 1
1397876.
0.3593 1
'l l
l l
i
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i 0322828 000000000000000000 SOGERAL ELECTRIC COMPAMif SPEC No.
22A7830 ItEV. NO.
BOILING WATER REACTOR SYSTEMS DEPARTMENT PAGE NO.
SRV FLANGE MSMENTtMS-0) 1 LEVEL D MORENT RATIS EO.
1 106. 104.
287484. 0.3215 2
ROS. 204, 413861. 0.4474 2
j 110. 111.
231552. 0.3858 2
210. III.
336226. 0.9804 2
l i
l l
4 l
i N
~
.^.
[.
0322828 000000000000000000 GENERAL *dECTRICCOMPANY SPEC No.
22A7930 REV. MS.
30lLIMO WATER REACTOR SYSTEMS OEPARTMENT PAGE No.
RELIEF VALVE ACCELIMS-0)
LEVEL 0 ACCEL RATIS EO.
106. 108.
AM 1.4788 9 1848 2
0.7585 O.1264 2
206. 208.
AM AV 1.7330 0.2198 2
0.7586 0.1281 2
(( ggt 800 t l!
e I
4 r
e 4
O...
OO.
NN
.E..
VG.
EA.
EP.
I 0.
3 p
8 7
A22 OM C.
E.
P S.
T.
121 111 N.
G E.
E PT.
D 212 R.
O 1S9 589 G
A LI 139 819 E
P.
ET 104 003 E
VA 000 000 B
D.)
ER O
205 Y
L 000 000 LI 501 NS.D ET 501 t
AP VA 001 WT.(
ES ER M
T 176 496 L
000 OS.T N
049 955 f
CY.E E
268 583 O
CS.L M
042 356 O
493 204 S
T 409 IR.
M N
7 8 RO.T M
14 11 TT.U 1
1
(
E 2
1 CC.O T
m 1 7
/
E 7
t EAT M
M 1
LE.E.
N ER.t O
t B
LR.I AE V
RT.v I
9 RM EA.i 2 RN 0 RM S
3AOO VW.S 3ASO 6ASO M
0FTM E
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3 N.
7 3
1 3
2 I
3 4
0 8
L.
0 0
2 I
2 O..
3 D.
0 b
i
,4!
]I
.R r
.r.
0322828 000000000000000000 GENEftAL dICTIllC COMPANY SPEC MS.
22A7830 REV. NO.
PAGE NO.
BelLIMO WATER REACTOR SYSTEMS DEPARTMENT 4
NDZZLE(NS-D)
LOCATION FORCE RATIO NO. COPE MONENT RATIO NO. COPS 003.
002.
LEVL D 43183.
O.1922 1
1853883.
O.3719 1
S e
D I
1
l ll(
Sveraar Suwom - So SnAm Sumw Ssevnee.
Seussut Haan LEVEL
~~Lobb kTuns kTIO SA1 B~~
/o 6 76 54600
./956 D
/7 /B4 l
7/000
./896 5Al 8
/4903 l
59600
.2729 D
2599f i
9/000
.2657 i
SA3 8
1 losHI 15300 66ze D
13673 l
23600
.5794 i
l 23600 SCI 6
8541 15300
.SS8 2
(
D I326I i
.56I9 SC2 B
11393 15300
.74H6 D
I4859 23600 6296 5C 3 8
/V375
/5300 9908 D
/7318 23600 73 5/
SCH 6
12I90 15300
.7969 D
/39/7 23600 5697 SC 5 6
18)22 15300 f.I8 %
D Zlfl9 23600
-9//6 Sc6 B
13116
/Saco
.&/z D
/72t3 23600
.7294
+ ( Ma Rvi ca Tov )
~~LEVEL B = SQRT {(OBESsTE SMinc.tSE LEVEt. D = SQ RT ff~~
(
Suppoev Sunsvi > - MAwSme (cour)
Surwar
" Savnet.
Snusera l
Mw Leve.c LoAo krw4 RAno l
581 8
12932
/5300
.8452 D
/8481 23600 79/6 i
562 B
l'/ %Z
/5300 9452 O
/6 744 23600 7 94/ 2 i
I g
i SB3 B
l 13 9)/
l
/S3co
.9092 D
/7//r 23600
.7252 j
i SBH B
II575 1
/5300 7565 I
(
D 12959
\\
23600 5'f91 l
SEr B
/7640 54600 1
3267 D
22966 9/000
.2524 I
t 586 i
B
/6535-54600 l.3028 D
20620 9/o00 j
.2266 i
50I B
7526 SY600
./3 76 D
> ll076 91000 12/ 7 g
i SD2.
8
/y95/
54600
-2738 i
i D
25775 91000 t
.2632
\\
e SD3 8
8598 I
15300
.562o D
//1'/4 l23600 506/
- _... _ - =
[f
)
l i
SureenT Susse MAioS7rm (coom Sveron r Same Lo/lb
. SuMonr
, Suueane MARK LSvce DLiise kno PArtua E297-608 B
C685 I5000 15300 D
/0543 23600 2297-609 8
/660 6000 6000 D
2 73 I 9000 2297 - G10 B
6727
/2000
/S300 D
//37'/
Z3600 i
2297-GII B
5934
/ZOOO 15300
(
D
/0570 236oo 2192-6 06 8
348 4000 4000 D
6 t'1 9000 2192-6 07 8
631 6 Coo 6 000 i
D II21 1000
{
Zl92 - 613 8
1343
'/000 6000 D
214 7 9c00 l
I alt 2-6 JH B
1398 4000 6000 i
D 2208 9000 l
l 2192-Gl5 S
/008 2000 6000 i
D ISOS 90C0 i
r t
(
Nort: Line 229'l :s THE HFCI STEAM SVPPL'1 PIPIAJG Lirit 2I92 is ins RCIC STrAm svPPC1 Pl FING 60
o i
APPENDIX G Seismic Analysis Inpue Summary 6/
o Item Criteria Equipment Damping OBE:
0.5%
Site Specific SSE:
2%
Site Damping Site Specific SSE:
5%
Cutoff Frequency (ARS):
33 HZ Response Spectra Selection:
All Spectra Applicable to Support and Anchor Locations.
Seismic Analysis Method:
Multiple Support Excitation f
5 i
i
[9 0
..

ML20052H310

Text

Dear Mr. Kintner:

References:

Subject:

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