ML20148K357
| ML20148K357 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick, 05003337  |
| Issue date: | 11/14/1978 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JNRC-78-57, NUDOCS 7811170110 | |
| Download: ML20148K357 (11) | |
Text
...
}
POWER AUTHORITY OF THE STATE OF NEW YORK to CotuMaus CIRCLE NEW YORK, N. Y.10019 (212) 397-6200 TR U STEE S GEORGE T. BERRY GENERAL MANAGER FREDERICK R. CLARK AND CHIEF ENGINEER g
MANA AL tflCE CHAl MAN RICHARD M. FLYNN WILBUR L. GRONBERG MAN E ENG NEER NG TsOCERT I. MILLONZ1 November 14, 1978
" " ";,",8,I, ",
wituxM r. Luoor C
- " ' " ' ' ' " ^ " * *
- JNRC-78-57 THOM SF MCCRANN,JR.
Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Thomas A.
Ippolito Operating Reactors Branch No. 3 Division of Operating Reactors
Subject:
James A. FitzPatrick Nuclear Power Plant i
Multiple Consecutive S/RV Actuation Evaluation Docket No. 50-333
Dear Sir:
Transmitted herewith is an analysis performed by Teledyne Engineering Services for the Authority concerning multiple consecutive safety relief valve actuation evaluation.
On September 28, 1978 the Authority transmitted information concerning the subject matter summarizing the results of the analysis and describing the methods and assumptions used.
The results of the analysis supported upcoming operation of the FitzPatrick Plant during Cycle 3 by assuring that the structural capability of the torus satisfies acceptance criteria established by the Short Term Mark I Containment Program.
Subsequently, the Commission requested by telephone on October 18, 1978 that the Authority submit the analysis done by Teledyne Engineering Services.
Very tryl
- ours, fl
, ; QJ Paul J. Earl i
Ass *stant Chief Engineer-Projects
/
h 9 <\\
(
7811170l10 l
I "vPTELEDYt'E
~
ENG:NEER;NG SERVICES l
October 19, 1978 2386-62 Page 1 of 10 James A. Fitzpatrick Nuclear Power Plant Multiple Consecutive S/RV Actuation Evaluation 11 SR7 Lines Assume multiple consecutive actuation of e
valves L, K, E and D.
- Assume multiple initial actuation of valves L and K and multiple consecutive actuation of valves E and D.
- Determination and evaluation of the maximum shell stress and support column load.
r
@~ ' l @
/
D i
A' e
w W
c, m
o W
(,Y J
W S.,
/
/
h @ p; a,
@,e l
"RTELEDYNE ENGINEERING SERVICES 4
October 19, 1978 2386-62 Page 2 of 10 1
L Support Column Evaluation Consecutive Actuation Factor = 1.96 From Monticello S/RV Test - Single Cold Actuation of Valve D:
Reference Outside Column Load = 196.7 kips Midbay to Ring Girder Factor =.84 Plant Unique Column Load Multiplier =.71 Outer Column, Single Hot Pop = (1.96)(.71)(.84)(196.7) = 230 kips Outer Column Deadweight = 270 kips e
4
'MTELEDYNE ENGINEERING SERVICES I
October 19, 1978 2386-62 Page 3 of 10 4 Valves Hot - L, K, E and D Factors for Multiple Actuation - Columns - Outer i
SRV Actuated Valve P
SRV Deadweight Column (kips)
(kips)
Location L
K E
D c
1
.08
.7
.11
~
1.04 239 509 C
.09
.15
.12
.12
.48 110 380 A
.10
.15
.15
.11
.51 117 387 H
.11
.12
.15
.10
.48 110 380 2
.12
.11
.7
.09 1.02 235 505 G)
.15
.10 1.0
.08 1.33 306 576 3
.15
.09
.7
.09 1.03 237 507 G
7
.08
.15
.10 1.03 237 507 GD 1.0
.09
.15
.11 1.35 311 581 F
.7
.10
.12
.12 1.04 239 509 J
.15
.11
.11
.15
.52 120 390 B
.15
.12
.10
.15
.52 120 390 4
.12
.15
.09
.7 1.06 244 514 GD
.11
.15
.08 1.0 1.34 308 578 5
.10
.7
.09
.7 1.59 366 636 GD
.09 1.0
.10
.15 1.34 308 578 I
"WTELEDYNE 4
ENGINEERING SERVICES October 19, 1978 2386-62 Page 4 of 10 t
STP Evaluation of Outside Colue.n - Location 5 f,= h =.13.418 ksi factor = 63 8
, (636 x.117 x 1.0056) + l49.5B x 1.0066) =.562 ksi fbx 222 i
, (636 x.057 x 1.3066) + (9.2874 x 1.0066) =.588 ksi f
78 by t
13.418
(.85)(.562)
(.85)(.583)
~ 0'5 V 6~ + }, 1.i.418 36 i - 13.418 36 121.0 38.2 _
.305 +.0149 +.0214 10.5 i
.3413 1 0.5 i
Weld Joint SEC = 1,951 kips (includes ultimate capacity of web weld
~
1 and yield capacity of flange welds) l i
Weld Joint S.R. = 636 =.32 l
g 4
I t
l
~
"WTELEDYNE ENGINEERING SERVICES October 19, 1978 2386-62 Page 5 of 10 Valves E & D - Hot Pop Valves L & K - Cold Pop Factors for MultipleActuation - Columns - Outer O
Hot Cold P
P h + h(kios)
+ Deadweight Column SRV SRV Location E+D (kiod L+K (kios) 1
.26 60
.78 92 422 C
.24 55
.24 28 353 A
.26 60
.25 29 359 H
.25 58
.23 27 355 2
.79 182
.23 27 479 1.08 248
.25 29 547 3
.79 182
.24 28 480 G
.25 58
.78 92 420
.26 60 1.09 128 458 F
.24 55
.80 94 419 J
.26 60
.26 31 361 B
.25 58
.27 32 360 4
.79 182
.27 32 484 1.08 248
.26 31 549 5
.79 182
.80 94 546
.25 58 1.09 128 456
4
+-
"RTELEDYNE 3
ENGINEERING SERVICES October 19, 1978 2386-62 Page 6 of 10 Code Evaluation of Outside Column - Location D
= 0.869 factor = 63 8
, (549 x.117 x.869) + (49.58 x 0.869) =.446 ksi fbx 222 (549 x.057 x.869) + (9.2874 x 0.869) =.452 ksi f
by 78 549 f, = 4, 4 = 11.582 ksi
(.85)1452)
< 1 *0
(.85)(.446) 11.582 TC6F,
~1 11.582-27.0
~1 _ 11.582-23.8
- 63. F, 19.9,,
.793 +.0195 +.034 5 1.0
.847 1 1.0 STP Evaluation of Outside Column - Location D 1
11.582,
(.85}1446)_
(.85)h452L < 0.5 44.0 j,,11.582~36 I
11.582 36
~
121.0 38.2 4
.263 +.0116 +.0153 5 0.5
.29 5 0.5 Weld Joint S.R. = 549
=.28 3
r-
_--.,.r--
s,-
"vPTELEDYNE ENGINEERING SERVICES A
October 19, 1978 2386-62 Page 7 of 10 Shell Evaluation Factors for Multiple Actuation - Shell - Midbay Actuated Valve Shell D
Location L
K E
D' 1
.11
.39
.11
.13
.53
.204 486 2
.11
.17
.13
.11
.32
.204 243 3
.11
.13
.17
.11
.32
.243 204 4
.11
.11
.39
.11
.52
.486 187 5
.13
.11
.8
.11
.99
.969 204 6
.17
.11
.8
.11 1.0
.969 243 7
.39
.11
.39
.11
.69
.486 486 8
.8
.11
.17
.11 1.0
.243 969 9
.8
.11
.13
.11
.99
.204 969 10
.39
.11
.11
.11
.52
.187 486 11
.17
.11
.11
.17
.34
.243 243 12
.13
.13
.11
.39 53
.486 221 13
.11
.17
.11
.8 1.0
.969 243 14
.11
.39
.11
.8 1.084
.969 486 15
.11
.8
.11
.39 1.084
.486
.969 16
.11
.8
.11
.17 1.0
.243
.969
@ =' 1.2 id(L2+K2+E2+D) 2 2
d,
= 1.2 id(E2+D) 1.2 /c(L2+K) 2 (3)
=
r,.-
=--r-e.
v--
-e-e y,,,
- - ~.
+
r :-
.,-w.
"RTELEDYNE ENGINEERING SERVICES 3
October 19, 1978 Page 8 of 10 2386-62 Factors for Multiple Actuation -
a Shell - Ring Girder Location Actuated Valve Location L
K E
D 1
.11
.59
.11
.15
.754
.223 720 2
.11
.19
.11
.11
.323
.187 263 3
.11
.15
.15
.11
.316
.223 223 4
.11
.11
.19
.11
.323
.263 187 5
11
.11
.59
.11
.744
.720 187 6
15
.11 1.0
.11 1.228 1.207 223 7
19
.11
.59
.11
.767
.720 263 8
59
.11
.19
.11
.767
.263 720 9
1.0
.11
.15
.11 1.228
.223 1.207 10 59
.11
.11
.11
.744
.187 720 11 19
.11
.11
.15
.345
.223 263 12 15
.11
.11
.19
.345
.263 223 13 11
.15
.11
.59
.754
.720 223 14 11
.19
.11 1.0 1.236 1.207 263 15 11
.59
.11
.59 1.019
.720 720 16 11 1.0
.11
.19 1.236
.263 1.207 1
2 h =
1.2 [c(L2+K +E2+D) 2
@=
1.2 /c(E2+D)
@=
1.2 c (L2+K)
L r
e y -w w-r e
-, m a
m
,e
-vn---
-e,,-
---w
-~e--
,,e,
,em
t W TELEDYNE ENGINEERING SERVICES 3
October 19, 1978 2386-62 Page 9 of 10 Shell Stresses
- Consecutive Actuation Factor = 2.37
- From Monticello S/RV Test - Single Cold Actuation of Valve D.
Extreme Fiber Shell Stress at Midbay, 45 up from bottom toward inside columns = 3400 psi j
- Factor relating stress at bottom midbay to stress 45 up from bottom midbay = 1.49
- Factor from extreme fiber to membrane stress =.86
- Plant unique shell stress multiplier =.63 Thickness of Monticello Shell = 0.584 in.
Thickness of Fitzpatrick Shell = 0.632 in.
Radius of Monticello Torus = 166 in.
Radius of Fitzpatrick Torus = 177 in.
SingleHot.Setuation=(1.49)(3400)(.63)(2.37)f'
= 7453 psi Hydrostatic Pressure Stress = 1708 psi Valves L, K, E & D Hot (38% of Code) P) + Pb = (1.236)(7453) + 1708 = 10,920 psi (50% of Code ) P,= (.86)(1.236)(7453) + 1708 = 9,630 psi Valves E & D Hot, Valves L & K Cold (Bay 14)
P) + Pb=
[(1.207)(7453)] 2 + [(.263)(3145)] 2 + 1708
= 10,742 psi (37% of Code) i
r,
"#PTELEDYNE ENGINEERING SERVICES October 19, 1978 2386-62 Page 10 of 10
/[(.86)(1.207)(7453)] 2 + [(.86)(.263)(3145)] 2 + 1708 P, =
= 9,477 psi (49% of Code)
Valves E & D Hot, Valves L & K Cold (Bay 15)
[(.720)(7453)]2 + [(.720)(3145)]2 + 1708 P; + Pb
=
7532 psi (26% of Code) d(.86)(.720)(7453)] 2 + [(.86)(.720)(3145)] 2 + 170 P,
= 6717 psi (35% of Code)
Material: A516 Gr. 70 S,= 19,300 psi 1.5 S = 28,950 psi g
Following references have been used in the preparation of this analysis.
" Mark I Containment Program - Multiple G. E. Letter MI-G-179, Consecutive SRV Actuation Evaluation-Task 7.1.3" dated 1.
June 16, 1978.
)
" Plant Unique Analysis Report for TES Report TR-2386 (a), Torus Support System and Attached Pipin 2.
dated August 25, 1976.
FitzPatrick Nuclear Power Plant"
.