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=Text=
=Text=
{{#Wiki_filter:. __.  .
{{#Wiki_filter:,
t
t
  .*  ,0 GENE 77101-0196. REV. O DRF NO. B13-01800 SHEET 1 PB ECR h(-N77       REV ATTACHMENT PAGE ~51   oF 1           ,
,0 GENE 77101-0196. REV. O DRF NO. B13-01800 SHEET 1 PB ECR h(-N77 REV ATTACHMENT PAGE ~51 oF 1
Dwo a
Dwo a SHT*
REV
+
+
SHT*        REV CORE SPRAY LINE DOWNCOMER REPAIR SEISMIC REPORT  
CORE SPRAY LINE DOWNCOMER REPAIR SEISMIC REPORT  


==SUMMARY==
==SUMMARY==
for PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 Modificadon P00335 f
for PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 Modificadon P00335 f
Prepared by:       /// Ash- M-Pr.
Prepared by:
T. E. Gleason, Principal Engineer                                   l Mechanical Design Engineering Verified bv:
/// Ash-M-Pr.
                                            ~
T. E. Gleason, Principal Engineer Mechanical Design Engineering A O'c-i(,
A O'c-i(,
~
Verified bv:
C. Lung, Consulting EngineerC/
C. Lung, Consulting EngineerC/
Approved by:       # -
7 Approved by:
7 D. W. Smith, ProgranrManager 1
D. W. Smith, ProgranrManager 9609180235 960903 DR ADOCK 05000277 p
1 9609180235 DR 960903 p    ADOCK 05000277 PDR
PDR


  ..  - ~ . . . . -~                   - . - . . . -.    ...-      ,      -_._          -    . _ . -  . _ _ - - - - - - -
- ~.... -~
i a
i a
'          ca               '
ca s
s t
t GENE 771-01-0196. REV. O DRF NO. B13-01800 I
GENE 771-01-0196. REV. O DRF NO. B13-01800                       ,
SHEET:
I                                                                                    SHEET:
P8 ECR N-N/f Rw 1.
'                                                                                  P8 ECR N-N/f Rw
INTRODUCTION
: 1.       INTRODUCTION                                     #",^'",
#",^'", MENT PAGE M OF o,
o, MENT PAGE M OF ser a _     nu -
ser a _
j                      1.1       Background I
nu j
Peach Bottom Atomic Power Station L' nit 2 has avo Core Spray Lines ( SC L) which                       ,
 
l enter the reactor pressure vessel (RPV) at the 120' and 240 azimuth locations.
===1.1 Background===
The CSL entering at 120' splits at its T-box with the downcomers at 7.5* and at                         ,
I Peach Bottom Atomic Power Station L' nit 2 has avo Core Spray Lines ( SC L) which l
172.5' locations. The CLS entering at 240* splits at its T-box with the downcomers j
enter the reactor pressure vessel (RPV) at the 120' and 240 azimuth locations.
at 187.5' and at 352.5' locations. The weldedjoints in the CSL downcomers near the shroud penetration may be cracked and will require reinforcement if the
The CSL entering at 120' splits at its T-box with the downcomers at 7.5* and at 172.5' locations. The CLS entering at 240* splits at its T-box with the downcomers j
!                      cracks are found. The reinforcement is required to maintain the pipe alignment and to prevent a crackedjoint for separating. This modification is of a bolted                           l' design utilizing clamps for attachment to the CSL.                                                       j i
at 187.5' and at 352.5' locations. The weldedjoints in the CSL downcomers near the shroud penetration may be cracked and will require reinforcement if the cracks are found. The reinforcement is required to maintain the pipe alignment and to prevent a crackedjoint for separating. This modification is of a bolted design utilizing clamps for attachment to the CSL.
The same type modification was used on Peach Bottom Atomic Power Station Unit                             f 3 at the 172.5' downcomer location.- The design and analysis used for the Peach Bottom 3 modification has been reviewed and the results are utilized where applicable.                       ,
j i
j                       1.2     Scope i'
The same type modification was used on Peach Bottom Atomic Power Station Unit f
The analysis covers the CSL from the thermal sleeve at the RPV to the CSL shroud penetration including the 90* elbow, but excluding the penetration sleeve. Two 9
3 at the 172.5' downcomer location.- The design and analysis used for the Peach Bottom 3 modification has been reviewed and the results are utilized where applicable.
different cases were evaluated, one assuming the downcomer integrity was intact i                        and the other assuming the propagation of the crack to 360 degrees which a!! owed rotational freedom at the crack location.
j 1.2 Scope The analysis covers the CSL from the thermal sleeve at the RPV to the CSL shroud i
I                       This report transmits the results of the CSL design stress analysis which assesses the effects of the proposed modification on the CSL. The purpose of the analysis l
penetration including the 90* elbow, but excluding the penetration sleeve. Two 9
j is to demonstrate the seismic structural adequacy of the CSL with the downcomer modification installed at Peach Bottom Unit 2.. The analysis is contained in Design Record Files (DRF) B13-01800, B13-01732 and B11-00642.
different cases were evaluated, one assuming the downcomer integrity was intact and the other assuming the propagation of the crack to 360 degrees which a!! owed i
rotational freedom at the crack location.
I This report transmits the results of the CSL design stress analysis which assesses l
the effects of the proposed modification on the CSL. The purpose of the analysis is to demonstrate the seismic structural adequacy of the CSL with the downcomer j
modification installed at Peach Bottom Unit 2.. The analysis is contained in
}
}
: 2.       CORE SPRAY LINE EVALUATION j
Design Record Files (DRF) B13-01800, B13-01732 and B11-00642.
2.1     Assumptions The following assumptions are used in the CSL structural analysis.
2.
: 1.     The CSL downcomer sleeve / spigot assembly near the shroud penetration is assumed to have one or more 360* through wall cracks. No credit is taken for any 9
CORE SPRAY LINE EVALUATION j
2.1 Assumptions The following assumptions are used in the CSL structural analysis.
1.
The CSL downcomer sleeve / spigot assembly near the shroud penetration is assumed to have one or more 360* through wall cracks. No credit is taken for any 9
ir


PB ECR h[4h 72 Rgv h
PB ECR h[4h 72 Rgv h ATTACHMENT PAGE M OF GEN E-771 01 0196. REV. O Dwo,
;                                                                    ATTACHMENT PAGE M OF   GEN E-771 01 0196. REV. O         ;
DRF SO. B13-01800 l
Dwo ,
SHT #
DRF SO. B13-01800 SHT # REV l                                                                                          SHEET 3                         (
REV SHEET 3
remaining ligament at the postulated crack location. Cracks may exist at one, two,
(
:                      three or all four downcomers.                                                                         ]
remaining ligament at the postulated crack location. Cracks may exist at one, two, three or all four downcomers.
: 2.     The seismic analysis shall take into account both partial and complete cracking of the shroud welds. The degree of cracking assumed shall be the                             l l
]
maximum crack length permitted without requiring shroud repair and complete                           j
2.
The seismic analysis shall take into account both partial and complete l
cracking of the shroud welds. The degree of cracking assumed shall be the l
maximum crack length permitted without requiring shroud repair and complete j
)
)
,                      cracking with the tie rod repair installed.
cracking with the tie rod repair installed.
I 2.2     Seismic Evaluation l
I 2.2 Seismic Evaluation The seismic evaluation for the Peach Bottom 2 downcomer repair utilizes analyses from the shroud repair work and from previous downcomer repair work.. The applicable i
!                      The seismic evaluation for the Peach Bottom 2 downcomer repair utilizes analyses from i                      the shroud repair work and from previous downcomer repair work.. The applicable l
l analysis are summarized below and can be found in DRF's B13-01800, B13-01732 and B1100649 f
:                      analysis are summarized below and can be found in DRF's B13-01800, B13-01732 and B1100649                                                                                             ;
l
f
: a. The shroud repair seismic analysis predicts 1.2 inches for the maximum CLS l
: a. The shroud repair seismic analysis predicts 1.2 inches for the maximum CLS l
anchor point displacements. The analysis assumes the shroud with 360' through l                                wall cracks and with the tie rod repair installed.
anchor point displacements. The analysis assumes the shroud with 360' through j
j l
wall cracks and with the tie rod repair installed.
: b. Seismic analysis which assumes the shroud cracked to the maximum extent without requiring the tie rods installed predicts the maximum CSL anchor point to l
l
a                                be 0.4 inches.
: b. Seismic analysis which assumes the shroud cracked to the maximum extent l
$                                c. Confirming seismic analysis using Peach Bottom 2 fbel loads validate the used of the previous analysis for Peach Bottom 2 application.
without requiring the tie rods installed predicts the maximum CSL anchor point to a
1
be 0.4 inches.
$                        2.3       CLS Stress Evaluation I
: c. Confirming seismic analysis using Peach Bottom 2 fbel loads validate the used of the previous analysis for Peach Bottom 2 application.
A CSL structural analysis has been completed for the previous shroud repair work and additional analysis prepared for the previous downcomer repair. The Peach Bottom 3 i
2.3 CLS Stress Evaluation A CSL structural analysis has been completed for the previous shroud repair work and additional analysis prepared for the previous downcomer repair. The Peach Bottom 3 i
analysis accounts for the repair brackets welded to T-box near the vessel inlet nozzle.
analysis accounts for the repair brackets welded to T-box near the vessel inlet nozzle.
1                       The analysis applicable the Peach Bottom 2 downcomer repair are summarized below.
1 The analysis applicable the Peach Bottom 2 downcomer repair are summarized below.
4
: a. Core spray line analysis show acceptability of CSL in the non cracked 4
: a. Core spray line analysis show acceptability of CSL in the non cracked condition.
condition.
i
i
: b. Core spray line analysis shows acceptability assuming 360* through wall crack and with the downcomer repair hardware installed. The analytic model includes a           j pinned joint (no moment carrying ability) to represent the cracked pipe and additional mass to represent the repair hardware.
: b. Core spray line analysis shows acceptability assuming 360* through wall crack and with the downcomer repair hardware installed. The analytic model includes a j
pinned joint (no moment carrying ability) to represent the cracked pipe and additional mass to represent the repair hardware.
i l
i l


_ _ _ _ .    --.                  .. -..      - -        - ._ .      . - . - ,      . - - - . -        ~ _ - .     - - _ - _ . . . .
~ _ -.
                                                                                      ~
PB ECR h[*ki72 pgy g#
PB ECR h[*ki72 pgy g#
GENE 771-010196. REV.0 ATTACHMENT PAGE M CF
~
<                                          Dwo #                                   DRF SO. B13-01800 SHTi         REV             SHEET 1
GENE 771-010196. REV.0 ATTACHMENT PAGE M CF Dwo #
-                  2.4     Summary or nomm                                                                                               1 4
DRF SO. B13-01800 SHTi REV SHEET 1 2.4 Summary or nomm 1
The analyses summarized above show the piping stresses satisfy the requirements of Article NB-3600 of ASME Section III. A summary of the maximum stresses obtained by solution of Subarticle NB-3650 equations is shown in Table 1. Table 1 i                 also includes the allowable stresses for each senice level.
4 The analyses summarized above show the piping stresses satisfy the requirements of Article NB-3600 of ASME Section III. A summary of the maximum stresses obtained by solution of Subarticle NB-3650 equations is shown in Table 1. Table 1 i
:                  The analysis model used to calculate these stresses assumes a 360' through wall
also includes the allowable stresses for each senice level.
]                 crack in one downcomer and no cracks in the other downcomer. With the
The analysis model used to calculate these stresses assumes a 360' through wall
.                  exception of the thermal case, the higher stresses are found in the uncracked branch of the CSL. A cracked pipe section is unable to carry a moment and helps reduce the bending stresses. Cracks assumed in both branches of the CSL is not expected to increase the stresses in either branch.
]
The main contribution of the fatigue usage is due to the relative Operating Base Earthquake anchor displacements between the shroud penetration and the RPV                                           .
crack in one downcomer and no cracks in the other downcomer. With the exception of the thermal case, the higher stresses are found in the uncracked branch of the CSL. A cracked pipe section is unable to carry a moment and helps reduce the bending stresses. Cracks assumed in both branches of the CSL is not expected to increase the stresses in either branch.
nozzle (OBED). The value of relative displacement is 1.20' 0-peak. 2.4" peak to                                       j peak. This is the worst displacement condition calculated for 360' through wall cracks in the shroud with the tie rod repair installed. Twenty total cycles are assumed for this load condition.
The main contribution of the fatigue usage is due to the relative Operating Base Earthquake anchor displacements between the shroud penetration and the RPV nozzle (OBED). The value of relative displacement is 1.20' 0-peak. 2.4" peak to j
Table 1 Maximum Stress Summary Pipe Elbows and Components Senice Level                         Calculated Stress Intensity         Allowable Stress (ksi)
peak. This is the worst displacement condition calculated for 360' through wall cracks in the shroud with the tie rod repair installed. Twenty total cycles are assumed for this load condition.
Table 1 Maximum Stress Summary Pipe Elbows and Components Senice Level Calculated Stress Intensity Allowable Stress (ksi)
(ksi)
(ksi)
Normal / Upset (Priman')             10.5                           l 1.5Sm = 25.4 Normal / Upset (Primary +             5.5                               3.0Sm = 50.8 Sec. excluding thermal bending)
Normal / Upset (Priman')
Normal / Upset (Primary +             286.0                               N/A Secondary)
10.5 l 1.5Sm = 25.4 Normal / Upset (Primary +
Service Level C                       10.6                             l 2.25Sm = 38.14         __
5.5 3.0Sm = 50.8 Sec. excluding thermal bending)
Service Level D                       13.9                           l 3.0Sm = 50.8 Max. Cumulative Usage                 0.71                             l1.0 Thermal Exo. (Ea 12)               l 21.4                             13.0Sm = 50.8}}
Normal / Upset (Primary +
286.0 N/A Secondary)
Service Level C 10.6 l 2.25Sm = 38.14 Service Level D 13.9 l 3.0Sm = 50.8 Max. Cumulative Usage 0.71 l1.0 Thermal Exo. (Ea 12) l 21.4 13.0Sm = 50.8}}

Latest revision as of 12:16, 12 December 2024

Core Spray Line Downcomer Repair Seismic Rept Summary for Peach Bottom Atomic Power Station,Unit 2,Mod P00335
ML20129A430
Person / Time
Site: Peach Bottom 
Issue date: 01/08/1996
From: Gleason T
GENERAL ELECTRIC CO.
To:
Shared Package
ML20129A406 List:
References
GENE-771-01-019, GENE-771-01-0196-R00, GENE-771-1-19, GENE-771-1-196-R, NUDOCS 9609180235
Download: ML20129A430 (4)


Text

,

t

,0 GENE 77101-0196. REV. O DRF NO. B13-01800 SHEET 1 PB ECR h(-N77 REV ATTACHMENT PAGE ~51 oF 1

Dwo a SHT*

REV

+

CORE SPRAY LINE DOWNCOMER REPAIR SEISMIC REPORT

SUMMARY

for PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 Modificadon P00335 f

Prepared by:

/// Ash-M-Pr.

T. E. Gleason, Principal Engineer Mechanical Design Engineering A O'c-i(,

~

Verified bv:

C. Lung, Consulting EngineerC/

7 Approved by:

D. W. Smith, ProgranrManager 9609180235 960903 DR ADOCK 05000277 p

PDR

- ~.... -~

i a

ca s

t GENE 771-01-0196. REV. O DRF NO. B13-01800 I

SHEET:

P8 ECR N-N/f Rw 1.

INTRODUCTION

  1. ",^'", MENT PAGE M OF o,

ser a _

nu j

1.1 Background

I Peach Bottom Atomic Power Station L' nit 2 has avo Core Spray Lines ( SC L) which l

enter the reactor pressure vessel (RPV) at the 120' and 240 azimuth locations.

The CSL entering at 120' splits at its T-box with the downcomers at 7.5* and at 172.5' locations. The CLS entering at 240* splits at its T-box with the downcomers j

at 187.5' and at 352.5' locations. The weldedjoints in the CSL downcomers near the shroud penetration may be cracked and will require reinforcement if the cracks are found. The reinforcement is required to maintain the pipe alignment and to prevent a crackedjoint for separating. This modification is of a bolted design utilizing clamps for attachment to the CSL.

j i

The same type modification was used on Peach Bottom Atomic Power Station Unit f

3 at the 172.5' downcomer location.- The design and analysis used for the Peach Bottom 3 modification has been reviewed and the results are utilized where applicable.

j 1.2 Scope The analysis covers the CSL from the thermal sleeve at the RPV to the CSL shroud i

penetration including the 90* elbow, but excluding the penetration sleeve. Two 9

different cases were evaluated, one assuming the downcomer integrity was intact and the other assuming the propagation of the crack to 360 degrees which a!! owed i

rotational freedom at the crack location.

I This report transmits the results of the CSL design stress analysis which assesses l

the effects of the proposed modification on the CSL. The purpose of the analysis is to demonstrate the seismic structural adequacy of the CSL with the downcomer j

modification installed at Peach Bottom Unit 2.. The analysis is contained in

}

Design Record Files (DRF) B13-01800, B13-01732 and B11-00642.

2.

CORE SPRAY LINE EVALUATION j

2.1 Assumptions The following assumptions are used in the CSL structural analysis.

1.

The CSL downcomer sleeve / spigot assembly near the shroud penetration is assumed to have one or more 360* through wall cracks. No credit is taken for any 9

ir

PB ECR h[4h 72 Rgv h ATTACHMENT PAGE M OF GEN E-771 01 0196. REV. O Dwo,

DRF SO. B13-01800 l

SHT #

REV SHEET 3

(

remaining ligament at the postulated crack location. Cracks may exist at one, two, three or all four downcomers.

]

2.

The seismic analysis shall take into account both partial and complete l

cracking of the shroud welds. The degree of cracking assumed shall be the l

maximum crack length permitted without requiring shroud repair and complete j

)

cracking with the tie rod repair installed.

I 2.2 Seismic Evaluation The seismic evaluation for the Peach Bottom 2 downcomer repair utilizes analyses from the shroud repair work and from previous downcomer repair work.. The applicable i

l analysis are summarized below and can be found in DRF's B13-01800, B13-01732 and B1100649 f

l

a. The shroud repair seismic analysis predicts 1.2 inches for the maximum CLS l

anchor point displacements. The analysis assumes the shroud with 360' through j

wall cracks and with the tie rod repair installed.

l

b. Seismic analysis which assumes the shroud cracked to the maximum extent l

without requiring the tie rods installed predicts the maximum CSL anchor point to a

be 0.4 inches.

c. Confirming seismic analysis using Peach Bottom 2 fbel loads validate the used of the previous analysis for Peach Bottom 2 application.

2.3 CLS Stress Evaluation A CSL structural analysis has been completed for the previous shroud repair work and additional analysis prepared for the previous downcomer repair. The Peach Bottom 3 i

analysis accounts for the repair brackets welded to T-box near the vessel inlet nozzle.

1 The analysis applicable the Peach Bottom 2 downcomer repair are summarized below.

a. Core spray line analysis show acceptability of CSL in the non cracked 4

condition.

i

b. Core spray line analysis shows acceptability assuming 360* through wall crack and with the downcomer repair hardware installed. The analytic model includes a j

pinned joint (no moment carrying ability) to represent the cracked pipe and additional mass to represent the repair hardware.

i l

~ _ -.

PB ECR h[*ki72 pgy g#

~

GENE 771-010196. REV.0 ATTACHMENT PAGE M CF Dwo #

DRF SO. B13-01800 SHTi REV SHEET 1 2.4 Summary or nomm 1

4 The analyses summarized above show the piping stresses satisfy the requirements of Article NB-3600 of ASME Section III. A summary of the maximum stresses obtained by solution of Subarticle NB-3650 equations is shown in Table 1. Table 1 i

also includes the allowable stresses for each senice level.

The analysis model used to calculate these stresses assumes a 360' through wall

]

crack in one downcomer and no cracks in the other downcomer. With the exception of the thermal case, the higher stresses are found in the uncracked branch of the CSL. A cracked pipe section is unable to carry a moment and helps reduce the bending stresses. Cracks assumed in both branches of the CSL is not expected to increase the stresses in either branch.

The main contribution of the fatigue usage is due to the relative Operating Base Earthquake anchor displacements between the shroud penetration and the RPV nozzle (OBED). The value of relative displacement is 1.20' 0-peak. 2.4" peak to j

peak. This is the worst displacement condition calculated for 360' through wall cracks in the shroud with the tie rod repair installed. Twenty total cycles are assumed for this load condition.

Table 1 Maximum Stress Summary Pipe Elbows and Components Senice Level Calculated Stress Intensity Allowable Stress (ksi)

(ksi)

Normal / Upset (Priman')

10.5 l 1.5Sm = 25.4 Normal / Upset (Primary +

5.5 3.0Sm = 50.8 Sec. excluding thermal bending)

Normal / Upset (Primary +

286.0 N/A Secondary)

Service Level C 10.6 l 2.25Sm = 38.14 Service Level D 13.9 l 3.0Sm = 50.8 Max. Cumulative Usage 0.71 l1.0 Thermal Exo. (Ea 12) l 21.4 13.0Sm = 50.8