ML18044A651
| ML18044A651 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 03/11/1980 |
| From: | Frost S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8003170381 | |
| Download: ML18044A651 (12) | |
Text
....
I consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 March 11, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LIC.ENSE DPR PALISADES PLANT - SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING SYSTEM (STUB-_IN BRANCH CONNECTIONS)
Consumers Power Company was requested on March 3, 1980, by l1r Keith Whitman o.f the NRC, to answer the following questions in regard to stub-in branch.connec-tions at the Palisades Plant:
Item 1 How many "stubbed-in" joints exist and how many are over stressed?
Response to Item i The Palisades piping class sheets show that for the three piping classifica-tions, RB, HC and JB, stub-in branches were allo~ed in the fabrication.
All of these stub-in branch connections were used in low-temperature, low-pressure
- piping. systems.
A total of 45 piping stress systems would fall under the three classifications
_as noted above.
These piping systems contain 249 stub-in branches.
Of these, 160 are in the piping systems which.have been computer analyzed.
The status of all of the stub-in branch connections is as follows:
- 13 stress systems have no stub-in branch connections.
- 24 stress systems either meet the interim criteria or will meet it before th"! plz.nt start-up.
- 7 stress systems were not analyzed in detail; been proposed, where required, as a result of judgment.
however, modifications have
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conservative engineering
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- 1 stress system (03387), Service Water Return From Air Coolers, has two stub-in branch connections where the calculated stresses do not meet the stress allowables as defined for the interim criteria.
The calculated stresses exceed the Operating Basis Earthquake (OBE) allowables by 13.6% and 52%.
For the Safe Shutdown Earthquake (SSE) condition, the allowables are exceeded by 11.4% and 36.6%.
Item 2 In the reanalysis of "stubbed-in" joints, what* equations or code versions are involved in th.is problem?
Response to Item 2 The B31.1 Power Piping Co.de version was employed to indicate whether or not the piping stress system meets the FSAR (1967 Code) or the Interim Criteria
(.1973 Code).
There are presently seven stress systems on which detailed computer analysis is unavailable.
Enginee~ing judgment was utilized to evaluate potential hanger modifications, additions or deletions.
The location of the stub-in branch connections in these stress systems is known.
Based upon the analysis of other systems, the stress intensification factors for these connections can be anticipated.
Therefore, a nominal bending stress guideline for incorpora-tion of the appropriate stress intensification to meet the interim criteria has been part of the engineering judgment evaluation.
Four of the seven stress systems are being subjected to support modifications to meet the interim criteria.
Item 3a What functional piping systems are involved in this problem?
Response to Item 3a There are 45 piping stress systems which are identified in the attachment under the "Piping System Branch Stub-Ins Allowed by Class Sheets" column.
Item 3b What is the seismic category of each piping system?
Response to Item 3b All of the piping stress systems are seismic Category I.
Item 3c What is the size and thickness of each pipe?
Response to Item 3c The size and thickness of the pipes are identified in the attachment only for the piping that has an identified overstressed stub-in connection.
Item 3d What is the operating temperature of each piping system?
Response to Item 3d This information is located in the "Pipe Class and Operating Temperature &
Pressure" column of the attachment.
Item 3e What are the stress values at each junction point, and what are the allowable stress at each joint?
Response to Item 3e The stress values for each junction point and the stress at each joint are displayed in the attachment for pipes with overstressed stub-in connections.
Item 4 3
When will we complete our evaluation of those unanalyzed pipe stress problems, and when will we complete reanalysis of all pipe stress problems?
Response to Item 4 At the present time, a schedule for the completion of the evaluation is not available.
All appropriate information will be sent to the NRC when this evaluation is completed.
Steven R Frost Palisades Nuclear Licensing Engineer CC JGKeppler, USNRC (9 Pages)
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oG Remaining Stub-ins Allowable CJ...c c
Stress l'iping System Branch c
1-4
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Calculated Stress Stress QJ QJ Prob.
Stub-ins Allowed By Vl...,
1-4
.D Q) (/)
etc.
Interim Class Sheets Vl CQ
- J e
Q) µ.
No.
CQ 1-4...,
Q)
- J Vl
- c --
CQ STATUS/COrn1ENTS
.-f CJ CQ 1-4 z c e *..-<
u
- 0. 1-4 1-4 1-4 biameter/ Wr-d !~lit + "'eight +
0 Q)
Vl
.-f I Q) 1-4 Q)
Q)
- 0. r.r:
<I:.D
.D Q)...,
fall Pres:;ure Pressure OHE/SSE
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..., :i e..,.....
- ..-< c Q) 1-4 0
- J c 1-4
<1l 1--
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ZHU 03311 Component Cooling llB-24 8
8 Modifications in Progress Hater System ll5°F to t!eet FSAR Criteria 135 PSI 03312 Component Cooling rn-24 7
7 Modifications in Progress-System 90°F to Meet Interim Criteria 102 PSI 03313 Component C6oling Pur.1p lB-24 3
3 FSAR Meets.Criteria As Is (discharge) and Supply tl.15°F to Component Cooling
- n. 35 PSI Heat Exchangers 03314 Component Cooling from HB-24 No Detailed Analysis Per-9 HPSI, Containment Spray 115°F formed, however, *5 Supports and LPSI Pumps 135 PSI 10 to be Modified/ Added Based Upon the Review.
03315 Component Cooling to HB-24 13 No Detailed Analysis liPSI, Containment Spray 115°F Performed and LPSI Pumps 135 PSI U\\ttaclunent 1 I
Page : Of 9
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Remaining Stub-ins Allowable
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Stress I' i ping System Branch i::
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Calculated Stress Stress Allowed
- rl (lJ (lJ Prob.
St11h-ins By (J)._..
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(J) ro E
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etc.
Interim No.
Class Sheets ro QJ
- l (J)
- c........ ro STATUS/COMMENTS (lJ ro z
c::
E *rl u
P-
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'"-' *rl '"-'
Diameter/ Je1ght + ~eight +
0 (lJ (J)
I (lJ (lJ QBE/SSE (lJ P-(J)
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,.CJ (lJ fall Pressure Pressure P- "O E QJ
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<lJ 0
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!thickness I+ ORE tt-SSE 11.* ro r< i:i.
b V'l ZHU 03316 Service Water from HB-23 6
6 Modifications in Progress Con,ponent Cooling Heat 75°F Exchangers 65 PSI to Meet Interim Criteria 03317 Service Water Supply to HB-23 10 No Detailed Analysis Component Cooling 75°F Performed, however, 2 -
Heat Exchangers 65 PSI Supports Were Added 03318 Critical Service Water HB-23 20 No Analysis Performed From Service Water 75°F Pump 65 PSI 03322 Safety Injection, HC-23 2
2 Modifications in Progress~
Containment Spray and 75°F Satisfy Interim Criteria Shutdown Cooling System 65 PSI 03323 Boric Acid System HC-20 &
22
_No Detailed Analysis Performed HC-7 however, 6 Supports to be 120°F 100 PSI Modified/Added Attaclunent 1 PCl6e 2 of <
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'Stress
- Prob.
No.
03324 0332-S l'ipin1*. Syst1:m Branch St uh-ins Al lowed By Class Sheets Fuel Pool Cooling Pumps (Suction) from SIRW Tank Fuel Pool Cooling Pumps (discharge) to Spent Fuel Pool Heat Exchangers
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HC-4 125°F 125 PSI HC-4 125°F 125 PSI Q)
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ZHU 7
19 Remaining Stub-ins Calculated Stress etc.
HameterJ1*~P.ip,ht + ~Jeight +
Jail Pressure Pressure hicknes~~ OHE
~ SSE Allowable Stress Interim OBE/SSE
~ - - -
r-STATUS/COMMENTS Modifications in Progress to Meet Interim Criteiia Modifications in Progress to Meet Interim Criteria
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1 l
l l 03326 i
SIRW Heat Exchangers to SIRW Tank i 03327
.Hake-Up Water Piping Supply 03328 Make-Up Water to Conden-
. rate Water Tank (T-2) lAttaclunent l HC-23 180°F 150 PSI HCD-901 HC-9 100°F 75 PSI HCD-901 HC-9 100°F 75 PSI 0
12 0
Page 3 < f 9 No Detailed Analy~is Per-formed, however, 3 Suppor9 to be Modified/Added
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Piping System Branch Stub-ins Allowed By Class Sheets
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Remaining Stub-ins Calculated Stress etc.
li aml't er /~.JP 1>:1ir +
h~ i ght +
J;t 11 Pr,*s:~11rl' Pressure
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St rt*ss Interim OBE/SSI-:
STATll s / C< >~lrlENTs
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3330 3131
- 3 332
,3333 3334 Receiver Tank l'ump (Suction)
Miscellaneous \\.Jaste System to Condensate Stornge Tank Condensate r1ake-Up and Reject from Condensate Storilge Tnnk Auxili;iry Fccdwater from Condensate Stora~e Tank Make-Up \\.later Supply Piping to Condensate Storage Tank Attachment l llC-2 180°F 50 PSI llB-26 l00°F 75 PSI llB-26
1 Meets Interim Criteria 0
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0 0
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Page L of 9
):>tress
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Piping System Branch i::
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Class Sheets rc.....,
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>3 335 Pr i nw r y System Make-Up 111.-ll 0
Tr'ansfer Pump (Suction) 100°F 150 PSI
)3338 Waste Gas Surge Tank llB-20 l
1 Piping 120°F 100 PSI
)])39
\\fas te Cn s Surge Tank llH-1 l
1 Piping Supply 100°F 100 PSI
)3340 Containment Drain Piping llC-12 2 PSI 104° F 1
1
)3343 Radioactive \\~as te llC-2 1
1 Treatment Piping 180°F I
50 PSI Page 5 Remaini1:ig Stub-ins Calculated Stress etc.
hamt*t£'r/11 41"1)',ht + foight +
-!:! 11 l'rl*s:a1r~ l'rPssure hick11t'ssk-Cll\\E f+ SSE I- - - -
of 9
- \\ I l nw :1 b l l' St rl*ss IntL*rim OttE/SSE
. s TATU s I rn~1~11-::-..:rs Meets FSJ\\R Criteria Meets FSAR Criteria Meets FSAR Criteria Meets Interim Criteria With 5 MOdifications e
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Remaining Stub-ins
,\\) low;1hll*
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c Stress Piping System Branch c
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Calculated Stress Strt.'SS Q,
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Prob.
Stub-ins Allowed By
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etc.
Interim.
No.
Class Sheets
<t Cl
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<t STATUS/ cm1mxrs llJ co h
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rt SSE 0..
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()]3115 Drain Tank Pump llC-1 2
2 Met.~ts Interim Criteria (Suction) 180"F With 2 Modifications*
ATM-PSI 03347 Deg.1sifier Pump HC-2 0
0 (Discharge) 180°F 50 PSI 01351 R.~ceiver Tank Pump HC-2 1
1 Meets FSAR Criteria (Suction) 180°F 50 PSI 03353 Containment Purge JB-16 2
No Detailed Analysis e Pei-formed
- 03351, Containment Purge JB-16 0
I Page 6 [)f 9 I
i
Stress Prob.
No.
))355
)3356
~l3369 03370 03377 Piping System Branch Stub-ins Allowed By Class Sheets Containment Purge A11xili<:iry Fccdwater Pump (Suction)
Containment Spray Containment Spray Charging Pumps (Suction)
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c:
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v:
re
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re I.,; c..,,_,
C ru f.h CJ c.. Vl c..-oecv
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<ll P:.rer~
JB-16 HH-35 100°F 75 PSI HC-44 llC-44 HC-16 120°F 10 PSI I
re.L 0
I-- v.
0 2
7 7
3 2
- 7 7
3 lh*m:llning St11h-ins Cn I culatL*d St rt.>ss etc.
li;1ml".tt>r/ 4i>11*.ltt + Jcight +
Ja 11 l'r.... s:atrl* Pressure 1tliick1ll~sstt 01\\[
i+ SSE
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Page 7 cf 9
,\\I 1 ow:1 bl l*
St rt.>s,;
lntcrim OBE/SSE
. ~
S'J'i\\TLIS/ cm1m:~:Ts Meets FSAR Criteria e*
Meets FSAR with Modifications*
Meets FSA~ Criteria
t-........:;
gi>
l<C'maining* Stuh-in,:;
i\\llowabl.:*
Stress
- Piping System Branch c:
- i ~
Calculated Stress St ri:*ss Cl.
Cl.
~ t Prob.
Stub-ins Allowed By CJ,...,,_
.c.
<lJ (/)
etc.
Interim er.
rc
- l E
<lJ µ:..
No.
Class Sheets re 1-....,
QJ
- i v.
- ?!!-ell STATUS/COMMENTS QJ rc,_
~ c:
a *r-1 Wt> 11'.li r + Jc i~ht +
l.) c..,_
- l
- rt H *r-1 H
)i a meter J c
CJ Vl I
<lJ H
<lJ Prt*s:;url' OHE/SSF.
~ l' CJ
- 0. Vl re.c.
p
<lJ +:>
fa I l Pressure c:... "O r=
QJ
§ +:> *r-1
...... c:
QJ,_
0...,
S:: H Ith i ck1wss+ OHE rt SSE 0...
Ill...... 0...
...... lJ)
ZHU
")3 381 Spent Fuel Pool lie at llC-4 1
1 FSAR Criteria Meets 125°.F Exc:hangers to Cross-Tie Piping 125 PSI I
llB-24 90 °,..
102 PSI
~
)3182 Ret11rn Piping from 1111-23 4
4 Meets FSAR Criteria Cooler VllX-3 90°F 65 PSI e
13383 Supply Piping to Air llB-23 4
4 Meets FSAR Criteria Cooler VllX-3 75°F 65 PSI
)3384 Return Piping from 4
4 Meets FSAR Criteria e
Air Cooler VllX-4 HB-23 90°F 65 PSI
-,3385.
Supply Piping to Air HR-23 8
8 Meets FSAR Criteria Cooler VllX-4 75°F 65 PSI Page 8 cf 9
Stress Prob.
No.
I 1) )Hf1 03187 03388 03389 03390 Piping System Branch Stub-ins Allowed By Class Sheets Supply Piping to Contnlnment Air Coolers Return Piping from Cont<1 inment Air Coolers
- spent Fuel Pool Cooling Reactor Cavity Drain Recirculation Piping Piping to SIRW Tank Attachment l llB-23 75°F 65 PSI HB-23 90°F 65 PSI HC-4 125°F 125 PSI HC-4 125°F 125 PSI HC-1 180°F 15 PSI I
rt.c c....
f--
If.
30 0
0 0
Remaining Stub-ins Allowable Calculated Stress Stress etc.
Interim liamt*[l'r/ ~1'1)',hr +,'eight +
fa 11 l'res:;ure Pressure OBE/SSE Ith i cknt>;;~i+ 01\\E i+ SSE 30 10.75 x 20,480
.40, llO 18,ooo; 28
- 365 6.625 x 27,492 0.28 49, 2ll 36,000 r-Page 9 Pf 9 STATUS/COMMENTS Meets Interim with 2 Modifications I * *
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