ML17317B258
| ML17317B258 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/08/1979 |
| From: | Maloney G INDIANA MICHIGAN POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| AEP:NRC:00182, AEP:NRC:182, NUDOCS 7906140500 | |
| Download: ML17317B258 (5) | |
Text
INDIANA fi MICHIGAN POWER COMPANY P. O. BOX 18 Bo WL IN G G R E EH STATION HEW YORK, N. Y, 10004 May 8, 1979 AEP: NRC:00182 D.
C.
Cook Nuclear Plant Units 1
8 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 IE Bulletin No. 79-04 Incorrect Weights of Swing Check Valves Manufactured by VELAN Engineering Company Mr. J.
G. Keppler, Regional Director U.S. Nuclear Regulatory Commission Office of the Inspection and Enforcement Region III 799 Roosevelt Road Glen Ellyn, Il 60137
Dear Mr. Keppler:
This letter and its attachments constitute our response to I.E.
Bulletin No. 79-04, "Incorrect Weights of Swing Check Valves Manu-factured by Velan Engineering Company."
An extension was granted to our Mr. Castresana by your Mr. Hartster on May 1, 1979 to respond to the bulletin by May 7, 1979.
The responses are provided to the corresponding items as cited in the bulletin.
Item 1:
All SeismicClass I piping systems (or portions thereof) which contain Velan swing check valves (diameters of 3", 4" or 6") are tabulated on Attachment "A".
Mr. J.
G. Keppler, Regional Director May 8, 1979 AEP:NRC:00182 Item 2:
The correct valve weight (450 lbs) was used in the reanalysis of the systems containing the 6" Velan swing check valves.
Westinghouse notified us on March 19, 1979 of the correct weight of the 6" Velan check valves.
I.E.
Bulletin No. 79-04, dated March 30, 1979, notified us of the estimated maximum weights for the 3" and 4" Velan check valves.
Item 3:
Those portions of the systems containing the 3", 4" and 6" Velan check valves listed on Attachment "A" were reviewed.
This was accomplished by examining the piping layouts and considering the following items with regard to the increased weights:
a.
The locations of the valves with respect to the points of highest com-bined stress (seismic plus dead weight plus pressure).
b.
The values of the combined stresses for OBE and DBE.
c.
The stress margin available.
d.
The locations of pipe supports.
e.
The support load margin available.
The 6" valves have the greatest weight difference.
Considering the stress margins available, we felt assured that these systems would not be over-stressed under seismic loading; nevertheless, they were reanalyzed and none of the lines were overstressed.
Attachment A shows the results of the re-analysis for the 6" safety injection lines.
Attachment B shows the increase in the cold leg safety injection lines and their supports due to the in-creased valve weights and that in all cases the increases in the maximum combined stresses amounted to less than five percent, and of the support loads to less than 30Ã, even though the weight of the valve was doubled.
Item 4:
Considering the slight increase in valve weights for the 3" and 4" piping
- systems, and the reanalysis results of the 6" lines, we conclude that the stress and support load margins available to absorb the additional weights of the valves are more than adequate.
We therefore conclude that these systems and supports are not overstressed and that the reanalysis of these systems is not required and that, consequently, no modifications to the piping systems or their supports listed in Attachment "A" are necessary
Mr. J.G. Keppler, Regio a
Director AEP:NRC:00182 May 8, 1979 Item 5:
The seismic analyses for the piping systems shown in Attachments "A" 8 "B" performed by E.D.S. Nuclear, were done using the computer code PISOL-IA that utilizes the response spectrum modal analysis method.
Both spatial and intermodal responses were combined without regard to sign.
The analyses of the systems in Attachment "A" performed by Westinghouse, were done using an updated version of the WESTDYN code which combines the i ntramodal responses through absolute summation.
The WESTDYN code was documented to the NRC in WCAP-8522, Revision No.
1 "Documentation of Selected Westinghouse Structural Analysis Computer Codes,"
May 1977.
As can be seen from our submittal, the additional weight of the Velan check valves will not adversely affect the capability of the Donald C.
Cook Nuclear Plant to withstand a seismic event.
Very truly yours,
. Malon Vice Presid n
cc:
R.
C. Callen G. Charnoff D. V. Shaller - Bridgman R.
W. Jurgensen
ATTACIOIENT A V T H l
A tllNB VELAN CHECK VALVES
- Eel OESCRIPTICtl LEIGHT OBE R
P ALLO'e>ABLE OBE R
r P
OBE STRESS I'ARe I
pn CNT)ItlEO OBE TÃ S
~ R ALLOMABLE OBE TR S OBE STRESS (PSI)
I'l" Il mXIISNI AVAILABLE llIE sw'RT Au o'>JABLE su>?CRT VA V r
OA A
r (A IHNCNT
>Y ANALYSIS I'AINIICNT SPRAY ANA y R
IAIH.'lcnT SPARY
~NA C
IAIHNCNT SPRAY AHALYsls
'AIR>>Cte T SPRAT ANALYSIS 10>769 20,000 9>231 18,214 135¹ 100¹ 14,170 19,86o 5,690 24,52o 10,/69 20,000 9>231 18,214 410 860 6oo w4 30>000 29>790 3o,ooo 10,769 20,000 9>231 18,214 30,000 8
4 0
8 Fm 100¹ 60¹ 12 e 219 17,16o 4,g41 20,536 25,74o 5,815 17,16o 11>345 7>043 25,74o 60¹ 10,031 17,16o 2,749 15>936 25,74o 11,786 5> 270 11 >78'I
? 0 11 >7d1 4
5>204 9,8o4 18,697 4n 3>e 3 le 3>e 3> I 1 C5-34 2-CS-84 1-cs-34
?-cs-JI 1-05-32 s "5-8 1-05-95 cs-8 1-CS-96 2-C5-120 1-CS-96
~~1 1 CS-92 2-05-121 1-CS-93 1-CS-121 1378 Las.
137o 1590 1590 3065 350 1714 1714 1591 1591 1591 1591 340 340 3I>O 2681 I,ss.
2681 2M1 2681 8ooo 1130 6ooo 6ooo 4ooo 4ooo 4ooo 4coo 1000 1000 1000 1000 1303 1303 1091 1091 4935 780 4286 4286 2409 2409 2409
- TY IN~CCT>on
- e. ALYc I
- TY INJCCI ION ANALY<\\S
- TY InyCCT>onr IA'ZCO I>Y
- S'TIN, ess
- TY I le CCT Ion 4'5o¹ 4rmp 4~1 et50>T 9>225 45ON 9>73R 4500'0>763 450'0,050 135¹ 350¹ 6 >905 135¹ 3 0¹ 6 905 1o,541 10 541 19>200 19>200 19,200 3,635 3,o36 9>9>4 9,462 8>437 9>150 21 ~ 150 21 >150 13,008 1'>,012 16,o32 14,555 31,720 31,720 e 8.4 28,;o 2),800 2.>.300 10>570 10,5l>0 15 e792 14,788 12,718 14,144 4>e 4>e 6>e oee 5II Ge ~
1-5 I-19 S-1 SI-74 sl-64
'420 Lss ~
3560 42o 1810 Lss 15>)5 O)00 4440 1810 1605 P
4:>40 1SI 26 1-5 I-22 TNERE ARKNO PIPC SUPPORtS ON TTIEST LI>4ES 1-Sl-27
'Tel S
~ PV Vgi v5 ¹ 450¹ 12,343 9,364 450¹ 10,303 450>JI 11,oo6 19>200 19>200
- 19. 200 19>200 6,857 9,836 8,897 3>194 14,738 11>075 12,123 13>1'>5 23,800 2oescr>
28,8oo 17 725 16,657 15,655 6>e Gee 6>e En 1-51-63 1-5 I-Ge) 1-SI 70 1-51-/1 897 845 3e620 3,620 19, 18 2.723 2,674 2 >775
,0>!Sllecs STRcsscs ncf Less AQJI>STco VALYc etc l sntse
ATTACIPKlrT REAHALYSIS RESULTS FOR 6" S.I.
LINES SAFETY ItrJECT ICrt SYSTEN TO COLD laGS 1tETRIc trrtsER VALV ICHT m PPM VIXII&I I"AXI t%I1 C011IINEO COIBIIIED O.B.E.
O.B.E'TRESS (as')
STRESS (asr) e AXIIXt'I CCr B I IIEO O.BaE.
STRESS (asl)
YAXII'XX1 CCIB It(ED O.B.E STRESS (as')
VALVE '~~104 =
~~ Ct'At:SE Itl OoBoEo STRESS (asl)
Jf CI1AIICE Itl OoB E ~
STRESS (as')
ALLOJABLE O.B oE ~
STRESS (as')
ALLO:NBLE O.B.E STRESS (ast) 225sr 450sr vALvE vALvE SH>PCQT CA I; ctrA:ICE Irt SLPPORT LOAD ALLIABLE SIPPORT LOAD 1-S1-68 11>753 14,078 12,343 14 '38
+ 4.98
+ 4,7 19o200 28,800 890 1115 25."4 20,300 1-Sl-69 9, 165 10,834 11 o075
+ 2 17
+ 2+22 19,200 28,o00 897 1122 25.1 3,620 1-Sl-70 10 018 10e303 12e123
+ 2.84
+ 2.92 19,200 28,800 946 1171 23.7 3,620 1-51-71 10,744 12,858 11 ~006 13,145
+ 2.44 2e23
- 19) 200 28,800 845 1070 26.6 3,620