L-98-193, Calculation EA-C-PAL-98-1939-01, Evaluation of Corrosion on Studs Between Casing & Cover of Pump P-50A,Ref C-PAL-98- 1939
| ML20198H030 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/19/1998 |
| From: | Gupta R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18066A353 | List: |
| References | |
| EA-C-PAL-98-193, EA-C-PAL-98-1939-01, EA-C-PAL-98-1939-1, NUDOCS 9812290222 | |
| Download: ML20198H030 (25) | |
Text
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M Nun comumme amara-amm g pesangsg PALISADES NUCLEAR PLANT EA C PAL 981939 01
- 0: ::En:t:0."J:"J."::: 00"En :::::T Total Number of SheetsIO Title Evaluation of Corrosion on studs between casina and cover of Pumo P 50A. Reference C PAL 981939 INITIATION AND REVIEW Calculation Status Preliminary Pending Final Superseded O
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---,M PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET onne 9
one #n 1
2 1.0 Obiective Reference / Comment 3
4 The objective of this EA is to evaluate the acceptability of 5
tt.e Primary Coolant Pump P-50A joint between the casing and 6
the cover with local degradation of two of the 16 studs.
Each
'7 stud is 4.58" diameter.
C-PAL-98-1067 documented the 8
condition of these studs during REF01'T 98 and EA-C-PAL 9 1067-01 accepted the joint. as is.
C-PAL-98-1939 documents 10 the corroded condition during the forced outage in 12/98.
11 12 2.0
References:
13 14 2.1 ASME B&PV Code Section XI. 1986 Edition.
15
2.2 Drawings
M1-EA-5. M1-EA-5001, M1-EA-2006 16 2.3 Byron Jackson Tech manual. Vendor file.
17 2.4 ASME BB&PV Code Section III 1965 Edition.
18 2.5 Palisades FSAR, Rev. 20. Table 5.2-3, Sheet 1 of 18 19 2.6 EPRI Report (EPRI TR-104213s). Bolted Joint -
20 Maintenance and Application Guide. December 1995 21 2.7 Telecon Record with Flow Serve dated 12/18/98 22 2.8 Fax dated 12/18/98 from Flow Serve.
23 24 3.0 Desian Criteria:
25 26 References 2.4 and 2.5 provide the design criteria.
27 28 4.0 Desian Inout:
29 30 4.1 During the forced outage in December 1998, the P-50A 31 pump casing to cover joint was inspecteo again to 32 assess the condition of the studs and document the 33 condition of local degradation of the same two studs.
34 The stud measurements show 0.2" and 0.11" additional 35 corrosion of the studs.
The corrosion is because of
, 36 boric acid mist leaking from a cresumably degraded l 37 casing to cover gasket in the v.a. This adverse i 38 condition is documented by C.P4 i3 1939.
The 39 corroded area of the stud compr' -s approximately 1/3 40 of the stud circumference as ccn*:rmed by the 41 machinist who measured the stud diameter.
42 l
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PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET naat 1
pau en 1
4.2 The Primary Cooling Pump P-50A is one of the four 2
pumps to circulate water through the reactor.
The Re M ence/Cament 3
joint between the casing and cover of the pump is
'4 characterized by 16. 4.58" diameter studs which
- 5 reflect a measure of redundancy in bolt reactions. The l 6 studs are made of A-193. Grade 87 material with flash 7
chrome plate and phosphate coating on the tap end.
8 The nut material is A-194 Class 2H.
The casing and 9
cover material is A-351 Graae CF8M.
10 11 4.3 The original stud dimensier.s are given in Reference l 12 2.2.
Per Reference 2.3, the applied preload to the
' 13 stud is 25.000 psi. This stress level is about 1/3 of
- 14 the stud's yield strength of 75 Ksi per Reference 2.4
15 and stud's deformation during preload is well in the 1
16 elastic range.
17 18 The stud has upset threaded ends. 4.73" in diameter.
19 l20 4.4 The degraded stud configurations are depicted in 21 of this EA.
The Attachment 1 shows the 22 measurements taken by the machinist included in the
, 23 condition report. C-PAL-98-1939. Only two studs have
' 24 visible degradation.
There is no visual evidence that i 25 the casing. cover or the chrome plated threads are l 26 degraded.
' 27 28 4.5 shows the measurements of the same studs i
- 29 taken during REFOUT 98 and included in condition
.30 report C-PAL-98-1067.
31 32
5.0 Assumntions
33
, 34 Major:
None
' 35 Minor:
The stud OD is assumed to be corroded to as shown on 36 page 10.
One stud measures 3.81 inches, the other 37 measures 3.77 inches.
3.77 inch is used as the i 38 corroded dimension of both studs. to be conservative.
, 39 40 C-PAL-98-1067 documented corroded stud diameters as 41 3.97" and 3.92" respectively. For calculating 42 corrosion since Refout 98. 3.97" corroded diameter is 43 used conservatively.
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--M PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET chnnt a
pov #n i 1 The corrosion fro'
/ until Refout 99 is considered 2
to be linear witt. t.ime.
m n s m ent 3
l4 The height extent of the corrosion is taken to be 5
uniform over a 1 inch length.
6
- 7 The two studs adjacent to the studs being evaluated 8
have no visual signs of degradation as evidenced by 9
comparision of the Attachments 1 and 2.
10 11 6.0 Analysis 12 13 The ASME Code stipulates that the bolted joint be designed for 14 preload, operating pressure and any differential thermal 15 expanion stress.
The code does not specify how these stresses 16 are to be combined.
17 18 During discussions with Byron Jackson (Flow Serve) on 12/18, 19 we were informed that if a Finite Element Analysis model is 20 performed for the pump casing, stud, and cover to include the 21 effects of preload and system pressure loads, the pressure 22 loads will not have any significant impact on the calculated 23 bolt (stud) stresses.
24 25 For this particular very stiff configuration, external load.s 26 from dead weight, seismic and restraint of free end expansion, 27 are not controlling.
28 29 Normally, for connectic/1s using bolts or studs, the critical 30 design consideration is the preload. The applied preload is 31 intended to be greater than the operating load on the studs.
32 This ensures adequate compression of the joint and no leakage.
33 As the bolt or stud material is removed by corrosion, the 34 strain energy and thus the preload force is reduced.
- However, 35 the reduction can be accepted if sufficient preload force is 36 maintained.
Preload is a displacement-dependent load.
With a 37 smaller stud cross section, the stiffness of the stud is
, 38 reduced and the stress in the stud is increased.
39 l 40 Reference 2.6providesguidancetocalculatea"f" factor i 41 which depends on the relative stiffness of the fastener and
, 42 the joint members.
This ~f~ factor is applied to the 43 calculated pressure stress and the resultant factored stress 44 is combined with the preload stress in the bolt, to compare to 45 an allowable bolt stress
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Power auussan"ressass, PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET chant __n ocu an 1
During the 6 months and 10 days of operation since startup 2
from Refout 98, the reduction due to corrosion on the same Mmn K ent 3
stud is 3.97"-3.77" or 0.2" Assuming the plant will run for 4
another 10 months until Refout 99, the stud may corrode 5
further, although actions to mitigate the spray on the studs 6
have been taken.
7 8
Anticipated corrosion = 0.20"*10mo./6.33mo. - 0.32" 9
10 Anticipated corroded stud diameter is 3.77"-0.32" - 3.45" 11 12 Although the second stud has corroded less than the first, it 13 will also be conservatively assumed to corrode to 3.45" 14 between now and Refout 99.
15 16 The measurement of the stud diameters taken for C-PAL-98-1939 17 do not show any degradation on the studs adjacent to these 18 studs.
Therefore, the joint will be evaluated considering 19 only two studs being degraded.
20 21 Figure 1 on page 10 is a conservatively postulated cross 22 section of the degraded stud used in this EA to analyze the 23 impact of corrosion of the two studs on the pump joint.
24 25 PRELOAD STRESS 26 27 View AA on page 10 shows the stud configuration used to 28 calculate the effective stiffness of the corroded stud with 29 respect to the non-corroded stud.
30 31 Preload Force. F = K x a 32 33 Where.
6 - stud elongation in inches 34 K = Stiffness - EA/L 35 E = modulus of elasticity 36 L = length 37 A = Cross-section Area 38
-39 The corroded stud cross section is considered as shown on page
' 40 10 which is a half circle and half ellipse.
Also, there is a
! 41 0.5" diameter hole in the stud.
( 42
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For a stepped member. the stiffness is calculated as two 2
series connected springs. The effective stiffness Ke is given Reference /Coment 3
by 1
4 5
1/Ke -1/K1 + 1/K2 6
7 K1 = EA1/L1 K2 - EA2/L2 8
1 9
A1 - Area of half circle - Area of 0.5" dia hole + Area of 10 half ellipse.
11 12 n/4* 4.582*0.5 - n/4* 0.52 + n/4* 4.58*2.32*0.5 13
- 8.24 - 0.2 + 4.17 -12.21 sq in
'14 Cross sectional area of the original stud 15 16 A2 - A n/4 (4.582 -0.52) - 16.28 sq.in.
17 18 A1/A2 - 12.21/16.28 - 0.75 19 20 The actual thickness of the bolted joint is 18".
The 17" l 21 dimension is the length of the stud between the upset ends.
22 23 L1 - L/17. L2 - 16L/17 24 25 K1 - 17 X 0.75 EA/L 26 27 K2 - 17 X EA/16L 28 29 1/Ke = 1/K1 + 1/K2 30 31
[1/(17 X 0.75) + 1/(17/16)] X L/EA 32
.33 1/Ke = [0.078 + 0.941] X L/EA 34 35 Ke - 1/1.019 X EA/L - 0.9813 EA/L 36
, 37 Therefore the effective stiffness of the corroded stud is 4
l 38 98.13 percent of the original stud.
39
, 40 Overall stiffness of the joint - (14 X 1 + 0.9813 X 2)/16
' 41 42
-0.9976 43 44 This shows that the joint effeciency with the local 45 degradation on two studs is 99.76 percent of what it would be
.-,M PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET Chont 7
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if there were no degradation.
This shows a very insignificant 2
decrease in the overall effectiveness of the joint and is weeKnet 3
therefore, acceptable.
4 l 5 The preload stress in the corroded stud 6
7
- 25 X 0.9813/0.75 - 32.71 ksi 8
9 0.75 is the area ratio of the locally corroded stud to the 10 non-corroded stud.
11 12 DIFFERENTIAL THERMAL EXPANSION STRESS 13 14 Because the casing and cover material is different from the 15 stud material, there is some minor differential thermal 16 expansion. Stresses due to this expansion are secondary in 17 nature and generally self relieving.
Therefore. these 18 stresses are deemed to be acceptable without further 19 evaluation.
20 21 DESIGN PRESSURE STRESS 22 23 Design pressure - 2500 psi acting on a diameter of 48 inches.
24 This is the outer diameter of the outer gasket, per Reference 25 2.8.
26 27 Total pressure force = (n/4)*48 *2500 - 4.523.9 Kip 28 29 Considering about 122.3 Kip load of the motor and the cover.
30 net pressure force resisted by the studs = 4.401.6 Kip
-31 32 Force per stud =4401.6/16 - 275.1 Kip 33 34 Pressure Stress on non corroded stud = 2.75.1/16.28 - 16.90 ksi 35 36 Pressure Stress on the corroded stud -16 90/0.75 - 22.53 ksi l37
'38 39 STRESS COMBINATIONS 40 41 For design pressure or operating pressure conditions, the 42 pressure stresses and differential thermal stresses are not 43 directly additive to the preload stress.
44
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PALISADES NUCLEAR PLANT EA-C-PAL 1939-01 ANALYSIS CONTINUATION SHEET
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onu en 1 to this EA shows the original design details of 2
the stud.
Reference / Comment 3
4 Reference 2.6 provides guidance to calculate the factor by 5
which the pressure stresses should be modified.
6 7
Refer to page 6-21 of Reference 2.6 8
9' Le - grip length + 1/2 engaged thread length + 1/2 bolt head 10 thickness.
11 12 Le - 18 + 10/2 + 4.58/2
- 25.29" 13 14 4.58" is the assumed thickness of the nut.
15 16 Le/D = 25.29/4.58 - 5.52 17 18 From Fig 6-17. page 6-23 of Reference 2.6. for Le/D equal to 19 5.52. the ratio Kj/Kb is 3.
20 21 From page 6-21. equation 6-4 of Reference 2.6.
22 23 f=Kb/(Kj+Kb) 24 25 1/f=Kj/Kb+1 26 27
- Kj/Kb +1 28 29
- 3 +1 30 31
-4 32 33 f=0.25 34 35 The preload stress plus pressure stress in the locally 36 corroded stud - 32.71 + 0.25 X 22.53 37 38
- 32.71 +5.63 - 38.34 Ksi 39 l 40 Reference 2.4 specifies the allowable stress at the operating l 41 pressure equal to 39.6 Ksi which is two times Sm at 600 l 42 degrees operating temperature.
l 43 44 The calculated stress in the corroded stud (using the design 45 pressure which is about 25% more than the operating pressure
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of 2060 psi) is 38.34 Ksi.
This is acceptable and, therefore, 2
the corroded stud can take the stress imposed on it by the M m nc m m nt
!3 preload and design pressure.
4 i
5 The fact that the corrosion is on one side of the stud only 6
may cause an eccentric load path through the corroded length l
7 of the stud.
This insignificant eccentricity may cause a I 8 small local bending in the stud. but the resulting moments are l
9 minimal and do not impact the load carrying capacity of the 10 studs.
The two adjacent degraded studs being less stiff than 11 the other 14 may cause a slight joint asymmetry.
By i
12 engineering judgement, this is not of concern.
l 13 14 The Primary Cooling Pump 50A meets the ASME III Class A. Code 15 requirements.
The degraded studs meet the ASME Section III 16 stress allowables.
17 18 CONCLUSION l 19 20 Based on current corroded condition and extrapolating this 21 rate of degradation until REFOUT 99. it is concluded that the 22 Primary Coolant Pump joint meets the ASME Section III l 23 allowables, and therefore, complies with the FSAR 24 requirements.
l 25 26 Based on the above analysis, it is concluded that sufficient t
27 preload still exists (and will exist until such time when the 28 studs are replaced) to prevent the joint from separating under 29 design pressure conditions.
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SUMMARY
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On December 18,1998, Palisades conducted a telecon with engineering personnel from clowserve Corporation to discuss the draft review of EA-C-PAL-98-1939-01, " Evaluation of Corrosion on Studs between Casing and Cover of Pump P-50A, Reference C-PAL-98-1939."
Flowserve participants included Frank Costanzo, Manager of Engineering, Pump Division; and t
Gerard Lenzen, Senior Project Engineer, Pump Division. Among the Palisades participants were Don Riat, Al Lyon, Raj Gupta, and Don Bemis. Other people came and went during the i
conversation, l
r DISCUSSION j
Flowserve comments on the draft calculation were discussed. In general, the comments were similar to comments generated internally at Palisades.
Flowserve assumes the hydraulic lifting area to extend to the outer diameter of the outer casing gasket, which is 48 inches. This is based upon the conservative assumption that the inner gasket is nonfunctional, allowing full pressurization up to the outer gasket. They believed that a slightly smaller effective diameter would be justifiable in accordance with standard gasket principles.
l The code maximum yield stress allowable for the stud at the assumed temperature (600* F.) is 61 ksi.
l s
l Flowserve engineers said that we should not add bolt preload stress to actual pressure stress.
Finite element analysis shows only a marginalincrease in bolt stress due to pressure. The i
larger of the two stresses (pressure or preload) should govern design.
l Section 2B of the original code stress report dealt with bolting design. Unfortunately, Flowserve cannot physically locate that section.
l Based upon Flowserve's experience with pump maintenance, preload relaxation is very hard to l'
quantify. Their suggested value is 15%. This is based upon tensioning the stud in order to determine the lift-off load.
Stud temperature would be close to pump operating temperature inside the flange. In the exposed area, it may be a hundred degrees cooler.Most plants insulate these studs and flanges, but those at Palisades are uninsulated. Due to the nature of the localized boiling, surface temperature of our stud is cooler in the exposed area.
Flowserve also provided a fax detailing pump and stud materials, as well as gasket dimensions.
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[CA8EMISCR981939 TEL debemis pmted December 20.1W8
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FLOD SERVE-616 764 2251:# 1/ 1 E A {-961L-3 N D N FLOWSERVE CORPORATION g
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s syron Jackson
- Pumps United CentrWugal Pumps N
FXX TRANSMITTAL Date
~ 18 Dec 98 Pages 1
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- min frown C F.ItR Y I F N 7EN 4
- a Nrlear Plant Tectuucal Samces Crroun 616.764 7101 Ptione 213-584-1879 Fan 213-589-2529 subject: Palisades RCP i
The following is some information requested on the Palisades RCP.
Driver <nount material - A-216 Grade WCB 4
I Cover material
- A-35i Orade CF8M Case material
- A-351 Grade CF8M Stud material
- A-193 Grade B7 Nut material
- A 194 Class 2H I
Outer gasket groove - 46"ID and 481/8" OD Outer gasket
-461/16"ID and 48-1/16"OD inner gasket groove 1/2"ID and 45" OD Inner gasket 9/16"ID and 44-15/16" OD The thickness of the gasketis 0.175".
The depth of the gasket groove is 0.125".
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DEC 18 '98 12:29 213 5822529 PAGE.00;
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T ABLE N.422
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1 DE!lGtl STRESS INT ENSITY V ALUES, S,, FOR STEEL BOLTING M ATERI ALS*
.._.._..___..,_.___.,_..___.____mm For metal temperature not exceed,ng 'F
- )
200 300 400 500 600 700 800 900 1000
.9 33,000 31.100 30,300 28,R00 27,700 06,300 21,100
..,a 29,000 28,100 27,100 26,000 23,100 23,800 22,100
,, s.
23,*>00 22,100 21,600 20,700 19,800 iH,000 17,100
,..m i 38,000 33,200 3 2,*>00 31,800 30,900 29,400 27,700
....o0 30.700 30,000 29,100 28.800 27.900 26.600 2 *>,10 0
- ,i, ;irl 27,500 26,900 26,300 0;700 2",000 23,000 22,400
,0 33,000 31,900 30,600 29,500 28,100 06,100 24,200 d
TABLE tt 423 (in course of preg >aration) i s
30
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Tal>le N 122 SFCTION ll! NUCl.1:.\\ll VI.Ml;LS Cl. ASS A h 1.
TABLE N 422 DE51GN STRESS INTENSITY VALULIS,5,,, FOR STEEL BOLTING MATERI ALS*
Min Min Min Tempering Tensile
. Yield Spec Nominal Diameter Temp Sir Sir Numi,er Grade Composition in.
'F PS)
PSI Low Allof Steel S A 19.1
!!?
I Cr-0.2 \\ti.
2'i anel 'under 1100 12*i.000 10,.000 Ou r 2'i to 1 inc, i100 1I". 000 9*,.000 Ou r i to 7 inc.
1100 100.000 R 000 2', anil undt r 1200 125.060 105.000
( Ovr 2'i lo 1 inc.
Ia00 110.000 9i.090 S A 193 111 1
] Cr-0.3 \\lo V Ose I tu 7 inc 1200 100.000 as.000 S A-193 1116 i Cr !j\\lo-V SA 320 1A3 2 Ni-0.8 Cr-!al) 4 ami l'nder 125.000 10">.000
-,=
'The allawable stre a value, f,n holting m tcri21. given in thin t.,ble do not eed the lesser of one-third of the avecifirJ mioimum yield strength or one-third of the yield strength at temper ture, v.ith credit are.,.I for the enhancement of propertn 41 re duced la I cat treatment.They sre intended for use in the denian formulan of Api endiv ti For llowable values of.ictual prelu.d and ervice stretace, se e N-4 t ei.
0 32
IARI F 5.2-3 (Sheet 1 of 18)
MECHANICAL.
SYSTEM /COMEONENLCLASSIElCAllON Seismic Class Class per per RG 1.29 CP Co Design RG 1.26 System / Component Interpretation (a)
Class (b)
Interpretation (c)
Standards Used in Plant Desia'n RFACTOR COOLANT SYSTFM Reactor Vessel Category i Class 1 ASME lil ASME 111 (1965) - Class A Class 1 Reactor Vessel Supports Category i Class 1 ASME Ill 9
Subsection NF j
/'
J' Steam Generators - Tube Side Category i Class 1 ASME Ill ASME 1I1 (1965) - Class A Class 1 g
Steam Generators - Shell Side Category 1 Class 1 ASME 111 ASME Ill (1965) - Class A Class 2 M
Steam Generator Supports Category i Class 1 A S M E let Subsection NF Pressurizer Category i Class 1 N A S M E lil ASME Ill D 965) - Class A Class 1 ASA 831.1 (1955)
Primary Coolant Pumps IPCP)
Category 1 Class 1
- A S M E lil ASME Ill (1965) - Class A Class 1 Standards of Hydraulic Institute (SHI)
ASA B31.1 (1955)
ASA B16.5 (1961)
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P (e) Sesamec category as ident6ed in the Franidn Research Center Techncal Evda% Report TER-C5257-428 Pursuant to SEP Topsc lil-1 and other related materials.
I (b) Equipment h*% as identAed in the Pdh 1980 FSAR, APPENDIX A, and TE-C5257-428.
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(c) Class pursuant to the ASME B&PV Code. Section lit. Osweeson 1, Subsechon NB,1977 eddson,1978 addende, as deterrvuned by TER-C5257-428, pursuant to SEP Tope ill-1 modhed by CP Co 1 (p f
eal Current damagn requmoments for non-PCS papang are reconciled to ANSI B 31.1,1973 Ed with 1973 Summer Addenda See Section 5 to 1 and 5 to 2.
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Neragen Gas Backup Stahans 1 and 2 reRect a sersmic desagra from an earlier revisson of the FSAR not consestent with the requrements en Secten 5 2 2 of the current revision of the J ts) lSAR Ihe deeqpn of Statone 1 and 2 (FC-675) used 0 5 x OBF. for seismic design oJD its he.sma. Class i Supported hem Receevers to Operators on Engineered Safe-guards Systems Rev 20 h
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3.1.'1 ASME Iloiler and Pressure Vessel Code, Section Ill, Nuclear Yessels plus V.
addenda.
3.1.2 ASME Iloiler and Pressure Vessel Code,Section II, Material Specifications plus addenila.
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3.1.4 Standards of the flydraulic Institute Centrifugal Pump Section.
3.1.5 NEMA, ASA, and IEEE Standards.
3.1.6 ASA.B 16.5 Steel Pipe Flange and Flanged Fittings.
3.1.7 ASA.B 31.1 Code for Pressure Piping.
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.'4,1.1 ne pump simil be a vertical centrifugal type with bottom suction and
' horizontal discharge. The driving motor simil be of the conventionalinduction j
i type. Provixions shall be made for the collection aml removal of shaft seal
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leakage. Suitable scif. contained lubrication system for pump and motor must he inciudcd with the pump assembly. The pump amt its. performance 4
characteristics shrJ1 be suitabic for parallcl. operation willt identical units..
i 4.1.2 The design life of the pump shall be forty years. The predicted life of those s
4 positions of the pump assembly with less than a forty year life shall be listed in the technical manual.
' 4.1.3 The pressurt. containment design of the pump assembly shall conform to
.Section.111 of the ASAlE Doller and Pressure Vessel Code.
ne pump casing, pressure housing, and suction cibow shall be considered as a Class "A" vessel per paragraph N.131 of Section Ill.
t 4.1.4 The pump shall be designed to requhe maintenance at a minimum interval of
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one (1) year. It shall be a design objective to require maintenance at three year Intervals.
, 4.1.5 Provisions shall be made to change seals without draining the pump casing. %e
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pressure inside the casing will be between atmospheric and 20 psig.
4 l4.1.6 The pump assembly shall be designed for continuous operation at any point on the characteristic > curve from 80,000 to 110,000 gpm including operation at f
specific gravity 1.0 as specified in 4.1.7.
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The pump assemby shall be designed to operate foA.000,h
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- Specification No. 70P.005 Rev.2 Page 5 of 31 Mod. I 10/6/69 9
E A-c - PAL-9 g-/9 3 9-o f Attdd 9 BWilP International, Inc.
Pump Division FACSIMILE TRANSMISSION COVER SHEET BW/IP INTERNATIONAL, INC BYRON JACKSON PUMPS NUCLEAR PRODUCTS OPERATION (NPO) 2300 E. VERNON AVE.
VERNON, CALIFORNIA 90058 PHONE # : (213) 587-6171 -- FAX # : (213) 589-2080 FAX NO.:
616-764-2251 DATE: 20 December 1998 To:
Paul Harden FROM: Frank J. Costanzo COMPANY:
Consumers Energy - Palisades Nuclear Plant
SUBJECT:
Stud Analysis
REFERENCE:
This is to document that we have completed our technical review of Consumers Energy report EA-C-PAL-98-1939-01 entitled " Evaluation of Corrosion on studs between casing and cover of Pump P-50A" and concur and approve this report based upon the incorporation of minor comments previously discussed and agreed upon.
Best Regards, Fr&J. Coftmp Manager of Engineering Nuclear Products Operations i
CC:
K. Lemmon PAGES TO FOLLOW:
0 G. Lenzen C. Reimers s
r 1
l DEC 20 '98 13:05 1 714 9687572 PAGE.001
PAllSADES NUCLEAR PLANT Proc No 3.07 10CFR50.59 SAFETY REVIEW Revision 9 Page 1 of 1 l
E il - C - r'A L - 9 8 - l 9 3 i - o '
Log no sog. 9 e - 1 go r; f
item identification: No 8464 L 'l8 Rev C2 Title M - 8 0 A C ue,er Jc Cc.'ir N#3 1
- / 9 31 -,f Describe IssuelChange:
M UA f t&d W
Nf CC o'2/E 00 2 O Sia D 5 AJO
/ldf f f 7A d C E Dtt /2 t d C, P4 M T OPE /2A TtDa i t L t.
Mf w 'r q q Reason for issue / Change:
d - f4 /
'3 8 - / 't 3 'I i
j 1.
Does the item involve a change to procedures as described in the FSAR7 Yes No FSAR Sections affected NOA/6 FSAR Sections reviewed 4-2./ - 3 f-/ f-2 G 4 /n f-2./ 4-c
/
c m.t 5 '9 2.
Does the item involve a change to the facility as described or implied in the FSAR7 FSAR Sections affected
^/CdE i
FSAR Sections reviewed A> abo 's 9ttl5 bbits 4
'2_ 4 S'.2.- 3
/
1 4
3.
Does the item involve a test or experiment not described in the FSAR7 FSAR Sections affected A/CA/E FSAR Sections reviewed
^/O 7 6 W / 6 x /'d ^ M d d T /d V*W6 O
/
i 4.
Should the Technical Specifications or any of their Bases be changed in conjunction 1
with this item?
TS Sections affect.
MO^/d TS Sections revies
. M'!'i 3 I I
- i. /, 9
- 1. /. 9 a n/
- 7. < 7 Vsf4 If any Safety Review ques M listed above is answered "YES," perform a written USO Evaluation. Justify "NO" answers below if logic is not obvious:
The. e A sk.ar ma & Asme coa,o c;. fi c s b y & F 5 A F J 5 me*
h7 b debi.
l-l NOTE: DBD change requests shali be processed in accordance with Administrative Procedure 3.15.
r" '
M I'N,'3,33 Affected Mod 6 DBD Sections Reviewed j
NQIg: SDR forwards a copy of all changes potentially affecting proposed improved Technical Specifications to the Licensing Dept.
3 4 &(M Proposed ITS & Bases Reviewed Affected Ald^/5 This attachment shall accompany other review materials for the item to document whether or not a USQ
)
Evaluation was required.
0.S.i M tilid9s i
w'
- n. i r en Prepared by Date Reviewed by Date i,
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ATTACHMENT 3 l
CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 l
INSERVICE INSPECTION PROGRAM -
SUBMITTAL OF RELIEF REQUEST NO. RR-13 FOR NRC APPROVAL ENGINEERING ANALYSIS EA-C-PAL-98-1067-01 P-50A CASE TO COVER BOLT EVALUATION May,1998 l
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