ML20072L348
| ML20072L348 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 06/20/1983 |
| From: | Walker L, Zegar M COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20072L320 | List: |
| References | |
| EQ&T-EQT-204, EQ&T-EQT-204-R, EQ&T-EQT-204-R00, NUDOCS 8307130322 | |
| Download: ML20072L348 (84) | |
Text
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t e i, EQ&T-EQT-204 l
ENVIRONMENTAL QUALIFICATION OF MECHANICAL EQUIPMENT FOR THE CCMMONWEALTH EDISON COMPANY BYRON STATION UNITS 1 AND 2 .
BRAIDWOOD STATION UNITS 1 AND 2 COMPONENT:
PACIFIC SAFETY' INJECTION PUMP MODEL 3" 10 STAGE JHF i
REV. O j 5/23/83 0 20 SS PREPARED BY: ff.J. 2EyR t 7
APPROVED BY:
h kyuubhs}es L :1.1TALKElt 8307130322 830707 PDR ADOCK 05000454 A PDR
.o TABLE OF CONTENTS ITEM PAGE Introduction 1 1.0 Equipment / Document Identification 2
- 2.0 Environmental Summary 3
. 3.0 Pump Outline Drawing 4
} 4.0 Methodology y 13
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5.0 Acceptance Criteria . 13 18 6.0 Critical Parts Material l Discussion ,
t 7.0 Pump Motor ,
20 8.0 Lubricants 21 9.0 Maintenance 21
! 10.0 Conclusion- 22 List of Tables Table i Bill of Materials / Paris List 13 '
Table 2 Critical Parts List 17 Table 3 Critical Parts - Environmental 23 Oualification Summary References 24 i
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i Introduction
. This report documents the Environmental Qualification of the Pacific
- Safety Injection Pump Model 3" 10 Stage JHF for Commonwealth Edison Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2.
The evaluation documented herein verifies that the component, as originally designed, is adequate to meet the plant environmental conditions as specified in the Equipment Specification.
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l 1.0 Equipment / Document Identification 1.1 Specification No.: 677474 Rev. 0 (motor) 678815 Rev. 2 (pumo)
-l' l.2 Vendor: Pacific Pumps 1.3 Model/ Type: 3 inch 10 stage JHF Safety Injection Pump 4
1.4 Spin No/ Serial No.
SIAPSI - CAE/CBE/CCE/CDE CAE - 49758/59,.CBE - 49760/61 CCE - 49762/63, CDE - 49764/65 1.'5 Reference. Drawings: AXS-49754 Rev. 7, MB-7187 Rev. E, H-SP-1786-5 Rev. E, JLF-49754 Rev. 2, 5-162-06-018-003 Rev. 2, FC-49758 Rev. 6, VBC-49754 Rev. 4, PLO-49758 Rev. 2.
7 1.6 Equipment Function (s): To provide emergency core cooling in the event of a break in either the reactor coolant or steam system.
Injects water from the refueling water storage tank (RWST) and recirculates water from the containment sump after the RWST supply is exhausted.
1.7 Seismic Qualification Report:
l, K363, X386 Rev. 3 (pump)
S.0. 75F32374 (motor) 1 r
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, '. 2. 0 ENVIRONMENTAL
SUMMARY
ENVIRONMENTAL POSTULATED PARAMETER SPECIFICATION MAXIttUM TEMPERATURE
( F) 120 130 MAXIMUM PRESSURE ATM ATM MAXIMUM RELATIVE HUMIDITY 95% NOT SPECIFIED CONTAINMENT NOT APPLICABLE NOT APPLICABLE SPRAY 40 YEAR NORMAL RADIATION DOSE 1.2 x 10 7- 1 10 (RADS)
ACCIDENT INCLUDED IN RADIATION DOSE INCLUDED IN NORMAL DOSE NORMAL DOSE RADS TOTAL RADIATION 1.2 x 10 7 1 x 10 7 DOSE (RADS)
SUBMERGENCE N0 N0 (YES/N0)
FLUID CONDIT0NS: DILUTED B0 RATED WATER: 40 T0 100*F, 0 - 35 FT.
ACCIDENT SUMP WATER: 40 TO 300 F, 0 TO 350 FT.
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, t 12 #046 sty Gl aa PlaqP a2020F 28 I I4
' I 12 ( ON I 5Hati lOtta GEat at9337 se$
1 82 8 m. a Gfar IDt t a elot44 3 39 2 24 W J ( a I fi w/Pa aux P ACu 851 St at 2 2 r,nal at C H 5 tat te n5 g T Ha U 16 858 8 2 24 T SP F Pialf st at Fl hat ttfelt 5P
' 24 N 374 2 Gaint t O alNG an P 568 246 2 2 .a *6 5t At Pt&Tt o af4G Aar %A4 246 8 184 e 96 7 Sta CAP Sota No SP20 Is2 13hC a t 3/4tG 4%2 iP 2 4 f.uam rt a f f af t alNim e 468970 t JI 2 24 (.uos 5(a (ar So(E **O 3/8 16ssC a l/4t G am0068 40 82 23 8 96 a.all 5(. a 50C H D C a r t / 4 20hCal/2tG seas 0042 0 25 g 2 24 wil $P le 5t t a vt Stat %Hati A20284 164 21 SP 1 2 2+ JT\t 5:4 Ss T 5t y anP <;6e 22 0 t74 2 24 ..uk6 PON Dal Vt ttaI%/16tG Ja0004 IJ 23 l 2 24 (S St at Cott aa Shat t 5tv a 619 e.'s 28 12 let GJts 5(a 500 5t t Cup PI 3/P 16a.C z)/ et c asco64 r0 6 23 6 #2 ., u t i Va 500 Sif He DOG Pit /4 208sC At /4tG =00042 4 25 1 24 Gute SP 20 Elf Set 5t y a22822 8 23 SP b
TABLE 1 (CONTIfiUED) .- -- 3 PACIFIC PUMPS, INC. '"*'*" ~ l PAFIT2 LIST
- ~~= = W1511Ncleoust' I t f CTRIC n>RP" 349111
- 2 y *: -
*7 _ y n =; ~y g '
2 14 t, ul e sta #tal HO M at H SP 20 4 40NCR)/$tG 23 LP 1 2 n$$ w/NEW G (Pt G 2UaN B02 3/2 3 1 2 n54 CPtG 2uwN 102 t/2 satahCEO 8
,\ l 2 2 e 5 5 CPt G 2UNN 802 t /2 BA L ANCIO O i ., .5 . i502.. ,2 i. ,.
366 ont 0E A tml0N A Mite >6 99 1 l 3 6 695 mIPPL E 181 8/2X2t G SCH90 A 500 g 3 & Pu6 .s 5N A STOP cot t 6Al 22t Y 3/1611/2X8/4 A f5300, to 224
' 5 6 sal SPW ING C t NIUN Y SIOCs 384 A Allg2s 3 p.2 3 6 992 d i s k ut t 3/16 lMPf M I AL 880 60 F S A tA500F I4 ?to
! 6 12 vat st at h5pm 40 32 soll Silf a tanoot 12 /to l
. 6 toro o eG ARPSh8000 A LUS6SG G lit !
t ) 6 1244 HD4 It#MINat S Cl5666 F IG2 A
- 1 2 I/*e i t f' ai fet 5HfAlte StG A >
2 4 124d ttiMtNI Stit a f H 8 LG A I it i l l/ 1 1 4 I i I J 7-i _4=
16 4.0 Methodoloay 4.1 The evaluation / verification was performed by first reviewing the complete pump assembly inclusive of the bill of materials (Reference 1). Each part was then evaluated as to its specific function with respect to the function of the overall assembly. The parts were then categorized as critical or noncritical. 4.2 Critical parts are defined as those parts whose integrity, when exposed to the postulated environments, are critical to the overall component operation and whose failure would preclude the equipment from performing its intended safety function. The critical parts are identified in Table 2. , 4.3 Subsequent to the above, the critical parts were then individually evaluated with respect to their ability to withstand the postulated environmental / operating conditions. 5.0 Acceptance Criteria 5.1 The acceptance criteria is defined as follows: l The critical parts shall be technically shown to be able to withstand the postulated environmental conditions without exhibiting common mode failure effects. i j t Y v * --- ~f
" * -= "
TABLE 2 - CRITICAL PARTS LIST Part flo. Quantity, Description Material A551 13 Gaskets / Parting Conpressed . Flange Gasket Asbestos Sheet A612 24 Flexitallic Gasket Stainless Steel and Asbestos B010 26 Seal Housing Gaskets EPDM D095 130 Suction Spacer EPDM 0-Ring and Suction Ccver 0-Ring
- G006 26 Gasket 0-Ring and EPDM Seal Plate 0-Ring a
G013 24 Seal Ring-Shaft Sleeve EPDM . G002 26 Mechanical Seal EPR Graphite F060 12 Worm Gear Canvas Micarta (Heat Exchanger 2 Gaskets Comoressed Asbestos Items 4 & 5) , N
18 6.0 Critical Parts Material Discussion 6.1 _ Ethylene Prooylene Rubber (EPR) ! (Cranelast) and graphite safety bushings 6.1.1 EPR and graphite are specifically used for the bellows and bushings respectively in the pump seals Part G002. While previous industry tests were performed on these materials under static conditions. Additional tests were required under dynamic conditions. Tests were performed on the complete seal assembly (Reference 2 ) which simulated the seal environment and operating conditions. The testing encompassed the following conditions inclusive of exposure to boric acid moderator solutions: Pressure - 0.2 - 400 psig Temperature - 140 - 300*F - Test Duration 500 hrs. Shaft Speeds - 1800 and 3600 RPM 0 ' Radiation - 1.1 x 10 rads gamma 6.1.2 The tests concluded that the seal assembly which included the organic parts successfully performed their function under both normal and adverse conditions. 4 6.1.3 Graphite is considered not to be effected by thermal acing. 10 It's radiation threshold, however, is 1 x 10 rads gamma. 4
...a., ,, , , - , _ , g -r--- . ,-- p- , -w- -e,
. 19-6.2 Asbestos / Compressed Asbestos 6.2.1 This material is used in parts A551 and A612 for gasketing applications. Based on common industry data, asbestos is acceptable for use in elevated temperature aoplications up '
to 150 C. This material is not considered as organic and, therefore, not subject to heat aging. Asbestos retains its properties and is usable for radiation doses in excess of 10 10 Rads. Whenthismaterialisuset)incontactwith coolant fluid and/or stainless ; steels, the chloride /flouride content is controlled to not exceed 200 PPM. This eliminates any possible stress corrosion effects. 6.3 Ethylene Prooylene Diene Momer Rubber (EPDM) 6.3.1 EPDM is used in various parts of the pump assembly in gasketing and/or seal applications. (Parts B010, 0095, G006, G013). This material has excellent thermal aging and radiation restance at temperature in excess of 300 F and 2 x 100rads gamma respectively. l f 6.3.2 Additional full sequence' test data has been made recently available through the W Environmental Qualification of ASCO Solenoid Valves (Ref. 3). This additional data further reinforces the adequacy of EPDM for the above listed parts. e
-. , . . - - - , , . - - .,,,,a - - - - . ,
20 t 6.4 Canvas Micarta 6.4.1 This material is specifically used for the gear pump worm gear j Part F060. The property of importance is flexural strength. Using standard acceptance criteria of 50% ret'ation, the data i indicates acceptable cerformance up to 230*F. 6.4.2 The most radiation sensitive' properties are elongation and impadt strength which are not considered to be primary properties for this application. However, these properties, used for comparison purposes, are only reduced by 25% in the dose range of 8 x 106 Rads. + t i 4 s l I t-I l, i_
.o 4
7.0 Pumo Motor 7.1 The h[ motor used on this pump application has been qualified by separate}ltesting. The test specifics are reported in Reference 4. 8.0 Lubricants 8.1 Various lubricants are acceptable for use under the operating conditions specified in the Pump Instruction and Maintenance Manual. It is the responsibility of the user to provide documentation for the lubricant used and maintain the equipment as recommended in the Instruction and Maintenance Manual. (Reference 1) 9.0 Maintenance ( - , 9.1 Maintenance shall be considered to be the responsibility of the user. The user shall establish a maintenance program to maintain the equipment as described in Reference 1. Periodic maintenance to maintain qualification is required on critical parts per the qualified life as stated in Table 3. l l
..- , . - - . c- .,_. y e + e , - . 9
22 10.0 Conclusion 10.1 As stated in Section 5.0, the environments postulated for the critical l parts were compared with the specific material capabilities. Table 3 summarized this comparison. Based on this evaluation and comparison, the Pacific flodel 3" 10 stage JHF safety injection pump is considered environmentally qualified to perform its intended safety function of Para,1.6 without common mode failure effects. 10.2 The qualified life of this equipment is 40 years provided the recommended maintenance is performed per Reference 1 and the critical parts i .1 identified on Table 3 are replaced at the end of their individual qualified lives. 1
,------,-e r. , m--. . , - . ,
TABLE 3 $ CRITICAL PARTS - EflVIR0fiMENTAL A Qua.LIFICATJ0fl SUMARY l Material Postulated
- Material Property Environmental Capabilities Activation Quali fied Conditions Evaluated Energy Life (Worst Case) (eV) (Yrs)
Asbestos 120 F flormal 300 F (2) 300FAc9ident 1010 Rads N/A > 40 I 1.2 x 10 Rads Ganma Gamma (l) EPR (Seal) 120 F Normal 300 F 8 60% Elongation 0.93 300 F Accident 1.1 x 10 Rads 1(4) 1.2 x 107 Rads Retention Ganna Gamma (1) Graphi te 120 F Normal 300 F Accident
}300j0 ""#" "^
1 x 10 Rads
- 1.2 x 107 Rads Ganrna(I)
Canvas 140*F f3) 230 F Micarta 4 x 106 Rads 6 50% Retention 2.10 >8 i
> 8 x 10 Rads of Flexural Gamma (l) Gamma Strength EPOM(5) 120 F Normal l A300g Retention of 0.94 8 l 300FAcgident 2 x 10 Rads Initial 1.2 x Ganma Ganna(1QIl Rads Elongation Notes: 1. Includes normal plus accident dose
- 3. Environment is governed by maximum (accident duration is one (1) year).
allowable lubricant temperature.
- 2. Considered to be uneffected by thermal aging. 4. Based on continuous operation with '
maintenance. -
- 5.
Can also be used as an alternative seal material in place of EPR. m w
,..* ., 24 REFERENCES
- 1. Pacific Pump Instruction and Maintenance Manual for Commonwealth Edison 3" 10 Stage JHF Safety Model Injection Pumps.
- 2. " Seal Performance Testing for Nuclear Power Plant Safety Injection Systens," by Crane Packing Company. Bulletin
#3472 (W Proprietary).
- 3. Cesarski, W.V. " Equipment Qualification Test Report ASCO Solenoid Valves" WCAP 8687, Supplement 2 - H02A (Proprietary)
June 1981.
~
- 4. Anderson, A.A., "Equipmeni Qualification Test Report for the Westinghouse large Pumo M6 tor," WCAP-8687, Supplement 2-AE-2A (Proprietary).
- 5. W Corporate Thermal-Radiation Materials Application Data Manual.
l
ATTACHMENT B2 AIR OPERATED VALVE 8028 (PVORT/NSSS) Responses to the audit findings are as follows: Open Item l_ - During the audit the final static deflection test report prepared by the vendor for this valve had not been opproved by Westinghouse.
~
, As noted in Attachment A20. Item 3, this report has been reviewed. Open Item 2 - As discussed in the FSAR, operability testing is done on a representative number of valves. Each valve tested covers a series of valves' and is selected based on size, type, weight, vendor and other pertinent valve characteristics. The valve selected represents the worst set of parameters for the particular series of valves being grouped together. As noted in the approval of the test report for this valve (see Attachment A20, Item 1), a number of valves were covered by the one report. Additionally, the enclosed letter from the vendor (ITT Grinnell) documents the applicability of the test report to this valve. Open Item,3 - This item refers to the air supply used to actuate valve 8028. During operability testing a pressure of 72 psig was applied to the air operator. The specified pressure range of the valve is 63 to 85 psig. The 72 psig used during the testing is adequate to demonstrate operability of-the valve for the following reasons: The valve is designed to fail closed (safe position) in the event of low or a complete loss of air pressure. Hence, if the valve did not remain open at the lower end of the actuator
. design pressure, no safety problem would be encountered.
- The air pressure applied to the operator is used to hold the valve in the open position. Thus, if the valve functioned at 72 psig, it would also remain open at. higher pressures in its
-design range.
o t The air line to the valve is equipped with regulators to limit the actuator pressure to 85 psig. The valve functional specifications require closure within 10 seconds. During the operability tests the valve closed in the 2-3 second range at 72 psig. An increase in the actuator air pressure by 20% (i.e. , to 85 psig) would have very lit'tle effect on the closing time and the closing forces on the valve. Based on the above discussion, operability testing with the valve actuator at 72 psig adequately demonstrates the functional capability of this valve and testing at the maximum and minimum actuator air pressure limits is not considered necessary. Oper Item 4 - A static analysis using a finite element model was performed by the valve vendor (ITT Grinnell) to calculate the natural frequency of the valve and extended structure. In performing tests on similar valves for other organizations, Grinnell determined that the horizontal natural frequencies of this valve were below 33 Hz. Hence, the natural frequency analysis reviewed by the audit team has been invalidated. Grinnell nas performed additional static fragility testing on this valve and determined that the valve's opera-bility is not impaired for accelerations as high as 10g's. In light of this information Westinghouse has reanalyzed piping systems containing similar valves in the Byron plant using flexible valve models. The results of this reanalysis indicate that both the valve and piping system loads are acceptable. The information described above is currently in draft form with final reports in the process of being completed. Upon issuance of these reports and the finalization of piping analyses SQRT and PVORT Forms will be revised and sub-mitted to the NRC. Open Item 5 - The impact of. dynamic fluid loads on operability testing is described in Attachment 38 Item 6. 'For the valve in question fluid dynamic effects are negligible.
o Open item 6 - The approach implemented by Comonwealth Edison to address the environmental qualif'ication of mechanical equipment is discussed in response to draft SER Item 3. In order to demonstrate the acceptability of this approach Westinghouse has prepared information on the critical soft parts of the safety injection pump as agreed to with the Staff at a May 13, 1983 meeting. Please refer to Attachment B1, Item 4, and Attachment B8 Item 3. l l
^ " 'T l. [ l.
i)m ~
~ ~ ' ~
iTTGrinnellCorporation f_,#N14 y %799Sj:l7; Q Q p DIA-R0 Division ll ! 33Centerville Road q,,_ Wu::.?" - -l Lancaster, Pennsykania 17603 (717) 291-1901 June 8, 1983 Tg/gy;g.gfg Westinghouse Purchase Order 191000 Valve Operability Test Certification This is to certify that ITT Grinnell Operability Test Report W-210 qualifies valve I.D.'s as listed below: 3/8DA42R, 3/8DA92R,3/4DA32R, 3/40A42R, 3/4DA62R, 3/4DA92R, IDA32R, l IDA42R, IDA42RZ, IDA92R, 2DA42D, 2DA920, 2DA32R, 2DA42R, 2DA62RZ, 20A92R, 3DA42D, 3DA32R, 3DA42R, 3DA62RZ, 4DA42D, 4DA32R, 4DA42R, 40A92R, 3/4X320, 3/4X42D, 3/4X92D, 1X32D, 1X42D, 1X92D, 2X320, 2X42D, 2X920, 3X320, 3X42D, 3X62D, 3X92D, 4X32D, 4X42D, 4X92D.
.{ - . (, f*if -
, Michael J. Panciera Sen. Prod. Eng. MJP/twa l 1 l l f
' .\ M Attachment 83 Gate Valve - Main Steam Isolation (PV0RT-80P) Response to the audit findings are as follows: a) The maximum pressure in the accumulators will be 5000 psi under accident conditions. As a result the design pressure used was 5000 psi rather than the 3750 psi normal pressure. The accumulator was supplied as part of the MSIV operator and as such, was not subject to a separate test program by Anchor / Darling or Commonwealth Edison. However, the accumulator was purchased as an ASME Section VIII component. As a result, the vendor (Parker-Hannafin, holder of ASME "U" Stamp) certifies that the accumulator met or exceeded code testing requirements. This requirement is a test pressure of 1.5 x design pressure or, in this case, a minimum of 7500 psi. Documentation of subcomponent design and testing is retained by the valve supplier, Anchor / Darling.
REFERENCE:
F/L 2756L MS-Isolation Valve Specification b) The original external environmental temperatures &nd pressures specified were everly conservative. FSAR Section C3.6 summarizes the calculatica of the valve room and steam tunnel pressurization. The calculated peak pressure is less than 20 psig. A calculation to
. extend the transient shows that the pressure in the valve rooms is very close to ambient within five seconds. The transient is very rapid with the peak occuring less than 1.0 second after the break.
The sharp pressure rise will force open doors and ventilation areas in the valve house and rapidly vent the steam to the environment. This ventilation also serves to rapidly reduce the temperature in the valve house and steam tunnel. The temperatures used in the environmental condition specification were very conservatively calculated. A more recent calculation shows that the temperature will drop to below 1500F in less than 15 minutes after an exterior door opens. The concern about valve operability under elevated pressures results from a design limitation of the actuator. The air supply must be 59 psig above the environmental pressure. The supplied pressure at Byron will be in a range of 80-100 psig. Since the calculated maximum pressure is actually less than 20 psig, the required minimum supply pressure would be less than 79 psig. Therefore, a small margin is available even if a design basis double ended break occurs while the supplied air pressure is at its minimum value, and the closure signal is received at the valve during the short (1-2
-seconds) time that the environmental pressure is elevated.
o 1
.e Gate Valve - Main Steam Isolation (PV0RT-80P) -..
c) Assurance of the ability of the valve to function under full flow conditions is achieved by a combination of analysis and test. The vendor provides assurance that the closure time requirements are met by calculating the force necessary to close the valve against a full flow load and then testing the actuator to insure that adequate closing force was available. Documentation of this testing is retained by the valve manufacturer. Because it is not practical to fully stroke these valves during normal operation. the valves will be part stroke exercised every three months and fully stroked during shutdown. This is documented on Page 21 of the Byron Inservice Testing Program Plan for Valves. A description of this program was submitted to the NRC in the November 4, 1982 letter from T.R. Tramm to H.R. Denton. d) The actuator used for seismic qualification was identical to the actuators installed at Byron. The actuator, Model 64324-C, was qualified by analysis. Wyle Lab report number 43847-2 lists this model number which is identical to the model number of the installed actuator. e) The actuator was vibrationally tested (Wyle Lab report 43847-2) and ' this report is available. The valve itself was qualified by analysis and, as a result no vibration testing data is available. The analysis establishes that the valve is not sensitive to vibration predicted in seismic events. The Byron vibration monitoring program detects any unusually high amplitude vibration during pre-operational testing. l Aging of the Class lE electrical equipment is considered in the qualification program for lE equipment in a harsh environment. For tested equipment, the sequential test requirements of IEEE 323-1974 have been complied with. Aging of mechanical components is addressed by a program of maintenance and surveillance which will detect age related degradation of mechanical components. This program is further discussed in SQRT Draft SER Generic Item #6. f) A loss of air in the accumulators would lead to inability to close the valve. However, the loss of air would have to occur in both accumulators to actually cause the valve to fail to close. The accumulators are independent, and are subject to surveillance. As noted previously, th accumulators are ASME code designed and J. inspected components. Failure because of accumulator leakage would require an initiating event plas two independent failures in a ' safety grade system. This scenario is beyond the required plant design basis. 3120b
Attachment B4 Main Steam Safety Valve (1MS013A) (PV0RT-80P) Responses to the open audit items are as follows: a) The leakage rate of the Main Steam Relief Valves, while an important . consideration for plant operating efficiency, is not a safety concern. The secondary side of the steam supply system is not normally radioactive. Leakage will cause an offsite release only if the-primary to secondary side boundary is breached. The analysis in FSAR Section 15.6,3 for steam generator tube rupture assumes a loss of offsite power and control of steam generator pressure by opening of steam generator relief valves. This clearly conservat,1vely bounds the effect of a leaking valve. ; b) The Byron Preservice and Inservice Testing Program Plan for Valves includes valve IMS013A (page 21 of the Program Plan). Prior to startup and at each refueling outage, the valve setpoint will be vertfied in accordance with IWV-3510 of ASME Section XI.
; c) The test report for the Main Steam Safety Valve 1MS0'13A (EMD 003901) is divided into three parts. Phase 1 is a determination of the
- resonant frequency. Phase 2 is a determination of the effects of vibration and resonance on the valve operation. Phase 3 is the actual test of valve operability under vibrational loading. Phases I and 2 can be characterized as developmental testing.
! The valve'has a lowest horizontal natural frequency of 37 Hz. When j
~ tested with a'high amplitude 30 Hz input some operability problems were noted in the Phase 2 testing. Some modifications were made to the valve but the object was not to completely eliminate the F resonance problems associated with the 30 Hz input. Phase 3 is the actual qualification testing of the valve. The prototype as tested in Phase.3.is the same as the production valve
- installed by Byron with the exception of the differences noted in
- . Section 4.2.1 of the report.
~
l The results of the testing-indicate that the valve will perform as required. d) Establishment of'a qualified life as a resu'lt of aging is not required for these: valves. These valves are all metal and do not have any critical non-metallic parts subject to aging. A maintenance and surveillance program has been established to . schedule repair or replacement of-the valve or valve parts based on
- - manufacturers recommendations.and operating experience. The i surveillance = program for these valves is described in the response to f.inding (b).
t 3120b. ~
Attachment B5 Essential Service Water Pump (ISX0lPA) (PVORT-80P) Responses to the open audit items are as follows: a) The minimum critical speed has been determined by the pump manufacturer to be 2611 rpm. This is approximately three times the normal operating speed of 880 rpm. Therefore, the critical speed has no effect on the operation of the pump. b) A revised PV0RT from has been prepared and i s attached. c) Attached is a section of the preoperational test procedure for the subject pump. Section 9.20 is the procedure for the Essential Service. Water Pump 1A Performance Test. In addition, this pump is included in the Byron Preservice Inspection Testing Program Plan for Pumps. (Page 2 of Program Plan for Pumps, T.R. Tramm letter to H.R.
- Denton dated November 4, 1982) This program has been developed in j accordance with ASME Sec. XI requirements and includes provisions for monitoring pump vibration, flowrate, discharge pressure, and
, bearing temperature. Although final preoperational test results are l not available, these test plans show that adequate pump performance will be demonstrated prior to plant operation. d) The essential service water pumps are normally operating components located 19 a mild environment. As a result, the aging is only due j to normal operation. This is addressed by the maintenance and. surveillance programs which have been established at Byron. The maintenance program is described in the response to SQRT draft SER generic item 6. The surveillance program is described i n the response to item (c) above. e) The pump is qualified by analysis (EMD-013374). In the dynamic ,
- model, the bed plate is assumed to be supported only at the i
foundation bolts. This is true for upward forces but for downward forces the bed plate channel flanges =are-continuously supported. This conservative assumption was made so that the idealized model would be=more flexible than the actual assembly, thus leading to conservative stress and deflection calculations. In the qualification document, a seismic analysis for the coupling
-(see 6.2 of Mcdonald; Engineering Analysis Company Report.No ME-523) i is presented for functional capability of the pump. -
.3120b 4
- e , ,--., -.y4,-,%- 4 y-[- . yc r-.-, --,y --,--
, , . Msfach.T.ent . 3 f, Rev. 0 c /. ,- ..
,, . Rev 1 0% ;7-82
-Bev. 2 06. 2-83 i i
PUMP ANL ',it !E
- ~
i {
- '0PERABILITY AS5 '. A 'E RE!IEW l' I. PLANT INFOR'4ATION Name: Byr n/Br81d" d Unit No.1&2 2. 50-454,'50-455
{ 1. Docket No.: so /is6. sn-4s7 .
~
- 3. Utility: Commonwealth Edison Company l 4, g333; Westinghouse Electric
{x} pyg {} g.gg
- 5. A/b . Sarg nt & Lundy .
- l II. ' GENERAL COMP 0NENT* INFORMATION
! ~ '
i
, 1. Supplier: -
[] NSSS' [9 B0P 1 ~ 2 g . 2. . Location: . a. Building / Room Auxiliary
- i
?
- b. Elevation 330' (15-N) 1
. hstem Essential Service Water j 3. Component number on in-house drawings: ISX01PA
.], -
- 4. If component is a M Pump comolete 11.5.
-If component is a [] Valve complete II.S. . .
j 5. General Pemo Data
~ '
j a. Pump b. Prime-mover . Name *ISX0lPA Name ISX01-PA-M gyg, Bingham-Willamette Westinghouse gfg, ,
$ R Model Sueti n Double Volut HHS-DP0 1 Model S/N 16210001 1013BA-0*1 -
S/N j ' ' Type 'HSA Type Frame 8009S55
.1 u -
. s I
i
- Tne component, whether pump or valve, is considered to be an assembly
.} ,
ccmposed of the body, internals, prime-mover (or actuator) and func::enal accessories. . . . I, 4 . S g .
. s e
- y .
)' z .: t' . .
; . .. .g. . . .
at Pump , (continued) $. Prime-mover (contint r) l 3g7, 24 :: 30 x 30 Sjgg 1250 tiP 12,000 lbs. Weight .14,200 lbs. Weight
! . Mounting Bolted M udng Method
- Method Bolted H.P. 1250 Required B.H.P. 1247 Parameter Desien Ooeratine Power recuirements: (include normal, maxi. mum and minimum).
3 . . _. 15 100 j ' Press . Electrical _4000 VAc Temp 100 - loo 60 llz, 3 phase
- Flow
~
24,000 24,000 1250 lip l: Head 180 180 Other 80% Minimum r,tartine voltane
!{ .
l Reouired NPSH at maximum If MOTOR list: 1 i - flow
- 46' - Outy cycle Continuous .
t Available NPSH 40' Stall current 520% full load {- ,I Operating Speed 800 rpm
- Class of insulation B' i ,
R Critical Speed 2611 rpm' . 7 , l, List functional accessories:, conto 1. switch 0 1PM06J'and IPLO4J. Lube oil pump and motor space heater. " _' List control signal inputs: Interlocks with ISX027A, IPS-SX139, Jube oil pressure, ISX,016A, ISX001A, IPSL-SX023 ESW pump low suction 1 pressure, ,
~
- Functienal accessories are those sub-ccmpenents not suoplied by the
. manufacturer that are required to make the pump assemoly operational, (e.g., coupling, lubricating oil system, etc.) ,
l
. 9 e '.
*
- e
<--.-g- , - - - - - ~ g, ~ . . , ,
'1- ,
g ,' ,, 3 b - 6. ,, General Valve Data . .
- a. Valve b.
Actuator (if not an' integral 6 unit) -- t Name Name
-e Mfg. -
Mfg.
' Model Model . -
- .t . .
i U 5/N S/N t lI . Tm
' ' ' ~
Tm
~ ~ ' ' '
.''~
~
l
- i -
Size
- l
.:J,
-Size -
}l Weight
- Weight -
.I q Mounting *'. Mounting - i .. Method Method fi a ' ' Required . il . . Torcue . Torque i Parameter ' Design. ' Ooerating Pcwer recuirements: , (include L
- . . . . . . . . normal, maximum and minimum). .
a1 .. q . Press - Electrical 41 . 11 .. Temp - d; - p - 73 , . c ', Max AP across valve n - ij , Closing time 9 max 3P Other: [] Pneumatic [] Hydraulic fi -
, Opening time 9 max AP - -
Power requirements for functional - -
, accessories, (if any) 1 , ~
d
, List centrol signal inputs: '
6-a . . 1 .
. l 1
1 . t .
---m.., , _ . , --.e, ,
.,m,re,. ,
,- - - ~ .a m . .. a :n v __ n
~~m t ..
4 , s -
. . \
l
; List, functional accessories:* -
i III. FUNCTI0ft
- 1. Briefly describe components normal and safety functions:
TraTafers--he'at loodt gienerated by safety-relnecd equipment; tr mquip-ment essential-to safe shutdown of the react,or to the ol.timate heat
.. sinu
*;~ -'- - ' ' - -- ' --- ~
4 j j . . . . The cmponents normal state is: . [] Standby i 2. [>] Operating 5 -
'j 3. Safety function: '
i . j . a. . [3 Ernergency reactor
~
- b. [@ Containment heat- .
- shutdown rerroval j . c. . .[], Containment isolation d.' ,[] Reactor heat removal ,
e., []Reactorcorecooling f. []Preventsignificant release of radio-active material to 'l *
,, erivironment ,
1 -
- g. [] Does the component function to mitigate the consecu'ences j'
.of one or more of the following events? [8 Yes [] No If "Yes", identify.
[8 LOCA [x] HELB '[@ MSLB
. []'Other
.J
- 1
- l 4. Safety requirements:
,[] Intermittent Operation [] During postulated event
[@ Continuous Operation [] Following postulated event '. - 'l _.. . . If component operation is recuired following an event, give 8 -
, approximate length of time ccmponent must remain operational.
k throughout duration of accident (e.g., hours, days,etc.) Functional accesscries are those sub-ec=cenents not suoplied by the manufacturer that are recuired to make the valve assembly operational, 1
. (e.g., limit switches). . .
} . .
= _ __ -
1
. . ~. .
[-
.' \
1
}
'i
- 5. For .', .'.15 : . . . . . .. ..
) . . . does tr.a ecmponent .[] Fail.cpen [] . tr:1 cicsed [] Fall as is .t 't l; . . . . .Is this .e f all safe positton?, [] Ye: []No , p
- Is the valve used for throttling purpcsec2 []'Yes [] No Is the valve part of the reactor coolan :ressure bcundary?
, ., [] Yes [] No .
Does the valve have a specific limit fer _ ,eakage? []Yes []No . If "Yes" give limit: . ,
' ' " ~ ~ '
, IV. QUAL.IFICATIt'4 .' ,.. ._ . . . .
( . a
- 1. Reference by specific nudber those app 11:acle sections of the design cedes and standards applicable te :me component:
ASME Section III 1974 Ed.. throngh 5 '76 .CD. Refe'rence those cualification standards, used as a g'uide to 2.
.l qualify the component: 1EEE 323 - 1974 Notor only) R 1EEE 344 - 1975 -
)
- 4
- 3. Identify those parts. of the above cualification standard's deleted
.: or modified in the qualification program.
1 ! Deleted: ,,
. Modified: .
{ _ 4 . .
. 4.- Have acceptance criterias been established and documented in the '
test plan (s) for the component? [x] Yes [] No i .
- i. . ~ 5. What is the expected f ailure mode that wcui:' kedp the pump or
- valve assembly frem performing its safety function? Pump trip, R loss of power to motor, loss of. pump suction.
- 6. .
Are the margins
- icenttitea in tne cualifica:1cn cocumentationi
.[3]Yes [] No .
- d. Margin is. the difference between design blasis param'eters and the~ test parameters tised.for ecuipment qualificatien. .
- . c .
, , ~ - , -
m.~ -. ,,
Y
. ~
. .c l , . s .. '
~.
j If ccmponent is a PUMP, complete IV.7. 2 - If cccoonent is a VALVE, ccraplete IV.S. . i . .
- 7. Pump operability has been demnstrated by: [] Analysis
- j '
[x] Test [] Combination , , p; . . . . Identify PUMP tests perfor:cd: ~~j . a. '[x] Shell hydrostatic b. [] Bearing temperature - n!
- (ASME Section III.) - .
evaluations . l Si c. Q Seismic loading . d. [] Vibration levels . ,
-l , . _ . - . . . ..
@] Exploratory vibration f. [] Sial leakatje 9 hydro press
~
ej ., e. .j - . l.] (Fundamental freo. . ) - - Q Aging: 9 Thermal
.R g. h. .
[Q Flow perform:ince
.(Hotot only.) []. Mechanical Are curves provided [>] Yes .
[]No 3
- 1. @ Pipe reaction end' ,j . []Others
~ ~ ~' 'i .-.
loads (nozzle loads) .
'~ ' ' ~ ' ~
'4 R k. [>] Ext,ref.e environ $ent:
. Motor only [.3 Humidity - -
'l [] Chemical H .
'j '
Q Padiation Valve operability has been demonstrated by: [] Analysis
~
.8 .
.j. , [] Test [] Combination , , Identify VALVE 1 tests performed:
~ ' ]'
- a. [] Shell hydrostatic- b. []Coldcyclic List times:
(ASMESection,III) ,j Open ! Closed 5 -
.{
c.- [] Seismic loading d. []Hotcyclic list times: ' Open
')i Closec a ,
- e. [] Explor'a tory vibration f. [] Main seat leakage'
' ~
(Fundamental frec. ) ,
.( i n~ , , ,
, . . '..e
- i l
a j
. l
~
l 1
i
, l
, -7 . -
q [] Aging: [] Ther=1 t. [] Sack seat leakage [] Mechanical ,
- i. []Pipereactionpnd j. [] Disc hydrostatic loading "
k.' < []Extremeenvironment 'l. [] Flew interruptien capability
. []liumidity
' "~
[] Chemical , . i - [] Radiation , i
- m. []Flowcharacteristics n. []Others
,Are carves provided? -
[] Yes - [] No
- 9. hsaresultofanyofthetests(oranalysis),wereany deviations from design reatrir'ments e icentified? []Yes [7] No If "Yes", briefly describe any chances made in tests (or ..
analysis) or to the component to correct the deviation. ~ 4 j .. t - 1
- 1 R. 10. Was the test ccmp'onent precisely identical (as to model, size, o etc.) to the in-plant ccmponent? [x] Yes* [] No If "No", is.
i . installed component [] oversized or [] undersized? .
., *for pump tests only, motor qualified- by generic test 1- 11. If _tyoe test was used to qualify the component, does the type test meet the reouirements of IEEE 323-1974, Section 5.?
4 j [>] Yes - [] No Motor only l -
- 12. Is component orientation sensitive? []Yes []No [x] Unkncwn
.I ' -
If "Yes", does installed orientation coincide with test
', orientation? Yes However, installed orientation concides
. with test orien[]tation [] No
- j. '
- 13. Is the ccmponent mounted in the same manner in-plant as it was I during testing (i.e., welded, same number and size bo~lts, etc.)
.] [S Yes [] No [] Unknown g ,
Motor only. j . . e
I .
.p. .
j
- a 14 Mr s the'cualificaticn tes.5 ;e f or- ed in secuence' and on oniv one component? [2 Yes [] to Motor only If "Yes" identify secuence, (e.g., radiaticn, seismic, cyclic, 4
thermal,etc.): thermal nochantent cycti m wie l1 1 -
- 15. If " aging"* was performed, icentify the significant aging
> mechanisms:
8 ' i R, 16. Identify loads impose'd (assumed) on the component f.or the . qualification tests (analysis) performeo: . .
- a. [] Plants- (shutdown loads) b. []Extremeenvironment I c. [<] Seismic load d. [] Others q - -
R 17. llave component design specifications been reviewed in-house to assure they envelope all expected operating, trans.ient, and -
- accident conditions? .[4 Yes [] No .. - - .. . . . . ,
R
- 18. Does the component utilize any unicue or special materials?
j (E.xamples are special gaskets or packing, limitations on nonferrous ' materials, or special coatings or surf aces.) i 1 [] Yes .E<] No , .
.1 .
1f "Yes", identify:
]q y . , . _. , ,
q
-j R 19. Does component recuire any special maintenance procedures or .
d practices, (including shorter perioos between maintenance). ~- d [] Yes [] No If "Yes", identify: The standard plant maintenance proaran will ad-dress all required ma'intenance considerations for this component. 4 L 20. Is the qualified life for the component less than 40 years? c.
?! []Yes [9 No If "Yes", what is the cualified life?
I .
- As outlined in Section 4.4.1 of IEEE-627 1980.
'i i . . l' l t .
+ . - f.,
, ~~ '
7 . g . (Q .
(] ,
8-30-82' ]'.~,'* 21 . Infonnation Concerning Qualification Docisments for the Component ISxolPA - , , b
- Report Report l Company / Organization I(Company / Organization tiumber Ti tle Date iPreparing Report Reviewing Report
--i I FL- Miscellaneous Pumps 5-4-77 S&E S&L/ CECO 2758A (Safety Category I) i FD-162 Essential Service- 4-12-7f: Bingham Pump Co S&L/EECo 10001/ Water Pump - .
2 &5/6 NPV-l' Manufacturer's 8-31-7f Bingham - Willametto S&L/ CECO Data Report - . j
'I
~
. 4 i
p 16210001 Performance.7 Test 4-13-78: Bingham -7Wil:1cinette S&L/ CECO j i 1 1013EA Seismic Analysis 7-31-78! Westinghouss S&L/ CECO for SX Pump Motors ME-523 S ' 3-23-78 Bingham - Willamette S&L'/ CECO . na so , Horizontal Pumps, i 2.7.6. Essential Service .., I 3 10 Water Pre-Operation 11 ECo 'S&L/ CECO Test , . . i 2 p
. 1 .
e
e 4.0 - ACCEPTANCE CRITERIA
~
4.1 Each Essential Service Water pump shall have a minimum capacity of 24,000 gal./ min. at a discharge head of 180t10% feet. 4.2 Each Essential Service Water Diesel Make-up Pump shall have a _, minimum capacity of 1500 gal./ min. at a discharge head of 360 10% feet. 4.3 Each Essential Service Water pump shall provide a minimum supply of 5320 gal./ min. to the RCFC units. 4.4 Eacn Essential Service Water Pump shall provide a minimum supply of 16,000 gal./ min. to either the Unit 1 or Unit 0 Component Cooling Heat Exchanger. M 4.7 Each Essential Service Water Pump shall provide a minimum supply of 105 gal./ min. to each ESW cubicle cooler (1 A and IB).
~
l M m M i M M M e M
.'m 4
. , I. . .
3-9.0 TEST PROCEDURE (Continued) 9.20 Essential Service Water Pump 1A Performance Test NOTE The following section will test the performance of the 1A SX Pump. The OA SX cooling twer basin must be filled to a normal level. The strainer must be clean'.
-] 9.20.1 Verify OPEN suction valve ISX001A using handswitch lHS-SX017 on IPM06J. ,
/
9.20.2 Verify OPEN RCFC inlet valve ISX016A using handswitch 1HS-SX106 on IPM06J. '
/
, 9.20.3 Verify OPEN RCFC outlet valve ISX027A using handswitch lHS-SX107 on IPM06J. /
9.20.4 Verify alarm window 12D01 **ESS SW PUMP SUCTION PRESS LOW is CLEAR Pump 1A. / MI 9.20.5 Verify pump casing is filled and vented. /
,a 9.20.6 Verify normal oil levels in sight glasses. /
m j 9.20.7 Verify cooling water is lined up. / 9.20.8 Position discharge valve 1SX143A to approximately
- 10% open. /
^
9.20.9 Verify Racked in the breaker for SX Pump 1A. 4160 V Bus 141 CUB #2 (ISX01PA). / 9.20.10 Verify the breaker for Aux. Lube Oil Pump 1A is CLOSED.
-] MCC 131 XI Compt. J2 /
9.20.11 START the Aux. Lube Oil Pump 1A from the local
- handswitch. /
j s l 3 -181-
)
o
T 9.0 - TEST PROCEDURE (Continued)
*] 9.20.12 START SX Pump 1A by placing handswitch 1HS-SX001 to the CLOSE position until the main pu:np starts. As soon as the pump discharge pressure begins to rise, slowly throttle the discharge valve, ISX143A, open approximately 40%. /
9.20.13 STOP the Aux. Lube Oil Pump 1A. / NOTE: Allow the pump to reach normal operating temperatures.
. 9.20.14 Take pump data on Data Shedt 11.3. /
9.20.15 Take vibration signatures on the pump and motor.
/
- 9.20.16 Using RCFC outlet valves ISX021A, ISX025A, ISX021C and 1SX025C, balance the flow to the individual coils.
Each individual flow must f all within t 25 gpm of the average of the four flows. Record data at item 11.5.1.
/
9.20.17 _ Verify ESW Diesel Makeup Pump OA is in PULL TO LOCK. 1 , 9.20.18 Using blowdown, bring the Tower 0A level down to the minimum operating level. Record tower level and record any vortexing observed near the suction duct. Monitor OLS-SX096. Record the level at which the switch closes.
- Level Observed vortexing OLS-SX096 (level) /
s
-182-N-.
'9 9.0 - TEST PROCEDURE (Continued) 9.20,19 Increase the tower level using available makeup.
Establish a maximum operating level of approximately S74'2" or 6'5" from the Basin Bottom. Record tower level and any observed vortexing. ,
*" Level
.. Observed Vortexing
.. . /
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1
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-183-
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DATA SHEET 11.3 PUMP DATA FOR SX PUMP 1A SUCTION DISQlARGE FLOW RATE DATA PRESSURE (PSIC) PRESSURE (PSIG) (GPM)
. PO LNT LPI-SX148 IPI-SX008 FLOW METER ~
l . a 2 , 3 i 4 I 5 6* q d NAME DATE G J ,
- Data Point 6 will prove the capacity of the SX Pump per the Acceptance Criteria.
1 1 3 s
., g.
O O
.) <-
- q
?
\ l Attachment 86 Containment Spray Pu;ap (ICS0lPA)
(PV0RT-80P) The responses to the open audit items are as follows: Open Item 1 - The qualification documentation has been corrected to be consistent with the serial number of the installed "A" pump. The L documentation has been approved and signed off. Open Item 2 - Attached is a section of the Containment Spray System preoperational test procedure results for the subject pump and the corresponding acceptance criteria. The test results meet the acceptance criteria and demonstrate that the pump performs adequately within the system. In addition, this pump is included in the Byron Preservice/ Inservice Testing Program Plan for Pumps (page 1 of Program Plan for Pumps, T.R. Tramm letter to H.R. Denton dated November 4, 1982). This program has been developed in accordance with ASME Sec. XI requirements and includes provisions for monitoring pump vibration, flowrate, and discharge pressure. The preservice and periodic inservice testing described above will demonstrate the operability of the pump for the life of the plant. Open Item 3 - The containment spray pump and pump motor are located in a cubicle. They are exposed to a harsh environment only because of the radiation levels associated with the location adjacent to the containment and the accident mode of operation (handling radioactive containment sump fluid). The containment spray pumps are operated only during system tests and following a LOCA or Main Steam Line Break inside containment. The containment spray pump motor has been environmentally and seismically qualified (Westinghouse Report WCAP-8754 Rev. 1 and Shop Order 77F14089) and has a qualified life of 40 years under Byron specific conditions. The pump has been seismically qualified (Ingersoll-Rand Report EAS-TR-7801-IR). Although a specific program for environmental qualification of mechanical equipment is not required, a' review of the design of this pump has been performed to insure that it has been properly designed to function in the specified high radiation environment. A summary of this review is attached.
. 3 Q .e Containment Spray Pump (ICS0lPA)
(PVORT-BOP) Open Item 4 - Seismic qualification of the containment spray pump was accomplished by analysis (S&L Report EMD-025038). The analysis was done using the-faulted-condition. The results of the analysis indicatec that the lowest natural frequency was greater than 33 Hz (page 4, EMD-025038 attached) hence the equipment is considered rigid and qualified by static analysis. .The containment spray pump is designated as seismic Cat. I, active equipment which means the pump must meet performance requirements during and following a safe shutdown earthquake. In the static analysis, the seismic forces _on the pump assembly are obtained by concentrating the entire mass at the center of gravity of the assembly and multiplying it by the appropriate seismic accelerations. In this case the seismic accelerations for safe; shutdown conditions are as follows: Horizontal = 0.259 (in each of two orthogonal directions) Vertical = 0.859;. (page 3, EMD-025038 attached) These acceleration values are used to produce the equivalent static
-forces for the analysis.
3120b
i
- 1 APPROVED i _
i i,0 ~~ST OBJECTIVES c0R TEST'NG i 3 .1 To demonstrate the ability of the Unit One components 1 8 of the Containment Spray System to meet their design and [ operational requirements. 3.2 To insure proper operation of all equipment, controls, alarms 4 and interlocks associated with the Containment Spray System. 3.3 To insure that the Containment Spray System will be capable of delivering a fluid solution at proper flows and pressures to the Contaidnt Spray headers. 3.4 To verify the spray nozzles are unobstructed. ACCEPTANCE CRITERIA 4 .1 Verify that the capacity of containment spray pump 1CS0lPA is a minimum of 3545 gpm at a head of 450 feet. 4.2 Verify that the capacity of containment spray pump 1CS01PB is a minimum of 4055 gpm at a head of 450 feet. 4.3 Verify the ability to educt a minimum of 55 gpm indicated of fluid from the spray addition tank into the spray discharge flow using the installed flow instrumentation. 4.4 Verify all spray nozzles are unobstructed. I l l l l I~
! A?3 ROVE) !~
1 IST PROCEDURE (Continued) FOR TESTNG t --- a l i i.19 Containment Spray Pump ICS01PA Integrated Testing I
$ 1 7;
+
9..9.1 Verify the Blank Flange is installed at ICSO4MA and y [ the temporary jumper to the Fuel Handling Building
} rainwater header is installed. v'Jrkp g //2 /r-re.
i 4 9.19.2 Verify that CS pump 1.'. and all loop A piping has been filled and vented. Erdff/n-er-t2 9.19.3 Vent the pump seal cavity by opening the seal vent i valve 1CSO49A. 6274d' /f]-/S'A* *2 9.19.4 Verify that the CS pump 1 A motor oil reservoir has been filled to the proper level. @ f/r)-ir,s 2 9.19.5 Verify a minimum level of greater than 20% for the RWST. 477/4 if/r 2 /r,9 2 23
., 9.19.5 Iunull m. 2:r2cenic fleureter er li- Ic?l21.1. 3".
r? 9.19.7 Verify a normal operating line-up for containment Spray b Pump 1A and Containment Spray Loop 1 A from the RWST . I! .r as per M-46 and M-61-4. g&b;9 / o.f r-r2. (j d ' 1 9.19.8 Open test line discharge isolation valve ISI001A. th!n d /12-tC-f 2,, 1 1
. 9.19.9 Rack-in the breaker for CS pump 1 A at Bus 141, . Cub. 9. "?M A m //2-ir-/ 1 ,
9.19.10 Close valve ICSO40A. W/4 I / /A- frA'1 ; 9.19.11 "0 PEN" 1CS010A by placing its handswitch at IPM06J 'I in the " Test" position. N i $ / a-15 @ i 9.19.12 Place the CS pump 1A Test Transfer Switch on MCB IPM06J in the " Test" position. @'4'i7 /;'2-)f fa . ! 9.19.13 Start CS pump 1 A by going to close on MCB IPM06J. 4fno f /n-v-r4 l l i a
^
, e i APPROVED i F
1 TOR TEST NG fi r
,,, . ^ JROCEDURE (Continued) 9.19.14 Verify CS pump 1A operating parameters on Data Sheet 11-19, throttle valves ICS007A (i and ISIOOLA to obtain these flow rates. (
a l , l 49'kY$ /13- /f*-L? 9.19.15 Verify the SAT is filled to nominally 55% with Grade " A" water. ,h.ff / f 2 - > r - 9 2 .' t 9.19.16 Open valve ICS040A. he;/2 / s 2 -se-72 9.19.17 Open va,b,re 1HOV-CS019A at MCB IPM06J . 6/NJd //2.,3.yz 9.19.18 With CS pump 1A in operation at a flow rate of nominally 3545 gpm, adjust valve ICS021A to yield ff f~ l approximately 38 gpm as indicated on 1F1-CS015. l JP7m 4' /p1-Is"-12 9.19.19 Record the following: CS pump 1A Disch Flow Rate (lF1-CS0ll) t s CC gpm (m.kas. = .3sor9 p /htt1 % / /2-pr-V2. ( CS eductor lA Flow Rate (lF1-CS013) /3r - gpm t 1 (tct;t. E 1F1-cstnt ~J'j t'ap~) %g /pyy.yz ( ',
-l '-
[ N. A Spray Additive Flow Rate (lF1-CS015) 57 spm f. Y //7?t? A (se'y , -O, +2 2ry) shre I i 2 -o<-v 2. y.2 g icni; ric"ecter Cp cy 1.dditiu Tier nat; gnm-- gc rt *.23 _ (1 : ,,- , '*' ^ ' 9, } Spray Additive Tank level N Y2 % A :f / /2 -ir- 9'A C20 -r.r se. ) 9.19(.20LockvalveICS021Ainitspresentposition. Ah74 7D/ (2.-fr-S*3-9.19.21 Close valve ICS019A. //77Cf 7]l / / 2 -n -42. 9.19.22 Close valve ICS007A. #}ru 1 /12-/f- Q
APPROVED p. 2 u--
- ..: r PROCEDURE (Continued) FOR TESTING .
M.
-?t y
w 9.19.23 Open valve ICS019A and verify the CS pu:sp 1A g g e-c o 7; operatigng parameters on Data Sheet 11-19.
- 4 h /?%d'i / O as-Y2 l*
P 9.19.24 Close valve ICS019A. #7w d / o-27 r 2
?
7 9.19.25 Verify CS pump 1A operating parameters on I , Data Sheet 11-19. #21o p? / n -2sr-r2 9.19.26 Trip CS pump 1A. 44 n/ / fy .2g.e2 ,
, 9.19.27 Close valve ICSO40A. Sin,-p / f j-a r- r2 9.19.28 Close valve IS1001A. #fvf /12-x.e 2 t +
4 N 4 ;
) i a
4 i - -? ,
ws~w i inia r iter r i -t 9 - c.,- 13 Item # Nour; :: cme or Egalva lent 11.19.14 Flow Rate 2000 gpm * . d iMC- #' Ant /E-" c Suction Pressure (IPI-CS003ff4 P .,c vs a g. r.1 e.rd /g-a .r 2. c Discharge Pressure (IPI-CS004) Apsi j_ A 6 en ;:e / s2-y .s 2 c CS Perop 1 A Disch Flow Rate (IFI-CS011) gpm hed .. OS /rz e.9 2 c CS Edoctor IA Flow Rate (IFI-CS013) gpm / (As- . w , 1 /2/ - y -9 2. Running Current (amps)Ce.~,b 75%. g.) Ji 2 + Arf //,2-5 r2. Flow Rate 2800 gpm
- a yCO G*t:t / c-tr-St c Suction Pressure (IPI-CS003) fA. pts .rr' 'd' , l.. > .3 </- //'insf /,,a -,r r2 c Disci.arge Pressure (1PI-CS004) ft ,pri M p- mg_/y-sc 2.
C CS P a p 1A Disch Flow Rate (IFI-CS0ll) gpm 2 god e,n A / 82-ar-t2 c CS Eductor IA Flow Rate (IFI-CS013) gpm . /3t/) e, /2 / ,3 -4.u O 3 Running Current (amps)(e.arl- = vr n j.f) M') Wr M /s> -er.o. 4 -28 7 Flow Rate 3545 gpm * :LrsO .er.,f / A2.if r2 c Suction Pressure (IPI-CS003) ff t. p,,e b .3 3 y.a. w.f / ,,2 -ry, c Discharge Prssure (IPI-CS004) ,5f fs; **'" J. 4-2 e 4tf/,2.g,e2 C CS Pump 1A Disch Flow Rate (IFI-CS0ll) gpm 3550 Wa# li2vrez
\c CS Ecuctor IA Flow Rate (IFI-CS013) gpm r a c- fitt f /ra-<r t z
', Vibration Data Taken vo5 9<tti/ ,1-/6g2 L
-ARunr.ing Current (amps)(~asi : Pr .f.,) 'A Y #4A /s2-i.e4 7
TO 9GO VS CS 1 A MOT INBD BRGT (~oriaa.- -#4#*#) 15'2 5%a9/i> irs 2 TO 901 VS CS 1A MOT GUTBD BRGT(masie. a.=/Tr V) 62 9/r?d'/s2-ysm. 6] & f /L).~/S'-9% m O :e JJ U
~O H PJ m
(Z)9 ys m C ' G3 i
/ a*@m9te@@WMWeM%n -
>' *a ' ^
- e '*M > 99'!dW 9MM'd(Ii
'~
i brrA , t' Nameplate / Itan i Noun Name or Equivalent u. . o . . . c . i . . i . a . . .u - r s Y si~,*'e > x ,e. 11.19.24 C Suction Press. (IPI-CS003) fr. F wa _ Y A 4~ yo. f 9,ra r] / ta-a s .9 2 C Discharge Press. (IPI-CS004) it.pi "'"* __A d _ 29r .3r40 / fa.ne s.2 C CS Pump 1A Disch Flow (IFI-CS0ll) gpm '
- u. m 9,-; * /a-29 c2 ggt *2 Q' C Test Line Flow (IFI-SIOO6) gpm (or uur s,~,;d bc wo / ,2-2,-ca
**'" C Spray Additive Flow (IFI-CS015) gpm 55' em a / o -n eg z C CS Eductor I A Flow (IFI-CS013) gpm Iv r o. -r ,' /.x-u ea 11
[n s -s z- f c ~ ~ * >~ "b=.: : : by- ua Sp:37 !.dds4h L i^.; erte .1 G S 92-n ' 11.19.26 C Suction Press. (IPI-CS003) M pri saa s' yo 5 %s+ / ,3_3s o C Discharge Press. (IPI-CS004) Et'.pi 82 P '
- 2&5 #o / ,2 -as -e2 C CS Pump 1 A Disch Flow (IFI-CS011) gpm von e rf / st y .sy 7cA
- 2f2. C Test Line Flow (IFI-SIOO6) gpn G< udre.sc id in s .p.e s / ,2 .as -se me. * ' # C CS Eductor IA Flow (IFI-CS013) gpa /yr ,u-, / n _3 , . =
Vibration Data Taken oca e .'<r07 / a -21r.s.1
/
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SARGENT 1 LUNDY og c,c,jre.irar.fcirt'.WA'l Ft1aFs. n,,. o o o,,, . q,- iaNGINEeMS e C*""" N Safety-Related Non-Saf et y-R elated Pne /- ( of f / '7 Chent COMMot/NEhlT*1{ Eatsai Ccif'-rs'l Prepared bv 3% . Q4we . ostek2-SM Project 9//ROtl /P:f'ArDWCOM Reviewed by /) , I ft-te, Date 2 L* ] Proj. No.h/
. _.Q 3 ef-N O 00 Equip. No,/ 9 *]_ C,5 O / [A ff, 7 Approved by h t/ /h . , , , ,, j Date Md 7
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REFERENCES:
p l(A b k PaEe....C I8 'I CC 1 - Ingersoll-Rand Co.'s Drawings: C-8x23 UDF 86x7B; P.L. 8x23 WDF 500x6, pg. 1&2 C-8x23 WDF 500x6A; L.N. 8x23 WDF 86x7, Sheet 1, 2, 3 of 5. 2 - Durametallic Co.'s Drawing: #2D-157002-RI dated 7-7-77. 3 - Telephone conversation of M. Khan (S6L) with Stan Samuelson (Ingersoll-Rand) dated 11-19-82. 4 'Ielephone conversation of M. Khan (S&L) with F.B. Heakhcote and Henry Scheiter of Ingersoll-Rand, dated 11-18-82. 5 - L7on's " Valve Designer's Handbook". 6 - Wyle Laboratory's Qualification Plan #17491-5. i'. _ 7 - Byron & Braidwood FSAR, Table 3.11-2 for Zone A13C. 8 - Ingersoll-Rand and Durametallic maintenance and Instruction Manuals. 9 - K. J. Creen's memo to T. Thorsell, dated 7-21-82. 10 - Ingersoll-Rand Co. 's Certificate of Conformance for the design of the pumps. 11 - ASME See XI-Div.1, Article IWP-1000. 12 - NRC's memorandum from.Z. - R. Rosztoczy to W. V. Johnston, dated 6-23-82. h 13 - IEEE 627-1980, " Standard for Design Qualification of Safety Systers equipment used in Nuclear Power Generating Stations. j 14. .P&ID Drawings: M-46 and M-61 Sheet 4 of 6.
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. . ' Calc. No, SARGENT RLUNDY amow..,,,_ R 'V- Date
* "'C^"
A Safety-Related Non-Safety-Frefatch Page of Client Prepared by Date Project Reviewed by d Proj. No. Equip. No. Approved by _, , tw C@ @ _9 , , *[
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Cales. For Calc. No. SARGENT t LUNDY
- ~ R ev. Date E NGINE tMS .
. X Safety-Related Noa-Safety-Related Page of Client Prepared by Date Project Reviewed by Date Proj. No. Egitip. N o. Approved by . _ _ _ , _ ,, g n e,(,l Q D_ ate,.y l i
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Calcs For Environmental Qualification of Cate. No.CQD-006151
<. SARGENT h LUNDY c uwnca==
Ingersoll-Rand 's Centrifugal Pumps,8x2'b'DF R ev. 00 Dare2-25-83
'*"C"" ~
X Safety-Related Non-Safety-Related Page C 1f of C 15 i Client Commonwealth Edison Company Prepared by .;ggggD. o * - te Project Byron /Braidwood, Units 1 & 2 _ _ Reviewed by hMk Proj. No. 4391,2/4683,4-00 Equip. No. l . 2 CS01 PA. PB Approved by pM (f$ O! "' ENVIRONMENTAL QUALIFICATION PARAMETERS COMPARISON , Equipment Name: Containment Water Spray PumpsManufacturer: Ingersoll-Rand Co. Loca tion : Aux. Building, Elev. 346' for P'A Model (Catalog) No. : 8x23WDF,
& 343' for PB Centrifugal Function: To pump reactor grade water to the spray nozzles.
(see S&L spec. F/L-2758B and Proposal Technical Data in Spec.) PROCUREMENT DESIGN CONTROLLED ENVIRON-PARAMETERS SPECIFICATION SPECIFICATION MENT COFDITIONS Temperature 290"F 290*F ll5*F* Pressure 350 Psig -0.5-0 in H 2 O Ilumidity 0.90% Radiation
- 9 lx10 Rads Fluid R a tor grade Reactor grade water Reactor grade water r
Voltage Current Frequency Seismic Class Category I Category I %_Mm. NS--h, Power Qualified Life
~
40 years 40 years o o
*During operation, the water in the pump is at 93 - 290 F m
h .
=
E4 O l
e , e 3.0 DESIGN LOADit;G CONDITI0hs ' O. S_eismic - The DSE accelerations used in the static analysis for rigid, active equipment are as follows: Horizcntal .259 (in each of two orthogonal directions) Vertical .85g Multiplying these accelerations by the weight of the pump equipment produces the equivalent static forces for the analysis. Nozzle - The. faulted loads are listed in Appendix E. These loads are considered in the analysis of the casing, foot and anchor bolting. Torque - The torque created by the rated motor horsepower calculates to be 21,245 in.-lb. - Steadf-State - Design conditions for the pump are:
~
Pressure: 350 psi Temperature: 2900F ('b" Transient - The thermal and pressure transients are as follows: Temperature Differential Cycles Mode 2900F 1 Accident
' Pressure Differential Cycles Mode 275 psi 481 Testing & Accident The analysis considers the ccmbined loading which creates the maximum stressesanddehlections.. ,
b g 'e t ~.v
. '. .. * ?. ' . .
4 4 n . 4.0 SU'dARY OF RESULTS , 4.1 Natural Frecuency l First Five (5) calculates frequencies
- 1. 58.4 HZ
- 2. 58.5
- 3. 108.7
- 4. 108.8
- 5. 110.1 4.2 Structural Intecrity (Faulted Condition) ,
Component Calculated, psi A_11owable, psi casing Foot Attachment 1,745 23,250 Casing Disch. Noz. Attachment 4,708 23,250 Casing Suct. Noz. Attachment 3,625 23,250
-p Main Flange Bolting 16,767 37,500 1
( Foot 12,229 29,880 h
-? Foot Weld 12,320 29,880
- Anchor Bolting Tension 10,576 40,000 Shear 4,137 15,390 Support Head 174 18,900 Motor Attachment Bolting 3,043 37,500 4.3 Operability Description Calculated Allowable Rotor / Stator Deflection .0003 .051 in. -
(MotorAirGap) Impeller / Ring Deficction .001 .0115 Shaft / Cover Deflection at .0004 .010 Mechanical Seal c0
.e.. . ---g- _
..y -
Attachment 87 Essential Service Water Butterfly Valve (ISX027A) (PV0RT-80P) Responses to the open Judit items are as follows: a) A revised PVORT form is included, b) The subject valve was procured under Specification F/L-2834. This specification contained detailed information on four valve sizes (12, 24, 36 and 48") but not on 16" valves such as 1SX027A. This valve v s procured vic Purchase Order 803068 (attached) which references Data Sheet D5004, Rev. 1 (attached) and Specification f/L-2884. This data sheet provides all size specific information required and with Specification F/L-2884, fully defines the valve requirements. This method of equipaent procurement is a common procedure and is fully documented and traceable. As a result no revision to the specification is required. c) The subject valves are marked with an arrow to indicate the preferred installation direction. This installation direction is independent of flow direction; the valve will close against flow in either direction. The arrow indicates the preferred direction for sealing against flow. A field check has been made to verify that in the installed position the valve will seal against flow from the containment when used to isolate the containment. d) The seismic qualification report for this valve has been received, reviewed and approved (Jamesbury Corporation Report JCS 82-02, Rev. 2). The valve was qualified by analysis. The Limitorque operator has been qualified by test. (Limitorque generic qualification report). These valves are included in the Byron preservice and inservice test , program. The valve will be fully stroked every three months and a position indication test will be performed at refueling _ outages. Refer to page 43 of the Byron Preservice/ Inservice Testir~ Program Plan for Valves submitted to the NRC in the November 4, , , ' ietter from T.R. Tramm to H.R. Denton. e) The operating torque of 1180 ft-lbs., as reported in the vendor report VHA-76-71, was used to review the valve design and was compared with the available operator torque to verify that the valve would function as required. The operator torque was obtained from Liraitorque and found to be 1250 ft./lb. (memo of telecon attached) f) The valve operator has been environmentally qualified in the generic Limitorque qualification program. Environmental qualification of the valve itself is not required. The only non-metallic parts in the valve are the valve seat (EPT-Ethylene Propylene Terpolyner) and the valve packing (John Crane 187-I). This valve is included in the inservice testing program and containment isolation valve leak rate testing program. Any degradation of the valve which could affect its ability to isolate the containment will be detected by testing and surveillance. 3120b
lAtta,.nent i;
- Res,*0 0'-17 '12 .
l . Rev. I'06-72-83 l- r PUMP Atto '/ALVE l
- i , 0,PERABILITY ASSL'RA' ICE REVIEW -
l, . i 1. PLANT INFOR.vATIO:1 l 50-454, 50-455 Docket No.: 50-456, 50-457
- 1. Name: . nyron/nraidwood Unit No.1&2 2.
- 3. Utility: Commonwealth Edison I 4. Westinghouse Electric NSSS: g pyg {} g.gg Sargent & Lundy
.. 5. A/t: . . ! II. GENERAL COMPONENT
- INF0PMATI0tt l
l
', 1. Supplier: []NSSS [x] BOP
- 1 2. . Location": . a. Building / Room Auxiliary .
i . 395'-0 (13-Y)
- b. Elevation t .
l' 1 .
- c. System Essential Service Water
} 3. Component number on in-house drawings: ISX027A
- 4. If component is a [] Pump complete 11.5.
t
. If component is a [9 Valve complete II.S. . .
; 5. General Pumo Data -
' ~
- a. Pump b. Prime-mover .
f Name ' Name
~ ; Mfg. Mfg. -
Model Model - S/N -SIN'-~~~~~~~*-L-*' f , TypeI , Type t . 1 Tne cemponent, whether pumo or valve, is considered to be an asserbiv 4
, ccmposed of the body, internals, prime-mover (or actuator) and func:1:nai .
accessories.
.I -
. 1
. , i
~
e
~~ . -
a s i
. . J , . ,- 7 .
1 Prime-mover (continued) i a
- Pump , (continued) .i i Size Sna a'
. Weicht. Weignt Mounting Mounting
- Method Method Required B.H.P. H.P.
Parameter Desian Ooeratinc Power requirements: (include normal, maxi, mum and minimum) .
! Press Electrical '
Temp
~ ~'
- j Flow .
r l' Head Other l 't .' 1 _ j Reauired NPSH at maximum - If MOTCR list: . flow _' . 'Outy cycle .
~
- Available NPSH _
Stall current i Operatin'g Speed *
- Class of insulation 3 ..
I j . Critical Speed - 3 s
-j List functional accessories:*
^t
\ .- .
.. List control signal inputs: -
t 3 '
- Functienal accessories are those sub-ccmponents not sucolied by the manufacturer that are required to make the pump assemoly operational,
]
; (e.g., coupling, lubricating oil system, etc.) -
6
- l , .
. 3
- . i
- 6. General Valve Data
.. y...-
- a. Valve b. Actuator (if not an' integral unit)
Name 1SX027A Nhme ISX027A - Mfg. Jamesbury Mfg. Limitorque i Model 16-8026 Ex. "A" Model SMB - 00/7.5 H1BC S/N NC-48856 - 03C S/N 264/68 i . H1BC
- Wafersphere " ~ - - -
- . Type Type Size 16"
~ ~
Size SMB-00 .
} -l Weight 190 -
Weight 335 Ib's. j . i Mounting Mounting -- Method Bolted ' Method -
} -j .
1 Required ~
- Toraue 1180 ft./lbf Toraue 1320 ft-Ibf.
R j .
' ~
l Parameter ~0esien. Ooeratina ~ Power reautrements: '(include t
~ .' . . . . . .
normal, maximum and minimum). . 7 240 50 Electrical 33 up
- i. .
Press-
+ -
Temp 190 189 460 V l 3 phase j'- ' Flew - 6,600 __ 6,000 60 Hz
- 7. - Max)Pacrossvalve 100 hsi Class B insulation ,
i Closing time 9 max ZP 15 see Other: [] Pneumatic [] Hydraulic i j Opening time 9 max TP 15'sec , l , Power reautrements for functional - - 3
. accessories, (if any) 120AC 4
i
; List control signal inputs: 4106V breaker feeding ISX01PA; 480V breaker -
!' feeding IVP01CA and IVP01CC 4 . - . t *
\'
- li l ,. 4 List.functioral accessories:* OT2 Control Switch @ IPM06J j
III. FU'iCTI0t{ .
- 1. Briefly describe ccmponents normal and safety functions: Norma lly R open for normal and post necident essential-service-water system -(sx) -in the ev'ent br~a" breech' of the essential service' water . system in containment.
} 5. The cmponents normal state is: Q Operating '[] Standby ,
s
- 3. Safety function: '
. . .- g ,.
i . a. _[] Ecorgency reactor b. [] Containment heat'
- shutdown removal
- l. c.. . . [x] , Containment isol ation
- d. ,[] Reactor heat removal
; . *for breech of sx system 'nly o -
, e. . []Reactorcorecooling f. [] Prevent significant relca:e of radio-i
( . active material to i . . . _ . . _ . _ . environment 1
! . g. [] Does the ca:.ponent function to mitigate the consecu'ences R i
rx
; .of'Ifone or nore "Yes", of the following events?* confirmatory open sIg]nalYes* [
identify.
} " '
- [x] LOCA [] HELB - '[>] MSLB
.j g'Other Breech of the sx system inside containment 1 .
l 4. Safety requirements: .
,[] Intermittent Operation [] During postulated event f- [x] Continuous Operation [Q Following postulated event .
i
.... .If component operation is recuired following an event, give R I -
approximate lencth of time ecm-onent must remain operational. singic operatiod required immediately
) after accident (e.g.,hcurs, days,etc.)
4 Functional accessories are those sub-ctmoonents not sucplied by the < manufacturer that are recuired to make the valve assembly operational,
, (e.g., limit switenes). -
e e . 4 .- -
. .- .s. . .
l 1,, l-
- 5. For VfLVES: . _ . .
,,... does the ccmponent .[]hailcpen [] Fail cicsed. [>] Fail as is
* * ~
.Is this the f ail safe position?
~
Q Yes*
*except for breech of i,x' system Is the valve used for throttling purposes? []-Yes G No ,
. ._ Is the valve part-of the reactor coolant pressure bcundary?
. [] Yes G Ho -
Does thd valve have a specific limit for. leakage? [] Yes Q No If "Yes" give limit: IV. QUALIFICATION . .
- 1. Referencebyspecificnudberthoseapplicablhsections'ofthe design codes and st.indards applicable to the ccmponent:
< ASME III 1974 ed. thru S'75-
~
- 2. Refe'rence those cualification standards, used as a guide to qualify the component: IEEE 323 - 1974 (a'ctuator oniv)
IEEE 344 - 1975 *
- 3. Identify those parts of the above cualification standard's deleted or modifie3 in the qualification program.
Deleted: . Modified: . s .
\ .
, , 4.- Have acceptance criterias baen established and documented in the *
! test plan (s) for the component? Q Yes [] No t
. 5. What is the expected f ailure mode that would keep the pump cr valve assembly frcm performing its safety function? fail open i
after breech of sx system 6.. Are the margins' icentified in tre qualification cocumentation? [>] Yes [] No .
- d. Margin is the difference between design basis parameters and the test parameters used.for eouipment qualification. .
e I- -
r hi If cp=poner.t is a FUMP, complete 17.7. i 1-If cccoonent is a VALVE, co plete IV.S. ,
.i .
l . 7. Pump operability has been de.mnstrated by: [] Analysis
,) [] Test [] Ccedination J .
,i Identify PUMP tests perfor:ned: -- .
s . j *
- a. []Shellhydrostatic b. [] Bearing temperature 3 (ASME Section III) .,
evaluations H, c. [] Seismic loading - d. [] Vibration levels . VlI e. [] Exploratory vibration f...[] Sdal leaka'ge @ hydro press 1 . ,
,1) , (Fundamental freo. . ) - -
I
- g. [] Aging: [] Thermal
[] Flow performance h. j q
. . . - [-]. Mechanical Are curves provided [] Yes , ,
j g}i []No i 1 .
,1
- 1. [] Pipe reaction erid' j. []Others 3i loads (nozzle loads) i, .
k ., [] Extreme environment:
. _ .[] Humidity . ;] [] Chemical il '
[] Radiation
] '8.
. Valve operability has been demonstrated by: [] Analysis
-j [] Test [] Combination . . . . . . _ _ _ _ _ . _ . .
11 ' Identify VALVE tests performed: .
.4 .
I . 'j -
'a. [x] Shell hydrostatic b. []Coldcyclic List times:
(ASME Section.III) Open - ll Closed
- c. [3 Seismic loading d. []Hotcyclic List times:
j., - Open i ~i , Closed
- e. [x] Exploratory vibration f. [x] Main seat leakage' (Fundamental freo. ) ,
.
- Resonant frequenef . analytically determined.. ~
,. *~. _7 .
q- * [x] Aging: [x] Thermal !. [] Sack seat leakage
*4 e tuator only [y,] Mechaniw* I ,
- i. [] Pipe reaction end c, , [] Disc hydrostat ic loading *
'k. []Ficwinterruptioncapability
~
[x] Extreme environment ' 1.
^Ct"" tor
..Only.
[] Humidity '
?
i [] Chemical , . [x] Radiation ,
- i ,
'm. []FlowcharaC.teristics n. [x] Others Pneumatic test 14 .
- . . Are curves provided?
- i '
[] Yes -[] No d ,
- 9. ks a result cf any.of the tests (or analysis), were any deviations from design requir'ments e identified? []Yes [x] No
_ If "Yes", briefly describe any changes made in tests (or .. analysis) or to the component to carrect the deviation. k . . . ..
. . 10. Was the test component precisely identical (as to model, size, .i etc.) to the in-plant component? [x] Yes []No If "No", is. ]
installed component [] oversized or [] undersized? - ]; - 11. If tyDe test was used to qualify the ccmponent, docs the type i test meet the requirements of IEEE 323-1974, Section 5.7 .
- j
[x] Yes. [] No *for motor operator only 4 l
- 12. Is component orientation sensitive? []Yes [] No Q Unknown
- If "Yes", does installed crientation coincide with test l '
. crientation? []Yes [] No ,
i '
- 13. Is the component mounted in the same manner in-plant as it was
'l; during testing (i.e., welded, same num:er and size bolts, etc.)
[>] Yes [] No [] Unknown
~
*However, installed orientation coincides with test orientation.
i e *O,,
b . t . . ... . 3
- 14. Weie the cualificatien tests t.n Nmed in secuence and or g l. i
[ . one ccaponent? fr)Yes [] i'. A tuator only. If "Yes" identify secuence, (e.g., radiatica, seismic, cyclic, E . thermal,etc.): thermal aging, mechanical aging, radiation, seismic
- 15. If " aging"* was performed, identify the significant aging mechanisms:
Identify loads impose'd -(assumed) on the component f,or the
. 16.
l qualification tests (analysis) performed: . . I a. [] Plants- (shutdown loads) b. [] Extreme
*' environment 2
- c. [x]Seismicload d. []Others 1 -
.~ . .
j .
~;
1
- 17. Have component design specifications been reviewed in-house to assure they envelope all expected operating, trans.ient, and f .
accident conditions?..[Q Yes [] No _._.. . . . _ .. ,
, g i
- 18. Does the ccmponent utilize any unicue or special materials?
(Examples are special gaskets or packing, limitations on l nonferrous materials, or special coatings or surf aces.) 4 [3Yes.[y]No 2 ( .
- " If "Yes", identify:
h
., i .
- ?
": 19. Does ccmponent require any special maintenance procedures or .
practices, (including shorter periocs between maintenance). []Yes []No . If "Yes", identify: The standard niant innintonnne.n proernm will address all required' maintenance considerations for this component..
- 20. Is the qualified life for the component less than-40 years?
O Yes [@ No If "Yes", what is the cualified life?
} , , .
f . . I
- As. outlined in Section 4.4.1 of IEEE-627 19SO. .
G .
.e
- e ,
b .
.__x____-________-__________
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-Ph0 JECT BYRON /BRAIDWOOD a
1 l CLIENT C0!O:0NWEALTH. EDISON JOB No.439Il*0 3 UfSIGN BY j,(' fbv7.d l DATE L//.; f . / J -- 1 CJiy[Cp.n ay vi 7 o . - . u-. ~ ~ ,...., STANDARD gff, Q,,: 0 REV1 SED yy DATE b.7f~/~7 v,b..c. i i ih {.t,.aY DATA SHEET NO.
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SARGEN1 sk L. U N D Y D MEMORAN1'U.I C F TEl,EPHONE C0" 'E
- SATION t
Date: June 29, 1983 Time: 11:15 a.m. Person Called: Dave Montgomery og Limitorque Corporation _ (Name) (Company) Person Calling: !!. G. L. McCullough gf Sargent & Lundy (Name) (Company) Project: Byron /Braidwood project No.4 391-0 0 Subject Discussed: Motor operator for valves ISX027A, B, for Butterfly Valves Rponi fi cation F/1 2884. Lc_ . . . Summary of Discussion, Decisions and Commitments: n$r ne winn f!onan - ? shont n nnnntion. noes Motor onerator SMB00/7.5-HIBC develop _1180 ft-lbs nr mnrn of tnraun? l>: Answer: This model has a motor torque normal rating of 7.5 ft-lbs. HI BC refers to worm gear reducer, with a maximum rating of 1300 ft-lbs. For a 15-second valve closure time, the motor operator gear ratio is 24:1. When operated on 100% voltage required, the developed nominal torque is 1250 ft-lbs. The operator is adequate for the valve operational r.equirements . !
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.CC . . K. J. Green File: - ?
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Attachment B6 Responses to PV0RT Draft SER Generic Items e 3120b
f PORVT Draft SER Generic Item 1 The status of completion of qualification documentation is as shown on the attached updated SQRT summary sheets. The status of completion of equipment installation can be inferred from these summary sheets. Complete (C) means equipment is in place and mounted. However, incomplete construction details on individual pieces of equipment are not tracked by the SQRT summary sheets to ensure completion. There are provisions presently incorporated in the construction process and preoperational test program to identify and track incomplete construction details (such as temporary pipe supports, unconnected drain lines, etc.) In the construction process, contractors to Commonwealth Edison use procedures for installing equipment that have been reviewed and approved by Commonwealth Edison. These procedures include QC/QA signoffs to ensure installation is complete and in conformance with design drawings. The contractors' QC department inspects equipment to verify it is completely and properly installed. This review and inspection function is periodically audited by the contractors' QA department and the Commonwealth Edison QA department, also. In the preoperational test program, all systems are walked down and inspected by the construction department and the system test engineer before performing the preoperational test on the system. If any incomplete installation details are identified during these walkdowns, a turnover defielency is written to document the problem at the time of turnover for test, or thereafter. All turnover deficiencies and test deficiencies for each system are evaluated at the time the preoperational test results are reviewed and a schedule is established for resolving all deficiencies. In addition, all Category 1 piping systems are given an as-built walkdown for piping analysis reconciliation. Any incomplete installation details with respect to pipe supports or hangers would be noted at that tirse. Based on the documentation and inspection programs described above, all Category 1 equipment will be completely installed by fuel load. KAA/sb/3120b
PVORT Draft SER Generic Item 2 Qualification documentation for pump and valve operability primarily consists of QC Documents (Test Reports and Procedures) and Engineering Documents (Environmental Qualification Reports, Seismic and Stress Reports, Performance Curves, Vendor Calculations). The documentation required for safety-related pumps and valves includes various material test reports such as radiographs, liquid penetrant tests and magnetic particle tests. Documentation which assures pump and valve operability may include material test reports, welding reports, hydrostatic and seat leakage test reports, rotor balancing test reports, performance test raports, seismic and IE electrical qualification reports. Specific requirements for pumps and valves vary depending on type and required function. QC documentation has consistently been reviewed, approved and transferred to the Byron Site QA Office, however, an actual listing of required documents was not made until recently. Currently, Master Documentation Lists are being compiled for each S&L procurement specification on which all required QC documents and Engineering Technical Data Documents are listed for each piece of equipment (by S&L Tag Number). As of 06-01-83, all lists for safety-related specifications have been transferred to Byron Station. The lists show which items are on file at the Site QA Office and items which are still required for submittal by vendors for review. S&L Monthly Engineering Status Reports on Environmental Qualification, Seismic and Stress are used to correlate the status of items on these Master Lists. Engineering Reports (Seismic, Stress and EQ) are in the process of being transferred to both stations. All of the QC Documentation for the B0P pump and valve audit items has been transferred to the site. Engineering documents cre on file at S&L. Verification that all items on file at the site correspond with all items listed on the Master Documentation List is being performed by the site QA Department. To demonstrate the acceptability and completeness of the operability qualification for the Byron plant, the Westinghouse files were reviewed. Enclosed is a summary report of this review which identifies the qualification documentation associated with each active pump and valve. It was agreed with the Staff at the 05-13-83 meeting that such a review and summary report would be adequate to demonstrate completion of the operability qualification for Byron. 3120b
Attachment Al Electrical Penetration Assemblies (80P/1) Responses to the open audit items are as follows: Open Item 1 - The report describing the environmental aging and qualificatTon testing (Conax IPS-369, Rev. C) has been reviewed and approved and is available for SQRT review. This report was audited by the NRC during the Environmental Qualification Audit on June 21, and 22, 1983. Ogen Item 2 - The nitrogen supply to the Pyron Unit 1 penetrations was originally designed to meet the requirement of the Amphenol containment penetrations. Subsequently, Conax penetrations were installed in place of the Amphenol penetrations. The Conax penetrations are qualified to operate with air rather than nitrogen between the seals. The nitrogen has been' retained on Byron Unit 1 as an additional design feature beyond qualification requirements. The nitrogen lines are provided with a Category I isolation valve to allow for isolation in the event that one of the seals does leak. The nitrogen system is not Category I because l its failure will not adversely affect the penetration integrity. l 3120b-g _ _ _ _ _ _ _.___-_ _ ______-..---.._.-_ - 1- - - - - - - - _ - - - - .}}