ML041700559
| ML041700559 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/28/2004 |
| From: | Grecheck E Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation, NRC/RGN-II |
| References | |
| 04-078B, IR-03-008 | |
| Download: ML041700559 (40) | |
Text
VIRGINIA ELECTRIC AND POWVER COMPANY RIcIImIoN), VIRGINIA 23261 May 28, 2004 U.S. Nuclear Regulatory Commission Serial No. 04-078B Attention: Document Control Desk NLOS/GDM R1 Washington, D.C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNITS 1 AND 2 EVALUATION OF PRELIMINARY WHITE FINDING AND ASSOCIATED NRC RISK ANALYSIS CONTAINED IN NRC INSPECTION REPORT NOS. 05000280/2003008 AND 05000281/2003008 SUPPLEMENTAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION In a letter dated May 7, 2004 (Serial No. 04-078A), Dominion provided additional information supporting its position on the NRC's preliminary White finding relative to a postulated Appendix R fire in the Unit 1 ESGR and the associated Phase 3 Significance Determination Process (SDP) analysis. The information was provided pursuant to an NRC request for additional information made during the April 1, 2004, regulatory conference, which was held to permit Dominion the opportunity to present its evaluation of the NRC finding and Phase 3 SDP analysis. In that letter, Dominion also committed to provide any pertinent RCP floating ring seal design and/or test information that could be reasonably obtained by May 28, 2004. Through various vendor and industry contacts, we have been successful in obtaining additional design and test information associated with the floating ring seals. This information is provided in the enclosures for your review and consideration. The specific documents enclosed include the following:
- Enclosure 1 - Intemal Westinghouse letter dated June 23, 1992, "
Subject:
CVCS RCP Seal Injection and Seal Return Design Basis", (FSE-FSDA-92-1880),
- Enclosure 2 - Letter from Westinghouse Electric Company to Dominion Generation dated May 26, 2004 (VPA-04-19),"Dominion Generation, North Anna Units 1 and 2 -
Surry Units 1 and 2, RCP Seal Design and Testing Information," and
- Enclosure 3 - Westinghouse Instruction and Operating Book, Controlled Leakage Seal Reactor Coolant Pump Model W-11001-Al, Instruction Book 5710-79A (Excerpt).
A summary of the floating ring seal information included in the enclosures as well as a reiteration of applicable information previously submitted is provided below.
Serial No. 04-078B Docket Nos. 50-280/281 Page 2 Floating Ring Seal Design and Testing The information provided in Enclosure 1 notes that floating ring seals were originally installed in RCPs as an alternate seal design to the No. 1 controlled leakage seal pending confirmation of the reliability of the No. 1 seal design. Reliable performance of the No. 1 controlled leakage seal was subsequently demonstrated; therefore, floating ring seals were no longer required in subsequent pump models. However, since floating ring seals were originally installed in RCPs to limit leakage pending confirmation of the No. 1 controlled leakage seal design, the floating ring seals were clearly designed and relied upon to control RCP seal leakage.
Furthermore, the information provided in Enclosure 2 demonstrates that the floating ring seal was designed and underwent considerable testing to ensure its ability to control RCP seal leakage to 50 gpm or less. The seal leakage test results obtained during testing ranged from 28 - 40 gpm. The production testing results provided in Enclosure 2 demonstrate the ability of the floating ring seal to adequately perform its design function.
Floatinq Ring Seal Materials The materials used in the RCP floating ring seals were discussed to a limited extent in Dominion's March 25, 2004 letter and are further delineated in Enclosure 2. As noted in the enclosure, although the floating ring seals have not been specifically qualified for operation at elevated temperatures, the floating ring seal materials are in common usage in other RCP parts as well as in other plant equipment. Graphitar is used in the RCP radial bearing and in the #2 and #3 RCP controlled leakage seals, and the Stellite cladding on the shaft bushings is essentially the same as the Stellite cladding on the pump shaft bearing journal.
Although not specifically designed for thermal shock conditions, the fact that the materials used in the floating ring seals are the same as those used in the #2 and # 3 seals suggests that the performance expectations of the floating ring seals in a loss of RCP seal cooling environment would be similar to that of the other RCP seals made of the same materials. Furthermore, the relaxed clearances for the floating ring seal as discussed below would reduce opportunity for binding and wear due to thermal effects.
Industry Experience During normal seal package inspection and replacement, the floating ring seals are not normally removed from the pump since they are installed below the seal package. The Westinghouse Instruction and Operating Book for the Model 93A RCP does not include any requirements for periodic maintenance or replacement of the floating ring seal. As discussed in Enclosure 2, the floating ring seal cartridges self-align to maintain approximately a 0.005" - 0.008" radial clearance to the pump shaft. Therefore, little or no abrasive or rubbing type wear is expected during plant service. Also, during normal service, the pressure drop and associated flow velocity of water passing the floating ring
Serial No. 04-078B Docket Nos. 50-280/281 Page 3 seal toward the controlled leakage seal assembly is quite low such that flow erosion is not a concern. The only materials in the floating ring seals that would likely be susceptible to aging related degradation would be the two EPDM O-rings and Teflon backer rings.
Very few field examinations have been performed to monitor floating ring seals for wear.
In lieu of good floating ring seal operating wear data, an analogy could be made to the radial bearing and shaft journal assembly. The radial bearing and shaft journal are made from essentially the same materials as the floating ring seal and operate at similar close clearances. Of the over 300 Westinghouse RCPs in service around the world, only a handful have required bearing replacement, and then usually because of damage related to foreign material intrusion. The most recent bearing from a Model 93A RCP that was examined by Westinghouse after nearly 30 years of service exhibited almost no signs of wear to the Graphitar surface.
Furthermore, the durability of floating ring seals has been demonstrated through industry experience as discussed below:
Surrv - The floating ring seals installed in the Surry RCPs are the original seals from initial plant operation. No floating ring seals have been replaced due to unsatisfactory inspection or performance results. When the Surry Unit 1 RCP 1A was replaced in 1990, the floating ring seals from the original pump were inspected per procedure, determined to be satisfactory and re-installed in the replacement pump.
Beaver Valley - In the 1983 time frame, Beaver Valley Unit 1 removed the floating ring seal in one of their RCPs to facilitate maintenance on a separate pump component.
The floating ring seal was inspected and observed to be in excellent service condition.
Haddam Neck - As previously noted in Dominion's March 25, 2004 letter, the NRC has previously credited floating ring seals as providing additional leakage control in loss of seal cooling events. (Reference NRC letter to Connecticut Yankee Atomic Power Company, "NRC Safety Evaluation Report on Reactor Coolant Pump Seal Integrity Following Loss of Offsite Power," June 26, 1991.) The NRC Safety Evaluation Report (SER) closed out NUREG-0737 Item II.K.3.25 "Reactor Coolant Pump Seal Integrity Following a Loss of Offsite Power" for the Haddam Neck Plant by concluding that restoration of RCP seal cooling following a loss of offsite power complies with the requirements of the TMI Action Plan. Inthe SER, the NRC credited the floating ring seals as capable of withstanding full system pressure and limiting RCP leakage to 50 gpm in loss of seal cooling events. The NRC acknowledges that 'This is not standard on Westinghouse RCP seals and provides enhanced protection from excessive seal leakage."
Floatinq Ring Seal Failure Probability As previously noted, we have performed a calculation that establishes the failure probability of the floating ring seal as 0.5 based on the Haddam Neck event described in
Serial No. 04-078B Docket Nos. 50-280/281 Page 4 our March 25, 2004 letter. (The calculation was included in Dominion's May 7, 2004 letter as Enclosure 1.) The failure probability was determined in accordance with the guidance provided in NUREG/CR-5750, "Rates of Initiating Events at U. S. Nuclear Power Plants: 1987-1995," dated February 1999. A standard method in PRA, consistent with the Jeffreys noninformative prior in a Bayes updated distribution, is to give at least 50% failure probability to any design feature which has demonstrated the capability to perform its assumed function and has not suffered any failures. The performance of the floating ring seals at Haddam Neck in their loss of cooling event constitutes a valid challenge with no failure, which is directly applicable to the Surry RCP seal model.
Conclusion Based on the information contained herein, the information previously provided in Dominion letters dated March 25 and May 7, 2004 (Serial Nos.04-078 and 04-078A, respectively), and the information presented during the April 1, 2004 regulatory conference, it may be reasonably, and we believe convincingly, concluded that the RCP floating ring seals used in the Surry RCPs should be given credit in the NRC Phase 3 SDP analysis for limiting leakage commensurate with that given to the other RCP controlled leakage seals. At a minimum, a 50% failure probability should be assigned as discussed in Dominion's earlier correspondence and as discussed above.
Likewise, in conjunction with the previous information provided, we believe that Dominion has thoroughly and conclusively demonstrated that the NRC's preliminary White finding was overly conservative when considering plant specific features unique to Surry. We further conclude that when considering these plant specific features in the aggregate the safety significance of the postulated Appendix R fire in the Surry Unit 1 ESGR (or Unit 2 ESGR) corresponds with the Green range in SDP findings (very low safety significance) as opposed to the NRC's preliminary White determination (low to moderate safety significance).
Generic Implication The NRC violations assessed at Surry Power Station for a postulated Appendix R fire, which results in RCP seal cooling being lost, were predicated upon the potential effects of thermal shock on the seals when seal cooling is returned following a prolonged loss.
However, the objective evidence does not support this underlying hypothesis. Testing performed by Electricit6 de France on RCP seals demonstrates that the seals can withstand a prolonged loss and subsequent return of RCP seal cooling without catastrophic failure or the initiation of a seal LOCA. (Reference Dominion letter dated May 7, 2004, Serial No. 04-078A.) Furthermore, an actual prolonged loss and subsequent return of RCP seal cooling event occurred at Haddam Neck without consequent RCP seal failure.
Although Dominion decided not to contest the violations as noted in previous correspondence, we believe sufficient objective evidence has been presented to raise
Serial No. 04-078B Docket Nos. 50-280/281 Page 5 into question the underlying generic assumptions of potential effects of a loss of RCP seal cooling. It is our understanding that the Nuclear Energy Institute is attempting to schedule a meeting with the NRC to discuss this topic.
If you have any questions or require additional information, please contact Mr. Gary D.
Miller at (804) 273-2771.
Very truly yours, E. S. Grecheck Vice President - Nuclear Support Services Enclosures Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. G. J. McCoy NRC Senior Resident Inspector Surry Power Station Mr. S. R. Monarque NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mailstop 8-H12 Rockville, Maryland 20852
Serial No. 04-078B Docket Nos. 50-280, 281 Enclosure 1 Internal Westinghouse letter dated June 23,1992, "Subiect: CVCS RCP Seal Injection and Seal Return Design Basis", (FSE-FSDA-92-1880)
Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
FSE-FSDA-92 t880 From: Fluid Systems Engineering WIN: 2845629 Date: June 23, 1992
Subject:
CVCS RCP Seal Injection and Seal Return Design Basis < ,
To: RuM SyU. a-File: RD-28211 (CVCS)
File: RD-281/1 (RCS)
Cc: R. L. Loose, Consultant for Design Baseline & Licensing Programs File: PSE/PNJ (Salem) Operating Plant File: VPA/VIR (Surry) Operating Plant File: VGA/VGB (N. Anna) Operating Plant Fluid Systems Managers, this would be good routing matrial for your groups if applicable.
The purpose of this letter is to clarify why the CVCS seal Injecdon and seal return systems are designed to accomodate the relatively large flows associated with reactor coolant pump (RCP) floating ring seals rather than to the smaller flows associated with the RCP No. I controlled leakage seals.
According to Bob Loose, about 1960 a decision was made to go to mechanical seal pumps rather than to continue to use canned pumps which were used on oarly plts such as Yankee R-owe. Since the performance of the unique controlled leakage seal had not bcn proven, it was decided that provision for an alternata seal design should be made. Therefore, since the design of the mechanical seal pump had to be initated before the reliability of the controlled leakage seal was proven, provisions for an alternate floating ring seal arrangement was included In the RCP design. Also, the system design proceeded based on accommodating the larger seal injection and seal return flows associated with floating ring seals.
Based on testing azd operating experience the performanco of the RCP No. I controlled leakage seal proved to be very successful. However, RCPs continued to be built with provisions for floating ring seals and the CVCS seal injection and seal return systems continued to be sized for accommodating the higher flow associated with floating ring seals. Because much of the equipment, e.g. seal injection and seal return filters and seal return heat exchangers, was purchased as standard equipment by multi orders and since the seal return line handles the excess letdown and centrifugal charging pump miniflows, it was never considered worth the effort to reduce the capacity of the seal injection and seal return systems.
NS002268
Although the RCPs include provision for installation of floating ring seals, the only plants which are known at this time to have the floating ring seals installed are Surry 1 and 2 and North Anna I and 2.
This apparently was based on this customer's (Va. Pwr.) requirements.
In summary, provision for floating ring seals was originally included in the RCP design as an alternate to the unproven No. I controlled leak seals. Even though the performance of the No. I controlled leakage seal was successfully proven and floating ring seals were not necessary, the CVCS design, which accomodated the higher flows associated with the floating ring seals, continued to be provided/built.
G. G. Konopk, Engineer D. M. Scantlin, Engineer Fluid Systems Design & Analysis Fluid Systems Design & Analysis ICEDAL&MM
Serial No. 04-078B Docket Nos. 50-280, 281 Enclosure 2 Westinghouse Electric Company Letter Dated May 26, 2004 (VPA-04-19)
"Dominion Generation North Anna Units 1 and 2 - Surrv Units 1 and 2 RCP Seal Design and Testing Information" Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
~)WetingOuse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA Ms. Leslie Hartz Direct tel: 412-374-6345 Vice President - Nuclear Engineering Direct fax: 412-374-3451 Dominion Generation e-mail: rice I wr westinghousc.com Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 12060 VPA 19 May 26, 2004 DOMINION GENERATION NORTH ANNA UNITS 1 AND 2- SURRY UNITS I AND 2 RCP Seal Design and Testing Information
Dear Ms. Hartz:
Dominion requested Westinghouse to provide the following information, to the extent available, to help them address NRC questions received during a Regulatory Conference specific to the reactor coolant pump (RCP) floating ring seals (FRS) (Reference 1):
- 1. Any design analyses or test reports that address floating ring seal performance or design
- 2. The material used in the fabrication of the floating ring seals (including any coatings, etc.)
installed in the Surry and North Anna RCPs
- 3. Any analysis/evaluation that addressed the impact of environmental conditions on floating ring seal performance (e.g., cumulative radiation exposure)
- 4. Any industry experience associated with floating ring seal performance that may be available The Westinghouse responses to this request are as follows. All responses have been reviewed by Dominion and comments have been incorporated.
- 1. Design Documentation The FRS design efforts began at Westinghouse in the early 1960's in conjunction with the controlled leakage seal design development program. The FRS assembly (also known as a pressure breakdown bushing assembly) was developed as a backup seal that would effectively restrict reactor coolant leakage in the event of a number one seal failure.
The FRS assembly consists of a series of Graphitar rings that are located along a section of the RCP shaft between the bearing journal and the first stage seal. The original FRS maximum leakage objective was 100 gpm, with 2100 psi pressure differential and 130'F injection water. Westinghouse designers actually used a working objective limit of 50 gpm FRS leakage during the design development.
A series of prototype FRS tests were conducted in a special test rig by Westinghouse in the 1965-1966 time frame, including a 1000 hour0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> endurance test. These tests were performed to support t'le qualification Official Record ElectronicallyApproved in EDMS 2000 A BNFL Group company
Page 2 of 7 VPA-04-19 May 26, 2004 and manufacture of the first sets of Model 63 controlled leakage seal RCPs, to be installed at San Onofre Unit I (SCE) and at Connecticut Yankee (CYW) in the USA and Zorita (Model 70) station in Spain.
The prototype seal rings were configured with a smooth seal face, machined on a slight angle. The first set of production RCPs, for SCE and CYW, were tested with this style seal ring, which is part of the FRS cartridge assembly, P/N 620B215G01. Performance testing of these early production RCPs included FRS leakage tests, at 2000 psid with 1300 F water. Results are as follows:
Plant RCP S/N Test Report FRS Cartridge FRS Leak Rate Date P/N CYW 1-U150 4-29-66 620B215G01 31 gpm CYW 2-U150 10-20-66 620B215G01 28 gpm CYW 3-U150 11-30-66 620B215GI01 31.5 gpm CYW 4-U150 10-28-66 620B215G01 30.5 gpm SCE I-U149 Not Found Not Found Not Found SCE 2-U149 Not Found Not Found Not Found SCE 3-U149 3-3-66 620B215G01 40 gpm As a result of vibration problems found during the 1000 hour0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> prototype testing, Westinghouse redesigned the Graphitar seal ring faces to a labyrinth type configuration. The revised seal rings were incorporated into FRS cartridge assembly P/N 856C864G01. The Zorita RCP (Zorita is a single loop NSSS) received this revised cartridge assembly. The seal rings used in the Model 93A RCPs at Surry and North Anna use a similar seal face configuration.
Production test results for Zorita, using the same test specs as CYW and SCE, are as follows:
Plant RCP S/N Test Report FRS Cartridge FRS Leak Rate I Date P/N I Zorita 1-618J656-GO1 11-7-67 856C864G01 28.4 gpm The Zorita test results clearly show that the revised labyrinth type seal face performed comparably to the original smooth faced rings. All of the early FRS test data is tightly grouped with magnitudes well within the target maximum leak rate of 50 gpm. This tight grouping of data shows a close correlation between analytically predicted performance and tested performance. Therefore, performance of FRS assemblies of similar design used in Model 93A RCPs can also be expected to show good correlation to predicted performance values.
Copies of the test data referenced above are found in the attachment to this letter.
- 2. FRS Materials The following materials were used in the Surry and North Anna FRS assemblies:
Official Record Electronically Approved in EDMS 2000 A BNFL Group company
Pagc 3 of 7 VPA 19 May 26, 2004 Part GIA Item Part Number Material _y.
F.R.S. Lower Housing Assembly 84 856C448G01 NIA 2 Pin (.50 DIA x .88 LG., SST) 620B604H05 304 SST Bar 2 Housing 856C448H01 304-SST. Forg. 1 F.R.S. Upper Housing Assembly 85 856C416G01 NIA 6 Pin (.50 DIA x .88 LG., SST) 620B604H05 304 SST Bar 2 Housing 856C448H01 304-SST. Forg. 1 F.R.S. Assembly 86 856C418G01 NIA 8 Weld Metal 4942A24 SST Bare Welding Wire AR Pin (.50 DIA x .88 LG., SST) 620B604H05 304 SST Bar 2 Graphitar Ring 620B435H01 Graphitar 14 1 Cartridge 620B434H01 304-SST. Forg. 1 F.R.S. End Ring (Assembly) 87 856C419G01 NIA 1 Pin ( .750 DIA x .88 LG) 620B604H07 304 SST Bar 1 Ring-15.5 O.D. x 10.4 I.D. x 2.0 THK 856C419H01 304-SST. Forg. 1 F.R.S. Retaining Ring 88 856C592H01 304-SST. Forg. 1 F.R.S. Lock Segment 89 856C422H02 304-SST. Forg. 4 Backup Ring 83 360A975H02 MS-27595-458 Teflon 2 O-ring 82 620B494E58 Ethylene Propylene 2 Belleville Washer 81 620B605H01 Inconel X-750 1 Silicone Compound 103&76 4934A28H01 Silicone Dielectric Compound I Shaft Bushing 620B599H01 304 SST Forg. wl Stellite Cladding 1 Shaft Bushing 620B599H02 304 SST Forg. wI Stellite Cladding 1 Shaft Bushing 913C480H01 304 SST Forg. w/Stellite Cladding 1
- AI bolded items are called out on the General Assembly Dwg.
North Anna General Assembly - 689J041 Rev 12 Surry General Assembly - 618J776 Rev 14
- 3. Impact of Environmental Conditions on FRS Performance The design record archives reviewed to date have not revealed evidence of any "special" environmental impact studies associated with the FRS design efforts. The FRS were originally designed and tested for operation with seal injection water temperature and pressure of 130'F at 2000 psid. The design differential pressure was later changed to 2235 psid when the FRS were adapted from the Model 63/70 RCPs for use in the Model 93A RCPs. No attempts have been made to qualify the FRS for operation with elevated temperatures above 130 0F.
Review of the materials of construction tabulated above shows that the following materials are used in the FRS:
Official Record Electronically Approved in EDMS 2000 A BNFL Groupcompany
Page 4 of 7 VPA 19 May 26, 2004
- Stainless steel, type 304
- Inconel X-750 (one washer)
- EPDM and Teflon (0-rings and backup rings)
- Graphitar 14 (seal rings)
Although the FRS have not been specifically qualified for operation at elevated temperatures, the above materials are in common usage in other RCP parts as well as in other plant equipment. Graphitar is used in the RCP radial bearing and in the #2 and #3 seals, and the Stellite cladding on the shaft bushings is essentially the same as the Stellite cladding on the pump shaft bearing journal.
The floating ring seal assembly is designed to be non-contacting during service. The FRS cartridges self-align to maintain approximately a 0.005" - 0.008" radial clearance to the pump shaft. Therefore, little or no abrasive or rubbing type wear is expected during plant service. Also, during normal service, the pressure drop and associated flow velocity of water passing the FRS toward the controlled leakage seal assembly is quite low such that flow erosion is not a concern. The only materials in the FRS that would likel be susceptible to aging related degradation would be the two EPDM O-rings and Teflon backer rings.
Very few field examinations have been performed to monitor the FRS for wear. In lieu of good FRS operating wear data, an analogy could be made to the radial bearing and shaft journal assembly. The radial bearing and shaft journal are made from essentially the same materials as the FRS and operate at similar close clearances. Of the over 300 Westinghouse RCPs in service around the world, only a handful have required bearing replacement, and then usually because of damage related to foreign material. The most recent bearing from a Model 93A RCP that was examined by Westinghouse after nearly 30 years of service exhibited almost no signs of wear to the Graphitar surface.
Perhaps the best available source of operating service FRS wear data would be the spare contaminated RCP from Surry that was removed from service around 1997, after about 25 years of service.
- 4. Industry Experience with FRS To the best of our knowledge at this time, Westinghouse only installed FRS at the following plants:
Plant RCP Model No. of RCPs San Onofre Unit 1 63 3 Connecticut Yankee 63 4 Zorita 70 Surry Units 1 and 2 93A 6 N. Anna Units I and 2 93A 6 Beaver Valley Units I and 2 93A 6 Official Record ElectronicallyApproved in EDMS 2000 A BNFL Group company
Page 5 of 7 VPA-04-19 May 26, 2004 During our recent research through old design records, our priority was to search for design and performance testing data for the FRS. Operating experience documents were not closely reviewed. The only event found was from 1969, during the first fuel cycle at Connecticut Yankee plant. Since Dominion already has a summary of this particular event, it will not be repeated in this letter. Should Dominion desire additional details of this event, further search through Westinghouse records could be performed.
Reference:
- 1. Letter from Leslie N. Hartz (Dominion) to Bill Rice (Westinghouse), May 11, 2004, "Request for Reactor Coolant Pump Seal Design and Testing Information, Surry and North Anna Power Stations Units I and 2" If you have any questions concerning this information, please contact Mr. Eric Colvin at (724) 722-5379 or me at 412-374-6345.
Very truly yours, WESTNGHOUSE ELECTRIC COMPANY W. R. Rice Customer Projects Manager Ajf Attachment Official Record ElectronicallyApproved in EDMS 2000 A BNFL Groupcompany
l Roland Wood - MissingPagesWLetter.pdf Page 1 I
Page 6 of 7 VPA-04-19 May 26, 2004 cc: K. L. Basehore (Innsbrook)
R H. Blount (Surly)
T. B. Sowers (Surry)
J. Davis (North Anna)
D. E. Jernigan (North Anna)
J. M. Surface (Innsbrook)
C. L. Funderburk (North Anna)
W. Renz (Innsbrook)
G. T. Bischof (Innsbrook)
B. Foster (Surry)
D. Buchite (Innsebrook)
G. Miller (Innesbrook)
Official Record Electronically Approved in EDMS 2000 A BNFL Group company
i Roland Wood - MissingPages WLetter.pdf Page 2I Page 7 of 7 VPA-04-19 May 26, 2004 bcc: W. R. Rice - Westinghouse / ECE 5-10 RIGrendys - Westinghouse / ECE 5-7 E. Colvin - Westinghouse WM Project Letter File Internal
Reference:
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WESTINGHOUSE ELECTRIC CORP ATOMIC EQUIPMENT DIVISION
- .s. >4 , HE iV 'rK4-eP~ :-...~... .,v.t .4 .,8-.$%t '
r40 ' MOTOR SR NO), a 70P0M.ODEL NO DATV/ kSY-Ai JiRS OF. O iE'ON .207. 0 OF STARTS '.STOPS i ;
RY RERFORMANCEL DATA COL) _-_Ol'-_---
FR E'QUENCY-CPS 6o I 6.
,VOLTAE .AMPERES
.M.
I CJEN.
.PR5533 . 434.1 0INPUT POW'ER-KW JIdl, 2760 I
r .PF1OWER FACTOR 41.8 90.6
,.. -I o N0.O'.I 79.8
.: 0; 2, _89.7 79.8
- , i317~ I0 Z NO.4 88.3 ! 78.0 "2 0ct° 0
o C.
w "NO. S
_NO. 6 U
AMBIENT TEMtPERATUJRE UPPER RALIAL BEARING OF.
UPPER THRUST BEARIKG OF.
LOWER THRUST GEARING °F
°F 915.
fo 13, 11,ri i
t_ __
81.0 7?.5 155 16re3
. LOWER RAIAL BEARING c- ___._u U PP E R! -C W iN
. F / O ' T " rr'/F7 _ ________
a: CIS FLOW GPM 119 _ __' _
-j 112.1 V 0 K v. REMO)VED 130.3 LOWER-CW IN "F/OUT 'F CWVj FLOW GPM .; 5 I
,EKW REMOVED 6f.6. _ _._
.f AT UPPER OIL POT-I DISCHtARoE .01 .00135 V.
II DISCH RGE -
- _. _ t
- LOWER FLANGE - 1 DISChARGL .032 .003' I; DISCIARGE I .0 ?
_ *DOJ>LE AMPLITUDE AT RUNNING S>EED .. _ __
I.-,^-
_I_
I DATE AND TIME OF DATA POINT 3-1i4-66.
1.000 1 3-19-66 70 .
Wr g h LOOP. TEMPERAT RE _ _ 1 __ _ __ _ _
' .UMP "FLOW- GPM (EST, FROM HEAD) ____
~PUMPHEAD-FEET227 1 21 6EIAR ING, WATERTTE MPE RATURE F 1OF 1'3
'T-ERM~AL B ARRIER HEAT EXCHANGER --
CW IN 'F/OUT 0 F 5/3 ____
CW FLOW.GPM 25 2 ___
' KWd REMOVED _ 1____
&P (INJECTION PRESS - LOOP Pk-ESS,), P SI -
7
'INJECTION FLOW INTO LOOP-GPM - .i 2.
AP ACROSS ITHERMAL BARRIER TaPS--INH 2 0 ________33*-3 DOUBLE AMPL. V/IER A~i UNNtN'.1 SrFfV--..
VIBRATION Al MAIN rL ANGE- 1 01 .IshAPGL d05 OO I
I TEf.4PLF-t.iT1JE AT NO I SEAL N111- T.O 1I I N0 I SEAL LLAt,01rF FLOW .GVM .... m i TEM~PLf.IAI LM*.*W IJO 2-0 r I NL ET 'IFr ___
Wj NO 2 E IL LLE Ar.)F F F LOV F k' .~__
NO. 2 FS AL Z%F ~S I NO. 3 SEAL :_EAKAf',E Ce~ ____-j, NO. SEA L 6, P -1 ti-.') 7. 7.0 r Lt) AT! I ~I N (ISSE A L L. E A ~GL AT rs ~p
'n n Go .
'(
1'.'-. . _
(W)
CON-NTROLLED LEAKSAGE PUMP TEST' FREPORI I
MQWD 3 L. NO. Ev 4%-. .
MQ;g kR fS ilt R !AL. NO..,,- 1,2 C' .4 0 P , ,),_ -,5
!3ELq C" Erf N(. BS (IRn)
'j , A S. ' . 1, NO
,,61 5l-J-ig.,6 OUTLINE DWG. NO r r; ), r CtIFlCATI0N TT78_
F)TP, V - p _ _I.AT E WESTINGHOUSE ELECTRIC CORP ATOMIC EQUIPMENT DIVISION
", -., . - I . . ?-.."
. ,'P . :
~
l l -
s -
V O '. I4
- O&
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.4070 . --*-Aio3
_ ,, !,- ^, ,*
c'PJRENT:," AMPER.S 530 -
4
-. 98
,--o -p-pY-"Pbwtp-
- ,., - t. - ,~2w7 ,: .
pWR .fA4e&1
_1:
S . . . . 0 . .. ..
. S S * . . . w
' .-- -9
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)... .
NO. 4 I.
NO. S NO. 6 AMBIENT I LmPERA7'JPL I"f t I UPPER RADIAL BEARING "F.
x A 0 , 1UPP£P THRijU3T BEARI.C FF.
I-0 i II LOWER TH4H¶e- B6F %RJN:-; I
! 41
, I~n LOACt4 RADIAL.etAX9So :
UPPER C. 1 '°F/ J F.,
CW FL.0% '-'DM ui
-. 1 I XW REMOVLi 0
LOWEfl---W tjN 0 F/(,: T r CW F:.OW GPM KW REMOVED AT UPPER OIL PtlT-IDISCtfAkGE 2:
- OIPCifARGE 0
LOWER fLAGE -i DISCHARGE 4
a: 11 DI SUslARGE
- DOUE3L' AMPLITUDE AT PUNNING SPEED DATE AND TIME OF, DATA POINT .
--A , - - .. , j - , ,. -,"
1.1Z."I": -l'.....
l: , " -
.4 rg >i I. -11
.1 - . ,. .--
, .... I , . I.." . . .. ,. .:. -,-j 1
-.. , I-, -,
G,.,--^. '.
- v. l..... ...-....-.-.-.-.. rE.
F6 66. 5. . _
PUM.F'_E -,PEE'T.~ *D .F.
EAR R P.: -
TEItTE PHE;cATUE X Fr_ E _ ___ !!
~~~~~~t-. 'R. t. SL ~RlEa ,;FIt f..............>:CHiAN.,EPk.... ___...'____ ..
CW N F OUt c 60/75 101/3124
,CW Fl (W CGM l 21 21
. V,V, tP t .1 O V E D)If 1-,
> ..a .OE . 1 _,4.__.___....._ ___J {
PQ .NJc .TON PRES:S.-- LC:C'-C fRE P .i_
.- -T- L. _ Il . AFLW I _ _ AL_ IG L _____
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.30030
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r . A
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.43r 1.4. 4~ae ALO
- C",}.- .. ,,}- {s.. '.X---t 11 ', -0' __2; Frm.date ot li-1.6.66
t,%T"C
'-1*'
r7.t
- 1 i I '- .;",0 POLLED L AKAGE i
DUMP t- -
TE-S T- R-EPOR.T 1I
.I t ill'..,.
4 -
I il
,i, . ,
.I-I -I
'i, MO{EOL. NC
_V-I4'-A PUMPi ;; S[WFAL _
NQ.1.-U-1-L MT070 _
S E AL NO. 3;70702 SHOD (n-DE.R NO. .150
_ A3S'Y. _D
- 1. A
. N O). 618J646 UTLi 7L N E D W N . - -6 64
- SI SPFcFlcarJON T-712282-r W RITTEN Yt / 7K 4~Pt~ROVED~ BY_ T ]C :
AE .
ATOMIC UQUP"MENT L-'-11 1.4 ' , .. D.IVIS ION I a mm"Wom"Mm, I
cio~w Indian I
- MEMW,
P-77-7, x-o "'YI. ERr-SNO MODEL _____
WOML~
QPRATI)N
'SUMi tMA-R.Y PJE.-R:F0 iMAI ThDAT-A;
.+ . , NO L-STARTS'S J O. -. .1ST POWtLP. VA_______ ___
zi nfl. 6 2 'N PPE
'. . iC3,
~ . -10. O
-. 12036 149~ -
12 11 5.
- - .-- A )011.06-
-;-------- -----..-----.- 15 -
L f~.
---. 0 -
.00 L ~ .. ~
- *~ ..
. 4?r
~
" ~N;?4,
- i f { 6-44 4. . "J!J9-29-66 0600 10-5-66 i6oo
CC)LD
- t. L~Y E SSURL -,ISIc (PUM 1f-KS JCT O-) 2010~.:0 P;5EMERATRE F:K- I K
i W U6I .U D F E F'> . I s o_ _ _ _ _ -.
'3/4 Eri&~~ ATLR E;V W L,V 1"X C H A ; I Li C LC W 21 21 .
- C fi. . ~J1 4~T0C~i .(~- ~' G J ~ ~F L W~6 .14 I ~ ' '. *I1 A 2 1 .30
.~ - - _ _ 2 .40 4
- -.-. -. - - --- 1 I Theoe values not applicable. !=P We tested in F-loop w.1th reduced-lond 1 im~peller 6!6j.')56 TD)C.
i
. I
.. " ;- , f. _ _- .., -_ - I; ... - . , . .1 0, '-11 1, .!. .. -
1i 2, Z
f.
Ir CONTROLLED LAK AGE PU MP:
TEST ,:SREPORT
.- ,MODEL
' ' NO.
P-UMAP SE RIAL NO._ 3-1-o _
MOTOR SERIAL N0. _ 2-70'7 SHOP O-.DER NO
- OEIN. U IRDUR N C)_
GENi. AS c ,Y. oDw; rqo 6n-VJ6L-,
- uTLIN E DtWG. NO 610J6Z.5 _
.E S ,-1 r C IF IC AT OItmŽ _T-712?282-B I
. 0 , ^a ...
WRITTEN BY- DATE ,L APPROVED 8Y. ...
WE S 'liciU.-L:ESELECTRICr 0DFRp ATOMIC EQUIPMENT DlIVISION
- ~ *1*4 .,Z~. *'17 J*; ,r. . .
ta:
.4I
.N 4
i T-A C,I" Jo ;OURS -: ND, OF S-ARTS 8-STOPS i i
I I-Mto4RY S__JM________________
IPE-fORMANCE .DAT.A P .
1 COLD
. HOT-I 6o .6o VOLT--E __ 2 . _ . .
- . K :: l. .j E __ .__
__ . .2 761.6-I.' 7 POW ER f§ CT LŽ j7 .
I . J. O..
- - 0 X ..
'. o Si> .-....... '3.5 _73.-
- tJO2 72 73 Ad .. .- - . - - - - - - _ _ _ - -, _ *. ._
Qi N __ ___L.Bt_ 7_
.0 _ . _ _ ___ _ _ ._ _ _7_._ _
1tO: N 5 . 7 78R
- 1. ..
0_ ___ _ _ _;___
r
__ ___ B..
M .15*
- OE . 7L3 .
I
-C - 12'--
0_.: t O WPPER oRi; T'f .~ Et 3EAR 1 -. °129 '_ _ _ 156 1..
A 2 L E %I' I A . .1 Q
~_:ill_ - - - ------ 12 K 7.I TP E FJL P T - T CF)I
!-E,.
° t _ ._ .U I~
_ __1N. ~ M N._ '. . .j .- .
I U r- C1-A1
!-J~~
C>~.626
~C r00;T DATA"---;s 4
P--!MT-151 rI s' 1245Cv 9-o6CJo:D3 Il L_ _ , . -4 5 9 1 6 0300
.; _ . -_- I-
.. "t-_ --:z ---.; , "- . . r -11, E .-Ilf
I _'- %.'- I 1- ;f . - 11
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'(Pw . - .SUC,". to N I_Z' ts i . w. ,"I 1_
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- 0. .
.' '.' -, . -, , ;.. . I...
.1
-1.
- ' E;r1 R t. r U
.- t . . 2* :, :, " . . .
120 ;- , f
-. .'.%, 4 5-.. `I : .
2
"'":F,-'
P-INF., - -
Ll-di""' - '-'""('E
!M. __ .ST- . FR-OtA I -- "I, 140 - AD,' 1-
,L' 1.
- 1"7w.
-1 -. L--
, _- , - - .1 I. I 1 . .. -
1i ,7 I 9.ul ,"
- E A 0. .1... r-EET _.'... .. . . .'. :. - II . 4 : . I -,
I
.1, -
BEARI 56'-:
I .I- THERfAL.13ARRI.ER jr'A T., L-XCIIANGER Cy; I F. POT 59ho lvi
'>- I NV v%-C, 21 D!
a- 14E IOVE ------ 33'.'9 I -
..1,
.6 -.- '.- - -'iIONM,'.4;.MINJEC ESS.-'LCiCF; i'P.Sl
-, I AKlid-Tib"
. I- tj FLOW-i"" IN TO 'L .0 -L ' P --C-r-I AP %U-:RtAAt. BARNIER T,'."-"i 114 pi Sv'C' A 7 IC-N rA fN j C 7 IC' T N1 j- f,'
-42,9 F' I 1;4 T. N' U 1L6 153_
1-31s 1.22 n C U)
I 2(A-S, 2060
'T Ci N F T w 1-! A F M 1 .269 o47 N0 2 SF P PS I -F. La L E A y A i
i II 11 These valuen not applicable. Pu.7.p was tested in P loop vith reduced-load i impeller 618jW) TD)cD.
(n W_ i
.'i LIJ OL:
i
i I
- Emn 4T1 70 COUIRTILLED LE AIIGE pIu ,1,:p v
TEST REPORT MODEL NO. 10070 PUMP SIERIAL N O. .- 61&J656-ool MOTOR Sly IAL NO.11-730 SSHOP 4ORDER I1NOI U-222 GEN. C)RDER 1FI0. P.201 1
- 3-AAE GEN. ASS'Y DVVG. N 618J656Sub8
- OUTLINE DWG. No. 618.rio sub 9
. TEST SPEC!FICATION 712282B & 788426 WRITTEN BY ,A- r-____i____ DATE: 11-7-67 APPROVED BY --' - j DATE: . a ti]
10 WeIiinghouse E13ctriC Corporation ATOMIC EQUIPMENT DIVISION
'CHESWIC K PA 7w ." pm 1_H Mexico=
MMM-
PUMP SER. NO. lI TOR SER. NO. l MDEL NO. DATE TOTAL HOURS OF OPERATION' 750 NO, OF STARTS & STOPS 9 o,,IJWARY PERFORMANCE DATA COLD Hor I DATF AN'D TME OF DATA POINT 5-9-67/CeW 6_4 -67/0300 FREQUENCY -- CPS __ 60 VOLTAGE, VoiTS 3052 _ _3149 CUPRNMr._ AMPERES _ 1_.___ _ __7_
INPUT POWER -^ KVI 91.0.8 750.4 POWER FACTOR 84.i3 79.3 c- NO. I 46.7 .
.57
__ __ __ __ __7_ ____ _ _ _ _ _ _ i+6 .7 51.1 NO. 3 4_.7 _ 51_
2_ _ _ __4 46.7 51.1 z NO. 5 '6.7 51.9 6 4N 16.7 51.1 AMBI ENTTEMPERATURE F - _ 87 UPPER RADIAL BEARING, OF ____._150 UPPER THRUST BEARING, °F 128 1i0 6 LOWER THRUST BEARING. OF _27.5 148 M LOWER RADIAL BEARING, OF 107.5 126 UPPER -- CW IN9 FIOUT 0 F 59170 100/108 CW fLOW GPM 100 100 KAY REMVED 161.7 117.6 o LOWER -C IN°F/OUT°F 59_67 100l/o6 CW FLOW GPM 5 5 o KW REMVED 5.88 4.41 z DOUBIE AMPLITUDE AT RUNNING SPEED __. __
hT lUPPER OIL POT --.LDISCHARGE o.6 0.5 c II DISCHARGE 0.25 0.4
,> LOWER FlANGE-- IDISCHARGE o.8 0.5 ISCIIARGE DII o.8 1.1 t
PAGE I
S M -
I PUIP SER. NO.
l MOTOR SER. NO.
LOOP PRESSURE - PS1G ( PUMP SUCTION)
LOOP TEMPERATURE OF
_ _ _ _ _CO MODEL NO.
2080 162 L.D DATE I
21Q0 OT 555 MP1JP FLOW - GPM P EST. FROM HEAD) -
PUMP HEAD - FEET 26'*3 272.8 BEAR I NG WATER TEMPERATURE 0 F _________
THERMAL BARRIER HEAT EXCHANGER Q CW INOF/CUTOF 59170 ____
CWFLOW GPM 25 25 KW REMO)VED _ O,______
L ECTIONPRESs -LOOP BESS- I SI 72 5_0 INJECTION FLOW INTO LOOP -- PM. 7.1 7.0 is P ACROSS THERIALAL BAR. TAPS -- IN 1120 21.66 19.1 DOUBLEAMPL. VIBR. AT RUNNING SPEED:
VIBRATION AT MAIN FLANGE - IDISCHARGE 0.35 o.27 If DISCHARG _ _ _ _ _
INJECTIONTFJTAPERATURE°F 120 t TEMPERATURE AT NO. I SEAL INLET1 'F 125.5 169 NO. I SEAL LEAKOFF FLOW. GPM 2."99 2.019 l NO. I SEALtLP, PSI 2100 2100 TEMPERATURE AT NO. 2 SEAL 1NET, °F 179; V) NO. 2 SEAL LEAKOFF FLOW. GPH I .uo'9 0 I NO. 2 SEAL AP. PSI 46.5 7.0 NO. 3 SEA1. tFAKAGE O_ Inter1ent NO. 3 SEALA P. FT. 11 20 7.0 _ 7.0
__ - FLEAmIG RING SEAL LEAKAGE AT 2000 PSIAP AND 130F - GPM - 29.4-
's Lcaks back into 13 sc".
PAGE 2 T" - II I, E
Serial No. 04-078B Docket Nos. 50-280, 281 Enclosure 3 Westinghouse Instruction and Operating Book, Controlled Leakage Seal Reactor Coolant Pump Model W-11001-A1, Instruction Book 5710-79A (Excerpt)
Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
I /
, 11 . . . .
L7k
~Westinghouse
'* Instruction And Operating Book
... CogolI~d
^~f-Rea or Leakage Seal . s**.
. .~ M. IlW-1 Coolant Pump ..
- ~, ~..
- z7.
1001 -Al for
.A?
.;I Virginia Electric Sur-ry PoWer Station and Powe% Co~P~ny-a Un itM.}1 -and'No. 1 -. .
Hog land, Virginia2 .s, .Y n
!j r C ntractB'- EL18 OO3~A RG
~ J I § and '.. .
RM-1 9003-ARGAE. ,.
- 4,
'i Instruction Book
- E 57,19-79A'-
... 1', - . .:
J Manufacture~d by.. .
, VWestingh4gse Electric.
'..Elearo-hMechariical@<ivisiorf Corpnratidn.R;:
- Cheswick, P-ennsyk!rania ..t, '.A-'s
- .. .tI t Jn~ar
- 18. f'";.,.'
. .,",.,r ;
NSoO27 6 2
WPJER MOIAL ANTI-4 fOTATIOl TRVSr I mOOR UNITr As.
FLOATING DING SEALS COOLING VATER OUTLET 0 c
_ C:
en _
a-AjI.
asE.
NOZI
During normal operation of the pump, the thermal barrier prevents the transfer of heat from the reactor coolant to the pump internals. This insulation is accomplished in the vertical direction by approximately 33 thin cylinders.
Horizontal insulation is provided by approximately 26 flat discs which prevent heat from flowing across the thermal barrier top flange. The can material is
.017 inch thick Type 304 SST sheet metal.
On the bottom of the thermal barrier is the heat exchanger portion of the assembly. In the event that the injection flow is lost, the heat exchanger would lill cool the reactor coolant system water leaking through the seals. The heat exchanger is fabricated of eight pancake-coiled layers of 3/4-inch O.D. tubing.
The heat exchanger cooling coils are connected to two manifolds which are connected to 1-1/2 inch tubing located in two positions on the inside diameter of the thermal barrier shell. Water is supplied to and removed from the cooling coils through this tubing.
- 6. Radial Bearing Assembly (See Figure 2-3.)
The radial bearing consists of a two-piece horizontally split housing, a bearing cartridge, and a journal. The I.D. of the housing is machined to a spherical diameter that mates with a stellite-overlaid spherical surface on the bearing cartridge. Graphitar 14 rings are shrunk on the bearing cartridge and form the bearing surface. The bearing operates against a stellite-overlaid Type 304 SST journal which is shrunk on the shaft.
2.2.2 Seal Section The seal section consists of the floating ring seals; the Number 1 controlled-leakage, film-riding face seal; and the Numbers 2 and 3 rubbing face seals. These seals are contained within the main flange and the seal housings.
- 1. Floating Ring Seals (See Figure 2-4.)
The floating ring seal is a radial-clearance type of seal and consists of a series of stationary housings with floating rings, an end ring, lock segments, a retaining ring, a Belleville washer, backup rings, and a journal. The floating rings, which ride on the journal, are made up of Graphitar 14 rings shrunk in Type 304 SST holders. The floating rings fit inside the stationary rings with ample radial clearance and are pinned to the stationary rings to prevent circumferential rotation. The lower two stationary rings contain O-rings and backup rings to prevent leakage outside the stationary rings. The radial clearance between the floating rings and the stellite-overlaid journal, which is shrunk on the shaft, is .010 to .015 inch. The stationary rings are clamped axially between the Belleville washer at the bottom and the end ring and lock segments at the top.
x0o0o 2-5
Bearing Assembly FIGURE 2-3. Radial Ring Seal FIGURE 2-4. Floating 2-6 X0090
- 2. Number 1 Seal (See Figure 2-5.)
The Number 1 seal, the main seal of the pump, is a controlled-leakage, film-riding face seal. Its primary components are a runner which rotates with the shaft and a non-rotating seal ring attached to the seal housing. The ring and l ll the runner each have a ceramic faceplate clamped to a Type 410 SST holder.
The flow path is formed between the interfaces of the seal ring and seal runner.
The face separation is in the order of .0045 inch and depends upon seal geometry and pressure distribution.
- 3. Number 2 Seal (See Figure 2-6.)
The Number 2 seal is a rubbing-face type of seal consisting of a carbon graphite insert which is shrunk into a stainless steel seal ring. The carbon graphite insert rubs on a chrome carbide coating of a Type 304 SST runner which rotates with the shaft. This seal directs the leakage from the Number 1 seal into the volume control tank.
- 4. Number 3 Seal (See Figure 2-7.)
The Number 3 seal is a rubbing-face type of seal consisting of a carbon graphite insert which is shrunk into a stainless steel seal ring. The carbon graphite insert, loaded by bellows and springs, rubs on the chrome carbide coating of a Type 304 SST runner which rotates with the shaft. This seal directs the leakage from the Number 2 seal to the waste disposal drain tank. The leakage passing through the Number 3 seal is directed to the sump.
2.2.3 Motor The motor is a vertical six-pole, Class B Thermalastic Epoxy-insulated, air-cooled, squirrel-cage induction motor of drip-proof construction designed to operate on a three-phase, 60 hertz, 4000-volt power supply.
The motor is equipped with upper and lower radial bearings, a double Kingsbury-type thrust bearing, flywheel, thrust bearing oil lift system, and a coupling flange.
The motor is also equipped with bearing temperature detectors, winding temperature detectors, bearing oil coolers, an optional water-cooled air cooler, oil level limit switches, and an anti-reverse rotation device.
- 1. Coupling The motor and the pump shaft are joined by a solid coupling composed of two mating 24-inch O.D. flanges. The pump coupling half is a carbon steel flange keyed and shrunk onto the upper end of the pump shaft. The motor half of the coupling is integral with the motor shaft and is constructed of carbon steel.
xoo0o 2-7