ML20127M165
| ML20127M165 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 09/30/1992 |
| From: | Fanto S WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19303F229 | List: |
| References | |
| WCAP-13560, WCAP-13560-R, WCAP-13560-R00, NUDOCS 9301280126 | |
| Download: ML20127M165 (581) | |
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i WESTINGHOUSE CLASS 3 ; i q PCAP-13560 b ADVANCED NUCLEAR PLANT CHECK VALVE STUDY - 1 AP600 000. #PV08-20R-001, Rev. 0 1 E} (C) WESTINGHOUSE ELECTRIC CORPORATION 19.22 : A hcones le reserved to the U.S. Government under contract DE Acos-90SF1H95. > O WESTINGHOUSE PROPRIETARY CLASS 2 The document contains informahon propnetary to Wesunghovee Electnc Corporaton; it to submitted in confidenas and is to be used solely for he purpose for wNch it la lumiehed and retumed upon request. This document and auch informabon is not to ba reproduced, transmitted, decioned or used othermee in whole of in part whout suborl2abon of Wootnghouse Electnc Corporebon, Energy Systems Bumneen Urut, autgect to the legende contamed hereof. GOVERNMENT LIMITED RIGHTS:
- (A) These data are subnutted wth lwnsted nghts under Govemment Contract No. DE AC03 90SF16495. These data may be reprodJood and used by the Govemment wth the orprese lanitahon that they wel not, without wntion permisson of the Contractor, be used for purposes of manufacturer nor declosed outende the Govemment; except that he Govemment may decioes hees data outside he Govemment for the follown0 purposes, if any, provided hat the Govemment makes such destosure outgoct to proNbiton agemet further ues and deciosure (I) The 'propnetary data' may be declosed for evabaton purposee under he restrictone above.
(!!) The 'propnetary data' mm) be decioned to the Electric Power Research InstehJte (EPRI), elece6c uttty representatves and heir droct consultante, orciudng droct commerdal compettors, and he DOE Natonal Laborator6ee under the proNtubone and restnchon* ebove. (B) The notice shal be marked on any reproducson of heee data, in whole or h part 3 WESTINGHOUSE CLASS 3 (NON PROPRIETARY) EPRI CONFIDENTIAL / OBLIGATION NOTICES: NOTICE: 1E 2 O' 3 04 Os O CATEGORY: AEaOC OoDE OF O O DOE CONTRACT DELIVERABLES (DELIVERED DATA) Subject to specmed exceptone, deciosure of INe data se reatncted unti September 30.1995 or Design Certheaban under DOE contract DE AC03-90SF18495 whichever is later, Westinghouse Electric Corporation a Energy Systems Business Unit Nuclear And Advanced Technology Division P.O. Box 355 Pittsburgh, Pennsylvania 15230
'O O .
@ 1992 Westinghouse Electric Corporation All Rights iserved 4 .<-r--,e e , _ ~ - - , .,-+---a
AP600 DOCUMENT COVER SHEET'
. Form 68202C(W92)lWPxxrr tDj - APc00 DB USE ONLY Pages Attached 522 ,
ene n.u AP600 DOCUMENT NO. REVISION NO. DATED CONTROLLED COPY NUMBER: N/A PV08-20R-001, Rev. 0 0 Sept. 1992 ASSIGNED TO: N/A ALTERNATE DOCVMENT NUMBER: WCAP-13560 ATTACHMENTS DESIGN AGENT ORGANIZATION: Westinghouse PROJECT: AP600 i
TITLE: ADVANCED NVCLEAR PLANT CHECK VALVE STUDY WORK BREAKDOWN #: 2.6.10.5 Thie secton mcorporates the folbeng design changes DCP URev.:
S El(C) WESTINGHOUSE ELECTRIC CORPORATION 19.2.2 A feense is reserved to the U.S. Govemment under contract DE AC03 00SF18405.
O WESTINGHOUSE PROPRIETARY CLASS 2 - !
This document contains iniormabon _propnetary to Weshnghouso Electne Corporaton; it is submitted in conhdence and is to be used solely for the -
purpose for wtuch it is lumished and retumed upon request. This document and such information is not to be reproduced, transmitted, dsclosed or used o'herwise in whole or in part without authorizaton of Westinghouse Electne Corporshon, Energy Systems Business Unit, subject to the legends '
conWned hereof.
GOVERNMENT LIMITED RIGHTS: 4 (A) These data are submittud with hmited nghts under Govemment Contract No. DE AC03 90SFtB493. These data may be reproduced and used . '
by the Govemment with the express krnitation that they mil not, without wntten permission of the Contractor, be used for purposes of .
manufacturer nor esclosed outside the Govemment; except that the Govemment may dsclose these data outside the Govemment for the following purposes,if any, provided that the Govemment makes such dselosure subject to prohibit on against further use and disclosure:
(l) ' This 'propnetary data' may be disclosed for evaluaton purposes under the restnct ons above.
(ii) The 'propnetary data' may be dsclosed to the Electne power Research Institut= (EPRI), electnc utihty representatives and their 3 rect consultants, excksdng droct commercial compebtors, and the DOE Nabonal laboratori., under the prohibibons and restrichops above.
(B) This nobce shall be mnrked on any reproducton of these data, in whole or in part O WESTINGHOUSE CLASS 3 (NON PROPRIETARY)
EPRI CONFIDENT 8AL/ OBLIGATION NOTICES:
NOTICE: 1'] 2O a04 Os 0 CATEGORY: AOB DC DDDE O r. O O DOE CONTRACT DEllVERABLES (DELIVERED DATA)
Subject to specif,ed exceptions, disclosure of this data is restncted until September 30,1995 or Dessgn Certhcahon under DOE contract DE AC03-90SF tB495, whichever is later.
ORIGINATOR SIGNATURE /DATE 7
Susan V. Fanto .h , $,h 4 / 7* j A AP600 RESPONSIBLE MANAGER A)
E. J. Piplica G(, rg, ' N f/-
9 w--- --
w siol operation of the check valves. This is not a concem for check valves in the APNW) application for the saf etyclated systems.
At the boric acid concentrations experienced by these salves in the plaat, frecting of the water in the piping would occur before boron precipitation occurs, lloric acid crystallitation can potentially occur at locations where there is an air / water interf ace, which allows water evaporation to increase the turic acid concentration. This can occur in locations such as valve packing or in a valve with a iody-to-bonnet leak. Ilut with the check valve design selected for the AP600 applications, any crystallization that occurs will not aticci valve operation since none of the operating parts penetrate valve body.
A second concem identitied in the study is the possibility of self-weld ny or corrosive bonding of the seat materials in the valves. Discussions with industry and vendor exp'rts indicate that this tailure mechanism is not an appropriate concem for the check valves in the Alh00 safety-related systems.
Sell welding can occur in valves with soit seat materials and where valve seat stresses are relatively high.
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s > , , i ji. t [ WESTIlJGHOUSE CLASS 3 L , The AlWO safety related systern check valve applications, in contact with the reactor coolant systein. [
- require the use of stainless steel valves and these valves have hardened stellite valve seats, in order a for self welding to beconic a potential concern in valves with hanlened seats, the stress would have to approach the yichi stress for the valve seat. At the existing backpressures in the safety related passive systeins, these stress levels do not occur and therefore selbwelding is not a valid conceni for the AlWO applications. In addition, there is no evidence of this type of failure in the NPRDS data base.
The purpose of this study is to supplement the extensive vendor design efforts to select an appnipriate ! valve design that can perfonn the required safety related functions to suppon AlWO passive systein applications. The study helps to evaluate potential check valve probleins that have occurr J in the
- industry to suppon the design selection process. 7 The design selection ellons to suppon the design certification application are not intended to establish detailed equipinent qualification or in service testing requiresnents. The design selection process is ,
intended to identify a check valve design that pnivides a high confhience that the valves can perlonn i the required safet)-related functions and reduce potential uncertainties conceming valve perfonnance to an acceptable level. The prolmed use of a siinple swing check valve deslyn, fabricated froin stainless steel, with hardened stellite seats, satisfies the design requireinents identified for successful operation in the AlWO safety-related passive systerns. i l i I - t s l' , /7 , 1 t l na ,- y ~_, _,.-.m , y., , , - ...._.,,.,-,.._.,,,w,.:,,.,,__,,y,,
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WESTINGHOUSE-CIASS 3 Nuclear Eng.' Dept. 92 02 - Revision 0 ADVANCED NUCLEAR PLANT CHECK VALVE STUDY (AP600) ,
. by.
T. J. Gillen A. J. Baratta G. E. Robinson -
.i The Pennsylvania State University: .
Nuclear Engineering Department - 231 Sackett Building
. University Park, PA 16802.- ,
i
' September 1992 -
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WESTINGHOUSE CIASS 3 1 I 1
\
p' . II ( TABLE OF CONTENTS P_itzs
- 1. INTR O D U CTI ON . . . . . .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. ... .. . . .. . . .... .... .. . . .. . . . . .. .. .. .. .. .. .. ... .. . . .. 1 I
- 2. OBJEC1TVES .............................................................................................. 1 l 2.1 Ta s k s To B e Perform ed ............................................................. 1 l 2.2 Methadology Used To Satisfy Tasks .................................. 2 i
- 3. CHECK VALVE FAILURE HISTORY ........................................................... 3 3.1 Nuclear Plant Reliability Data System (NPRDS)
Reports............................................................................................. -3 3.2 Specialized Seareh # 1 - Corrosion ........................................ . 3.3 Specialized Seareh #2 - Valye Size ...................................... I1 3.4 N P R D S D a ta S e are h R e s ul ts ................................. ..................... 14-4 LITERATURE SEARCH OF PENN STATE DATAB ASES ....................... 14
- 5. NRC/ WESTINGHOUSE VALVE MEETING ............................................... 15 s
- 6. MEETING WITH CARLYLE MICHELSON OF THE ADVISORY COMMITTEE ON REACTOR S AFEGUARDS .............................................. I6
- 7. OVERVIEW OF NUCLEAR INDUSTRY CHECK VALVE G ROUP (NIC) MEETING . ........... .. .... ........... ............. ...... .... .............. ... ..... . .... 17
- 8. V ALVE VEND O R IN QUI RIES .............. ...................................................... 18 8.1 A n c h o r/D arli n g V al y e C o. ........................................................ 18 8.2 A tw ood an d M orril Co., I nc ..................................... ............. 19
- 9. IND U STR Y IN QUIR IES ...... .. .... .................. ....................... ............ .... .. ... ........ 20 i 9.1 B oili n g Wat er Re ac t ors ......................................... .. ............. 20 9.2 Pre s s u ri z e d Wa t e r R e a e t ors .................................................... 21 9.3 Re sults of Ind u stry Inquiries ................................................. 21 1 0 . CONCLU SI ON S . . .. . . .. .. . . .. .. .. . . .. .... . . .. . . .. . . .. .... .. . .. . . .. .. .. . . .. .. .... .. . . . . .... .. .... .. . . .. .. . .. . . .. .. 22 1 1. TESTING RECOMMENDATIONS ........................ ........................................ 22 1 1.1 Tests in Nuclear Power P1 ants ............................................... 23 1 1. 2 A cc e I e ra t e d A gin g Te s t s ...........................................................
24 p.- - - _ , 4
WESTINGHOUSE CIASS 3 TABLE OF CONTENTS (Continued) hit
- 12. REFERENCES .................................................................................................. 25 APPENDIX A -
NUCLEAR PLANT RELIABILITY DATA SYSTEM (NPRDS) COMPONENT MASTER FAILUIG REPORTS APPENDIX B - SEARCH OFPENN STATE DATABASES: TITLES AND ABSTRACTS APPENDIX C - SEARCH OFPENN STATE DATABASES: RELEVANT PAPERS APPENDIX D - NRC/WESTINGilOUSE VALVE MEETING TRIP REPORT APPENDIX E - TRIP REPORT OF MEETING WITH CARLYLE MICHELSON OFTHE ADVISORY COMMITEE ON TEACTOR SAFEGUARDS (ACRS) APPENDIX F - NUCLEAR INDUSTRY CHECK VALVE USERS GROUP (NIC) MEETING TRIP REPORT AND NON-INTRUSIVE TES'ITNG SURVEY g APPENDIX G - VALVEVENDORS CONTACTED APPENDIX H - UTILITY CONTACTS O
WESTINGHOUSE CLASS 3 ( iv FIGURES 3.1 PERCENTAGE OFFAILURES AS A FUNGON OFFAILURE TY P E - B WR S AND P WR S ...... ............ .. ... ....... .. ....... .... .. .. .......... .. .. ... ...... .. .. 5 3.2 PERCENTAGE OF FAILURES AS A FUNGON OFFAILURE TYPE-BWRS.................................................................................................... 7 3.3 PERCENTAGE OF FAILURES AS A FUNGON OFFAILURE TYPEPWRS................................................................................................... 9 3.4 PERCENTAGE OF FAILURES AS A FUNGON OF VALVE SIZE ..... I2 O U -
. , . , ,~. y. , - ~ -.r-e. - - - ,
- , e - -- -.- n a WESTINGliOUSE CLASS 3 TABLES 3.1 FAILUTG TYPE CATEGORIZED BY SYSTEM - BWRS ........................... 8 3.2 FAILURE TYPE CATEGORIZED BY SYSTEM - PWRS ........................... 10 l
l O l O l
WESTINGHOUSE CLASS 3 1 O
- 1. INTRODUCTION The Westinghouse Advanced Plant (AP) reactor series are advanced light water reactor designs that have as their basic !
objectives simplification, reduced costs, and reliability. Integral l constituents of the AP600 passive plant safety systems are the q isolation check valves which seal against the primary system l pressure. The plant safety systems depend on these check valves to l function reliably at low pressure differentials so as to ensure that ; cooling water will flow into the reactor system by gravity either from l the Core Make up "'ank (CMT), the Inside Containment Refueling -l Water Storage Tank (IRWST), or the containment sump. ) In preparation for anticipated check valve reliability. tests, The 1 I Nuclear Engineering Department of The Pennsylvania State University has conducted a study to determine both (a) the experience level the power industry has accumulated on check valve performance and (b) the information required to plan and develop a check valve test program. This report summarizes the results of that study. O 2. onaectives This section outlines the tasks that were to be performed and the methods employed to address these tasks. 2.1 Tasks To Be Performed The primary tasks of this work were two-fold. The first involved a review of the literature to reveal the present state of power plent operating experience with respect to check valves, while the second task was to provide information on h_ow to perform experiments in as short a time period as possible such that the valves experience accumulative operating conditions - similar to those anticipated in the actual plant. The first task of this study was to be met by performing a consprehensive investigation of the literature and operating experience of nuclear power plants (NPP). Specifically, this investigation was to be performed to determine the following:
- 1. An inventory of Nuclear Steam Supply System (NSSS),
check valves, operating experience, and application. The
WESTIliGHOUSE CLASS 3 2 selection was to be limited to simple swing disk designs, g stainless steel bodies, stellite seats, clean water and W borated water (PPM < 3000). This inventory was to include both Pressurized Water Reactor (PWR) valve applications as well as Boiling Water Reactor (BWR) valves
- 2. Cases where valves failed to open against a small differential pressure
- 3. The disk / dynamics of check valves at low flow conditions
- 4. Cases where the check valves have experienced corrosion, either in the body, bearing, or disk in NSSS type of chemistry, pressure and temperature environments For each failure found, a root-cause analysis was to be provided where available.
The second task was to be fulfilled by supplying information on how to perform (a) experiments that can simulate accelerated aging such that experiments do not have to be performed in real time or (b) tests that could be done in a NPP. Statistical analysis was also to be performed to determine the minimum sample size of valves that could be used to perform an experiment such that meaningful reliability data can be obtained, particularly to address common mode failures. g 2.2 Methodolony Used To Satisfy Tasks This study primarily focussed on the 6 in. check valves which are located in lines from the IRWST to the reactor vessel in direct contact with the Reactor Cooling System (RCS) water, These check valves are normally held closed by the backpressure of the RCS. The normal system pressure of the, RCS with the plant generating electricity is 2235 psig. After being in the closed position for up to two years these valves are required w open with a differential pressure of approximately 10 psig. It is clear that these check valves are used under unique conditions not commonly found elsewhere in the AP600. The first task of this study was addressed by consulting several sources of information. These included the Institute of Nuclear Power Operation's (INPO) Nuclear Plant Reliability Data System (NPRDS), several valve vendors, a number of people from various utilities, Mr. Carlyle Michelson of the Advisory Committee on Reactor Safeguards 3 T (ACRS), and Mr. Don Casada of Oak Ridge National Laboratory. A
WESTINGl!OUSE CLASS 3 3
~'s Nuclear Industry Check Valve Group (NIC) meeting was attended to (d procure information on what the industry is doing with respect to check valve applications and frequency of testing. A search of four technical databases available at Penn State University yielded several articles on the flow considerations and disk dynamics of check valves.
With regard to testing information, the second task of the study, Dr. Howard Pickering, a corrosion expert at Penn State University, was consulted. Dr. Pickering provided information on accelerated age testing considerations. Mr. Michelson of the ACRS also added valuable input with regard to testing. In addition, Dr. J. Paul Tullis of Utah St. University was contacted as was Kalsi Engineering, Inc. of Sugar ' Land, Texas. During the course of this work information was also gathered on non-intrusive check valve diagnostic techniques and tests.
- 3. CIIECK VALVE FAILURE IIISTORY There are two comprehensive sources of check valve _ failure data. These are the Institute of Nuclear Power Operation's (INPO's)
Nuclear Plant Reliability Data System and the Nuclear Regulatory Commission's (NRC's) Sequence Coding and Search System (SCSS). O Abstracts of all Licensee Event Reports (LERs) that were issued by U. S. utilities are stored on the SCSS 1 Due to a redundancy of approximately 95% between these two databases, Oak Ridge National Laboratory (ORNL) is beginning a general practice of using NPRDS data when available 2 This, coupled with the ability- of Westinghouse to directly access NPRDS, led to the use of NPRDS as the prime source of check valve historical failure data consulted in this study. 3.1 Nuclear Plant Reliabili v Data System (NPRDS) Reports The NPRDS data base contains records collected by utility personnel and submitted to INPO. These records include engineering data and failure reports for components in over 25 safety-related systems, as well as those in condensate, main feedwater, main steam and electrical distribution systems 3 Using NPRDS as the basis, ORNL is currently performing a review of check valve historical failure data 4 under the sponsorship of the Nuclear Regulatory Commission's (NRC's) Nuclear Plant Aging Research Program. The results of this review are to be used as a foundation for the American Society of
] Mechanical Engineers (ASME) Committee on Operation and Maintenance (OM) of nuclear power plants, which has established a
WESTINGHOUSE CIASS 3 4 Working Group (WG) on check valves, OM-22. The main function of OM-22 is the development of check valve performance test requirements, including the required frequencies of in-service testing. To date these frequencies have not been finalized 2, ORNL conducted an initial review of approximately 4500 check valve failures and eliminated those failures in which there was external leakage, only minor seat leakage, or other failure modes which were not related to the valve's proper functioning otherwise. Due to improved reporting practices to NPRDS beginning in 1984, only failures occurring between 1984 and 1990, inclusively, were considered. Failure events occurring in 1991 and afterward were not considered because, at the time the data was downloaded, all failure orts for 1991 were not filed. A total of 1140 records remained after this initial cut. Mr. Don Casada of ORNL provided us with a copy of these cases for use in this study. A primary concern for the AP600 IRWST isolation check valves is their ability to open under a small differential pressure. With this in mind, the 1140 failure records were carefully filtered to reveal cases where valves have stuck closed or only partially opened, regardless of the pressure available to open them. This resulted in a total of 87 fail to open or only partially open cases. The full reports for these failures are provided in Appendix A and are preceded by a listing of the failure records. ' The NPRDS data as received from ORNL had already been classified according to failure type. The categories used to sort the records were corrosion, foreign debris, wear, other, and unknown. Figure 3.1 shows the percentage of failures as a function of failure type for BWRs and PWRs combined. Approximately 17% of the failures in these cases were attributed to corrosion while foreign debris was responsible for a little more than 20%. While wear was responsible for the largest percentage of failures ( -43%), this does not appear to be a credible failure mode for the AP600 IRWST check l valves due to their infrequent use ( under normal circumstances l these valves will be stroked once every refueling outage ). The percentage of failures for BWRs alone is shown in Figure 3.2. Corrosion comprised only about 10% of the fail to open cases while 25% of the cases were attributed to foreign debris in l BWRs. A further breakdown of the BWR data can be seen in Table 3.1. The data in this table categorizes " failure type" according i to " system". Approximately 1/2 of these failures were due to wear. O
FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES
- IN WHICH DESIGNATED MECHANISM WAS INVOLVED
-BWR'S AND PWR'S-50 #
Note that the total percentages exceed 100% due to more than one mechanism j be!ng designated in some failures f W: fd] 40 - ; . X H M' en
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- TOTAL NUMBER OF FAILURES EOUALS 87
. SOURCE : NUCLEAR PLANT RELIABILITY DATA SYSTEM - COVERAGE YEARS 1964-1990 l u l: Figure 3.1 Percentage of Failures as a Function of Failure Type - BWRs and PWRs .-
.i
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WESTING 110USE CLASS 3 6 Almost 1/3 of the fall to open cases oncurred in Main Steam systems and each of these involved the failure of a carbon steel vacuum g breaker check valve. Of the failures due to corrosion, 60% occurred in High Pressure Coolant Injection systems. Figure 3.3 illustrates the percentages of different types of failures in PWRs. Again, wear is the major failure mechanism comprising airnost 38% of the total. In contrast to BWRs, corrosion comprised 25% of the failures in PWRs. Fifteen percent of the fail to open cases were due to foreign debris. The particular systems that were responsible for the different fallut:s can be seen in Table 3.2. Component Cooling Water and Diesel Starting Air systems each contained 20% of the failed valves. - 3.2 Snecialized Search #1 - Corrosion A specialized search was performed based on corrosion failures for the fail to open or only patially open cases. The purpose of this search was to locate any stainless steel check valves that failed due to corrosion and then appraise their relevancy for comparison _ to the AP600 IRWST check valves. Because the NPRDS reports do not specify the specific type of check valve, all types were included. The criteria used for this specific search is as follows: , h Records: Fail to open or only partially open cases Valve Size: All Check Valve Type: All Failure Type: Corrosion Body Material: Stainless Steel The above search yielded one event that met the criteria and is given belov>: Plant: Point Beach 1 NSSS: Westinghouse System: Reactor Coolant Component: Pressurizer Relief Tank Nitrogen Supply Check Valve Cause: Valve plug was found to be corroded in place Size: 0.75 in. O
f V V bl FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES
- IN WHICH DESIGNATED MECHANISM WAS INVOLVED
-BOILING WATER REACTORS-So / Note that the total percentages exceed f a 4 -
100% due to more than one mechanism s
- being designated in some faDures
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- TOTAL NUMBER OF FAILURES EOUALS 47 SOURCE : NUCLEAR P1 ANT RELIABUTY DATA SYSTEM - COVERAGE YEARS 1984-1990 -a Figure 3.2 Percentage of Failures as a Function of Failure Type - BWRs
Table 3.1 Failure Type Categorized by System - BWRs FAILURE TYPE : VEAR?&Q1 DAMAGE CORROSON FOREGJ DEBRIS HUMANEfVUU OTFBI trMOVAi UNSURE 41tT1 ACED TOTALS 8OF .ORNL FAILURE TYPE NO.: It) [1] [2] [3] [41 [5] [6] [11-16] FAILURES SYSTEM MA!N STEAM 11 1 4 16 16 g FNORCOREISOLCOOLFJG 2 2 3 1 8 8 M HGi PRES COOLM4T RU 1 3 1 5 5 9 ESS&lTIAL SERVICE WATER 1 1 3 1 6 3 $ O DIESEL STARTING AIR 1 1 2 2 LOWPRESCORE SPRAY 1 1 2 2 6 SUPPRESSON POOLSUPPOR1 1 1 2 2 N COMBUSTIBLE GAS CONT-Dil 2 E 2 M RHRtOW PRES IFUECT 1 1 2 2 O REACT BtDG CCW 1 1 2 2 h DIESEL FUELOlt 1 1 1 FEEDWATER 1 1 1 y CONTROL FDD DRPE 1 1 1 TOTALS: 22 5 12 2 8 1 0 50 47 PERCE?TIAGES: 46.81 % 10.4 % 25.53 % 426% 17.02% 2.13 % 0.00 % 106.38% I POTE :THG TOTAL PERCENTAGES EXCEED 100% DUE TO MORE THN4 ONE MECHANISM BEG 1 DESO4ATED PJ SO*E FA! LURES ce O O O
O O O l 1 I FAILURE TO OPEN OR ONLY P7DTIALLY OPEN ' PERCENTAGE OF FAILURES
- IN WHICH DESIGNATED MECHAN!SM WAS INVOLVED
-PRESSURIZED WATER REACTORS-l 40 # A~ l
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- TOTAL NUMBER OF FAILURES EOUALS 40 4 SOURCE : NUCLEAR PLANT RELIABluTY DATA SYSTEM - COVERAGE YEARS 1984-1990 e
- Figure 3.3 Percentage of Failures as a Function of Failure Type - PWRs .
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Table 3.2 Failure Type Categorized by System - PWR3 FAILURE TYPE : WEAR 1AECH DAMAGE uin.dtri FOREG4 DEBR!S HLuv4 ERRORS OTim LtMONN UNSURE 41EFtACED TOTALS *OF ORtit. FAILURE TYPE NO.: [1] [1] [2] 131 I idi [5] [61 111-[6] FAILURES SYSTDA COWCOOLtJGWATER 4 2 ' 1 8 8 :c DIESEL STARTING AIR 2 2 1 1 1 1 8 8 $ NUCLEAR SEfWICEWATER MAIN STEAM 2 2 2 4 4 y 1 3 3 = AUXILIARY FEEDWATER CONTAf4MENTSPRAY 1 2 1 1 3 3 $ 1 7 3 CONDENSATE 2 m 1 3 3 HIGH PRESSURE FUECTION 2 2 2 COMBUSTIBLE GAS CONT-D:L 2 2 2 O MAri REDWATER SYSTEM 1_ 1 2 2 NACTORCOOLNET 1 1 1 c2 CHEMICAL & VOLUME CNTRL 1 1 2 1 u TOTALS : 15 10 6 3 1 5 1 41 ' 40 PERCEffTAGES: 37.50% 25.00% 15.00 % 7.50 % 2.50% 12.50% 2.50 % 102.50% NOTE :THE TOTAL PERCENTAGES EXCEED 100% DUE TO MORE THAN ONE MECHANISM BEG 1 DESG4ATED P4 SOME FA! LURES U O O 9 ' G
4 WESTINGHOUSE CIASS 3 , 11 9 Upon closer scrutiny of this particular failure a discrepancy in O the report was found to exist. While the engineering notes listed the body material of this valve as Austenitic 316 Stainless Steel, the descriptive failure narrative stated that this was a carbon steel valve in a stainless steel pipe and therefore attributed the corrosion to the dissimilar metals in contact. This is a blatant contradiction and serves to illustrate that caution must be taken when usine the NPRDS data. Although reporting practices to NPRDS began to improve in 1984, the narratives are still sometimes vague or misleading. If a ' high degree of confidence is demanded of NPRDS categorizations it may be necessary to consult the utilities' rnaintenance records for the specific valves of interest. Because of the error in valve body material and the fact that this , valve is located in a gas system, it is not an appropriate failure for comparison to the 6 in, check valves in the AP600 IRWST system. The conditions seen by this valve would be extremely different from those experienced by the AP600 valves. 3.3 Specialized Search #2 - Valve Size O A search was conducted based on check valve size. Figure 3.4 shows the distribution of valves as a function of size for the fail to open or only partially open cases. Referring to this figure it is seen that over 50% of the failures occurred in valves that are 2 in. or less in diameter, while valves in the 6 8 in. range comprised less-than 3% of the failures to open. Based on a recommendation by Mr. Carlyle Michelson of the Advisory Committee on Reactor Safeguards (ACRS) another specialized search was conducted. Mr. Michelson suggested - discarding all valves with a diameter less than 6 in., stating that the failure modes for these smaller valves are different than for larger valves 5 A search was thus performed for stainless steel valves with a diameter of 6 in, or larger. The criteria used for this specific search is as follows: l Records: Fail to open or only partially open cases Valve Size: 6 in, or larger Check Valve Type: All
- Failure Type
- All '
! Body Material: Stainless Steel l
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- AS A FUNCTION OF VALVE SIZE 60 #
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WESTIliGl!OUSE CLASS 3 13 p This search yielded two failures that satisfied the above criteria. The s first is as follows: Plant: Browns Ferry 3 NSSS: General Electric System: Essential Service Water Component: North Header Check Valve to Control Bay Chiller Cause: Dirt and crud collected inside valve internals / Ilinge pins were also bent Size: 6.0 in. This valve is located in a " dirty" water system, where system components -are more susceptibic to corrosion and foreign material obstruction than components within the AP600 Reactor Coolant System 6 This valve is also exposed to frequent use and pressure surges, whereas the AP600 IRWST valves will experience very limited use under normal operating conditions. For these reasons this failure was not deemed appropriate for comparison to possible failure of the AP600 valves. This search resulted in one other failure as given below: Plant: Brunswick 1 NSSS: General Electric
- System: Suppression Pool Support Component: Suppression Pool Vacuum Breaker Check Valve Cause: Stripped magnet bolt and a broken magnet. The failure was due to previous maintenance.
Size: 20.0 in. This check valve serves a purpose quite different from that of the AP600 valves. The flow of steam from the drywell to the pressure suppression chamber will create a negative pressure in the drywell with respect to the pressure in the suppression pool. The purpose of this valve is to " break" this vacuum when it occurs. This valve is in a steam system and is therefore not appropriate for comparison to the AP600 IRWST valves which are located-in a high pressure, reactor grade water system.
WESTINGHOUSE CIASS 3 14 3.4 NPRDS Data Search Results The above specialized searches of the NPRDS data revealed no failures of valves that can be directly compared to the 6 in, stainless steel check valves which are located in lines from the AP600 IRWST to the reactor vessel in direct contact with the Reactor Cooling System water. Only 8 of the 87 fail to open cases involved stainless steel check valves, the majority of the valve bodies being made of carbon steel . As will be discussed in Section 9, the valves that experience the closest set of operating conditions in present nuclear plants compared to the AP600 valves appear to be (1) accumulator check valves in Westinghouse units, (2) safety injection tank discharge valves in Combustion Engineering units, and (3) core flood tank check valves in Babcock & Wilcox units. A search of the fall to open or only partially open cases uncovered no events involving these valves. It should also be mentioned that no Westinghouse /Hagan valves , appeared in any of the 87 fail to open cases.
- 4. LITERATURE SEARCH OF PENN STATE DATABASES A search of four databases available at Penn State University was conducted in an effort to locate articles dealing with the disk dynamics of check valves and check valve monitoring methods. The databases covered, including contents and coverage years, are as follows:
NTIS - National Technical Information Service Technical reports (NASA, DOE, DOD, etc.) 1983 to present Compendex - Engineering & Applied Sciences Journal articles & conferences Last 5 years
. Wilsonline - Applied Science & Technology Index Technical reports 1983 to present g
WESTINGHOUSE CLASS 3 15 I N . RLIN/El - Engineering Index (G Journal articles & conferences
- 1986 to present This search revealed approximately 325 articles. After an initial cut was performed to eliminate studies that were deemed irrelevant for the present work, a total of approximately 125 articles remained. The titles and abstracts (where available) of these articles are given in Appendix B.
Of these papers seven were chosen as being the most relevant to the present study. Four of the articles deal with disk stability and wear, two involve non intrusive monitoring methods, and one paper addresses the question of in service testing requirements. The titles and abstracts of these articles are given in Appendix C along with the papers themselves.
- 5. NRCAVESTING110USE VALVE MEETING On March 3 and 4,1992, Dr. T. J. Gillen attended the NRCAVestinghouse Valve Meeting at the Westinghouse Energy O Center. The purpose of this trip was to procure relevant information on check valve design and testing. A detailed trip report is included in Appendix D while a brief summary of this meeting is provided '
below. Many topics were discussed at the meeting, including the following: general valve design considerations; AP600 safety systems; unique AP600 valve applications, which covered both Automatic Depressurization System (ADS) valves and low differential pressure opening check valves; and other AP600 valve applications. The ADS design, including location and function of ADS valves and check valves, was presented in some detail. The four stages of the ADS system were discussed, together with design specifications and requirements of the ADS valves for each stage. A general discussion of check valve selection and experience, together with a detailed description of check valve requirements and parameters for the AP600 IRWST injection system was presented. It should be mentioned that the parameter sheet that detailed the requirements of the AP6001RWST check valves was a basic source of information on these valves. 'niis information was used as the basis for inquiries of valve vendors and utility personnel as ( discussed in Sections 8 and 9. 1
~ WESTINGHOUSE CLASS 3 16 A videotape of the AP600 Pascive Core Cooling System Check Valve Test was also shown. This test investigated the performance of both 4 in, and 6 in. Westinghouse /Hagan swing check valves. A presentation of check valve failure information was given by Don Casada of ORNL. As stated in the previous section, ORNL is currently reviewing and categorizing historical check valve failures using the NPRDS database. It was this data that was supplied to Penn State through Westinghouse (with approval from INPO) for tase in the present study.
- 6. MEETING WITH CARLYLE MICHELSON OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS Dr. G. E. Robinson and Dr. T. J. Gillen of Penn State University met with Mr. Carlyle Michelson of the Advisory Committee on Reactor Safeguards (ACRS) in Bethesda, MA on August 4,1992. The ,
purpose of this meeting was to obtain Mr. Michelson's specific concerns with regard to the operation of the 6 in. simple swing check valves that are being proposed to isolate the RCS from the IRWST. A detailed trip report is included in Appendix E while a brief summary of this meeting is provided below. Mr. Michelson's major concern was the possibility of bonding of g the seat to the disk. Although he referred to this as self-welding he was not sure that this was the appropriate term. He repeatedly expressed concern for the possible bonding of these surfaces and strongly recommended that metallurgists and corrosion experts be consulted. He also mentioned that if there is no experience base for low differential pressure opening check valves then self-welding (bonding) may have to be experimentally researched. Mr. Michelson also expressed cor.cern with regard to hinge pin corrosion, emphasizing that material selection is crucial since there will not be any continuous sweeping action to keep tne pin cleaned up. He also felt that the system may need to be heat traced due to the possibility of a boron precipitation problem, especially between the valves. With regard to previous experience, Mr. Michelson indicated that Westinghouse may have to develop their own data because he does not think there will be much in the literature about cases where the valve is required to open under such a small differential pressure. He also indicated that there would have to be some type of external diagnostic equipment on the valve to sense disc position. g
WESTI!1G1!OUSE CLASS 3 17 p' The most important point that Mr. Michelson expressed was that Westinghouse must be able to prove that the valve will open (J under the specified conditions. He indicated that even though he could not prove that bonding will occur, Westinghouse must be able to prove that it won't.
- 7. OVERVIEW OF NUCLEAR INDUSTRY CIIECK VALVE GROUP (NIC) MEETING Dr T. J. Gillen of Penn State University attended the Nuclear Industly Check Valve Group (NIC) meeting in Dallas, TX on. August 13 and 14,1992. The purpose of this trip was to procure information on what the industry is doing with respect to check valve applications and frequency of testing. A detailed trip report is included in Appendix F while a brief summary of this meeting is provided below.
The NIC group is comprised of three committees. These are the Non-Intrusive Examination of Check Valves Committee, the Check Valve Applications and Maintenance Committee, and the Technical Information Committee. The Non-Intrusive Examination of Check Valves Committee has been working on producing a maintenance guide on non-intrusive testing. The committee reported that the guide is currently about 70% complete. This committee has also beca reviewing the three - phases of the work on evaluations of non-intrusive diagnostic testing currently being investigated by_ Dr. J. Paul Tulbs of Utah St. University. Phase I deals with water 7, Phaso II with air, and Phase III is concerned with steam systems. The Phase 11 testing was reviewed by the committee and upon incorporation of the committee's comments the document will be completed.
. The Check Valve Applications end Maintenance Committee actually consists of two subcommittees. The Applications Subcommittee has been involved with making revisions to the EPRI report NP-5479 " Application Guide for Check Valves in Nuclear Power Plants". Based on the NIC Phase I testing, the equation for v mio , the minimum velocity required to hold the disk in the fully open position, has been redone and will be incorporated into the report. This report is undergoing major revisions and is expected out by the end c. the year.
The aim of the Maintenance Subcommittee is to provide a comprehensive maintenance manual fer check valves. Don Casada-presented recent results from ORNL's review of check valve historical O' failure data. The major objective of this study is to address the
WESTINGHOUSE CLASS 3 18 question of frequencies for disassembly of check- valves. . Don reported several interesting preliminary results. Failure rate was W found to be directly proportional to age of the valve. There was no significant increase in failure rate for systems that are normally in service as compared to tnose that are infrequently used. As was discussed in Section 3.2 of the current study, Don has also found that the characterization of valve failures from NPRDS is difficult due to the lack of adequate descriptions. A draft of the NUREG based on the ; ORNL study is due out in October of this year. The Technica' Information Committee reported on a new NIC database which is dedicated exclusively to check valves. This database is planned to become active on September 1,1992 and will contain two; sections. There are currently 2400- entries in the valve section while the library section will list approximately 1700 documents that deal with check valves. Although this is not a failure database, that is it will not contain maintenance records, it will indicate system, flow, manufacturer, people to contact, and additional , items relating to the valves contained in the database. Mike Belford of Southern Nuclear Operating Company presented a recent survey of the nuclear industry regarding the usc of non-intrusive testing of check valves. This survey. has been a valuable source in making numerous utility contacts and a- copy of it is provided in Appendix F following the NIC trip report. This surve'y h also prompted further inquiries into the testing of existing valves ~in nuclear power plants. These queries will be discussed in Section 9.
- 8. VALVE VENDOR INQUIRIES A list of valve vendors that were contacted throughout the course of this study is provided in Appendix G. Interviews and phone conversations that were conducted with representatives of Anchor / Darling Valve Co. and Atwood and Morril Co., Inc. are summarized below.
8.1 Anchor /Darline Valve Co. A meeting was held with Mr. Rich Boyle of Anchor / Darling at Penn State University on July 2,1992. With regard to the question of self-welding he stated that the only time that he heard that term used was in the work that he had previously done with Westinghouse on Auto Depressurization Valves. He mentioned that g
WESTINGHOUSE CLASS 3-19 -(~Y he was not familiar with self-welding and could not recommend any - V sources of information on the topic. In the area of testing he mentioned that no flow loop testing is done at -Anchor / Darling. In a conversation with Mr. Boyle at a latter date 8, he stated that from his experience the only -time he-could remember of self-welding being a concern was with a particular Westinghouse solenoid type valve which had some problems with self-welding under extreme temperature and environmental conditions. He suggested that Mr. Lill Knecht, a technical supervisor at Anchor / Darling, be consulted. Mr. Bill Knecht was contacted by telephone 9 and the conditions-that the valve is expected to see were described-to him. The concerns of;Mr. Michelson of the ACRS were also relayed to Mr. Knecht, particularly those relating to self-welding and -the; concern of the valve opening under the small differential pressure after sitting-at a high pressure for so long. He stated' that the term self-welding is a misnomer since there is no- chance of any actual metal to metal-welding due to stellite having a compressive strength on- the order of 200,000 psi. He thought that what'Mr. Michelson is really concerned with is the corrosive effects of the borated water binding the surfaces together. He mentioned that the borated water has little effect on the stellite and he knew of no self-weldment of stellite to stellite. Mr. Knecht stated that the only way to prove that the valve - will not experience corrosive bonding is to put the valve in _a system ~ for two years and then try- to open it. . Anchor / Darling Valve Co. recommended that a simple swing check valve be used in the current application 8 They suggested a possible modified Anchor / Darling hardfacing' material for the seat to disk contact area and a backstop to- control and limit opening of the valve. 8.2 Atwood and Morril Co.. Inc. A conversation was held with Mr. Lauren Hutton of Hutton
- Associates Inc., a local representative of Atwood and Morril. This took place at the NIC meeting in Dallas, TX on August 14, 1992. Upon performing a series of calculations, Mr. Hutton came to the conclusion that a stainless steel, simple swing check valve is all that is necessary for this application. He mentioned that corrosive bonding does exist in valves in current plants, particularly in Safety Injection Systems, .
O V but he also stated that, with 10 psig available to open the valve,
l UESTINGHOUSE CLASS 3 j 20 corrosive bonding would never prevent this valve from opening. He g stated that the worst effect corrosive bonding could have would be to T raise the required opening pressure from 1/4 psig (the pressure required to open a clean valve) to 1/2= psig.
- 9. INDUSTRY INQUIRIES A number of contacts were made with industry personnel. The utilities that were contacted along with the person's name and. phone number are provided in Appendix H. The purpose of these conversations was to procure information on valves in current plants that are under similar operating conditions to the AP600 IRWST valves and also to obtain testing information on these valves.
9.1 Boiline Water Reactors , A review was conducted of the system description manual for Pennsylvania Power & Light's (PP&L's) Susquehanna plant. While the normal operating pressure of a BWR is significantly less than that of a PWR, it was still though to be worthwhile to search for valves that are required to open under small differential pressures (less g than 15 psig). Upon the identification of several possible candidates, Mr. Bill Lowthert of PP&L was contacted 10 Mr. Lowthert supplied drawings of these valves, manufacturer information, and conditions that these valves may see, Unfortunately all of these valves either contained external operators (such.as testable check valves), were of an incorrect type (such as piston lift), or had body protrusions (vacuum breaker valves with counteiweights) which rendered them inappropriate for the current study. In' any case, none of these valves were required to sit for an extended period of time under high pressure and then be demanded to self-actuate under a low differential pressure. Mr. Tom Fallgren of Northern States Power Co/s Monticello plant was also contacted 11 He searched through several systems and the only valves that he could locate that have a relatively low pressure available for opening were vacuum breaker valves and ! testable check valves. These valves had both been explored in the PP&L review and neither met the criteria for the current study. He also looked at Core Spray Valves but stated that they have a O l
WESTINGHOUSE CLASS 3 21 l significant pressure available to open them, although he did mention that they open before the full pressure is applied. He indicated he - had no way of proving this 12, 9.2 Pressurized ' Water Reactors Utility inquires 13-21 have revealed that there are check valves that experience similar operating conditions and environments in PWRs while in the closed position. . The valves that experience the closest set of operating conditions in present nuclear - plants compared to the AP600 valves appear to be (1) accumulator check valve,s in Westinghouse units, (2) safety injection tank discharge valves' in Combustion Engineering units, and (3) core flood tank check valves in Babcock & Wilcox units. These valves all serve the same purpose of isolating the RCS from a reserve tank of water similar to the IRWST in the AP600. The accumulator tanks are normally at a pressure of approximately 680 psig, the safety injection tanks at 250.psig, and the core flood tanks are normally pressurized to 300 psig. Thus, when the valves are closed, the differential . pressures across them are relatively close to the full RCS system pressure of the AP600 valves. Although these tanks are normally maintained at a higher pressure than that planned for the-AP600 IRWST, inquiries have revealed that they are tested under significantly lower pressures 16,18 (ranging from 35 to 100 psi). The valves also experience similar boron concentrations and water quality to that found in the AP600. A request has been made to-utilities (Appendix H) to supply information on the conditions and types of testing performed on these valves, along with maintenance records and the specific valve type. The results of these tests have not -yet been received but will be supplied to Westinghouse upon receipt. 9.3 Results of Industry Inouiries Inquires revealed no swing check valves in BWRs that are under operating conditions similar to those of- the 6 in, check valves in the AP600 Passive Safet3 Injection System. Although low differential operating check valves do exists, none are of a self-actuating simple swing design without body intrusions. O
WESTINGHOUSE CLASS 3 22 There are valves existing in current PWRs that experience conditions similar to the AP600 IRWST valves, at least in the closed position. These valves are stroke tested during refueling outages and nonintrusive diagnostics are used to verify valve opening. It may be possible to perform a modified test on these valves to address the question of the valve opening at low differential pressure. For example, this could be done by monitoring the disk position as a function of pressure drop across the valve as the valve is opened.
- 10. CONCLUSIONS Industry inquiries revealed no valves in present nuclear plants that are under identical operating conditions that will be required of the 6 in, check valves which are located in lines from the IRWST to the reactor vessel in direct contact with the RCS water. Therefore, even though the NPRDS data review does not support a co .ern for '
the failure of these valves to open, the absence of valves under similar operating conditions in present plants dictates that t:ne NPRDS data review is inconclusive with regard to the possibility of these valves failing to open. Based on the NPRDS fail to open cases found in non-reactor grade water systems, it does appear that the major concerns for valves of this type are corrosion and foreign debris. g Inquiries with valve vendors, utility people and NIC members have failed to reveal any experience base on check valves that are require to open under a small differential pressure of approximately 10 psig after being exposed to RCS pressures for extended periods of time. Thus, because there appears to be no hard physical evidence available to disprove the possibility of these valves failing to open with small differential pressure, it appears that some type of testing will be necessary to address this question.
- 11. TESTING RECOMMENDATIONS Dr. J. Paul Tullis of Utah St. was contacted with regard to tile existence of previous testing that would be appropriate to the current study 22 He knew of no previous test that addressed the question of corrosive bonding. He stated that it normally only takes a fraction of a pound to open a check valve, just enough pressure to overcome the weight of the disk.
Mr. Daniel Alvarez, a test engineer for Kalsi Engineering, Inc., was also contacted concerning the question of testing and corrosive
WESTINGHOUSE CLASS 3
=23-bonding 23 Ile stated _ that 10 psig provides_ a lot of force on the disk
[V3 of a 6 -in, swing check valve and it would almost be impossible for the valve to stick shut. He stated' that 10 psig was enough pressure to overcome any bonding forces'although he was not aware of any data to back this up. The only ( Ivice he could provide with respect to accelerated aging was to perform an elevated temperature test in order to accelerate the corrosion process. He also mentioned that Kalsi Engineering could possibly perform the tests. There exists two strategies for providing the necessary -testing of these check valves to verify their ability ~ to open under the specified operating conditions. The first is to test valves that experience similar conditions in current power plants. The alternate plan is to perform an accelerated aging test on a number of valves in an attempt to arrive. at statistically significant evidence of the valve's ability to open. Based on reasons given below, the first method of ! testing appears to posses significant advantages over accelerated age testing. , 11.1 Tests in Nuclear Power Plants l h Based on inquiries with people from various utilities, there exists the possibility of -performing non-intrusive tests on valves that are under similar conditions (see. Section 9) in present nuclear plants. ~ By monitoring disk position as a function of pressure drop across the valve the question. of low differential opening pressure can be addressed. Nonintrusive testing is currently being' performed at many plants and it is possible that some of this data already exists. Even though these existing . valves are not required to open under 10 psig, they still experience virtually the same conditions for the same time intervals as the AP600 valves while in the closed , position. Thus, by carefully monitoring the pressure that is required l to begin opening these valves, failure rates for these valves to 'open l ' can be derived. It is this similarity of operating conditions that L makes this means of testing the more attractive- course of action. This nonintrusive testing concept was a direct result of the survey (see - Appendix F) that was acquired at the NIC meeting in L Dallas, TX, on August 13 and 14. Due to this, adequate time was not L available to fully investigate this testing option. Lo
WESTINGHOUSE CLASS 3 i i 24 J l1.2 Accelerated- Agine Tests Dr. Howard Pickering, a corrosion expert at Penn State University, was consulted with respect to the question of disk- to seat bonding and accelerated age testing considerations 24 In order to address the question of corrosion, it was necessary - to choose a specific valve from a number of possibilities in order to perform the analysis. Due to the availability of detailed component information, a typical 6 in. swing check valve, manufactured by Westinghouse / Hagan, was selected. Dr. Pickering indicated that there was no way to answer the concerns of ' corrosion or bonding from the literature. As far as the bonding goes he could not predict how much of a corrosive surface layer would have to build up in order for the disk and seat to bond and therefore prevent the valve from opening under the available pressure. With regard to corrosion he indicated that corrosion will be localized in the highly corrosion resistant components of these , valves. He stated that pitting and crevice corrosion cracking will be the main mechanisms as opposed to generalized surface corrosion. According to Dr. Pickering, there currently is no way to predict the level of corrosion at these sites. He stated that the only way to address these concerns is by testing, Dr. Pickering suggested that an accelerated aging test would h require several elements. These include the following: (a) the use of the highest temperature available, (b) the use of worst case, highly polluted water, and (c) the use of the actual valve that is to be employed in the AP600 plant. He indicated that this test may require up to six months and could possibly involve three to five valves. The force or flow required to open the valve would also have to be monitored. Because of the difficulty in equating accelerated aging conditions with actual plant operating conditions, for the type of localized corrosion that is expected in these valves, it does not appear that accelerated age testing is the best method to use for the AP600 check valves. The difference between the accelerated aging conditions and true operating conditions could also lead to possible skepticism with regard to the validity of test results. O
WESTINGHOUSE CLASS 3-' 25 1 (q 12. REFERENCES Q.)
- 1. NUREG/ CR-4302 Vol.1, " Aging and Service Wear of Check Valves Used in Engineering Safety-Feature Systems of Nuclear Power Plants", Dec.1985.
- 2. Casada, D. A., Oak Ridge National Laboratory, telephone conversation, Aug., 1992.
- 3. Review, A bi monthly publication of the Institute of Nuclear Power Operations, Jan./Feb.1992.
- 4. Casada, D. A. and Todd M. D., "A Review of Historical Check Valve Failure Data", Proceedings of the Second NRC/ASME Symposium on Pump and Valve Testing, Washington, DC, July 21-23,1992.
- 5. Michelson, C., Member of Advisory Committee on Reactor Safeguards, private meeting, Aug.,1992.
- 6. Guassardo, G. and-Kerch, S. P., AP600 Document #: PXS-GOA-002, Component Failure Modes, Effects and Criticality Analysis (FMECA) Westinghouse /Hagan Check Valve, June,1992. ,
- 7. Tullis, J. P., Rahmeyer, W. J., Baasiri, M. S., and Barfuss, S. L.,
" Evaluation of Nonintrusive Diagnostic Technologies for Check Valves (NIC-01)", Prepared by Utah State University Foundation for Nuclear Industry Check Valve Group and Electric Power Research Institute, Feb.1991.
- 8. Boyle, R., Anchor / Darling Valve Co., telephone conversation, Aug., 1992.
- 9. Knecht, B., Anchor / Darling Valve -Co., telephone conversation, Aug., 1992.
- 10. Lowthert, B., Pennsylvania Power & Light, telephone conversation, June, 1992.
I1. Fallgren, T., Northern States Power Co., telephone conversation, Aug., 1992. L)
WESTINGHOUSE CLASS 3 26
- 12. Fallgren, T., Northern States Power Co., telephone conversation g>
Sep., 1992. W
- 13. Dusek, L., Portland General Electric Co., telephone-conversation, Au g., 1992.
- 14. Jones, R., Entergy Operations, Inc., telephone conversation, Aug., 1992.
- 15. Bloyd, C., Omaha Public Power District, telephone conversation, Aug., 1992.
- 16. Noffke, K., Commonwealth Edison Co., telephone conversation, Aug., 1992.
I
- 17. Hunter, G., Baltimore Gas & Electric Co., telephone conversation, Aug., 1992. ,
- 18. Pany, B., Public Service Co. of New Hampshire, telephone conversation, Aug.,1992.
- 19. Koblwey. J., Wisconsin Electric Power Co., telephone con versation, Aug., 1992.
g
- 20. Carlson, M., Northern States Power Co., telephone conversation, Aug., 1992.
- 21. Conea, J., GPU Nuclear Corporation, telephone conversa: ion, A ug., 1992.
- 22. Tullis, J. P., Utah St. University, telephone conversation,- Aug.,
1992.
- 23. Alvarez, D., Kalsi Engineering, Inc., telephone conversation, Aug., 1992.
- 24. Pickering, H. W., Distinguished Professor, Department of Materials Science and Engineering, The Pennsylvania State University personal meeting, Aug.,1992.
O
.l WESTINGHOUSE CLASS 3 ,
1 th 4 AFPENDIX A NUCLEAR PLANT. RELIABILITY DATA SYSTEM (NPRDS) COMPONENT MASTER FAILURE REPORTS-1984-1990 . l Fall to Open- or Only Partially.Open Cases O . l O
WESTINGHOUSE CI. ASS 3 TABLE A1 Fall to OpOn or Only Partially Open Records g Unit NPRDS System Component ID Manf. COOPER 1 Reactor Core isolation Coolino-GE RCIC-CV-12CV R340 OCONEE1 Hioh Pressure injection BW 1 H P-24 0 V085 OCXJNEE1 High Pressure injection-BW 1 H P-24 6 VOSS BROWNS FERRY 1 Diesel Fuel Oil-GE DCV00012525 B485 HATCH 1 Diesel Startino Air-GE R43 F30418 V135 POINT BEACH 1 Reactor Coolant W 1-528 R340 DAVIS-BESSE 1 Combustible Gas Control-Dilution BW CV 191 V085 DAVIS BESSE 1 Combustible Gas Control Dilution-BW CV 117 V085 BROWNS FERRY 2 Low Pressure Core Spray-GE BMV0005442 H037 BROWNS FERRY 3 Essential Service Water GE BlV00023605 C684 CUNTON1 Low Pressure Core Spray-GE 1E21F033 A391 PERRY 1 Suppression Pool Support-GE 1M16F0020A G202 t NINE MILE POINT 1 Feedwater-GE 31-01 C684 OUAD CITIES 1 Reactor Core isolation Coolino-GE 1-1301 50 R340 QUAD CITIES 1 Combustible Gas Control - Dilution-GE 1-2599 23A D243 OUAD CITIES 1 Control Rod Drive-GE 1 -3 01 2 B R340 i OUAD CITIES 2 Combustible Gas Control - Dilution-GE 2 2599-238 D243 WNP-2 Reactor Bido. Closed Cooling Water-GE RCC-V 238 WO30 W N P-2 Reactor Core isolation Cooling-GE RCIC-V 111 R340 W N P-2 Reactor Core isolation Coolino-GE RCIC V 111 R340 WNP 2 Reactor Core isolation Coolino GE RCIC-V 112 R340 TURKEY POINT 3 Main Steam-W POV-3-2605 S075 TURKEY POINT 3 Nuclear Service Water W 3 50 311 P340 ZION 1 Nuclear Service Water-W 1SWOOO7 M358 GRANO GULF 1 Essential Service Water-GE 01P41F169A YO10 HATCH 1 Residual Heat Removal / Low Press inject-GE E11 F031D WO30 j CATAWBA 1 Auxiliary Feedwater-W CACK0191 K085 CATAWBA 1 Auxiliary Feedwater W CACK0192 K085 SEQUOYAH2 Auxiliary Feedwater W BAV00017186 WO30 SEQUOYAH2 Condensate W SDV00017139 YO10 OCONEE2 Comoonent Coolina Water-BW 2CC-11 C665 BRUNSWICK 1 Hioh Pressure Coolant injection-GE E41-F076 V080 BRUNSWICK 1 High Pressure Coolant inlection-GE E41-F077 V080 BRUNSWICK 1 Reactor Core isolation Coolino-GE E51-F063 V080 BRUNSWICK 1 Reactor Core isolation Coolino-GE E 51 - F064 V080 , BRUNSWlCK 1 Suppression Pool Suoport GE ' 1 -C AC-X-20 A G112 FARLEY 1 Main Feedwater System-W N1N21V504 A A391 FARLEY 1 Component Cooling Water-W Q1 P17V263 A K085 FARLEY 1 Component Coolina Water W Q1P17V2638 K085 FARLEY 2 Nuclear Service Water W O2P16V602 K085 FARLEY 2 Component Coolina Water-W O2P17V263B K085 FARLEY 2 Component Coolino Water-W O2P17V2638 K085 TROJAN 1 Main Steam W C V-2276 A585 PEACH BOTTOM 3 High Pressure Coolant injection-GE A O 2 3 - 018 R340 MONTICELLO 1 Residual Heat Removal / Low Press inject-GE CST-98 V135
WESTINGHOUSE CLASS 3 p TABLE A1 Fall to Open or Only Partially Open Records (cont.) J Unit NPRDS System Component ID Manf. l DAVIS-BESSE 1 Diesel Startino Air BW DA 24 C600 PALO VERDE 2 Diesel Startino Air-CE 2PDGAV066 D243 PALO VERDE 2 Diesol Startino Air-CE 2PDGAV066 D24? l PALO VERDE 2 Diesel Startino Air-CE 2PDGAV066 D243 CALLAWAY 1 Nuclear Service Water W EF.V 0076 V085 SURRY1 Diesel Startino Air W 1 EG1-40 B345 SURRY1 Diesel Startino Air W 1 5EG 1 4 2 B345 SURRY1 Diesel Startino Air W 1-EG142 8345 BRUNSWICK 2 High Pressure Coolant injection GE E41-V60 V080 ~ BRUNSWICK 2 Reactor Core isolation Coolino-GE E51-F040 A391 ' CRYSTAL RIVER UNIT 3 Component Coolina Water BW SWV 356 C665 i DUANE ARNOLD 1 Diesel Startino Air-GE V32-0047 V085 I CONNECTICUT YANKEE 1 Main Steam W MS NRV-38 R340 l BEAVER VALLEY 2 Diesel Startino Air-W 2EGA 131 V135 HATCH 2 Reactor Bido. Closed Coolino Water GE P42 F047A WO30 SAN ONOFRE 1 Component Coolino Water W CCWO24 C684 PAUSADES1 Containment Spray-CE CK ES3401 V135 PAUSADES 1 Containment Spray-CE CK-ES3404 V135 PAUSADES1 Containment Soray CE CK-ES3405 V135 FITZPATRICK 1 Essential Service Water-GE 46ESW-19A V085 p PAUSADES 1 Component Coo:ing Water-CE CK CC941 C665 V ZION 2 Condensate-W 2CD0043 C684 l UMERICK 1 High Pressure Coolant injection-GE 056 1 F 081 R340 l SURRY2 Chemical & Volume Control-W ' 2 -C H- 181 R340 ROBINSON 2 Condensate-W C-273 V135 ROBINSON 2 Main Feedwater System W ) FW-1 A A585 j COOPER 1 Main Steam-GE MS-CV-26CV G202 GRAND GULF 1 Main Steam-GE N1821 F078W A585 GRAND GULF 1 Main Steam-GE N1 B21 F037M A585 GRAND GULF 1 Main Steam GE l N1 B21 F037M A585
- GRAND GULF 1 Main Steam GE N1821 F078 A A585 GRAND GULF 1 Main Steam GE N 1821 F037F A585 GRAND GULF 1 Main Steam-GE N1 B21 F078B A585 l GRAND GULF 1 Main Steam-GE N1821 F037U A585
! GRAND GULF 1 Main Steam-GE N1821F037L A585 GRAND GULF 1 Main Steam-GE N1821 F037R A585 ! GRAND GULF 1 Main Steam-GE N1821 F037N A585 l GRAND GULF 1 Main Steam-GE N1821 F078K A585 GRAND GULF 1 Main Steam-GE N1 B21 F078C A585-l GRAND GULF 1 Main Steam GE N1821 F078D A585 GRAND GULF 1 Main Steam GE N1821F078R A585 GRAND GULF 1 Main Sisam GE N1821 F078U A585
WESTINGHOUSE CLASS 3 ACCEPTANCE DATE: 06/17/91 Utility...................... Nebraska P etic Power District Unlt......... ...............C00PER 1
. . . . . . . . . . . . . . . . . . . . . . . . . G ene ra l E l ec t r i c Application.........
L. sonent.................... VALVE Funct10n............ U t i l i t y conporwnt l d. . . . . . . . . R CI C CV- 12CV systee.............. Reactor Core Isolation Cooling GE Start Date...... 09/12/90 Utility Systam...... RCIC Start Time...... 12:00 out of Service Mours... 120 Data Start Date. 01/01/84 In-service Date..... 02/21/74 Discovery Date.. 09/12/90 Restoration Hours...... 120 Accepted Date... 07/09/91 out of Service Date.. End D a t e. . . . . . . . .C9/17/90 Erd Time........ 12:00 Safety Class....... 4 Report Date..... 10/29/90 Irput Date. . . . . . 10/29/90 Mode................ Stan @ y condition S ys t em S t a tus . . . . . . . . . . . . . . . 8 Sys t em i n T es t Severi ty Level...... ... .. ....J Immediate F2iture S eptom..............D Internal Env........ Abnormal Characteristic Externet Env........ Teaperature / Ntaldity (Not Cntrid) Falture Mode.................F0 Failed.to Open Aablant Tenperature *107 to +120F Failure Detection............F Au:llovisual Alarm Supptler............ Crane Co Cause category...............C Unknown Supplier 1d........ 838T Caus) Description........... 8F - Blocked / Obstructed Manufacturer........ Rockwell Int / Flow Control Div tystem E f f ect . . . . . . . . . . . . . . . 8 Degraded Sys t ae Operat i on Mfr Modet Id........ Plant Ef fect.................G Resulted in No Significant Ef fect Mf r Model No....... 8387T4 Cerrec t i ve Ac t i on. . . . . . . . . . . . AG - R epa i r Ccaponent/Part Mfr Serial No....... Doctsnent a t ion. . . . . . . . . . . . . . . . Z None o f the Above Mfr Standard........ LER R eport Ntsnber. . . . . . . . . . . . ^ Drawing No.......... TACV353x System Affected by Falture...CEA Reactor Core Isolation Cooling-GE
................................................................................. .......... ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, O l
Fulture Description Narrative..... Engineering Codes REACTOR CORE ISQLAfl0N COOLING ( RCIC ) VACUUM PtMP DISCHAtr.E TO TORUS CHECK VALVE , ( RCIC CV 12CV ) , WAS STUCE IN THE CLOSE POSITION . RCIC A. Type................ Check VACLAM PLMP WAS STARTED DURING PERFORMANCE OF RCIC SYSTEM SURVEILLANCE 8.operstor............ None PROCEDURE , BUT IT DID NOT CREATE VACUUM IN SAR0 METRIC CONDENSER , AND C. Function /Applicatico One Way Flow LOW VACUUN ALARM IN CONTROL ROOM WAS ACTIVATED . PLANT WAS AT POUERD.lody Material....... Carbon Steel l DM ING TWIS EVENT . RCtc SYSTEM WAS CAPA8tE OF E.8cef Manufacturing M Forged F. Nominal inlet Site ( 2 to 3.99 IN Cau*e of Falture Narrative..... G. Site (Intet)........ j-2.000 IN FERiORMikG ITS DESIGN FUNCil0N , SUT ASILITY OF REMOVING RCIC TUR81kE M. Design Pressure..... 600.000 PSIG GLAND STEAM WAS LOST-WHICH DECRADED SYSTEM OPERATION . THIS INCIDENT J. Design Tenperature.. 900.000 DECF DID NOT AFFECT PLANT OPERAfl0N . 'NVEST!GATION REVEALED THAT RCIC VACLAJM PtMP DISCNARGE TO TORUS CHECX VALVE WAS STICKING IN CLOSE % Time operating When Reactor is Critical... 1% P051Tl0N . VALVE WAS MECMAN!CALLY AGITATED AND IT PERFORMED % Time Operating When Reactor la Shutdown... 0% SAftSFACTORY FROM THAT TIME . WNY VALVE WAS STICKING WAS NOT KNOWN . Houra Out Cserective Action Narrative..... Testing Performed Frequency / Period of Service SUSPECT THAT CHECX VALVE PLUG MOY; MENT WAS SLOCIED / CGSTRUCTED . VfLVE * * " * * - - - - -- - - * - - ---- WAS RETURNED TO SERVICE AND PERFORMED SATISFACTORT . VALVE WILL 8E check Testing 1 / Amust 0.0 l REPLACED DURING h*XT C4JTAGE , ( MWR 90 3548 , 8 90-4455 , FF ) Functional Testing 1 / Month 0.0 Calibration Testing 0 / Not Done 0.0 0
ACCEPTANCEMSTNGHBUSE CLASS 3 +2 = Ut i t I t y. . . . . . . . . . . . . . . . . . . . . . Duke Power Caspeny unit.. .................'..~.. 0CONEE 1: WS% . . . . . . . . . . . . . . . . . . . . . . . .Babcoc k ' 8 W i l coa . Application.........; ( nt.................... VALVE fL4 y C onponent I d. . . . . . . . 1MP 240 F mc t i on. . . . . . . . . . . .
- System. .. . .. . . ... . .. Hi gh ' Pressure inject ion BW L
^
1 . Start Date...... 01/16/89 Utility System...... MPI' Starf T ime.. ... . 03:30 Out of service hours... 461 Data Start Date.'.07/01/74 In Service Date..... 07/16/73" Discovsry Date.. 01/16/89 Restoration Hours......'.461 Accepted Date... 06/01/90 0ut of* Service Date. 05/11/90: End Date.........C2/04/89 End Tise........ 08:00 Safety Class....... 3 Report Da.e..... 02/25/89 Input Date...... 03/04/89 Mode................ Operating
$rstem Statue...... .. ... . .. . .E Traln/ Channel in Service (OPC/S8c) - '
53vse l ty Level . . . . . . . . . . . . . . .J lopedi at e Internal Env........ Aablent' Temperature Over *180F--
~
- F a i lure Sympt om. . . . . . . . . . . . . .C
- Demand F aul t Borated teactor or Primary Cint Water-F ailure Mode. . . . . . . . . . . . . . . . 70 . F alled to Open External Env........ Radiation Field (Neutron / Games)
Failure Detection............A
- Operational Abnormality .
. Insulated Cause Cat egory. . . . . . . . . . . . . . .N = Wear Out Supplier............ Du Kane Pre-Cast Concrete Causs Desc r i pt i on. . . . . . . . . . . . AD Norma t / Abnormal Wear Supplier Id.........
AV Connection Defective / Loose Parts Manufacturer........ Veten valve Corp System E f f ect. . . . . . . . . . . . . . . .D
- Degraded Traln/ Channel Mfr Model Id........
Plant Ef fect... . . . . . .. . .. . ...G Resulted in No Significant E f f ect Mfr Model No....,... 95 384*13MS Corrective Action...., ......A!
- Modify / Substitute Mfr Serial No.......
Document at i on. . . . . . . . . . . .. . . . A . F ailure Repor*ed to Archi tec t/Eng ineer Mfr Standard........ LER Report NJ ter............ Drawing ko........., OM 246 10 SN12
-System Affected by Falture.. 3FD + High Pressure injaction BW e Description Narrative.....- Engineering Codes:
(n440 is A STOP / CHECK VALVE IN THE NIGN PRESSURE INJECTION SYST r l'! l$ IN A WARMING LINE FOR LOOP 'A2' FEEDWATER N022LES . THE VALVE WAS A. Type................ Check
$ TICKING IN IME CLOSED POSITION EVEN THOUCN THE STEM WAS MOVING TO THE B. Operator............ Manust OPEN POSITION . C. Function / Application One Way Flow :
D. Body Materiet....... Austenitic Stnis $tt*316 Cause of Failure Narrative..... E. Body Manufacturing M Forgec fxt VALVE $7RlWG AND STEM WERE uoRN . THE SPRING MAD SLIPPED CUT OF- F.Nominst Intet Site (. 1/2 to 1.99 IN PLACE CAUsla;G THE DISC TO BE MISALIGNED AND NOT ALLOWING SMOOTH IRAVEL G.Slae (Inlet)........ 1.000 lu FOR THE DISC , M. Design Pressure..... 30$0.000 PSIG-J. Design Tenperature.~. 650.000 DEGF Corr *ctive Action Warrative..... .
.itERE WERE NO VALVE SPRINGS AVAILABLE TO REPLACE THE WORN $PRING . 1 Time Operating When Reactor is Critical.. 100%
i ENGINEERING DECIDED TO CHANGE THE ORIENTATION OF THE VALVE WHICH WOAD 1 Time Operatin0'When Reactor is Shutdom .. 100% i ALLOW IT TO OPERATE WITHOUT A SPRING , THE VALVE WAS MOVED TO A-l t
-HORIZO%TAL PIECE OF PIPE AND INSTALLED IN ThE UPRIGHT POSITION ..THIS Hours Out--
J ~ AlicufD THE DISC TO CLOSE ST GRAVITT WHEN THE VALVE ACTS AS A CHECK Testing Performed Frequency / Period- of-Service
-VALVE . " " " " " * " " " - * " " " " " " " - -"*"*""
Check Testing 0 / Not Done 0.0 Functional Testing. 0 / Not Done . _0.0 l Cattbration Testing 0 / kot Done 0.0 l l: l-1 y
WESTINGHOUSE CLASS 3- Ad ACCEPTANCE DATE: 03/14/89 Ut i t i t y. . . . . . . . . . . . . . . . . . . . . .Duk e Power Ccepany Unit.........................OC0 NEE 1 NS$3...,..................... Babcock & Wilcox Application......... Co monent.................... VALVE F tav:t i on. . . . . . . . . . . . Utility Comonent Id........ 1NP 246 Systet.............. High Pressure Injection-BW Start Date...... 01/16/89 Utility System...... HPl St:rt Time...... 13:30 Out of Service Hours... 187 Data Start Date. 07/01/74 in service Date..... 07/16/73 Discovsry Date.. 01/16/89 R es t ora t i on hours. . . . . . 187 Accepted Date... 06/01/90 Out*of service Date. 05/11/90 ' ind Dete. . . . .. . . 01/24/89 End.fime........ 08:00 Safety Class....... 3 Ranet Date..... 02/25/89 Input Dete...... 03/06/89 Mode................ Operating Syst em St a tus.. . . . . . . . . . . . . . .E T ra ln/Chamet in Service (OPC/SSC) S:vtr i t y Levet . . . . . . . . . . . . . . . J t ernedi at e Internal Env........ AaClent leeperature Over +180F Failurs Symptom..............C Demand Fault Sorated Reactor or Primary Cint Water F e i t ure Moce. . . . . . . . . . . . . . . . . F0 f e l l ed to open External Env........ Radiation Fletd (Neutron / Casme). Failure Detection............A Operational Abnormality Insulated Cause Ca t egory. . . . . . . . . . . . . . .H
- Wear Out Surpt ier. . .. . . . . . . . . Utili ty Caus e D e s c r i pt i on. . . . . . . . . . . . AD N ormal / Abnorma l Wee r Susplier Id.........
AM
- Previous Repair / Installation $tatus Manufacturer........ Velan Velve Corp ,
- System E f f ect.. . . . . . .. . . . . . . .D Degraded Train / Channel M f r Mode l I d. . . . . . . . Plant E f f ect. .. . . . . . . . .. . . . . .G Resulted in No Signi ficant E f f ect M f r Model No. . . . . . . . 85 384 13MS Correct i ve Action. . . . ... ..... AH Rept see Part(s) Mfr Serial No....... Documentation.... .......... A Falture Reported to Architect / Engineer Mfr Standard........
~
G t ER R epor t Numer . . .. .... Drawing No.......... OM 246-10 System Affected oy Fatture...SFD High Pressure injection 8W Failure Description Narrative..... Engineering Codes 1HP 246 13 A STOP / CHECK VALW IN HIGH PRESSURE INJECTION SYSTEM . IT 15 IN A WARMING LINE FOR LOOP 'Al' FEEDWATER N0ZZLES . VALVE WAS .A. Type................ Check STICK!n.G lh THE CLOSED Postflou EVEN TMOUGH THE STEM WAS MOVING TO THE 5.Operstor............ Mamat OPEN POSITION . C. Function / Application .0ne Way Flow D . Body Materi al . . . . . . . Austenttic Stnts StL 316 Ccuss of Failure Narrative..... E. Body Manufacturing M Forged SEVERAL PROBLEMS WERE FOUND ON TH13 VALVE . THE INTERNALS . SPRING . F.Ncminal inlet Sl2e ( 1/2 to 1.99 IN DISC , STEM AND BACKSEAT SHOWED $1GNS OF WEAR . TNE RETAINING RING AND G. Site (Inlet)........ 1.000 IN CASTLE PUT HAD BEEN INSTALLED INCORRECTLY DURING MAINTENANCE AT SO4E H. Design Pressure..... . 3050.000 PSIG PREVIOUS TIME , J. Design Temperature.. 650.000 CEGF Ctrrective Action Narrative..... % Time Operating When Reactor is Critical.. 100% THE VALVE SEAT WAS LAPPED , A NEW YOKE BUSHING WAS INSTALLED AAD A NEW % Time operating When Reactor is shutdow1..100% BACKSEAT WAS INSTALLED . THE VALVE WAS REASSEMBLED WITH0JT A SPRlWG . ENGINEERING DECIDED TO CHANGE THE ORIENTATION OF THE VALVE SO THE DISC Hours Out WOULD USE GRAvlTY TO CLOSE INSTEAD OF A SPRING . THE VALVE WAS MOUNTED Testing Performed Frequency / Period of Service UFRIGHT IN A HORIZONTAL RUN OF PIPE . " " " " " " " - " * " " " " ' " - """"" Check festing 0 / Not Done 0.0 F eetional Testing 0 / Not Done 0.0 Cattbration Testing 0 / Not Done 0.0
A ' WESTINGHOUSE CLASS 3 uct0rPlantAtliabilityOsts$ystem Genera l Report f** Ralph L. H mter, Jr. ~ Report *ld: WPRG00AA
) 4stinghouse Electric Corporation (x._/. Job Nu eer: 8231 Run Date: _06/26/92 Run fime: -15:22
Introduction:
The attached report was generated by your query of the hPRDS data base. A surmary of your query is ilsted below. QUERTt lected the following search condition (s) 5 elected Cosponent is VALVE Selected VALVE Type is Check-Selected Unit ID is SROWNS FERRY 1 Selected System is Oleset Fuet Olt GE Find Utility Cenponent ids that are equal to DCV00012525 Selected Manuf acturer is Bruce GM Diesel Inc ,
-Th:re were 1 records meeting the search condition (s).
DISPLAY AND SORT: g I
/, 4 \j3lected to rm general report 5:
Ccaponent Master Failure Report (w/ Unit Information) You chose to sort the report by: Sort Sequence Field Name NPRG05AA Nuclear Plant Reliability Data System Failure Master Report Rm Date $6/26/92 Job kalber 8231 ACCEPTANCE Daft: 01/30/91 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . f ermessee Val l ey Authori ty Unit........................ 8ROWNS FERRY 1 N5$$......................... General Electric Application......... Conponent.................... VALVE Function............ Ut i l i ty Cenporwnt Id. . . . . . . . .DCV00012525 System.............. Dieset Fuet Oil GE Start DIte...... 09/11/89 Utility System..... 018 Stret time...... 12:00 Out of Service Hours... 761 Data Start Date. 01/01/84 In service Date..... 08, .1/74 Discovery Date..10/11/89 Restoration Hours...... 53 Accepted Date... 04/06/85 Out of service Date.. E* % te........ 10/13/89 t me........ 05:20 Safety Class........ $R -R. .<t Date......11/08/90 Input Date....... 11/26/90 Mode.............. . Standby Condition System Status................F - Train /Channet in Test Sev2rity Level....... .. ....K - Degraded Internal Env........
WESTINGHOUSE. CLASS 3 A-5 F a l t ure s yopt cm. . . . . . . . . . . . . . C . Demand Frut t E x ternal E nv. . . . . . . . Anci ent T enper:ture .10F t s *120F . F a i l urs Modt . . . . . . . . . . . . . . . . . F 0
- F a i l ed t o Open Tenperature / Mumidity (not Cntrtd),
failure Detection............C . Survelttance Testing suppl ier. . . . .. . . . . . . gruce GM Diesel Inc Caus) Category...............K . Unknown Suppl i e r I d. . . . . . . . 0 CKY. 018 0583A r + Description........... 8E . Dirty Manufacturer........ Bruce CM Dieset inc .
$, . .es E f f ec t. . . . . . . . . . . . . . . .C . Loss of one or More T ra in/Channe t f unc t ioM f r Model 1d. . . . . . . .
Plant E f f ect. ... . .. . . . . . . . . . .G
- Resulted in No $lgnif icant E f f ect Mfr Model No........ 8228789 C:rrec t i ve Ac t i on. . . . . . . . . . . . AG - R epa i r Cwponent/Pa r t Mf r Serial No. .. ... .
Docuwnt at i on. . . . . . . . . . . . . . . .Z . None of the Above Mfr Standard........ LER Report Nurcer............ Draw i ng No. . . . . . . . . 4 7VS40 1 System Af fected by f ailure...EEAFOA . Diesel fuel Olt.GE Falture Description Narrative..... Ergneering Codes WITN THE UNIT IN EXTENDED MAlNTENANCE OUTAGE , DURING A SURVEILLANCE iEST ON !NE DIESEL FUEL DIL'$YSTEM BY OPERAfl0N$ , THE 8A' DIE $EL A. Type................ Check NUMBER 2 FUEL TRANFER PUNP FAILED 10 INCREASE THE DAY TANK LEVEL Of THE 8. Operator............ kone REQUIRED 25 GALLONS . THE TRAIN WAS LOST BUT ONE OF THE TWO PUMPS ON C.Fmction/ Application One*Way flow THE DIESEL 15 CAPA8LE OF DOING THE J06 THERE8 ORE RESULTING IN No PLANT D. Body Materiet....... Cartaon Steel EFFICT , E.tody Manufacturing M Cast F.Norainal Inlet Site ( 1/2 to 1.99 IN Caus3 of Falture Narrative..... G. tite (Inlet)........ 1.000 IN THE CHECK VALVE WAS STICKING CLOSED DUE TO MECMANICAL SINDING DUE TO N. Design Pressure..... 100.000 PSIG DIRT CAUSING THE PUMP W (SE ITS PRIME . THE PLANT WA$ NOT AFFECTEDJ.STDesign Teeperature.. 150.000 DECF THIS CONDITION . 4
% Time operating When Reactor is Critical... It .,
- Corrective Action Narrative..... % Time Operating When Reactor is Shutdaun... 11 REMOVED VALVE FROM LINE , CLEANED AND TESTED AND REINSTALLED . LOOSEN THE PLUG ON DISCHARGE SIDE OF PUMP TO VENT FOR PRIMikG . PRIME THE PUMP N rs Out AND TIGHTENED THE PLUG PER PLANT lh5TRUCTIONS . 0 CKV 018 0583A Testing Performed frequency / Period of service MR 89395$ * ................. ................ .......... Check Testing 1 / Month 0.0 F m etl W L Testing 1 / Month 0.0 Ca'ibration Testing 0 / kot Done 0.0 0
. 'A-6 WESTINGHOUSE CLASS 3 uctose Plcat 'Rolicbility Date System -
General Report t f**1 Ralph L. Meter, Jr. Report Id NPRG00AA
.I estinghouse Electric Corporetton Job Nunt>er: 8238 Run Date: 06/?6/92 Rm flme 15:31 Intreduetion The attached report was generrted by your query of the NPRD$ Cata base.
A cu mary of your cpery is listed below. QUERT You selected the following search condition (s): Selected Conponent is VALVE . Selected VALVE fype is Check Selected Unit ID is NATCH l' Selected System is Diesel Storting Air C.E Find utility component ids that are equal to 843 F30418 Selectad Manuf acturer is Vogt , Henry Machine Co ., Thcre were 1 records meeting the search condition (s). DitPLAT AND SORT: Jetected to run general report 5: Corponent Master Falture Report (w/ Unit Inform 6 tion) You chose to sort the report by: Sort Sequence field Name NPRG05AA Nuclear Plant Rell&bility Date System
- Failure Master Report Rm Date: 06/26/92 Job Hu4er 8238 ACCEPTANCE DATE: 04/19/89 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Georgi a Power terrpeny Uhlt.........................NATCN 1 Ess$. . . . . . . . . . . . . . . . . . . . . . . . .Cenera l E l ec t ri c Aspli cat i on. . . . . . . . .
Component.................... VALVE function............ Ut i l i ty Congonent I d. . . . . . . . . R 43 F30418 System.............. Olesel startir3 Alr-CE start cate...... 12/27/85 Utility system...... A43 start fine...... 12:00 out of service Mours... 3000 Osta start Date. 01/01/80 In-service Date..... 12/31/75 Discovery Date.. 02/14/86 Restoration hours...... 1836 Accepted Date... 04/19/89 Out of service Date. 05/01/86 -
^ 0 ate........ 05/01/86 ime........ 12:00 Safety Class..... . SR Report Date..... 09/25/86 incut cate.. ...10/03/86 Operating
~
Mode................ System Status..... . ... .. .F Train / Channel in fest
$averi ty Level . . . . . . . . . . . . .J Irmedi at e I nt e rna l E nv . . . . . . . . A i r
l WESTINGHOUSE-CLASS 3 Felluro Sympt om. . . . . . . . . . . . . .E R e t e:s ed L e:k ag) Amo(ent Teepersture *10F v3 +120F Failure Mode..... .......... 70 Failed to open External Env. ..... .. Tenperature / Mumidity (Cntrld) Falture Detection............C + Survelttance Testing Ancient Treperature 10F to +1207-Cause Category...............M Wear Out Surpt ier. .. ... .. . . . . Fairbanks Morse Engirt Div / Co C- Descr ipt i on. . . . . . . . . . . . AD Norma t /Atanorma t Wear Supplier 1d......... Sys tem E f f ec t . . . . . . . . . . . . . . . .D Degraded T ra in/Channe l Manuf acturer... . . .. . Vogt , Henry Machine Co Plant Effect.................G Resulted in No Significant Effect Mfr Modet Id........ Corrective Action............AE Modify / Substitute Mfr Model No........ SVS 701 800 A105 Documentation................Z
- None of the Above Mfr Serit'. No.......
LER Report Nurrber............ Mfr Standard........ Systein Af fected t>y Falture...EEADAA - Dieset Starting Air GE Drawing Nc........., 4611631. REY 0 Failure Description Narrative..... DURING UNIT REFUELING , WNILE PERFORMING FUNCTIONAL TESTING FOLLOWING Engineering Codes PREVENTIVE MAlWTENANCE , THE 1*B EMERGENCY DIESEL CENERATOR Alt COMPRESSOR WOULD NOT PUMP THE AIR RECE!VER TO THE PROPER PRESSURE ANO A. Type................ Check TTE PRESSURE RELIEF VALVE WAS L1FilWG 700 SOON . THE Alt COMPRESSOR WAS 8.0perator............ None DOWN FOR REPA!R$ . REF , NWO 1 84 1399 , 3689 , 4010 , 4015 . C.f metion/ Application one Wey. Flow D. Body Material....... Carbon Steet
.Caus) of Falture Narrative..... E. Body Manuf acturing M Cast THE FAILURE WAS ATTRIBUTED TO NORMAL WEAR OF THE AIR CCMPRESSOR F. Nominal Intet Site ( 1/2 to 1.99 Ik DISCHARGE CHECK VALVE . THE VALVE INTERNALS WERE O N , CAUSING IT TO G. Site (Intet)........ 0.750 IN STICK IN THE CLOSED P031T10N , CAUSING THE PRES $URE RELIEF VALVE TO N. Design Pressure..... 2500.000 PSIG VENT TO THE ATMOSPNERE . J. Design Teeperature.. 400.000 DEGF Carrective Action Narrative..... % Time Operating Wnen Reactor is Critical.. 100%
A DEslGN CHANGE WAS IMPLEMENTED TO JNSTALL A DIRECTLY INTERCHANCEASLE % Tlee Operating when Reactor is shutdown.. 100% VALVE BECAUSE MANUFACTURER OF THE ORIGINAL VALVES WAS DISCONTINUED . THOUGH UNNECESSARY , THE Alt COMPRESSOR AND TNT RELIEF VALVE WERE ALSO Nours Out REP' ACED AS A PREWNTIVE MEASURE . THE SYSTEM WAS FUNCTIONALLY TESTED Testing Performed Frequency / Period of Service A 10VEN OPERA 8LE . """"""""- " " " " " " " " * " " " Check Testing 1 / Month 2.0 Fmetional Testing 1 / Month 2.0 Calibration Testing 0 / Not Done 0.0 O I i i i
._ _ e m- . _ _ - -
'A-B c -i WESTINGHOUSE CLASS 3 uclear Plant tilissf Hty Osta system .
L Ge wrat Report - s I -- , e i f Ralph'L. Nunter,-JrP R epor t *1ds' 'hPRGDCAA' it f estirVvusse Electric Corporstlen - - Job moeer: 82481 e bd kun Date: 06/26/92 t" *
.Run Tleet- 15:39-
-Introdued on - !
5 The' attached report was evneratec by your query of the urtOS data base. A suunsey of your query is ilsted t* low. GutRT You 83tected'the following search condition (s):
. Selected Component is VALVE l
-Selected VALVE Type is Check Selected Unit 10 is PolWT SEACH 1 Selected System is Reactor Coolant W
. Find Utility Camponent ids that are equal to 1 528
- Selected Manuf acturer is Rockwell Int / Flow Control Olv ..
There were 2 records emeting the search condition (s). LD! SPLAY AND sott []
.( v etected to run generet report 5:
Conponent mester Falture Report (w/ Unit Inforestion) You chose to sort the report by: - s s
-sort -
Sequence Fletd Name -
........ .......... r NPAGOSAA mucteer Plant tellebility Data system a Falture Master Report- Am Dete 06/26/92
' Job husber 8248 -
ACCEPTANCE DATE: 04/28/87
- Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .Wi scons i n E l ec t r i c Power Company Unit.........................P0lWT BEACH 1 .
W$$$.=........................ Westinghouse Application.........-
;Cosponent.. ................. VALVE Fur-f t l on. . . . . . . . . . . .
Tuttlity Component Id.'....... 1:528 System.............. Reactor Coolant V
' Start 0 te...... 04/09/85- Utllity Systes...... RCS'-
, start Time...... 08:00 - out of service Hours... 336 Dets start Dete. 07/03/74 In service Dete...~.. 12/21/70 Discovery Date.. 04/09/85-- Restoration Hours...... 33e Accepted Date... 12/09/85 Out of servlee Dete.. ' ?*" 9 te........ 04/23/85 l( me........ 08:00- Safety Ctess........ SR a b et Date..... 07/24/85 Input Date...... 04/22/87 Mode.........'....... Operating . System Status. .. .. . .... .. .. . .F f rein / Channel in Test
. $Tver i ty L eve l . . . . . .. . . . . . . . .J
- Ieredi at e : Internet Env........ Nitrogen
WESTINGHOUSE CLASS-3
! a l t ur e S ynot om. . . . . . . . . . . . . . C Omand F aul t E s t:ena t Env. . . . . . . . Ambi ent T eger a ture 10f ta *120F FCiture Mode.................F0 Failed t3 Open Air F:l ture Detect ion. . . . . . .. .. . .C Survelli ance Tes t ing Supplier............ Westinghouse Elec Corp / Nagan cause Category.. . . . . . . . . . . . . . A = E ng ineer ing/ Des i gn $upptler Id.........
C- Descr ipt ion. . . . . . . . . . . .BG
- Corros ion Manufacturer........ Rockwett Int / Flow Control Div 88 Mechanical Damage / Sinding Mfr Modet Id....... 3674 Sys t em E f f ect. . . . . . . . . . . . . . . .D + Degraded T ra in/Channe t Mfr Model No....... 3674F316J
.* lant E f f ect. .. ... . . ... . . . . ..G
- Resulted in No Signi f icant E f f ec t Mf r Serist No.. ... . .
. Corrective Act ion. ........... AG
- Repair Component /Part Mfr $tandard........
Documentation............... 2
- None of the Above Drawing No. . . ... . .. . ROCKED C 464528 LER R epor t NJeer. . . . . . .. . . . .
System Af f ected tnr Falture...C$N Reactor Coolant *W Engineering Codes Falture Description Narrative..... DURING CONTAINMENT ISQLATION VALW TESTIEC , PRESSURIZER RELIEF TANK A. Type................ Check NITROGEN $UPPLY CNECK VALVE WAS DISCOVERED STUCK IN A CLOSED POSITION . B.0peret:r............ None ATTEMPTS TO UNSEAT tNE PLtRI WITN AIR PRESSURE WERE UNSUCCES$FUL . C. Function / Application Shutoff / Isolation /Stop D.sody Material....... Austenttic stnts stL 316 Cause of Falture Narrative..... E.Sody Manufacturing M Forged TNE VALVE PLUG WAS FOUND TO BE CoeROCED IN PLACE . THE VALVE IS CARBON F.Neminal Intet Site ( 1/2 to 1.99 IN
$ FEEL WHILE THE CONNECTING PIPING 15 STAINLESS $7 EEL.. THE G.Stae (Intet)........ 0.750 IN Dit$1MILARITT IV METALS IS THOUGHT TO NAVE ENHANCED THE CORRo$10N . N. Design Pressure..... -150.000 PSIG J. Design Teaperature.. 200.000 DECF Corrective Action Narratl w.....
THE CORRCCED PLUG WAS FREED . THE PLUG AND THE CYLINDER WERE POLISHED . 1 Time Operating nAen Reactor is criticat..100% COATED UITH NEOLU8E AND REASSEM8 LED . THE VALVE WAS TESTED AND RETURNED 1 Time Operating When Reactor la Shutdown.. 1001 TO SERVICE , Noura Out Testing Performed Frequency /Perlod of Service Check Testing 0 / Not Done 0.0
. Functional Testing 1 / Annual 8.0 Calibration Testing 0 / Not Done 0.0 l
t i O l
. _ - - _ _ _. . _ ~. . _ .
i1
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-A-102 -
d - , .
-WESTINGHOUSE'CIASS13- o iuctqar Plant Reliability D3ta System J -
Ceneral Reportz *
. fir talph'L. Hunter.'Jr.-
^
Report ids NPRG00AA- - i
-' ' iWestinghouse Electric Corporation . - Job Nueert 8266 i Run Date:--- 06/26/92- '
Run 1imet- 15:56'
- Introductions-
.nj The attached report was, ponerated by your SJery of the NPRDS dett base. !
A'suunnery of your SJery le ilsted below.
- SWRT:
s si
-Tou selected the following search condition (s): . I
-[
Selected Component is VALVE - , s Selected VALVE Type is Check Setested Unit ID is DAVIS SESSE 1
' Selected System is Combustible Gas Control Ditution 8W Selected Manufacturer is Velen Velve Corp
-t find Utility Component ids that are equal'to any one of the '
following: CV 117 and CV 191 ' ' There were 2 records meeting the search condition (s). LAT AND SDRT: e estected to run general report 5: M
, Component Master Failure Report (w/ Unit'inforestion)
.You chose to sort the report by:
-Sort Sequence Fletd nune 5
........ .......... .t WPRG05AA Nuclear Plant Reliability Date System Failure Master Report nun Detet 06/26/92-Job Numbert 8266
!4 ACCEPTANCE DATE: 05/11/89 l Ut i L l t y. . . . . . . . . . . . . . . . . . . . . . Cent er i or Ene rgy Corpor e t i on " _l-Unit......................... DAVIS BESSE 1
,N$$$........................ 8abcock & WItcon ~ Appticetlon.........
l ~ Component.. ................. VALVE Function............- } Utility component Id.........CV 191- System.............. Coneustible ces Controt Dilution 8W 4 K : St:rt Date...... 05/04/86 Utility System...... CHDL l.' ( Sttrt Time.'..... 12:00- Out.of service Mours... 16491 Data stort Date. 01/01/84L .In service Date..... 11/21/77'
. . Discovery Date..11/20/86 ' R es t ora t ion Mours. . . . . . 11703 - -Accepted Date... 05/04/89 (AJt of Service Dete. 03/21/88 :'
' INete. . . . . . . . 03/21/88 :
Time........ 15:00 safety Class........ St aeport Date..... 05/04/89 Input Date.... ...C5/04/89 Mode................ Standby condition
.L 5ystens 5tatus. .. . .. ... . . . .. . .F Train / Channel in f est t
11 e i .v. . _.J
WESTINGHOUSE CLASS 3 Sever i t y LGv3 4. . . . . . . . . . . . . . .J . Imed i c t e ' Interrcl Env. . . .. . .. Art >ient Tenperaturo +120F to *180F F a i lur3 Syept om. . . . . . . . . . . . . .C Demand F aul t Air
;Falture Mode.................F0 - Failed to Open Eaternal Env. .. .. . .. Ancient Tecperature .10F to +120F Failure Detection............C Surveillance festing Radiation Field (Alpha / Seta / a Cr - Ca t egory. . . . . . . . . . . . . . . A - (ngineer i ng/ Des i gn Suppl ier. . . . . . . . . . . . Babcock & Wilcon Co Ca w Description........... 8G - Corrosion supplier Id......... P1 1184 W22 223.!!-
AA Foreipn/Wecng Part Manufacturer........ Velen Valve Corp Sys t em E f f ec t . . . . . . . . . . . . < . . . A L os s of One or More sys t em Func t i ons Mfr Modet Id........ Plant Effect.................G Resulted in No Significant Effect M f r Mode l No. . . . . . . . WOS 20348 02T S Cirrective Action............AE Modify /$ 4stitute Mfr Serial No....... Docupent a t i on. . . . . . . . . . . . . . . . F F a l t ure Ana l ys i s Pe r f ormed Mfr standard........ L E R R epor t Nmt>e r . . . . . . . . . . . . Drawing No.......... M 213A 39.$ System Af fected by Falture...$ECDil Coribustible Cas Control Dilution BW Falture Description Warrative..... Engineering Codes ON NOVEMBER 20 , 1986 TME PLANT WAS IN A PROLONGED FORCED OUTAGE . DURING A $U.tVEILLANCE TEST , THE 82 MYDR0 GEN DILUTION $YSTEM BLOWER A. Type................ Check INLET CMECX VALVE CV 191 FAILED TO OPEN . TME CORRESPONDING VALVE ON B. Operator............ None TME 81 TRAIN WAS FOUND STUCK $ NUT ALSO , TMUS RENDERING TME EWilRE C.Fmction/ Application One way Flou , NYDROCEN DILUTION $Y$ TEM INOPERABLE . D. Body Materlat....... Carbon Steet E.tody Manuf acturing M Forged cause ef Falture Warrative..... F Nesinal Intet $lte ( 2 to 3.99 IN THE CAUSE OF TWE FAILURE WAS DETERMINED TO BE CORPOS10N , TME VALVE C.$lte (Inlet)........ 2.000 IN INTERNALS WERE CONSTANTLY EXPOSED TO MolSTURE ANP THE VALVE MAD LITTLE M. Design Pressure..... 18.000 PSIG 04 NO FLOW GolWG THROUGH IT FOR LONG PEtt00$ OF 'llME . CORRO$10N J. Design Teaperature.. 150.000 DECF PRODUCTS SUILT UP AND TME VALVE CORRODED $MUT .
% Time Operating When Reactor is Criticat... 01 C rre tive Action Narrative..... 1 Time Operating When Reactor is Shutdown... 01 THE V*LVE WAS MECNANICALLY AGITATED TO FREE IT$ INTERI L$ . AN ENGINEERING ANALT$l$ WAS PERFORMED TO DETERMINE IF TME VALV2 WAS TRULY Mours out NT ART OR IF IT COULD BE ELIMINATED WITN Wo ADVERSE EFFECT (W TME Testing Performed frequency / Period of Service $Yb.cM OPERATION . THE ANALT$l$ DETERMlWED THAT TME VALVE CoutD BE """""""" " " " " " " * ~~"""
ELIMINATED , AND ITS INTERNALS WERE REMOVED ON MARCH 21 , 1988 . Check Testing 0 / Not Done - 0.0 Fmettonal Testing i / Quarter 0.0 Calibration Testing 0./ Not Done 0.0
................................................ o ..................................................................................
ACCEPTANCE DATE: 05/11/89 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . Cent er i or Energy Corpora t i on Unit......................... DAVIS BESSE 1 NS$$ . . . . . . . . . . . . . . . . . . . . . . . . .Babcoc k & Wi l c om Application......... . Conconent . . . . . . . . . . . . . . . . . . . . VALVE Fmetion............ ' Ut t t i t y Conconent Id. . . . . . . . .CV 117 Sys t em. . . . . . . . . . . . . . ContaJa t i bl e Gas Cont ro L D i l ut i on- BW St:rt Date...... 06/25/86 Utility System...... CMD
$t:rt Time...... 12:00 Dat of $ervice Mours... 15243 Data Start Date. 01/01/84 In-service Date.....11/21/77 Discovery Date..11/20/86 Restoration Mours......11703 Accepted Date... 05/04/89 Chat of $ervice Date. 03/21/88 End 0:te........ 03/21/85 End Time........ 15:00 Safety Class........ $2 Report Date..... 05/04/89 Irput Date... .. . 05/04/89 Mode................ $tatutyy condition System Status................F - Train /Channet in Test Sever i ty L evel . . . . . . . . . . . . . . . J Istnedi ate internal Env........ Antalent Temperature +120F to M80F Fal turo Synytom. . . . . . . . . . . . . .C - Demand Faul t Air Failuro Mode.................F0 Failed to Open External Env........ Anelent Tenperature 10F to +120F Fci t ure Detect ion. . . . . . . . . . . .C Surveillance T es t ing Radiation Field (Alpha / Beta / Carivna Caus2 Ca t egory. . . . . . . . . . . . . . A Engineering / Des ign Supplier............ Bechtet Group inc Caru Descr ipt ion. . . . . . . . 8G - Corrosion Supplier Id......... P1 1184-N22 223 !!
AA - Foreign / Wrong Part Manufacturer........ Veten valve Corp - S ys t em E f f ec t . . . . . . . . . . . . ..A Loss of one or More system f metions Mfr Model Id........ Plcnt Effect..... . . . . . . . . . .G
- Resul t ed in No $lgni f icant E f f ect Mfr Model No........ WO8 20348 02TS Cecrcetive Action............AE Modify /$ubstitute Mfr Serial No.......
2 WESTINGHOUSE CLASS 3 Document at ion. . . . . . . . . . . . . . . . F
- F a i l ur e Ana l ys i s Perf ormd Mfr Standard........
LE R Rtpor t wueer . . . . . . . . . . . . Drawing No.......... M 213A 39*$ system Af f ected by f ailure...$ECDit Contaustible ces Control Dilution 8W re Description Narrative..... Engineering Codes
.cVEMBER 20 , 1986 THE PLANI WAS IN AN EXTENDED FORCED CUTAGE .
DURl2G A SURWILLANCE TEST , TN! #1 MYDROCEN DILU110N $Y$ TEM BLOWER A.lype................ Check INLET CMECK VALVE CV*117 FAILED 10 OPEN . THE CORRESPONDING VALVE ON 3. Operator............ None INE #2 TRAIN WAS ALSO FOUND STUCK SMU1, THUS RENDERING THE ENTIRE C. Function / Application one Way flow NYDROCEN DlLUTION SY$ FEM INOP(RABLE . D.Sody Meterlet....... Carbon Steel E. Body Manufacturing M Forgad C;use of Falture Narrative..... F. Nominal Inlet Site ( 2 to 3.99 IN TNI CAUSE OF THE FAILURE WAS DETERMINED TO BE CORROSION . THE VALVE C. site (Intet)........ 2.000 IN l' ATERNALS VERE CONSTANTLY EXPOSED 10 PCISTURE AND THE VALVE hAD LITTLE M. Design Pressure..... 18.000 Psic OR No FLOW 00 LNG ikt0UCH IT FOR LONG PERlu)$ OF TIME . CORRO$10N J. Design Teaperature.. 150.000 deb 7 PRODUCTS BUILT LP AND THE VALVE CORRODED SHUT . 1 Time Operating When Reactor is Critical... 01 Corrective Action Narrative..... % Time Operating When Reactor is shutdown... 0% TKE VALVE WAS MECMANlCALLT ACITATED TO FREE THE INTEREALS . AN E%Gl:EERING ANALY$ll WAS PERFORMED TO DETERMINE IF THE VALVE WAS TRULY Mours out WECE55 ART OR 17 IT Cout0 BE ELIMINATED WITH No ADVERSE EFFECT ON THE Testing Perforined frequency / Period of service
""*"""~~~ -""aan" - ~~"
SYSTEM OPERATION . THE ANALYSl$ DETERMINED THAT THE VALVE COULD BE ELIMINATED , AND 11$ INTERNALS WERE REMOVED ON MARCH 21 , 1988 . Check Testing 0 / Not Done 0.0 Fmetional Testing 1 / Quarter 0.0 Callbration Testing 0 / hot Done 0.0 , O
A-13 WESTINGHOUSE CLASS 3 uci te plant'R*Llabl(ity'D ta $ystem' Ceneral Report For t;Lph L. Hunter, Jr. Report Id hPRC00AA - rctinghouse (tectric Corporation Job Nunteer: 8280 Run Date: 06/26/92 km Time 16:10 Introdxt ion: The attached report was generated by your query of the NPEDS data base. A sumery of your query is listed below. QUERY: You s:tected the following search cordition(s): _ 5 elected Component is VALVE ' Selected VALVE fype is Check Selected Unit ID is EROWW$ FERRY 2 Selected System is Low Pressure Core Spray CE Selected Manufacturer is Nancock Mfg Co Inc Ther2 were 3 records setting the search condition (s). DI$ PLAY AND SORT: Yo. '.ected to run general report 5: Component Master Falture Report (w/ unit Information) You chose to sort the report by: Sort Sequence Field Name NPRG05AA Muclear Plant Rettability Data system Falture Master Report ton Date: 06/26/92 Job kueer: 8250 f ACCEPTANCE DATE: M/08/92 Utility...................... Tennessee Valtey Authority Unit.........................BROWus FERRY 2 W355.........................Ceneral Electric Amtication......... Cosponent.................... VALVE Function............ Ut i l i ty rogenent I d. . . . . . . . 2 CKV 075 0606 Systes.............. Low Pressure Core sprey GE Start Date...... 03/09/89 utility System..... 075
-Start Time...... 12:00 cup of servlee Hours... 2952 Data Start Dete. 03/01/75 in service Date..... 03/01/75 Discovery Date.. 06/09/89 Restoration Hours...... 756 Accepted Date... 04/07/92 Out of service Date..
End 0;te........ 07/10/69 Erv* 'Ime........ 12:00 Safety Class....... 3 Rs Dat e. . . . . 07/25/91 input Date...... 07/29/91 Mode................ Operating System Status.. . . . .. . . . . . . . . .F Train /Channet in Test sever i ty Level . . . . . . . . . . . . . . .K - Degr aded Internal Env........ F ai l ure 5 yuptom. . . . . . . . . . . . .C Demand Fault External Env........ Antaient Teeperature -107 to +1207 l i
n~se WESTINGHOUSE CIASS 3 Rtdiatico fleLd (Alfa 4 / Site / Campe f a ( L yre Moca. . . . . . . . . . . . . . . . 7 0 F e ll ed t o Open f ailure Det ection. . . . . . . . ...C = $urveillance festing . Supplier............ Supptler Id......... BMV000005442 Cause Category...............K
- Unknown t Description............St . Dirty Manuf acturer........ Hancock Mf D Co Inc f~
BG . Corrosion Mfr Model Id........ ( biem E f f ect . . . . . . . . . . . . . . . .C
- Loss of One or More T rain / Channel Mfr Seriet f unc t ioM f r Modet ko. . . . . . . 5580W Plant tffect.................G
- Resulted in No lignificant Effect No.......
Correct i ve Ac t ion. . . . . . . . . . . . AG
- Repai r Conponent/Part Mfr Stendard........
D rewing No. . . . . . . . . 2 4 7WS14 1 Docutent a t i on. . . . . . . . . . . . . . . .!
- None of the Above LI R R e Dor t W J@e r . . . . . . . . . . . .
System Af f ected by f alture...$FA
- Low Pressure Core Spray GE Engineering Codes fatture Description kerrative.....
A.fype................ Check WWEN THE UNIT WA1 IN A REFUELING OUTAGE , WHILE PERFORMlWG A 8.0perator............ None
$URyt!LLANCE TE$1 ON THE LOW PRES $URE CORE $ PRAY SY$itM , CHECK VALVE C.f urstion/ Applic ation one Way flow 75 606 , 00VN11RE AJe FROM THE PRES $URE SUPPRES$10N CHAMBER HEAD T ANK D.tody Me t et t el . . . . . . . Carbon $teet PUMP 2A , F AILED TO OPEN . THE PLAN 1 WAS NOT AFFECTED SY Tkts CONDill0N
- t. Body Manufacturing M forged
- f. Nominal Intet $lte ( 2 to 3.99 IN G.$lte (Intet)........ 2.000 IN Cawse of fatture herrative..... H. Design Pressure..... 500.000 PSIG THE FAILURE WA1 CAUSED BY A BUILD UP OF DIRT AhD CORR 0110N PRODUCTS ON J. Design Tefoperature.. 350.000 DEGF THE VALVE DISC AND GulDE WALLS DUE TO No# MAL USE AND SERV:CE CokD1110NS THE ROOT CAu$t WAS UkKhouN . THE CHECK VALVE WA$ CLOSED BLOCKING
% time Operating When Reactor is Critical... 11 PRIl$URE ColNG 10 CORE SPRAY t03P 1 DISCHARGE P! PING CAUSING THE LOOP
% Time Operating When Reactor is Shutdown... 11 10 FALL BELOW 11$ REQUIRED 48 P11C DISCHARGE PRES $URE , THEREFORE '
LollNG THE LOOP . Moura Out Testing Performed f re<pency/ Period of Service Corrective Action Narrative..... """""""" " " " " " " " * """"" REMOVID THE VALVI FRCH $ER\lCE . OlSA$$tMBLED , CLEAN!D AkD INSPECTED . Check festing 1 / Quarter 0.0 tit $TED Tht VALY1 AND PASSED ACCEPTABLE PER THE $URVEILLANCE functional Testing 1 / Quarter 0.0 JCTIONS . THEN RETURNED 10 SERVICE . 891009982 2 tKV 075 0606 J5M 0.0 Calibration Testing 0 / Not Done
WESTINGHOUSE CLASS 3 ucLC:r Plant Reliability DIts System Generat aeport f ort tal$ L. Meter, Jr. Report *1d: NPAG00AA .
'.estinphouse Electric Corporation Job Nueer: 9010 Run Date: 06/30/92 Run Times 10:12
Introductions
the attached report was generated by your query of the NPRDS data base. A suenery of your query is (isted below. QUEtY: You selected the following search condition (s): Selected Component is VALVE ' Selected VALVE Type is Check Seiected Unit ID is SA0WNS FERRY 3 Selected Systes is Essentist Service Water CE Selected Manufacturer is f a vetve Prod / Crane to Fr Chepnen There were 2 records meeting the search condition (s.. O!$ PLAY AND SORT: Y tiected to rm poneral report 5: Component Master Failure Report (w/ unit Information) You chose to sort the report by: Sort Sequence Field Name NPtG05AA Nuclear Plant Reliability Date System Failure Master Report im Date: 06/30/92 Job Number: 9010 ACCEPTANCE DATE: 08/20/91 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . .Tamessee Val ley Authuri ty uni t . . . . . . . . . . . . . . . . . . . . . . . . . BR0Wil FE RRY 3 NS$3......................... General Electric Application......... Component.................... VALVE F metion............ Uti!lty Ccaponent Id.........Blv00023605 System.............. Essentist Service Water-CE St rt Date...... 09/15/90 utility Systes..... 067 Start Time...... 12:00 OJt of service Hours... 1425 Data Start Date. 03/01/77 In Service Dete..... 03/01/77 Discovery Date..10/15/90 Restoration Hours...... 717 Accepted Date... 08/13/91 Out of Service Date.. End 0:t e . . . . . . . . 11/13/90 End Time........ 21:30 Safety Class........ SR f t Date..... 06/02/91 Irput Date...... 08/13/91 Mode..............., Operating System Status. . . .. .. . . . . .. .. .F - T rain /Chanret in Test Swer i ty Level . . . . . . . . . . . . . . .K Degraded Internet Env........ Failur3 Sywotom..............C - Demand Fault External Env........
)
- m
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iWESTINGHOUSE-CLASS 3 A-l'6? t 3 F l ure Mode . . . . . . . . . . . . . . . . . F0 . F e l l ed t o open : Si.sipt i er .'. . . . . . . . . . . __
-l
*e_ Detection.. 6.......C M Surveillence Testing ~
Supptler'Id........ 3 CKV*067 07611 _ _ _' Category...............K Unknoem Manufacturer.......'. Crane Velve Prod / Crane Co Fr Chapman'
'Cause Description........... 8E.. Dirty .
Mfr Model.Id.... ,.. f
; System E f f eet..' . .. .. .~ ..... ...E
- System f unct ion /Operat ion Unef f ect ad " Nfr Model No....... 1238-
- Plant E f f ect. .. . . . .. .. . . . . . .'.G . tesulted f ra No Signif icent E f f ec t Mfr Seriet No.......
Cor r$c t i ve Ac t i on. . . . . . . . . . . . AG . R epe l r Component /Por t Mfr Standard........ J0ccumentation..............i.2 . None of the Above. Drawing No......... 47W859
. LE R hipor t uweer . . . . . . . . . . .'. -
; System Affected by failure...WAA . Essential Service Water GE Engineering Codes failure Description Norrative.....
WHILE PERFORMING A SURVEILLANCE TEST ST ENGINEERING SUPPoti ON THE ' A. Type................ Check EMERGENCY (GUIPMENT COOLING WATER STSTEM ( EECW ) . THE NORTN MEADER B.0perator........=....- Mech (Diff Press Open/Sprn CxtCE VAlvt To 3A CONTROL BAT CN!LLER FAILED TO QPEN . THE VALVE WAS C.Fenetton/ Application One Way Flow STICKING IN THE CLOSED POSITION NOT ALLOWING FLOW . THE PLANT WAS NOT D.Sody Meteriet....... Austenitic Stnis $tt 316-AFFECTED ST TNil FAILutt . E.Sody Menufacturing M F. Nominal Intet Slae ( 4 to 11_.79 IN. _f ' Ceuse of failure Norrative..... G. Site (Intet)........- 6.000 IN-DitT AND CRUD COLLECTED INSIDE THE VALVE INTERNALS NOT ALLOWING IT TO N. Design Pressur's..... 150.000 981G 0 PEN . THE N!NGE PINS WERE ALSO SENT . THE SYSTEM WAS NOT AFFECTED DUE J. Design Tsoperature.,. 150.000 DEGF TO MAVING TWO REDUNDANT NEADERS ( NORTM AND SOUTN NEADERS } , TO THE . CONTROL BAT.CNILLit . THE Roof CAUSE WAS UNENOWN . -% Time operating When seector is Criticot.. 1001 L % Time Operating When Reactor is shutdo n . 1005
-Corrective Action Narrative.....
DISASSEM8 LED TNE VALVE . CLEANED THE DISC AND STRA!GNTENED THE PINS . - Nours out
.tEASSEMSLED TNE VALVE AND' RETESTED . THE VALVE WAS SUCCES$FULLT Testing PASSED Performed . Fre@ency/ Period 'of, Service l-
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L } { 'E SURVEILLANCE INSTRUCTIONS . 90 19104 00 3 CKY.067 0761Check JSM Testing ' O / Not Done 0.0 l; '\ l functional Testing: 0 / Not Done 0.0 Collbretton Testing' .0 / Not Done 0.01
.........................................................................................................'............. ~ . A. ~ ..
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aw E. 1 t _{ k lt i LO . 'I d
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WESTINGl!OUSE CLASS 3 A " uclear Plant Rollebility 0 ta System Gerwrel Report f ort Reige L. Nunter, Jr. toport*lds WPRC00A4 ' Westfr@ouse Electric Corpot' ellen Job Ww oort 9026 Rm Oste: 06/30/92 Rm fleet 10:18 IntrcrJurtion: The atte:hed report was genereted ty your geery of the NPRot date base. A swinery el your 4>ery is listed below. DARY: You s*Lected the following eserch condition (s): Selected Component is VALVE Selected VALVE fype is Check Selected Unit ID le CLINTON 1 Selected System is Low Presours Core Spray Of Selected konufacturer is Anchor / Detting Velve Co Fird Utltity Corpunent ids that are ocpet to it21f033 Th:ro wre 1 records oeoting the search condition (s). DiteLAY AND Sotfl Vuu s lected to run gerwrol report $3 ' O Component Master failure Report (u/ Unit informetten) You chose to sort the report ty: Sort legance field home kPAGOSAA muclear Plant Rollebility Date System
- Failure Master Report Run Datet 06/10/92 Job Wumber 9026 l ACCEPTANCE Daft 01/26/89 l
l l Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . l l l ire t e Power Cospeny Unit.........................CLINTON 1 l N S$$ . . . . . . . . . . . . . . . . . . . . . . . . . General E l ec t r ic Application......... [ Component . . . . . . . . . . . . . . . . . . . .VALit function............ l Utility Component Id........1E21F033 System.............. Low Pressure Core Sprey GE Stirt Date...... 08/26/88 Utility Systen...... LP / Stirt flee...... 05:20 out of service nours... 37 Date Start Date. 11/24/87 In Service Date..... 01/03/86
- Discovery Date.. 08/26/88 Restoration Hours...... 37 Accepted Date... 05/13/86 Cut of Service Date..
Erd h:t e. . . . . . . . 08/27/88 l i Ime........ 18:00 Saf ety Class....... 2 Report Date..... 11/28/88 f rout Da t e. . . . . . 12/08/65 Mode................ Operating Sys t ee S t a tus . . . . . . . . . . . . . . . . f T r a ln/Chenne t in T es t Secri ty level . . . .. . . . . . . . . . .J 1mediat e Internal Erw........
WESTINGl10USE CIASS 3 failure S potese..............C a Dewe M fcult f a t erne t i tw . . . . . . . . f e l t ur e Mose . . . . . . . . . . . . . . . . . f 0 . F e l l ed t o Open $wiler. . . . . . .. . . . . Anchor / Darling Velve to f ei ture Detec tion. . .. .. . . . ...C . Survei t t orice f est ire Supplier Id.........
- Ca t egory. . . . . . . . . . . . . . .K . UrAnown korisf ac t ur er . . . . . . . . Anc hor / Dec l i ng ve l ve to
< Description.... ... . .. . 68
- Mechanical Damage / Birding Mfr Modet 1d........
$ rs t em E f f ec t . . . . . . . . . . . . . . . 8 . Degr aded s ys t es Ope r a t i on Nfr Model Wo........ W7720253 Plant E f f ec t . . . . . . . . . . . . . . . . .G . R esul t ed in he ll eni f icant E f f ec t >fr Seriet ko....... 16214 254 4 Corecctive Action............AN . Replace Part(s) M f r $ t erderd. . . . . . . .
Dceteent at l an. . . . . . . . . . . . . . . .I . worn of the Above Drawing k0.......... Lt A t tpor t WJd4 r . . . . . . . . . . . . tysten Af f ected by f elture...lf A . Lou Pressure Core Sprey.Ct Engineering Codes felture Description herretive..... Vlill PLANT At FULL POJtt , DutikG Pitf 0RMANCE Of LOW P8ttsutt Cott A.fype................ Check
$ PRAY ( LPCl ) MMP WitA81Liff $URVtlLLANCE , THf LPCS WAf tt LIG PLMP 8. Operator............ Manuel DISCIARGE CMtCK VALVI ( 1t21f 033 ) FAILtp to piu As ActuAtat MANDLt t C.f unc tion /Amlicat ion one.Wey flow LtVtt ) 6AOKE Off . D.Scdy Meterial....... Carbon Steet E.Sody Manufacturing M Cast Cause of felture Norrative..... F.kominst intet $1:e ( 2 to 3.99 lu DISAsstMsLY of VALyt AtVtAttD TkAt THREADED tub of VAlvt skAf f WAS G. tite (Intet)........ 2.500 IN BBC:E2 Off . M. Design Pressure..... 720.000 P$10 J.Deelen f esperature.. 100.000 DECf Corrective Action korretiva.....
halkithANCE ttPLAttb VALVE SKAf f . PACKlWG AWD CAlttTS . VALVI $1t0Kt0 % time Operating When teactor le critical.. 1001 5All5f ACf 0RILY . ( C56067 ', 1 fine Operating When Gesctor is shutdane.. 1001 Hours out festing Perforesed frequency / Period of Service Check f esting 0 / mot Done 0.0 ftnctionet feettre ) / konth 0.0 Cellbration festing 0 / hot Done 0.0 l i i
- . _ . - - - _ . _ _ . . _ _ _ . _ _ _ _ _ _ . . _ _ _ _ . _ . _ _ _____..______._._________m__._ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
WESTINGHOUSE CLASS 3 ucteer Plant Reliability Dets System ! General teport IP* Salph L. Neter, Jr. Reportaldt hPRG00AA Westirehouse tiectric Corporation Job Wunters 9053 i tm Date: 06/10/92 k m iImes 10:39 j inteodle Ione the attached report we generated ty your cuery of the werDS date base. A ouunery of your omry le Llated tetow. 00ftf i fou s:tected the following search condition (s):
.1 Selected Congxrent le VALVE Selected VALVE type is Check 1
Selected Unit ID le Pitti 1 l Selected lyetes is suppreselon Pool $tsport GE find Utility Component ids that are e< pet to 1M16700204 ' selected Manufacturer is GPt Controle Ther0 wre 2 records seetire the search condition (e). D P*'Af AND $081: Tou a:Lected to run general report 5: Component Master f elture toport tw/ Unit Information) You chose to sort the report ty Sort some Fletd usse NPtGOSAA Nucteer Plent tellebility Date Eyetse . felture Kaster Report am Date: 06/30/92 Job Nomtier: 9053 ACCEPTANCE Daft: 10/09/89 Ut i li ty. . . . . . . . . . . . . . . . . . . . . . Cont er i or Energy Corpora t ion Unit......................... PERRY 1 W$$$.........................Generet Electric - Application......... Sum Pool / Torus VacuJe Breaker Velve Component . . . . . . . . . . . . . . . . . . . .V A L VE haw t l on. . . . . . . . . . . . Ut i l i t y Conponent I d. . . . . . . . 1M 16 F 0020A s ys t em. . . . . . . . . . . . . . Stopres s i on Poot $tspor t CE st:rt cate...... 07/15/89 Utility systee...... # 16 Start Tisie...... 12:00 lbt of* service Mours... 100 Date Start Date. 11/18/87 In-service Dete..... 06/01/56 Olscovery Date.. 07/19/89 Restoration Moves...... 16 Accepted Date... 08/04/89 Out of* service Oste.. .. -f is t e . . . . . . . . 07/19/89 - L ilme........ 16:00 Safety Ctess....... 2 Report Date..... 09/28/89 t rgut D a t e. . . . . . 09/29/89 Mede................ Operettrq tys t em S t atus. . . . . . . . . . . . . . . . F t ra in/Chame l i n T es t lever i ty l evel . . . . . . . . . . . . . . . J
- 1eredi a t e Internet Env........ Air
WESTINGHOUSE CIASS 3 A-20 f o y ur e $ ptsn. . . . . . . . . . . . . .C
- Demand f aul t Ashlent fespereture *10f to +1tof !
\ e Muse. . . . . . . . . . . . . . . . . f 0
- F a i l ed t o Open laternet inv........ temperature / Neidity (Not Cntridt
[h 4 De t ec t l en. . . . . . . . . . . .C
- Surve l l t erc e f es t i ng Anblent Temperature *10F to ottof Ceute Ca t egory. . . . . . . . . . . . . . .K
- Unknown $ w iler............ GPt Controle Cause Description........... 8C Out of mechanical Adjustment S e ller Id......... $P635
$yetse t f f ect................C Lose of One er more f rein /Chamel f uretismerwf ecturer........ CPI Controle Plant Ef fect.................G
- Resulted in se llenificant Ef fect Nfr Model Id........
Carrective Action............AA
- tecellbrate/ Adjust Mfr kodet No........ LD240 339 Docment a t t en. . . . . . . . . . . . . . . .I
- None of the Above Mfr Serial Wo....... 7604 0488*1 Lit t oport NJitier . . . . . . . . . . . . Nfr standerd........ AtMt lit j
)
System Af fected try f ailure...sAA . * $wreselon Poot sport *CE Orewing No.......... 912 606 I f ailure Dettelption Narrative..... ! Ulf M INE REACf 0R lW COLD $NUTDOWN PtfPARING TO RISTART , tnt DRfWELL (ngineerftg Codet j
' VACUUM tittf f VALVE felltD 10 OPEN DURING sutVglLLANCE f tsf!NG . (
A.Iype................- Check j Cause of f elture Narrettve..... I.0perater............ Pno mstle (Diaphropa er C l 1.NVtsflCAfl0N FCUND A LOD $t SET SCREW ON THE VALVt's FLAPPER PlV0f PlW C.fmetlan/Aplication Vacum belief '. WHICN PtfVtWit0 THE WIN F90M 30fAflNG WITN TWE FLAPPER . 0. Body meterlet....... - Carten Steel t.lody Manufacturing N forced i- C$rrective Action Narrative..... F.Neminet inlet $13e ( 4 to 11.99 IN fHE Stf StatW WAS flCNitNt0 AND INE VALVE OPERATED SAfilfACTORILY . G.llte (Inleth....... 10.000 IN i N.Deelen Pressure..... 15.000 Psl0 J.Deelen fesperature.. 145.000 OtGF - E flee operating When Beector le Critical... SE ,
. E flee operating When teactor le shutaoun... 11 ,
Noure out iesting Perfenmod fregency/ Period of Service.
................. ................ .......... y Check festing- 1 / Week 0.0 functionet festing i / Month 1.0 !
Cellbretten festing I / Three foer 2.0 4 n i; L s
=
l t t I-
== -
. s , _ , - - - . _ _ . . . . _ _ . _ , _ . . ... ~ , L. ..,-,.,__._m . _ , _ , - . . , , _.
,_-..i. -
WESTINGHOUSE CIASS 3 A-21 O ACCEPTAkCE Daft 02/17/87 pt Utility......................Niegare Mohawk Power Corporation Unit.........................NINE MILE PotNT 1 k5ts.........................Conerst Electric Amt l cat i on. . . . . . . . . Comonent . . . . . . . . . . . . . . . . . . . .YALVE F metton............
- Utility Cceponent Id........ 31*01 S ys t oa. . . . . . . . . . . . . . F eedwa t e r. Ct Start Date...... 05/10/86 Utility tretes..... 31
$ tert Time...... 05:00 Out of service Mours... 1015 Dets $ tert Date. 04/01/86 in*$ervice Date..... 04/01/86 Olstovery Date.. 06/21/86 Restoration Hours...... 12 Accepted Dete... 04/21/89 Out of.$ervice Dete. 07/11/86 ErrJ D:te........ 06/21/86 ind Time........ 12:00 Safety Class....... 1 Report Dete..... 08/21/86 input Cote...... 02/D9/87 Mode................ Operating System status.... . . . . .. ......!
- Trotn/ Chemet in Service (OPC/$8C)
$ ver i t y L eve l'. . . . . . . . . . . . . . . J,
- lenodl et e internal Env........ Reactor or Primary Cootent Water F a l l ure $ ppt css. . . . . . . . . . . . . .C
- Demord Faul t Amblent Tens,oreture Over *180F Fe e Mode . . . . . . . . . . . . . . . . . F0
- F a i l ed t o open laternal Env........ Astilent Terversture .10F to +12D Fei..re Detection............A . Operational Abnormality Air Ceuse Cat egory. . . . . . . . . . . . . . .C . Nanuf ac turing De f ec t $ w ptler............ Crane to Ccuse Description........... 88 . Mechanical Damage / Binding 5 @ptier 1d.........
System E f f ect................C Loss of one or More TrairVChannet functioMenuf acturer........ Crane Velve Prod / Crone to Fr Chapnen . Plant E f f ec t. . . . . . . . .. . . . . . . .$ . Resul t ed in Unit Of f *Line Mfr Model 1d........ Ctrr:ctive Action............AG . Repelr Comp ment / Port Mfr Model No....... 1523V Doctanent a t i on. . . . . . . . . . . . . . . 2 . None of the Ateve Mfr Serlet No....... Ltt Report Ntater............ Mfr Stenderd........ systra Affected by failure...CNA
- Feedwater.Ct Drawing No.......... C18005C $N. 2 Fellure Description Narrative..... .
WHILE PLANT WAS STARTlWG UP AFTER ttFUELING OUTAGE AT 161 POWER , Engineering Codes FtE9 WATER Ex1ERNAL ISOLAfl0s, CNECK VALVI 3101 ON LOOP 11 FAILED TO Opts UPON DEMAND . THE OPitATIONS $NIFT SUPttYlSOR OBSERVED A LACK OF A.Tpe........ ....... Check FLOW 1:RCUCN #11 LOOP ( Okt LOOP OF MIGN PittSUtt COOLANT INJECil0N B. Operator............ None
$11 TEM ) , PLANT POWER WAS REDUCED AND SU8SEQUENTLY THE UNIT WENT C.Fmetton/ Application One Way Flou 0FF LINE . 0.lody Meterlet. .. . . . . Carbon Steel E. Body Manufacturing M Cost Cause of Failure Narrative..... F. Nominal Intet $lte ( 12 to 19.99 IN THE ChtCK VALVE FAILED TO CPEN BECAU$C TNE VALVI Ol8C WAS LOOCED CLOSED G.$lte (Intet)........ 18.000 IN ONTO THE $ EAT . THE REASN FOR THE OCCuttENCE 18 UNKNOWN . BUT IT 15 N.Desten Pressure...... 1425.000 P$1C SPECULATED TRA1 A MANUFACTUtlWG DEFICT ASSOCIATED WITN VALVE $ TAT MAY J.Deslen Temperature.. $M.000 DECF NAvt BIEN Tht CAUSE . ,
1 Time Operating When teactor is Critical.. 1001 C: rec <tive Action Narrative..... 1 flee operatirg When keector le $hutdwn... 01 A' PLANT P0utt WA$ RfDUCED AND UNIT St0UCNT OFF.LINE . VAtt0V$ MEs JS OF ttPAlt Witt DISCUS $CD AND IMPLEMfWTED . TME VALV! WAS Nours Out ! UNSTATED SUCCES$FULLT BY OPERATIONALLY CitATING A NICHER DIFFitENTIAL Testiry Performed frequency /Perind of $ervice l
' PRE 85URE Acto $s THE CHECC VALVE ST CONCENTRAflWG FLOW IN LOOP 11 . THE *.**....+ ....... + ..........+ .. ..........
VALVI AND LOOP WEtt atTURNED TO SElvitt AND PLANT STARTUP REtuMED . Check Testing 0 / Not Done 0.0
A-22 ,'. " WESTINGHOUSE CLASS 3 c I I l i 1 i 1 i 4 i
. ,i ,
ACCEPfAsitt DATtt 02/08/08 i
)
Utility......................Coemonwealth Edloon Caspeny L-Unit.........................ouAD tilitt 1 Applicellen......... RCIC Oloch to fdwtr Check Velve W155.........................Generet Electric . Component . . . . . . . . . . . . . . . . . . . .v ALW f me t t en. . . . . . . . . . . . system............... Reactor Core f eeletten teeting Gt l Utility Component Id........ 1 1301 $0 Utility System..... 1300 j Start Date...... 12/23/87 Out of service Hours... 114 Date stort Dete. 0;'/01/74 in service Dete..... 10/07/71 start ilme......16:53 016covery Date.. 12/23/81 testoration Mours...... 114 Accepted Dete... 05/22/91' out of Service Dete. 11/28/89 l frd Dete........ 12/28/87
. End f lee.. .. ....10:30 lefety Ctese....... 4 -. -
l Input Dete...... 02/01/88 Mode................ Operating. I toport Dete..... 02/01/88 ' system status................I + Traln/Chennel in Service (OPC/Sec) Internet Env........ Anblent fesperature +10f to +120F
$ verity Level...............J Ismedlete Roseter er Primary Coelant Weter. ,
f a i l ure sympt om. . . . . . . . . . . . . . C
- Demand f aul t Condonoste / Nigh Purity Water ;i ure Mode................ 70
- felled to Open ,
sure Detection............I
- Special inspection ,
. Externet Env........ Ambient Temperature -*10F. to et20f .
Cause Category...............N
- Wear QJt Other' Caus1 0escription............A0
- eormat/ Abnormal Wear Supptler............ General Electric Company
- System Ef f ect................t
- System fection/ Operation Unaf fected S w ifer_Id......... _
f 3 ll P g 5 _. ,
A-23 WESTINGHOUSE CLASS 3 Plant E f f ec t . . .. . . . . . . . . . . . . .G Resul t ed in to slynt f icant (f f ec t Manuf acturer........ Rockwell int / Flow Control Olv Ccerec t ive Ac t ion. . . . . . . . . . . . AM R epl ac e Par t(s ) Mf r Model Id. . . . . . . 97DY 00ctmufst at i on. . . . . . . . . . . . . . . . ! kone o f t he Above M f r Model h o. . . . . . . 9 70 t L po r t h ete r . . . . . . . . . . . . Mfr lertal h0....... System Af f ected ty Fellure...CE A . Reactor Core isolation Cooling Gt Mir Standard........ USAt 831.1 Drewing 40.......... M 50 Fellure DescelPtion kerretive..... ON 12 2347 At 1653 Houes WMitt PERFORMl=3 REAPOR CORE 150LAf tow C00LitG MAWUAL INifl Afl0W f t$f 11 WAS OllCOVERED THAT TMt RCIC Pup (ngineering Codes Wu)LD WQt luJECT WAftR INfD THE REACTOR Vt$1tL . AN thvtlflGAfl0N RIVtAttD THAT TME RCIC PtMP DISchARQt CHECK YALVE 1 1301*$0 FAlltD TO A.fype................ Check opt 2 . $Af tfi IMPLlCAfl0N$ WERE NikiMAL $1NCE RK Ftt0 WATER $f$f tMS & B.0oerator.........&.. Pnemistic (Dis $regm or C SAFF l#UfDOWW $f111M5 Wtat AVAILABLE . C.Func t ion / Arplic et t on one Vey Flcw D.tody kateriet....... Carbon Steel Cause of Falture Warrative..... E.Sody Maruf acturina N Cast fMt CxtCK VALVE WAS Olla 55tM8 LED AND THE CAust FOR IMit tVtti WAS DUE F.tominst intet $lte ( 4 to 11.99 IN TO WDRW MikCE Pitt AND VALVI BJ$NING WMlCM ALLOWID TMt VALVI D13K 10 G.$1:e (Intet)........ 4.000 lu BtCCME WEDGED INTO THE DISC SEAT . M. Design Pressure..... 1250.000 PSIG , J. Design fenpersture.. 575.000 etGF Corrective Action Warrative..... Mi%CE P!WS , GA$KEf 8 . VALVt PACKlkG AND LAuf tRN RikG WERE ALL parit OF 1 Time operating When Reactor la Critical.. 100% f t:t VALVt THAT WLRt REPLAttD UNDtt WORK REDutti 062912 . ALL INTERNAL 1 flme Operating When Reactor is shuttbwn..100% PAtt$ WERE CLEAWED PRIOR TO REAtttM8LY . THE VALVI WAS ft$tt0 AND APPROVt0 ON 12 28 87 At 1030 Moufts . DVR 04 01 87 119 Roure out festing Perforwed F re<pency/ Period of Service Check festing 1 / konth 0.0 Functional festing 0 / Not Done 0.0 Calibration festing 0 / Not Done 0.0 ACCEPTANCE Daft: 07/18/86 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Conmonwe a l th E d i s on Conpany Uni t . . . . . . . . . . . . . . . . . . . . . . . . 00AD C l f i t s 1 W15 5. . . . . . . . . . . . . . . . . . . . . . . . . Gener a l E l ec t r i c Applicotton......... Copponen t . . . . . . . . . . . . . . . . . . . . VAL VE F me t t on. . . . . . . . . . . . Utility Conponent Id........ 1 2599 23A s ys t em. . . . . . . . . . . . . . Contius t i bl e Gas Cont r ol
- D i lut i on Cf Start Date...... 02/18/86 Utility System..... 2500 s tart Time..... .11:00 out of service Mours... 673 Data start Date. 07/01/74 in+5ervice Oste..... 07/01/TA 01scovsry Date.. 02/18/86 Restoration pours.. .... 673 Accepted Date... 08/28/89 Out of service Date..'
trd Dat e. . . . . . . . 03/18/86 E nd t i me . . . . . . . . 12 :00 lefety Class....... 2 Report Date..... 06/09/66 Irput Da t e. . . . . . 06/18/86 Mode......... ...... Operating sys t em S t atua. . . . . . . . . . . . . . . . F . T ra ln/Channe t i n f es t 5:vsr l ty L evel . . . . . . . . . . . . . . .J . loned t a t e int erne t Env. . . . . . . . Failure $pptom..............C Demand Fault External Inv........ F a l t ure Mode. . . . . . . . . . . , . . . . .F0 F a i l ed to Open S e tter............ Dresser ind inc F e l lure Det ec t i on. . . . . . . . . . . . C Surve l t t ance f es t i ng $ @ ller Id......... Ceuss Ca t egory. . . . . . . . . . . . . . . F Ma int enance/T es t ing Manuf acturer........ Dresser ind viv & Inst Olv / Ashcrof t Causs Description... ....... ..BB = Mechanical Damage / Binding Mfr Model Id....... 5580 SE Dirty Mfr Mcdel No....... 1*5580W 1 ENC 062 System E f f ect. .. . . . . . . . .. . . . .C Loss of One or More T rain / Channel Funct ioMf r Serle t No.... .. . Plcnt Ef f ect.................G Resulted in ho significant Ef f ect Mfr Standard........ Correct ive Ac t ion. . .. . . . . . . . . AG . R epai r Cenponent/Part Droming ko......... 1 5580W 1 xuC062 D or -*nt a t i on. . . . . . . . . . . . . . . 2 k one of t he Above Lt port N wtaer............ System Af fected by Failure...$CADil Cont;ustibie Gas Control Dilution G Engineering Codes Failure Description Narrative..... A.fype................ Check ON 218 86 , At 1100 ht$ . UNif 1 WAS IN REFUELikG MCOE , DutthG B. operator............ None
A-24 WESTINGHOUSE CLASS 3 P(RF0eMANCE OF Atm0$PMERIC CONTAINMENT AT840$Phtti DILU110W ( ACAD 3 C.F eettun/ Application $huttf f / t sst at ion /S t op IN stRVitt CMECE VALvf it$1 Bf f(CW STAFF PtRlowktL , f tt 1*2599 234 D.tody Meteriet....... Carbon Steel CNICK VALVE FAlltD 10 OPEN . $AFETT IMPLICAflok$ WER( MlulMAL $1NCE thE E.$ody Manufacturing M F Nominal intet $lge ( 1/2 to 1.99 lN f ,tCK)P OF. THE ACAD Sv$1tM WAS AVAILABLE 4 ONif ING se:CE G.$lte 1 (Intet)........ REACTOR 1.000 WA$IN IN THE V N. Design Pressure..... 1640.000 PSIC Cause of failure Norrative..... J. Design feeperature.. ICO.000 DEGF PRotASLE CAU$t OF THE 125W21A CHICK VALVE NOT OPENING WAS DOE 10 Ditt ACCuMULAftt* tifWitN THE VALVE DISC AND IME VALVE GUILE . TMt % flee Operating When Reactor is Critical.. 991 VALVE DISC WAS BINDING AGAIN$f IMt GUICE . VALVE l$ MANUFActua[D Bf 1 time Operating When Reactor le $49tda dn.. 995 NANtott , Gil NO .1 5180W 1*XNC062 . Hours out C frective Action Narrative..... Testing Performed Frogsency/ Period of $ervite CWECK VALVI WAS DilA$$tM8LtD & CLEANtD . SURVE!LLANCE ft$f MAS " " . " . " " " . " ................ .......... PERFORMED TO YttlFT OP(RAtlLITT , WITN AN ACCtPTAtti FLCW RAlf 0F 64 Check Testing 0 / Not Done 0.0 SCFM . $1NCE fMil WAS A NEW $URVtlLLANCE , TNi$ WA$ THE FIR $f flME iMAT Functional festing i / cuarter -0.0 VALVE 1*2599 23A WA$ EVER TE$ftD .10 PREVENT A FUfuRE RECURRENCE OF Collbretton festing 0 / Not Done 0.0 TNil ifPt , IME SURVilLLANCE WILL tt PERFORMED tVERT 90 DAYS , WHICH s m ExtRCllt iMt VALVE . ACCEPTANCE Daft 07/30/90 Uillity......................Com e nwealth (dison Cm pany Unit........................ 00AD CITitt 1 k$$$.........................Generet Electric Application......... , Conponent . . . . . . . . . . . . . . . . . . . .vAlvt F me t t on. . . . . . . . . . . . Ut i l i t y Conponent I d. . . . . . . . 1 301 29 Sys t ee. . . . . . . . . . . . . . Cont rol R od Dri ve.GE Sttrt Date...... 12/20/89 Utility system..... 0300
$ tert flee...... 12:00 Out.of. Service Mours... 2640 Data $ tert Dete. 07/01/74 In $ervice Dete.....10/07/71 Discovery Date.. 01/23/90 Restoration Moors...... 1836 Accepted Date... 05/22/90 Out.of.$ervice Dete. 05/03/90 te........ 04/09/90 d ame........ 12:00 . Safety Class....... 2 Report Dete..... 06/27/90 input D e t e . . . . . . 06/27/90 Mode................ Oserating System Status.... ...... ... ...G f rein /Channet in Maintenance
$; verity Level...............t
- Degraded Internet Env........ Condensate / Migh Purity Water failure $yectos............. 3 . Out of Speelfication Esterne Env....... Nigh Nueldity failuro Mode.................F0 . Failed to Open supptler............ Rockwell Int / Flow Control Div Felture Detection............t . Corrective Melntenance suptier 16........ 1 301 28 Cous2 Category...............K . Unknown Manuf acturer........ Pockwell Int / Flow Control Div Cous) Description............ AV . Connection Def ective/ Loose Parts Mfr Model Id....... 7506Y Sys t en E f f ec t . . . . . . . . . . . . . . . .D . Degr o6ed T ra ln/Chanr el Mfr Model No........ FIGURE 7506Y Plant Effect.................G
- Resulted in No $lgnificant Effect Mfr Serlet No.......
Cirrective Actim......u.... AN = Replace Part(s) Mfr Standard........ Document at i on. . . . . . . . . . . . . . . . Z . None of the Above Drawing No.......... R340 P8419520 LER Repor t Nucer. . . u . . . . . . . System Af f ected by f alture...RLA . Control tod Drive GE ' l Engineering Codes
, felture Description Narrative.....
. ON 1 23 90 11 WAS DISCOVtRED WHILE PERFORMikG MAINTENANCE ON TMt A.1ype................ Check CONTROL ROD DRIVE ST$itM THAT TNE 1*301*2B CONTROL R00 DRIVE PUMP t.0perator............ Manuel
- DISCNARGE STOP CHtCK VALVE WOULD NOT FULLY OPEN UPON DEMAND AS REQUIRED C. function / Application one Wey Flow i
. D. Body Materlet....... Carbon Steet l E. Body Manufacturing M l Cause of Fellure Narrative..... F.Nomint.t inlet $lte ( 2 to 3.99 IN l- INE CAust 0F TNi$ FAILURE l$ U M N0uN VMEN THE VALVE WA$ DISA$$tMBLED G.$l te (Int et). . . . . .. . 2.500 IN 71 DISC WAS FOUND Loost , AND iMi$ COULD HAVE CONTRIBUTfD 10 fME N. Design Pressure..... 900.000 P$10 NOT FULLY OPENING UDON DEMAND , J. Design femerature.. 120.000 DEGF C*rrtctive Action Narrative..... 1 Time Operating When Reactor is Criticat.. 100%
kECHA21 CAL MAINithANCE DISA$$1M8 LED tnt VALVE , REPLACED THE SEAL RING % fime Operating When Reactor is shutdown.. 501 l t n--
WESTINGHOUSE CLASS 3 A-25
, AND af f 0RQUED THE SCmWEi 80Lis tNE Mot 04 WA$ *fWit!D AND THE VALVE M8 f uuCTIONALLY f(5f ED AND APPROVED CW 4'9 90 . WR 081848 Hours Out Testirq Performed F re<pency/ Period of Service Check Testing 0 / Not Done 0.0 Fwwtlonel festire 0 / Not Done 0.0 Calibration testing 0 / hot Done 0.0 O
I l i
A-26 WESTINGHOUSE CLASS 3 ucle:r_ Ptent tellebility Date system Generet toport
-/
( tal m L. Hunter, Jr. Repor**ld: WPRC00AA
- Westinghouse tiectric Corporation Job k a ber: 9082 tm Date: 06/30/92 Run Timet 11:06
'Introductlon
- The attached repcrt was generated by your query of the NPkD$ date base.
A senery of your Swry is listed teolow. OuttY You salected the following search conditlan(s): 4 Selected Component is VALVE Selected VALVE fype is Check Selected Unit ID is ouAD CITits 2 Selected System is Contustible Gas Controt
- Dilution GE telected Manuf acturer is Dresser ind Viv & Inst Div / Ashcrof t TN .>
Find Utility Component ids that are owel to 2 2599 238 Th:re were I records sweting the search condition (s). AT AND S0ti You sstected to rm poneret report 5
-Casponent Master Failure Report (w/ unit Information)
- Yass chose to sort the report try sort Sewence Fleid Name tPRG05AA- taucteer Plant Reliability Data system Failure Master Report t m Date: 06/30/92 Job humbert 9082 ACCEPTANCE Daft: 07/18/86
- Ut i l i t y.'. . . . . . . . . . . . . . . . . . . . .Comumnweal th E di son Company .4
. Uni t . . . . . . . . . . . . . . . . . . . . . . . ,cuAD C i f t t s 2 -I kS$1.........................Generel tLectrIc Applicetion.........
-Compenent.................... VALVE Fmetton............
Ut t t i ty Copponent I d. . . . . . . . 2 2599 238 system.............. Combustible Gas control Dilution GE L Start Date...... 02/18/86 Utility systes..... 2500 Sttrt Time...... 09:30 out of service Mours... 1251 Date Start Date.~.11/17/81 in tervice Date.....11/17/81 '
-; P *prery Date.. 02/18/86 Restoration Hours...... 1251 Accepted Date... 09/05/89 Out of+$ervice Dete..
k j >ste........ 04/11/86-End Tise........ 12:00 Safety Class....... 2 tiport Date..... 06/11/86 t re.it D a t e . . . . . . ,06/18/86 M ode . . . . . . . . . . . . . . . . Ope re t i r$ , -System Status................F frein/Cherret in Test
- 53v$r i t y L eve l . . . . . . . . . . . . . . .~J - t medi a t e Internet Env........ -
WESTINGHOUSE OLASS 3 F a i l uro S ymt on. . . . . . . . . . . . . .C Demard F eul t Enternal Env........ Failure Mode................ 70 Failed to Open supplier. . . . . .. . . . . . Dresser led inc Failure Detect icn, ... .. . . . ...C
- Surveill erce f esting $ p lier Id.........
Cause Ca t egory. . . . . . . . . . . . . . . F
- Ma i nt enorc e/T es t i ng Manuf actu.or........ Dresser truf Viv & Inst Div / As C Desc r ipt ion. . . . . . . . . . . .BB
- Mechanic a l Dama ge/8 t rding mf r Model id....... 5580 St Dirty Mfr Model h0........ 1 5580W 1 *NC062
$rs tem E f f ec t.. . . . . . . . . . . . . . .C
- L oss of one or More f ra t n/Chennel FW t iom f r ser ie t No. . . . . . .
Plant E f f ec t. . . . . . . . . . . . . . . ..G = t esul ted in No Signi fictet E f f ect Mfr Stendard........ C;rrective Action............AG
- Repelr Co m onent/Part Drawing No......... 1 5580W 1 xWC062 Documentation................Z None of the Above Lt t R epor t Netzer . . . . . . . . . . . .
$rste.n Af fected try Falture.. 5CADlL Canbustible Gas Control
- Dilution G Ingireering Codes f ailure Description Warrative..... A.fypt................ Check OH 218 84 At 0930 Nas UW112 WAs IN RUN MODE Af 90% PMR . DJtibC 8.0perator............ None Pitf 0twCE OF ATMosPNttIC CONTAIPMENT ATMc#Ntat DILU180N ( ACAD ) C.fmetion/ Application Shutof f/ Isolation /Stop IN 5EtvlCE CEECC VAlvt TEsf Bf TECW $1AFF Pit $0NNEL ThE 2 2599 238 D. Body Meteriet....... Carbon Steel CHICC VALVE FAILID TO CFEN . $Aftff IMPLICAfl0N$ uEtt MINIMAL SINCE THE t.Sody Manuf 4Cluring M
'88 LCUP Of fMt ACM $75 FEN WAS AVAILABLE & THE REMAINING THttE CHtCK I. Nominal intet Site ( 1/2 to 1.99 IN ,
t'ALVts IN THE SY$f tM ttMAlWED ortRABLE . G.318e (Intet)........ 1.000 IN N.Deelen Pressure..... 1440.000 P$1C Cause af f ailure Norrative..... J. Design Temperature.. 100.000 DECF PROBABLE CAUSE OF THE 2*2599 238 CHfCK VALVE NOT OPENING WAS Cut 10 Diti ACCleULAll0N BffWCEN INE VALVE DISC AND THE VALVE GUIDE . fME 1 fine coeroting When teoctor is Critical.. 99% VALVE DISC WAS BINDING AGAINST THE GUIDE . VALVE l$ MANUFACTUtfD Bf 1 Time Operetirig When teactor is Shutdoun.. 99% NANC0CK Ma0EL No . 1 5580W 1 xCN062 . Nours tut Corrective Action Norrative..... Testing Performed frequency / Period of Service CNECC VALVE WAS DISAS$EM8 LED AND CLEANtD . SURVtlLLANCE Tist WAS ****** ********** ********* ****** ********** PitfotMED 10 YttlFY OPitASILITY , WlfN AN ACCEPTABLE FLCW RAff 0F 83 Check Testing 0 / Not Done 0.0 $ $1NCE ful$ WAS A NEW SURVtlLLANCE , TNIS WA$ THE Fit $f f!ME INAT functional testing 1 / Quarter 0.0 VALct 2 2599 238 WAS EVER TEsttD . TO PttVENT A FUTURE RECuttENCE OF Calibration festing 0 / Not Done 0.0 TXIS TVPE , THE SueVilLLANCf WILL Bt PERFORMED FVERY 90 DAYS , WNlCN WILL EXERCitt THE VALVE . d O
e A-28 WESTINGHOUSE CLASS 3 m t i r ). r ACCEPTANCE DATE: 02/21/91 Utility......................Weshington Ptetic Power Supply System
- Unit.........................WWP 22 NS$$......................... General Electric Application.........
Consonent . . . . . . . . . . . . . . . . . . . . VALVE function............- , Utility Component Id.........RCC V 238 $)stes.............. Reactor 8tdg. Closed Cooling Water GE t Start 0:te...... 12/15/90 utility System...... ACC l
. Start Time...... 12:00 Out of*$ervice mours... 510 Data Start Date. 12/13/84 In-service Date..... 02/27/84 Olscovery Date..12/31/90 testoration Hours...... 138 Accepted Date... 05/23/85 Out of*$ervice Dete.,
tnd cate........ 01/05/91 l E nd T ime. . . . . . . . 18:38 Sefety Class....... 4 Report Date...... Input Date...... 02/18/91 Mode................ Operating Systee Status................t . Traln/Chennel in service (OPC/$8C) Sever i ty Level . . . . . . . . . . . . . . .K Degraded Internal Env........ Anblent Teeperature +120F to +180F f a l t urs Synotom. . . . . . . . . . . . . .C Demand f aul t Cheelcal solution Not Boric Acid l' f a t t ur e Mode . . . . . . . . . . . . . . . . . F0 f a l t ed t o Open taternal Env........ Anblent f esperature +10F to +120F . 7 Operational' Abnormality Supplier............ Wstworth to ( ~.Q)'s Detection............A Ca t egory . . . . . .~. . . . . . . . .K unkno m
' Caus) D;scription........... 88 Mechanical Demoge/ Binding supplier Id.........
Manufacturer........ Walworth Co BC Out of Mechanical Adjusteet Mfr Model Id........ $341 Sys tem E f f ect . . . . . .. ... . . . .. .C Loss of one or More t ra in/ Channel f tnc t i cetf r Model No. .... . .. $34161 Plant Ef f ect.................G - Resulted in ho $lgnificant Ef fect Mfr Serial No.......
A-29 WESTINGHOUSE CLASS 3 Cst ric t i ve Ac t i on. . . . . . . . . . . . AG R epe e r Comanent /Per t M f r S t erda r d. . . . . . . . DocWment a t i on. . . . . . . . . . . . . . . .Z
- gone o f ths Above D r co l ng to . . . . . . . . . . *:525 L E R R epor t h @te r . . . . . . . . . . . .
$rstem Af f ected by f ailure...WBA . Reactor Stdg. Closed Cooling Water G Engineering Codes . ure Description harrative.....
WHILE Af fEMPflWG TO SWAP REACTOR CLOSED COCLikG PVMP$ , DutlhG hORMAL A fype..............., Check PLiat OPERAfl0N , ThE CHECK VALVE ut fME 0U71F7 07 TME '0' P m P 8. operator............ hone DISCHARGE DID WOT FULLY OPEN CAU$lkG A *W PRES $URE ALARM . PUMP WAS C.F metton/Aceticatten One Way Flow
$UB$E0VEW7LY TAKEW QUf CF $ERVICE FDA VALVE REPaat RE$ULilkG th A Lost D.gody Material....... Carbon $ teel 0F TKE 'I8 LOOP 0F THE SY$ FEM . THERE WA$ #0 $lGulFICANT PLAuf EFFECT E.tocfy Maruf acturing M Cast l CUE TO ST$ TEM REDUNDANCY . F.kominal Inlet $lte ( 4 to 11.99 IN C.$lte (Intet)........ 10.000 IN Cause of Failure Narrative..... M. Design Pressure... .. 150.000 PSIG frE CouMTEPWEIGHT ARM WA$ FOUWD LAGGibG APeROMlKATELY 30 DEGatES stuimo J.Desten feeperature.. 150.000 DECF TNE VALVE Ditt itAVEL THEREBY WOT ALLOWING fME VALVE 10 FULLY OFEm .
CAUSE OF Mi$ALIGkNENT WAS NE 10 A DAMAGED CET AND KETWAT lb THE DISC % fime Operating When Peettor is Critical.. 1001 TC:,E AND $HAff AffAChlkG 70 THE COUNTE M ICtf . $ flee operatir>g When Atactor is $hutdawn.. 100$ Corrsctive Action Narrative..... Hours Out , . VALVE WAS DISA$$tM8 LED . Ik$PECTED AND CLEANED THEN REA$$EMBLED AND festing Performed Fre9;ency/ Period of Service REPACKED . PARTS WERE ORDERED FOR f ME $WAf f , KtV . AND DISC TOKE , BUT " " . " . " " " . " """"."."" " " . . " " WERE NOT AVAILABLE PRIOR TO CCMPONENT RETURN 10 SERV!CE . A check Testing 0 / Wot Done 0.0 SAflSFACTORT LEAKAGE TElf WAS PERFORMED AND THE ST$ FEM RETURNED TO Functional Testing 0 / Not Dore 0.0
$ERvlCE . Calibration festing 0 / Wot Done 0.0 ACCEPTANCE DATE: 07/76/90 Ut ili t y. . . . . . . . . . . . . . . . . . . . . .Wesh ington P4L ie Power $wpty $yt t em Unit.........................WWP'2 2 V '......................... General Electric Aplication.........
L anen t . . . . . . . . . . . . . . . . . . . . VA L VE Fmetton............ Utili ty Corponent Id.. . . .. ...RCIC V 111 S ys t es. . . . . . . . . . . . . . R eac t or Cor e I sol a t i on C ool i ng GE
$ tert Date...... 11/28/89 Ut ili ty Sys t em. . .. . . RCIC Stert f law. . . . . . 17:30 out of Service Pours... 266 Data $ tert Date. 12/13/84 in $ervice Dete..... 03/02/84 Discovery Date.. 12/05/89 Restoration Hours...... 43 Accepted Date... 05/23/85 Out of Service Dete..
End Dete.. ... 12/09/Ei9 E aj fl% ........ 19:19 Safety Class........ $t Repor.t D a t e. . . . . . Irput Date... .. 05/18/90 Mode................ Staniy Condition Sys t em S t a t us . . . . . . . . . . . . . . . .F T ra l n/Channe l in f es t
$mr i ty Level . . . . . . . . . . . . . . .J t wedia t e Internet Env........ Anblent Tenperature Over +180F F a l ture S ynot em. . . . . . . . . . . . . C Demand f aul t kesctor or Primary Coolant Water F a l l ur e Mode . . . . . . . . . . . . . . . . . F 0 F a i l ed t o open Externet Env........ Tenperaturc / Nualdity (Cntrld)
Fellure Detection............C Survelltance festing Ambient fesperature +107 to +120F Crus 2 Cat egory. . . . . . . . . . . . . . . F Ma int enarce/T est ing $pller............ Bovee & Crell Constructico Co Caues Descript ion. . . . . . . .. . . . AE Lubricat ion Probt ea $ w ller Id......... E51 F082 88 Mechanical Damage / sinding Manuf acturer........ Rockwett int / Flow Control Div
$ys t em E f f ec t . . . . . . . . . . . . . . .D
- Degraded f re in/ Channel M f r Mode t I d. . . . . . . 838Y Plant E f f ec t . . . . . . . . . . . . . . . . .G . Resulted in n o $len+ 81 cont E f f ect Mfr Modet ko....... 838YT Corru t i ve Ac t i on. . . . . . . . . . . . AG Repe l r Conocnent/Pa r t Mfr $erlet No....... WA972 Docment a t i on. . . . . . . . . . . . . . . .Z . None of the Above
. Mfr $tendard........
LER tiport uw ber............ Drawing ko.......... M519 System Affected by Failure...CEA
- Peactor Cort isolation Coot trq GE Failure Descriptiun kerrative..... Engineering Codes DU2f kG THE Po$f MODiflCAfl0W $URVEILLANCE TES'ilkG OF THE REACTOR CORE Afl0N C00LikG VACUUM SREAKER CMECK VALVE , THE VALVE FAILED 10 OPEN A.fype............... Check j m. 8 TEAK VACUUM ON f nt TUR8tWE thkAult LikE AT THE AEQUIRED PRES $URE . B. operator............ M.w t t
C.Funct ion / Amllcation One Way Flow Cause of Falture Narrative..... D. Body Materiet....... Carbon $teet l \
WESTINGHOUSE CLASS 3
- VALVE LUBRICAfl0N MAD SECOME 'f ACKY' AND 01D hof ALLOW INE VALVE TO E. Body Manufacturing M forced MDVE FREELY . F.Nominst intet $lte ( 2 to 3.99 lW m C.$lte (Intet)........ 2.000 IN q jcliveActionkerratlwe..... H. Design Pressure..... 3600.000 PSIG L.:$$EM8 LED AND Ik1PEC1ED VALW AND INTERNALS . TOOK MICR0KETER J. Design fem erature.. 100.000 DEGF READikCS OF THE DISK Wl1H NO DEFECT $ INDICATED . CLEAhED $URFACES AkD RELUSRICATED VALVE REtuREED VALVE TO $ERVICE AND C04PLETED % Time Operating When Reactor Is Critical... 0%
SURVEILLANCE . 1 Ilse Operating When Reactor is thutdows.. 20% Hours Out Testing Serformed Frequency / Period of Service
................. ................ .n.......
Check Testing 0 / Not Done 0.0 F met t ene t f esting 0 / Pat Done 0.0 Collbration festing 0 / Not Done 0.0
..........................................................................................................................~ ........
ACCEPTANCC DATE: 10/15/90 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . Wash ingt on Publ i c Pwer $wpl y Sys t ta Unit.........................WhP*2 2 N $$$ . . . . . . . . . . . . . . . . . . . . . . . . . Gene r a l E l ec t r i c Application......... Congonent . . . . . . . . . . . . . . . . . . . . VAL VE fmetion............ Utility Corponent Id.........RCIC V 111 System.............. Reactor Core Isolation Cooling GE Start Date...... 07/06/90 utility Systes...... RCIC . Start flee...... 12:00 Out of $ervice Mours... 749 Date $ tert Date.12/13/84 in $ervice Date......D3/02/84 Discovery Date.. 08/06/90 Restorat ion Nwrs......17 Accepted Date... 05/23/85 Out of *$ervice Dete.. End 0:t e. . . . . . . . 08/06/90 End Time........ 17:41 Safety Close........ $R i T 7 t Date...... Irgmet Date. . . . . . 09/26/90 Mode . . . . . . . . . . . . . . . . S t orut>y Cond i t i on ( U Level...............J rlty lemediate) e S t a tus . . . .Internet -
. . . . Env........
. . . . . .Ambient . . f .Temperature T r e t over n/Channe e160F t in l Felture Symptom..............A
- Physical fault Reactor or Primary Coolant Water F a ilure Mode. . . . . . . . . . . . . . . . 9
- F ai led t o Open Enternal Env........ Temperature / ikaldity (Cntrid) felture Detection............C Survelliance Testing AnAilent Temperature ~10f to +120F Cause Ca t egory. . . . . . . . . . . . . . .K . Unknowi $@ plier............ Sovee & Crell Construction Co cause Description............AE Librication Problem $ w ller Id......... E51 F0 V BE Dirty Manuf acturer........ Rockwell Int / Float Control Div s ys t en E f f ec t . . . . . . . . . . . . . . . .C
- Los s of one or More T ra ln/Channe t f unc t l Wa f r Model I d. . . . . . . . IL387 Plant Effect.................t . Resulted in Unit Off Line' Mir Mode! No....... 838YT
! Corrective Action............AG Repelr Component /Part Mfr Serial No....... WA972 . Document a t i on. . . . . . . . . . . . . . . . Z W one of t he Above Mfr Standard........ L E R R epor t Musber . . . . . . . . . . . . Drawing ko.......... M519 System Af f ected by Failure...CEA Reactor Core lactation Cooling CE l falturo Description Warrative..... Engineering Codes WITH INE REACTOR Af 6 PERCENT POWER AND HOLDIWG , AWAlfikG TME REACTOR CORE ISOLAfl0N SY$1EM OPERAtiLiff TE$f PERFORMANCE 70LLOWING REPAlt ON A.f pe................ Check AN ISOLAfl0N VALVE , TME 28 CNECK VALVES ON THE TUR8lkt EXKAUST VACLAM 8.0perator............ karual [ RELIEF LikE VERE FOUND STUCK CLOSED . VALVES ARE REQUIRED OPEN FOR C.Functices/ Application One Way flow IkCREA$ED POWER OPERATIC *$ . $0 PLANT $f ARTUP WAS DELAYED FOR WALVE D. Body Materlat....... Carton Steel REPAIR . E.$ody Manutecturing N for9ed F. Nominal Intet $lte ( 2 to 3.99 IN Caus) of failure harrative..... C.$lte (In ut)........ 2.000 lu VALVE INTERNALS WERE STUCK DOE 10 Lact CF ADEQUAff LU8klCAfl0N AND DIRT H. Design Pressure..... 3600.000 PSIG UP , CAUSE UNKNOWN . J. Design fe m erature.. 100.000 DEGF Czerective Action Warrative..... 1 Time Oprating When Reactor is Critical... 0% VALVE WAS D11 ASSEMBLED AkD INTERNALS WERE CLEANED AND LU$RICATED . % fime Operating When Reactor is $hutdown.. 20% VALVE Ws1 RE A$$EMBLED AkD FLOW VERIFIED . Nours Out
WESTINGHOUSE CIASS 3 Testing Performed Fre@ency/Perled of Service Check Testing
~
0 / Not Done 0.0 functional Testing 0 / Not Done 0.0 Calibration Testing 0 / Not Done 0.0 ACCEPTAhCE DATE: 10/1$/90 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .We sh ing ton P@l i c Power $4 ply Sys t ee Unit.........................WP*2 2 NS$$......................... General Electric Appilcation.........
.Comonent.................... VALVE F me t t on. . . . . . . . . . . .
Ut lli ty Conpanent Id.........ECic.V.112 Systes.............. Reactor Core Isolation Cooling.C! Start Date...... 07/06/90 Utility Systes...... RCic Start flav...... 12:00 Cut of Service Hours... 749 Date Stert Dete. 12/13/Ss In.Stevice Dete..... 03/02/64 Discovery Date...C8/(%/90 Restoration Mcure.......if Accepted Dete... 0$/13/E$ (Att.cf. Service Date.. End 04te........ 06/06/90 End T ime. . . . . . . . 17:41 Safety Ctess........ SR , Report Dete...... Irput Date...... 09/26/90 Mode . . . . . . . . . . . . . . . . S t an:by Cordi t i on S ys t ee S t a t us . . . . . . . . . . . . . . . F . T r e t n/Ch ame t i n T e s t Sever i ty L evel . . . . . . . . . . . . . . . J . lemedi at e internal Env........ Ambient Tesperature Over +180F Failure Symptom. .... . . . . .. . . . A
- Physical Foot t Reactor or Primary Cootent Water Fellure Mode.................F0
- felled to Open Externet Env........ Teeperature / Musidity (Cntrid)
Felture Detection............C Surveltlance Testing Aablent Temperature *10F to +120F Cause Category...............K
- Unknown Supplier............ Sovee & Crell Construction Ce Cause Description............ AE . L@ricetim Problem supplier Id......... E$1.F084 SE . Dirty Memf acturer........ Rockwell Int / flow Control Div sys tee E f f ect... .. . . . . .. . ... .C
- Lose of one or More Train /Chamel Fmet t oMir Model Id.... ... 834T Plat E f f ect. . . . . . . .. . . . ... . 8 . Resulted in Lhlt of f.Line Mfr Model No....... 838TT L cllve Action............AG . tapelr Cog onent/ Port Mfr Serial No....... WA990 Doceent a t i on. . . . . . . . . . . . . . . 2 . None of the Above Mfr Stenderd........
LER Rew rt Number............ Drawing No.......... M519 System Af f ected ty f ailure...CEA
- Reactor Core Isolation Cooling GE Felture Description korretive..... Enstneer ing Codes WITH TME REACTOR AT 8 PERCENT POWER AND NOLDikG , AWAlflWG THE REACTOR CORE ISOLAfl0N STSTEM CPERABILITT TEST PERFORMANCE FOLLOWING REPAIR ON A. Type................ Check AN ISOLAfl0N VALVE , THE 2' CHECK VALVES ON THE TURBINE EXHAUST VACUUM 8.0perator............ Manuel RELIEF LINE WEtt FOUND STUCt, CLOSED . VALVES ARE REQUIRED OPEN FOR C.Fmetion/ Application One.Wey Flou INCREASED POWER OPERATIONS . 50 PLANT STARTUP WAS DELATED FOR VALVE D.Br.dy kateriet....... Carbon Steel -
REPAlt . E.Sody Manuf acturirgi M forged F.kcelnet Intet Site ( 2 to 3.99 IN Cous3 of Fellure Merretive..... G ti te (Inlet)........ 2.000 IN VALVE INtttkALS WERE STUCK DUE TO LACK OF ADEQUATE LUBalCATION AND DIff M.9esign Pressure..... 3600.000 PSIG 8UILDUP , CAutE UM NOWN . e.wesign Teeperature.. 100.000 DEGF Corrective Action Narrative..... 1 Time Operating When teactor is Criticat... 01 VALVE WAS DISASSEMBLED AND INTEtkALS WEtt CLEANED AxD LUBalCATED . X Time Operating bhen Reactor is shutdown.. 20% VAtVE WAS REASSENSLED AND FLOW VEtlFIED . Nours Out Testing Performed Frecpency/ Period of Service Check Testing 0 / Not Done 0.0 F mettonal Testing 0 / Not Done 0.0 Calibration Testing 0 / Not Done 0.0 l l l I 1
WESTINGHOUSE CLASS 3 uclear Plent Reliability 0:te system , General Report F -* : Ralph L. Weter, Jr. Reporteld WPaG00AA i
\seetinghouse tiectric Corporation Job huutaer 9109 I . [( tm Detst 0/430/92 .
Im fleet 11:32 1
Introductions
The Attached report was ponerated tr/ your eJery of the NPRDS date bese. A sunnery of your esery Is listed below.
. CERT:
You silected the following seerer. condition (s): Selected Component is VALVE f
% Selected VALVE fype is Check telected Unit 10 la fueKtY PolNT 3 ,
Selected Systems are Main Steam W and Nutteer Service Water W Fird Utility Ccuponent ids that are eedet to any one of the following POV 3*2605 and 3 50 311 Selected Manuf acturere are Pratt , benry Co end Schutte and Koertitis Co ( Ametek inc) ,
~
There were $ recorde meeting the search condition (s). ( y Y AND SORT You 60tected to nn poneral report 5: Ceeponent Meeter f ailure Report (w/ unit Infonnetton)
'You chose to sort the report by:.
sort , Seesence Fletd Wome WPRC05AA hucteer Plant Reliability Date System
- Felture Master Report Run Date: 06/30/92 Job Wusters 9109 ACCEPTANCE DATE: 02/13/91 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . F l or i de Power _ & L i gh t Croeny i thit......................... TURKEY POINT 3 l
N$$$......................... Westinghouse Application......... Main Stees isol Velve
' Component.................... VALVE Functlen............-
[ Utility Component'Id.........POV 3 2605 system.............. Main steen-W utility System...... SG STM
~
8 tert Date.......C3/30/90 t t Time...... 12:20 Out of service Hours... 1101 Date start Date. 07/01/74 In Service Date..... 12/04/72
<ery Date...C5/08/90 Restoration Hours...... 1TT Accepted Dete... 06/14/89 Out ofa$ervice Date..
ste........ 05/15/90 '
.End flee........ 09:55 tefety Ctess....... 2 Report Date..... 05/22/90 .. Input Dete...... 05/29/90 Mooe................ Operating
_.=...
WESTINGHOUSE CLASS 3 A-33 Sys t ee S t a t us. . . . . . . . . . . . . . . F f rein /Channe t i n f est le 'ty Level...............J
- Im ediate i nt e rne t inv. . . . . . . . Ant)i ent f eeper a tur e Ove r + 180f fe e 5,wotcnn..............C
- Do u nd fault $ t eers fatture Mode.................f0 a felled to Open t a t e r na l E nv . . . . . . . . Ast>l ent T ecpe r a t ur e 10f t o + 120 F f ailur e De t ec tion. . . . . . . . . . . .I
- Specla t inspect ion Air Cause Category...............N
- Wear out Su@tler............
Cause Description. . . ... . ... 88
- Mechanical Damage /s trding Supptive Id......... POV.3 2605 AD Normal /Atriormet Wear Manuf acturer........ Schutte s'id Koerting Co ( Ametek Inc)
Sys t em E f f ec t . . . . . . . . . . . . . . . .D Degraded f rein /Cheme t Mfr Model Id........ Plant (ffect.................G Resulted in No Significant Effect Mf r MW L No. . . . . .. 627A Co*rective Action. . .. . . . . . . . . AG
- R epair Coevonent/P ar t Mf r Seriet No....... N67464 Docwent a t i on. . . . . . . . . . . . . . . I + None o f the Above Mfr Standsed........ AEA 4*16.5 Lit R epor t N tertae r . . . . . . . . . . . . Or ewi ng No. . . . . . . . . 5610 f t 4061/1 tystem affectec by felture...HBC Mein steem w fe!!vre Description Narretivet.... Engineering Codes usit IN RifutLikG *1;E . DUAlHG A $PECI AL Alt LEAK filt of fME Alt ,
Liktl FOR MAIN $ftAM ISQLAflCW VALVil ( M$lY ) FOR SitAM CtNtt.ATOR A , A . f yre . . . . . . . . . . . . . . . . Check 8A D C . THE 'O' $ff AM CENERATOR MllV FAILED 10 OPEN ON OtKAND . VALVE B. Operator............ Pl$ ton IRAIN WAl IN TElf AT THE flME . C.f unc tiorVApol(cetion Shutoff / Isolation /8 top D.Sody Materiet....... Carbon Steel Cause of f elture herrative..... E.Sody MornJfecturing M Cast CHECKED THE CONTROL STsitM AND VALVI ACfuATOR , AND FOUND WO PR00LEM . F.Nominst inlet Site ( 20 to 39.99 IN VALVI APPI ARED 10 SE tlNDlhG INitRNALLY . FCUND INDICAfl0N 07 CALLING / G. site (Intet)........ 26.000 IN ABRAllON ON TMt UPf ER AND LCNik RIGHT MINCE PlW AND COVER $USNING . H. Design Pressure.. ... 1085.000 PstG
$U$FEC1 N0aMAL WEAR ALL0ut0 INittkAL PARTI TO MISALICW . THIS CAUSED J.Deelen Teeperature.. 600.000 DtG7 CALLING AND SUS $(QU(NT $lNDING 0F THE VALVE .
1 time Operating When Reactor is critical.. 100% Cc ;tive Action Narrative..... 1 Time Operating When Reactor le shutdown... 0% PERfCMED A ' DRAG TElf' ON VALVE Ak0 INE VALVE STUCX . DISA5$tM8Ll0 AND INSPECTED VALVI IWitRNALS . MONED MINCE Pit $ AMD VALVE COVit BU$NING , Mours Nt CLEAktD BONNET AND 83)V GASKET l'.'UACE . AND CLEANED VALVE SitD$ AND festing Performed frequency / Period of Service
"""""""" " " " " " " . "a"-""
NUfs As A PRECAuflDN . STROKED VALVE SA11$f AC10RILY . *WA900508131633 / 63'2 'WA900509200651 / 63'1 Chect festing 2 / Three fear 0.0 Fum tionet festing 2 / Three Year 0.0 Calibration Testing 0 / Not Done 0.0 O
WESTINGHOUSE CIASS 3 {q _ $ V t
.t F
........................................................................................+...........................................
ACCEPTAdCC DATF.: 11/26/86 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . f l or ide Power & L i gh t Coweny Unit.........................TURKty PolNT 3 NS$$......................... Westinghouse ApptIcetlen......... Component . . . . . . . . . . . . . . . . . . . . VALVE fmetten............ Utility Component Id........ 3 50 311 8retem.............. Nucteer service Weter W start Date...... 07/16/86 Utility system...... IC TPCW . Start flee.... .. 09:58 Outaef' Service Nours... 65 Date $lert Date. 04/06/85 in Service Dete..... 04/06/85 Olscovery Date.. 07/16/66 Restoration Nours...... 65 Accepted Date... 04/19/89 Out of aservice Dete. 01/27/87-End Dete.. .. .. .. 07/19/86 I End T ime. . . . . . . . 03 :00 safety Ctese....... 3 i Report Date..... 10/09/86 Irva,tt Date......11/24/86 Mode................ Operating . s 8tetus................I
- TrottVChamel in Service 10PC/88C)
OIty Level...............J + Immediate - Internet Etw........ See Weter or trackleh Water - felturo Syupton-.............C Denend Fault Ashlent Temperature .10f to e120f F a i l uro Mode . . . . . . . . . . . . . . . . . F 0 + f a i l ed t o Oport Enternal Erw........ Ashlent Temperature ~107 to *120F Failure Detection............A
- Operstlanal Abnormality Air cause Category.......o ......N
- Weer out .
Swptler............ Cause Descriptlen........... 84 + Corroelen Sw ptier Id......... Systen Ef fect................C
- Loss of one or More Trel#VChamel FmetleManufacturer........ Pratt . Nenry Co i
- Plant Ef fect.................C Resulted in No $lenificant Ef fect Nf r Model Id. . ... .*. .
Corrective Actlen............AN Replace Pertte) Mf r Nedet be....... 24. WAFER (MWCS) Doctment a t t en. . . . . . . . . . . . . . . 1
- bone of the Above Rfr Serlet 5o....... -
LER Report husber. . . . . . . . . . . . Mfr Standard........ Systen Af fected by f ailure...lses- Nuctemr Service Weter*W Dravity me......... 5410.ft 4068/1 failuro Description Narrative ... WHEN INE 3A INTAKI C(X)LlWG WhTW PLSIP WAS STARTED FOR ROUTINE $ NUT 00ha: Engineering Codes OPERATIONS . THE PUNP DISCHAas Catcr VALyt 3 50 311 010 WOT OPEN As EXPECito . A.T wo................ Check 8.0perator............ Pneuestic (Olephropa or C Cause ** failure Narretive...., C.f mctlan/Applicellen One Wey Flew ACTUATOR IA30 NOT OPEN . CestRVED AIR LEAKING PAST $NAFT ON WEST 0.Sody Meterlet....~.. Stees/ Brent /Adelretty Mt! i CYLIN0ft AND D CESSIVE CORRD110N ON EAST CYLINDER . BOTN PROBLEMS WERE t. Body Merwfecturing M Cast j DUE TO EXPOSURE 'O SALT ENVIRONMENT . f.Nominst inlet $lge ( -20 to 39.99 IN G.stre (Intet)........ 24.000 IN-l: C:rrective Action Narrative..... W. Design Pressure..... 25.000 P$lt , . M ER$ REPLAct0' '6684 63'2 J. Design Temperature.. 102.000 OtGF l: g - V % Time Operating When Reactor is critical.. 100%
% Time operating When Reactor le Shutdown... 0%
l . l l I
WESTINGHOUSE CLASS 3 ^# uctser Plant Reliability Date System Generei Reputt fer N3tsh L. Hunter, Jr. Report
- lot kPRG00AA
.tinghouse Electric Corporstlen Job Nwter 9128 km Date: 06/30/92 km flee 11:47 IntroduetIont the attethed report wet genereted by your cpery of the NP8DS ai* Fate. .
A suenery of your cpery is ilsted 14 tow. tutti. You selected the following seerth condition (s): 4
$3tected Coeponent is VALVE
$3tected VALVI fype la Check telected Unit ID le !!ON 1 13tected system is Nucteer Service Water *W find Utlllty Conconent ids that are ewel to isWOOOT Satected Manufacturer le Mission Nfg Co/ Out of Business there wre 1 records meeting the search condition (e).
315P'" AND SORT: fou s*lected to run generet report $3 Conponent Master f elture Deport (w/ Unit Inforsistion) fou chose to sort the report by: Sort le<penc e field kame cPRC05AA Nucteer Plant Reliability Date system
- Fellure Master Report Rm Date: 06/30/92 Job Number 9128 ACCEPTANCE DATE: 10/23/91 Jt i l i ty. . . . . . . . . . . . . . . . . . . . . .C omonwe e t th ( d i s on Conpany Jnit.........................!!0N 1 K$$3......................... Westinghouse Amlication.........
Component.................... VALVE Fme t t on. . . . . . . . . . . . Jtility Conponent Id........ 1SWOOO7 System.............. Nucteer service Water W stcrt Date...... 05/20/90 utility system...... SW ttert ilme...... 12:00 out of service Hours... 4684 Date start Date. 07/01/74 In service Date..... 12/31/73 Discovsry Date..11/26/90 Restoration Hours...... 136 Accepted Date... 09/12/91 Out of service Date., trd e........ 12/01/90 trxl e........ 16:00 Safety Class....... 1 teport Date..... 10/19/91 Input D a t e . . . . . . 10/19/91 Mode................ Operating system Status................F Train / Channel in fest I Severi t y L evel . . . . . . . . . . . . . . . J 1 ernedi a t e Internal Env........ Tenperature / Mtsaldity (Not Cntrtd)
'A-36
-WESTINGHOUSE CLASS 3 f a il ur e s ynyt om. . . . . . . . . . . . . . C . Demand f aul t f ecsh Wet:r ( Wit / Rfwr / Lehe )
f a i l ur e mode . . . . . . . . . . . . . . . . 7 0 f a i l ed t o tywn laternet inv........ Tous.erature / Numidity (Not Cntrid) f ailure Detection............C . Survelt tance f esting Antalent fesperature .10f to e120F DCetopory.. . . .... ... . . . .J Other Devices $wiler............ Westinghouse Elec Corp / Neeen e sc r i pt i on. . . . . . . . . . . 8 f
- B l oc k ed/Obs t ruc t ed s w iler Id..... ... FIG.24 15sMF.641 BG . Corrosion Manuf acturer........ Mission Mfg Co/ Out of Bustrws At . foreiprVincorrect Meterlet Nfr Model Id........
S ys t em E f f ec t . . . . . . . . . . . . . . . . C los s of one or More f r e l rVChanne t f unc t i oMi r kode l No. . . . . . . 000 CNCK 0 Plant E f f ect.................G
- Resulted in No $ lent ficant E f fect Nfr Serlet No.......
C:r rec t i ve Ac t i on. . . . . . . . . . . . AK . R epl ac e Conponent ( s ) Mfr Standerd........ Doewmentatlan................! None of the Abeve Drawing to.......... P&lD M32 1 Ltt Aeport Wud4r............ System Af f ected t.y f ailure... WAD
- Wuclear service Water.W ingineering Codes
. f ailure Description herretive.....
' UNif At 93 PCT POWER WlfH SERVICE WAftt $f tfEN Ik $ERVitt . OPERAf 0R$ / A.fype................ Checa ItCHNICAL $fAff PERSONEL PERFORMING OUAtitRLY 788 !$.6 108 ( SERVICE 0.0perator............ None WAttR CHECK VALVE OPERAtiLiff itsf ) Woff0 THAT WHEN 1A SERVlCt WAftR C.f met t on/Appilc ellon One Wey flot, PLMP WAS stAtito .1A PUNP DISCMARCE CNECK VALVE FAILtD to OPEN .1A D. Body Meter f el. . . .. . . Carbon Steel PUMP DISCHARGE PRitSURE Rf ADING WAt NICH WHICH INDICAf tD VALVE PR00 LINS t. Body Mers/f acturing H 18 AND 1C SV PtMPS Wttt BOTH OPERABLE DURING f. Nominal Inlet 51 e ( 20 to 39.99 IN G. tite (Intet)........ 24.000 IN
- Couns af f elture Narrative..... N.Deslen Pressure..... 1$0.000 PSIG (VENT , $0 No ADVttst $7sitNS Ef ffCf 8 OCCURRtp . TRAIN WAS LO$f . J. Design fesperature... 120.000 DECF f ALLURE OF CNECK VALVE TO OPEN WA$ CAU$tD BY CORROS10N AND $1LT BUILD UP WifMIN INE VALVE INTERNALS TNil WAS A NEW VALVE , $UT 1A PUMP NAD % flee Operating When teettor le Critical.. 1001 NOT titN RUN FOR A400T 6 MONTH $ WHICN ALLout0 THE SILT 10 ENftR AND % fime Operating When Reettor is Shutdown.. 100E OLOCK OPERAfl0N of THE VALVE .
Houre Out C p .tive Action Narrative..... Testing Perfonned frequency / Period of Service ( h$WOOO7WASREPLActDWifNARtBUILTLittFORLIKEVALVEANDPosi ................. ................ .......... Cin d NANCE VERIFICAf!ON WA$ DONt 10 (NSURE OPttAtlLiff . IS$ 1$.6 108 Check festing 0 / hot Done 0.0 f mettonal festing WST St PERFORMED WNENEVER SW PtMPS ARE OUT.07.$tRVICE CREAf tR THAN 90 0 / Wot Done - ' O.0 Daft . ( WR 297257 , OR 90 0167 ) Cellbretion festing 0 / Not Done 0.0 7 4 7 1 / l t r 4
^~
wrsTmGHOUSE CLASS 3 uclear Plant 8;llability D:ta System Corwral Report For 4:lgt L. M mter. Jr. Report.lds hPtLOOAA sttrehouse tiectric Corporailon Job ku oers 9312 km Date: 06/10/92 Run times 13:18 introdxtient the attached report was perwrated try your query of the tiPRDS data base. A sumery of your query is listej below. QUERf Yeo selected the following search cordition(s): Selected co monent is VALVE - Selected VALVE Iype la Check selected Unit ID la GRAND CULk 1 Selected System is latential Service Water GE Fird Utility Cceporwnt ids that are equal to 01P41F169A
- elected Manufacturer is verway Corp Th;re were i recorde seeting the search cordition(s).
Ol$ PLAY AND $0RT: You e>etected to rm gereral report 5: Cceponent Master Fallure Report (w/ Unit Inforsetton) You chxe to se*t the report by: Sort Sequerce Field kame CPAG05AA Nuclear Plant Reliability Date System Failure Master Report Rm Date: 06/30/92 Job kuters 9312 ACCEPTANCE DATE: 09/14/86 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .t nt ergy Oper a t i ons , t re . Unit......................... GRAND GULF 1 WS$$......................... General Electric Amlication......... Component . . . . . . . . . . . . . . . . . . . . VAL VI F me t t on. . . . . . . . . . . . Utility Corponent Id........ 01P41F169A System.............. Essential Service Uater*GE Start Date...... 05/10/85 Utility Systes...... P41 Start time...... 12:00 Out of $ervice Mours...,6743 Date $ tart Date. 07/01/85 in Service Dete..... 06/16/82 Discovery Date.. 02/10/86 Restoration Hours......131 Accepted Date... 05/08/84 (Ast of Service Date.. t rd %t e. . . . . . . . 02/15/86 t r> o........ 11:00 Safety Ctess....... 1 Report Date..... 08/26/86 Input Date.. . .. . 08/27/86 Mode................ Operating system Status. . . . . . . . . . . . . . . .F T ra in/Chamel in f est $1ver i ty L eve l . . . . . . . . . . . . . . . J
- I medi a t e Internal Env........ Secordary Coolant or Treated Water
' WESTINGHOUSE CLASS 3
- f el lure lymptom. . . . . . . . . . . . . .C
- Demord f aul t ' tstarnet trw........ Aelent Temporsture .10f ts *lP0F
' /e l l ure Mode . . . . . . . . . . . . . . . . 70 . f a i l ed t o Open Air felture Detection............C
- Survelliance f esting - $wel l er. . . . . . . . . . . . T erway Corp C - Category...............F . Maintenance /festing $ $ ptier Id........ 60511
( escription............ A8
- f oreiprVincorrect Materlet Manuf acturer........ forwey Corp BG
- Corrosion Nfr Model Id........
AC + Particutete Contaminetton Mf r Model No. . . .... . $$518 Sys t em I f f ee t . . . . . . . . . . . . . . . .D . Degraded f reirVCherrwt Mf r $erlet No...... 7856 Plant Effect................ 0
- Resulted in No tientficant tffect Nf r Standerd........ ASMt StCT lit Corrective Action............AN ' Replace Part(s)
. Drawing No......... 9645.n.1061 tao Doctonent a t t en. . . . . . . . . . . . . . . .!
- Nore of t he Above LIR Roger t Ntaber. . . . . . . . . . . .
System Af fected by felture...WAA . Rosentlet Service Water Ct insitwerinj Codes iciture Description Narrative..... , A.fypt................ . Check
' DURIN3 A $URVilLLANCE till THE StuP ChtCK VALVE fl69A ON TM DtfWELL B.0perator............ Manuel .
JPORGE COMPkt580R INLtf FAllt0 TO STROKE OPEN . THERt WAS NO SIGNiflCANT C.functlerVApplication Shutoff / Isolation /Stop IfftCT ON tnt PLANI . Tht PLANT WA$ DPERAflNG Af 621 POWtt . D.Bedy heterlet....... Cerben Steet E. Body Manufacturing N forced Cause af felture Narrative..... f.Nominet inlet site ( 2 to 3.99 IN f 4 FAILust of THE $f 0P CHECK VALVE 10 CPEN WAS AllRltuitD TO CORROSION > G. Site (Intet)........ - 2.000 IN - AND TORE 10N MAf TRIAL IN THE ALVE INitRNALS . N. Design Pressure..... 75.000 Pslo - J. Design Temperature..--90.000 DEGF Corrective Action Narrative..... INE DATWLL PURQt COMPRESSOR INLtf $f0P CNECC VALVC WAS DISA55tMSLED X Time Operating When Reactor la Criticat.. 100E
- AND CLEANED . NEW $ FEM , DitK ASSEMBLY , AND SACKSCAf DUSNING Wttt 1 flee Operating When Reactor le Shutdown... SOE IN$fALLED . 6 RINGS OF PACKING WERE REPLAct0 . Atitti WAS SAll8FAC10ef
. ( N60839 ) _ _
Heurs out iestins Perfermed: fregaency/Peried of Service Check festing 0 / Not Done 0.0
- Fmettonet festing - - ) / Month -- 8.0-Cellbration festing 0 / Not Done' O.0 '
l-
A-39 WESTI!MHOUSE CLASS 3 uclear Plant R:llability D:ta system Gener;l Report foti R;tsh L. Hunter, Jr. Report *!d NPRGOOM - ttfrghouse titstric Corpretion Job Weber 9320 km Date: 06/30/92 km flee 15:33 Introche tions the attached report was 9erareted ty your gjery of the NPRD$ data base. A s>Juraary of your @ery is listed below. QUERY: You selected the follcwing search cordition(s): Selected Component is VAL %T ' Selected VALVE fype la Check selected unit ID is NATCH 1 Selected Manufacturer is Walworth Co telected Systes la Residaal Heat Removel/ Low Press inject *CE , find Utility Ccoponent ids that are ogJel to E11*F0310 there were 1 records sweting the search condition (s). D!$ PLAY AND SCait You selected to rm general report 5: Component Master failure Report (w/ unit Information) You choe) to sort the report by: Sort Se@ence Field Name NPRC05AA Nuclear Plant Reliability Data System
- Failure Master Report Rm Date: 06/30/92 Job Ntat4r 9320 ACCEPTANCE DATE: 02/02/88 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .Georg t e Power Conpany Unit.........................kATCH 1 NS$$ ........................ General Electric Asp llcation.........
Component....................VALb1 f me t t on. . . . . . . . . . . . Utility Cenpanent Id.........E11 F0310 system.............. Resichel Heat Roswal/ Low Press Inje: st:rt Date...... 07/19/86 Utility Systee.. ... Ett ! start Time...... 12:00 Out of service Nours... 8208 Data Start Date. 01/01/80 In-service Date..... 12/31/75 Discovery Date.. 10/21/86 Restor ation Hours...... 5964 Accepted Date... 10/09/91 Out of service Date.. End * *t e. . . . . . . . 06/26/87 E n. o........ 12:00 Safety Class....... 2 Report Date..... 01/04/88 i nput Dat e. . . . . . 01/05/88 Mode................ Stani y Condition system Status................E Traln/ Channel in Service (OPC/SBC) $;ve r i t y L evel . . . . . . . . . . . . . . . J I medi a t e Internal Env........ Resetor or Primary Coolant Water
WESTINGHOUSE CLASS 3 Fellure s ymptos. . . . . . . . . . .. . . A
- Phys i cal f cul t Radiction Field (Neutron / Commn) latture t' ode................ 70
- Failed to (pen Anblent longerature Over +1807 F a i lure De t ec t ion. . . . . . . . . . . . A
- Cper a t i ona l Atrers.n l l t y f a t er nal Inv. . . . . . . . Aa61 ent f osser s t ur e + 120F t o +1807 Cm Ca t egory. . . . . . . . . . . . . . .D + Ins t alla t ion f r ror lenterature / Numidity (bot Cntfld) f escription............BJ
- Incorrect Action $4pt le r. . . . . . . . . . . . Gener al f ltc t r l c CoRgany L ~ E f f ec t . . . . . . . . . . . . . . . .D + Degraded f r e i rVChame l supplier Id......... RMa PHP DISCM CHK Plant (f f ect.................G
- Resulted in ho Significant Ef f ect Manufactu*er........ Welworth to Correc t i ve Ac t i can. . . . . . . . . . . . AC
- R epe l t Cceponent / Par t Mfr Model Id....... 5344 Docu1 ent at i on. . . . . . . . . . . . . . . .I
- k one o f the At:ye Mir Model mo....... 5344 LE R R epor t N*ter. . . . . . . . . . . . Mfr Serial ko.......
Sretes Affected by failure...CFA
- tesicbel West twovel/ Low Prest inleMf r.steruserJ........ AWtl 831.1.0 Dr awing ko. . . . . . . . . M16329 Failure Cescription Warrative.....
(C ICC WORMAL OPERAtl0NS , COW 1ROL 8004 PitsCMWEL t!Potit0 THAT THE 'D' tillDUAL HEAT kleAL PWP89 D!$0 MARGE ChtCK VALVE WAS FAILING SHUT Engineering Codes B[tAUSE Cif THE EALANCING ARM 81K0lWG . THERE WAS WO SIGNIFICANT EFFECT C:1Lalf OPERAfl0N . A. Type................ Chec k B.0perator............ None Cause of failure Warrative..... C.f unct ion /Applic at ion One Way Flow THE CAust OF THE FAILUtt WAS AfftlButtD 10 EXCES$ IksVLAfl0N OW THE D.tody Meterial....... Carbon Steel CCK1T OF T (F CHICK VALVE . E. Body Manuf acturthe M Cast F.htnital inlet slae ( 20 to 39.99 IN Corrcctive Action Warrative..... C.51:e (Inlet ). . . . .. . . 20.000 fu THE IWSULAfl0W OW THE CHECK YALVE WA$ itlMMCD (WOUGH TO ALLOW THF H. Design Pressure..... 375.000 PSIG BALANCE ARM 10 OPERAff FtitLY . OPttAll0NS PROVED THE OPitAtlLITY OF J. Design fenperature.. 358.000 DtGF
- THf VAlvt .
1 Tise Operetiry When teactor la Critical... 0% 1 flew operating When teactor le shutdown.. 251 Houre Out Testing Perforned Frequer.cy/ Period of Service Check festing 1 / ouarter 2.0 Fmettonal Testing 4 / Five fears 2.0 Cellbretion Testing 0 / Not Done 0.0
WESTINGHOUSE CLASS 3
........................e....ee........e......e.e....................ee.. .....................e..........e..........e.............. !
I 1 ACCEPTANCE DAftt 09/12/90 j
. 'j Ut .y. . . . . . . . . . . . . . . . . . . . . .Duk e Powe r Conpany Un i t . . . . . . . . . . . . . . . . . . . . . . . . . CA T AWRA 1 W$48......................... Westinghouse A@t i c a t i on. . . . . . . . .
C cgwnent . . . . . . . . . . . . . . . . . . . . VAL YE , i me t t on. . . . . . . . . . . . Ut i l i t y C onoment Id. . . . . . . . . CAct0191 S ys t es. . . . . . . . . . . . . . Am i l l ary f ee&s t e r.W Stret Dete...... 01/04/90 Utility systee...... CA
$ttet flee...... 08:00 Ost.of service Hours... 1008 Data Start Date. 06/29/85 inserviceDate.....01/07/85 Discovery Date.. 01/04/90 Restoraticri Nours...... 1009 Accepted Dete... 02/12/85 ost.of. service Date..
Ind Dete........ 02/15/90 t nd f lee. . . . . . . . 08:00 Safety Cisss....... 2 Report Dete..... 07/20/90 Irgut Dat e. . . . . . 07/30/90 Mode................ Operating system Statue................t f rein /Chamel in Service (OPC/stC) sever i t y t evel . . . . . . . . . . . . . . .K . Degraded Internet Env........ Condensate / Migh Purity Water f ailure symptcm. . .. .. . . . . . . . 8 . Cut of $peci f icat lon laternal inv.. . .. . .. Ai r , f a il ure Mode. . . . . . . . . . . . . . . . 70
- f a i led t o Cpen Anblent fenperature .10F to e120F f l l uro De t ec t i on. . . . . . . . . . . .N . R out ine Observa t i on supplier............ /
Cause Category...............K Unknown Sw ptier Id......... Cause Description........... 88 . Mechanitet Demoge/Bir. ding Manufacturer........ Kerotest Mfg Corp s ys t em E f f ec t. . . . . . . . . . . . . . . .D
- DeG raded f re in/ Cham * ! Mfr kodel Id........
Plant Ef f ect.................G Resulted in no $lont ficant Ef f ect *
.fr Model No........ CN.1500 2206J 505 Corrective Action... . .. ...... AN . Replace Pa rt(s) Mfr Serial No.......
Document a t i on. . . . . . . . . . . . . . . 2 . None of t he Above M f r s t ande rd. . . . . . . . Lt R R epor t Nacer. . . . . . . . . . . . Drawing No.......... CNM1205.01 004 1 O System Af fected try f ailure...NNC Amillary Feedwater W f:llurs Description Narrative..... Engineering Codes
- CHICK VALVI , FOR AurlLIART f ttDWAf tR TEMPERING FLOW TO SitAM CtWERATOR 1C N0Z2LE , WAS NOT FULLY OPENING . OlsCOVERED DURikG ROUTINE REVitW 0F A.fype................ Check OPERATOR AfD COMuUTER DATA . CONDONENT FUNCTION DECRADED . LOW 8. FLOWOperator............ None THROUGH CHECK VALVE DECRADED ST$ TEM ftMPtRING FLOW TO STEAMC.Fmet CtWERATORt on/A@lication One.Way Flow 1C . INERE WA$ NO EFFECT ON PLANT OPERAfl0N . D.Sody kateriet....... Carbon Steel E. Body Manufactu-Ing M forged Cause $t Falture Narrative.....
F Nceinal inlet lite ( 2 to 3.99 IN fatalD P1h IN DISC ASSEM8LY TO BE LEOSE , PLACING DISC IN A MICHANICAL G.$lse (Intet)........ 2.000 IN l BlWD . CAust OF PIN tt!NG Loost COULD NOT BE DETERMENED . N. Design Pressure..... 1385.000 P81G J. Design feaperature.. 600.000 DEGF Corrective Actitn Warrative..... ( REPLActD DISC A$$tM8LY AND SPRING , LAPPED VALVE $1Af , AND $tAL WELDED % Time Operating When Reactor is Cri ) SONNET TO 80DT . RtfURNED VALVE T0 stRVICE PERFORMED visual 2 flee Operating When Reactor is shutdow1.. 100%- IN$PECil0N DURikG NORMAL $Y$ftM OPERATION . PRF 7355 ( EGL ) Noura Cut festing Perforsted frequency / Period of Service Check Testing 0 / Not Done 0.0 Functional festing 0 / Not Done 0.0 Cattbration 'esting 0 / hot Done
.................................................................................................................. 0.0 .......
,..,y - - - -- -r
A-42 WESTINGHOUSE CIASS 3 i b f% b) i ACCEPTANCE Daft: 11/01/88 Ut i t i t y. . . . . . . . . . . . . . . . . . . . . .Dd e Power Conpany Unit......................... CATAWBA 1 NS$ $ . . . . . . . . . . . . . . . . . . . . . . . . .Wes t i nghous e Application......... Component.................... VALVE f unc t i on. . . . . . . . . . . . Ut i l i t y Copponent Id. . . . . . . . .CACK0192 S ys t ee. . . . . . . . . . . . . . Aua i l i ary f eedwa t er
- W St:rt 0:te...... 03/18/87 Utility System...... CA S t:r t T ise. . . . . . 08 D0 Out of.$ervice Hours... 6244 Discovery Date.. 03/18/87 Data $ tart Date. 06/29/8% In service Date..... 01/07/85 Restoration Hours...... 6244 Accepted Dete... 02/12/85 Out of service Date..
E nd Da t3. . . . . . . . 12/03/87 End T ime. . . . . . . . 12:15 $sfety Cissa.......
- 2 Report Dete.....10/11/88 f rout Date......10/12/88 Systee status................t Mode................ Orwrsting
- TralrVChannet in service (OPC/$$C)
Sever i t y L eve l . . . . . . . . . . . . . . . J
- I mened l a t e Internal (tw........ Condensate / Nigh Purity Weter fel turo Synptos..............D
- Atriornal Character ist ic Externet Env........ Air F a i lure Mode . . . . . . . . . . . . . . . . . F0
- F a i l ed t o open F
Anblent Temperature +10F to e120F De t ec t i on. . . . . . . . . . . . A
- Opera t i ona l Abnorse l i t y
( ,Jategory...............K
- Unkroat $ w ller............
* $ w ller Id.........
Cause Description............AD . Nor1mnl/Abnorset Wear Systes E f fect.. ..............D Degraded Train / Channel Manufacturer........ Rerotest Mfg Corp Mfr Model Id........ Plant Effect.................G Resulted in No $lenificant Effect Mfr Model No........ CN 1500 2206J 505 Corrective Action............AN
- RepitCe Part(s) Mfr Serial No.......
Document a t i on. . . . . . . . . . . . . . . .!
- N one of the Above Mir $tandard........
LE R R epor t Ntacer. . . . . . . . . . . . Drawing No.......... CNM1205.01 004 1 System Af fected by failure...HNC
- Auxillary Fsedwater.W Falture Description Narrative.....
Engineering Codes
- C"*;CK VALVE ( CACK0192 ) , FOR STEAM CENERATOR 10 MAIN FEEDWATER
. TEMPER!hG FLOW . WAS STUCK IN THE CLOS [D PO$lTION . OlSCOVERED BY A . T wo . . . . . . . . . . . . . . . . Check OPERAfl0NS PERSONNEL WHILE PERFORMING NORMAL ST$ TEM OPERATIONS . ONLY 8.0perator............ Norw CINOR EFFECT ON $YSTEM AND N0 (FFECT ON PLANT . C.FunctiorVApplication one Way Flow D. Body Material....... Carbon Steel i cause af failure Narrative..... E. Body Marufacturing M Forged VALVE SEAT AND DISC WERE DAMAGED . ACTUAL CAUSE OF DAMAGE WASF.kaninal NOT Intet $1:e ( 2 to 3.99 IN OtttRM!NED .
G.$lte (Intet)........ 2.000 IN N.Desten Pressure..... 1385.000 PSIG Corrective Action Narrative..... J. Design Temperature., 600.000 DEGF LAPPED VILVE SEAT AND REPLAct0 DISC . PERFORMED FUNCTIONAL TE$f AND RETURNED YALV! 10 SERVICE , ( OPS 24088 ) ( EGL ) % Time Operating When Reactor is critical..100%
% Time Operating When Reactor is Shutdossi..100%
j< 3 Nours Out I ( Testing Performed Frequency / Period of Service Check Testing 0 / Not Done 0.0 Functional testing 0 / Not Done 0.0
'- a ;-s-Calibration testing 0 / Not Dor
- 0.0 -
l eJ O 4 9 0 9 l l l l l t (' O
A 44 i WESTINGHOUSE CIASS 3 : uclear Plant 8:llability 0:t3 System , General Report ! FN fciph L. Ikeiter, Jr. Report.lds hPEG00M t htlighouseElectrisCorporation (d Job Wumber 9334 Run Dates (xt/30/92 Run flee 15:50-
-I
, ~lntradactlent the etteched report wee ponerated by your query of the WPeps date bene. ' A usumery of your gJery le listed below. eutRT:-
. You eslected the following search condition (s):
letected Cenpanent le VALVE 8 lected VALVE fype is Check l Selected Unit 10 le SteuofAN 2. letected Systems are Auxtllery feedwater*U and Condersete W [ Find Util(ty Component ids that are egast to any one of the l foitowirg BAV00017186 and 30V00017139 ,. 6 elected Natuf acturere are Welworth Co end forwey Corp There ware 3 records meeting the search condition (s). c( ' AND $0Ris ! You sitectod to rwi poneret report 5: i temponent Master f ailure Report (w/ Unit Informetton) L You chose to sort the report byl sort segJonce Fletd base . NPR005AA hucteer Plant Rollebility Date system
- Tellure Master Report Run Dete 06/30/92-Job htsber 9334 ACCEPTANCE DATE: 05/25/89
! 'Ut i l'I ty. . . . . . . . . . . . . . . . . . . . . .T emes see Ye t t ey Author i ty -
- Unit.........................$E0VOTAN 2 MS$$......................... Westinghouse ApptIcetion......... .;
-Camponent.................... VALVE function.........'... i
- Utility Component Id.........BAV00017186 Syst em. . . . . . . . . . . . . . Aun t t l ery F eedwater*W 7
start cate...... 10/01/84 ~ Utility system..... 003
- Start time...... 09:00- . Out of alervice' Nours...1873 Date Start Date. 06/01/82 In/ service Date..... 06/01/82 ~f D ry Date..10/11/84 Restoration Nours...... 1642 Accepted Date... 01/24/85- Out of service Date..
E e'........ 12/18/84 -L pE me.....'.. . 10:00' . tefety Ctess........ SR I l' Report Date..... 03/12/85-Irput Date...... 01/21/86 Mode. . . . . . . . . . . . . . . . S t an*y Condi t ion , Sys t ee S t'a t us . . . . . . . . . . . . . . . . F a frein/ Channel in Test. *
* * - -r-wke - w m vvr we '-m,w --r-wewzv-.--&,r.+n-+-tee ~ rw v ,- .e- = m- e r r.%- - - - - r w w- r, y e -,-e r Y -t
* *w--- - r--
- WESTINGHOUSE CLASS 3 A-45 over i t y L eve l . . . . . . . . . . . . . . .K Degraded Int ernet Env. . . . . . . .
a f l ue) Sywpt om. . . . . . . . . . . . . .B
- Out of Spec i f icat i on External Env........ High Heldity
': a l t v*
- rode . . . . . . . . . . . . . . . . . F 0
- F a i l ed t o Open Ant > lent Tegerature *1DF to +120F
*i1 Jet ec tion............C Survelltance Testing Supplier............ Waitional Velve & Mfg to 43 Category...............) + Maintenance / Testing Suppl ler Id...... .. 2.vLv.M3 0861 5 5 Jte Descr iption. . . . . . . . . . . .BE
- Di rty Manuf acture. .. . . .. .. Welw% Co Id....... 5350 fnteo E f f ect... ..... ... .... .C
- Loss of One or More Traln/ Channel f uncticAf r Model tine Ef f ect.................G
- Resulteo in No Significant Ef f ect Mf r wonel No. . . . . . . 5350WE
- cerec t i n Act i cn. . . . . . . . . . . . AG
- R epai r Component /Part Mfr Serlet ho.......
'ocment a t i on. . . . . . . . . . . . . . 2 N one o f the Above Mfr Standard........
.E R R epor t k Jtt>er . . . . . . . . . . . . Drawing No......... 67WS03 2
;ystem Af f ected by Falture...HMC - Auxillary Feedwater.W allure 0:scription Narrative..... Engineering Codes CILE THE UNil WAS IN A REFUELING OUTAGE AWD DURING PERFORMANCE OF IURVEILLANCE INSTRUCTION $1 166 . 2 , A t.0U FLOW WAS EXPERIENCED ON THE A. Type..,............. Check 4AIN AND AUX'LI ARY FEEDWATER PUMP DISCHARGE Chiu VALyt . B operator............ Nr.ne C.Fmetton/ Application Ow.Way Flow tus2 of Failure Narrative..... D. Body Material....... Carbon Steel '
/ALVE WOULD NOT FULLY OPEN BECAUb! !) WAS DIRTT . E. Body Manufacturing M Cast F. Nominal Intet Sl e ( 4 to 11.99 lu
;orr:ctive Action Narrative..... G. Size (Inlet)........ 4.000 IN REMOVED VALVE BC4JNET AND CLEANED INTERNALS , FUNCTIONALLT TESTED PER St H. Design Pressure..... 1085.000 PSIG 166 . 2 AND RETURNED TO NORMAL SERvirE , MR A 290127 J. Design Tewsrature.. 600.000 DEGF
% Time Operating When Reactor is Critical... 51
% Time Operating When Reactor le Shutdown... 51 Hours out
- "'"'.'::'::"' ':'*""""::!' :'.':::!': O Cheet Testing 3 / Day 0,.0 functional Testing i / Quarter 0.0 Calibration Testing- 0 / Not Done , 0.0 O
l l
WESTINGHOUSE CIASS 3 A-4 6 (N L ACCEPTANCE DATE: 04/16/91 .. Utility...................... Tennessee Valley Authority Unit.........................SEQUDYAN 2 KSSS...... ................ Westinghouse Application......... Cospar* 1 ............ VALVE F metlon............ U; e C9.e Id. . . . . . . . .SDv00017139 Syst aa. . . . . . . . . . . . . . Condensa t e W Sy 4te.. 10/11/90 Utility System..... 002 ST rt flw. . 12:00 Out.of Service Hours... 671 Data Start Date. 06/01/82 In tervice Date..... 06/01/82 Discsvery Date.. 11/08/90 Restoration Hours......11 Accepted Date... 01/24/8! O,rt of. Service Date.. End D:ta........ 11/08/90 End Time........ 11:00 Safety Class....... 4 Report Date..... 11/27/90 input Date...... 12/12/90 Mode................ Operating System Status......... ......E . Train /Channet in Service (OPC/SBC) SIveri ty Level . . . . . . . . . . . . . . .K . Degraded I nt erne t E nv. . . . . . . . Fa i lure Sept em. . . . . . . . . . . . . .C . Denmd F aul t External Env........ Aablent Tenperature .10F to +120F Falture Mooe.................F0 . Failed to open -Temperature / Nualdity (Not Cntrid) Failure Detection............A . Operational Abnormality SuppLler............ National Valve & Mf g Co Cause Ca t egory. . . . . . . . . . . . . . .K . Unkruun Su m lier Id........ 2.VLV.002 0604 Caus2 Description........... 88 . Mechanical Damage / Binding Manuf acturer........ Terway Corp Sy tem E f f ect..... . .. .. . .. .. .C . Loss of one or More Tral VChannet f uncticMf r Model Id.. ...... Plant Effect.................G . Resulted in to Significant Effect Mfr Model No....... 5301 Corrective Action............AH . Replace Part(s) Mfr Serial No....... Document a t i on. . . . . . . . . . . . . . . . Z . None o f the Above Mfr Standard........ LER R:purt Number............ Drawing No... ... . . . 4NS04 1 System Affected by Failure...NHE . Condensate.V Failure Description Narrative..... Engineering Codes
'DURIZG UNIT 2 CYCLE 4 REFUELING CUTAGE , OPERATIONS ATTEMPTED TO OPEN THE CONDENSATE E00 STER PUMP DISCHARGE CHECK VALVE BY OPERATING ITS A. Type................ Check PILOT VALVE AND FOUND THE VALVE TO BE STUCK CLOSED , THE VALVE WAS B. Operator............ None BEIMERATED BY THE PILOT VALVE . THE PLANT WAS NOT AFFECTED BUT THE
/ \
C. Function / Application One.Way flow TE \$ LOST . D. Body Materi al.... . . . Chrbon Steet E. Body Manuf acturing M Cast Cause of Failure Narrative. .. F. Nominal Intet Site ( 12 to 19.99 IN tHE CAUSE FOR THE PILOT VALVE ( PIECE PART ) TO BE STUCK CLOSED IS G. Site (Intet)........ 14.000 IN
A-47 WESTINGHOUSE CLASS 3 '. UNr. MOWN . N.D: Sign Pressues..... 0.000 PstG J.Deslon Teaperature.. 0.000 DEGF-Corrective Action Norrative..... kE O *D VALVE , Ct,EANED , IksfAl, LED NEW BodNET GASKET AND NEW pilot % fine operating When Reactor is Critical.. 100%
% Ilme Operating When Reactor is Shutdown... 0%
VAL IECE PART of THE VALVE . Pltf 0RMED POST MlWTEkANCE TEST AND RETURNED TO $ERVICE ( WR C04$D86 ) 2 YLV Oo2 0604 Hours Cast Testing Performed Frequency / Period of Service Check Testing 3 / Day 0.0 f a tional Testing 0 / Not Done 0.0 calibration festing 0 / Wot Done 0.0 O 9
b- .. 1 WESTINGHOUSE CLASS 3
' f al ture Symptom. . . . . . . . . . . . . . F
- Cont ained Lc:kage . Secondary.Coottest or Treated Wat:r
-/alture Mode.................
- External Env........ Ad> lent Temperature 10F to +120F
" F al t ure Det ec t ion. . . . . . .'. . . . . N t Rout ine Observa t i on insulated-
'C ategory...............K
- Unknown Sgptier............
teceiption............ AD a Normat/ Abnormal Wear Supptler Id.........
.S Effect................E
- Systen F metton/ Operation Unaffected Manufacturer........ Crane Co Plant Ef fect.................G
- Resulted in No Significaat Ef fect Mfr Model Id....... 123-Corrective Action............ AH
- Replace Part(s) Mfr Model No....... 123 A Docmentat i on. . . . . . . . . . . . . . . .Z - hone of the Above Mf r Seriet No.......
LER Report N a ber............ Mfr Standard........ System Affected by Falture...WBB
- Component Cooling Water.sw Drawing No. . ... .. . . . CH 245 287 Failure Description Narrative.....
' VALVE 2CC 11 , COMPONENT C001,1NG PUMP 82Ae DISC H , CHECK VALVE , 18 Engineering Codes
- LEAKING PAST ITS SEAT .
A. Type................ Check
- Cause af Failure Narrative..... B.0perator............ None-DAMAGED DISC . C. Function / Application One Way Flow-D. Body Material....... Carbon Steel Corrective Action Warrative..... E. Body Manufacturing M Cast
; REPLACED DISC , NINGE PlWS AND HINCE PIN CASKETS . F. Nominal Inlet Site ( 4 to 11.99 IN G.51:e (Intet)........- 4.000 IN H. Design Pressure..... 150.000 PSIG J. Design Temperature.. 225.000 DEGF
% Time operating When Reactor la criticat.. 100%
1 flee operating When Reactor is Shutdown..1005 Nours out. Testing Performed. Frepency/ Period- of Service Check Testing 1 / Annust 0.0 j Functional Testing 0 / Not Done 0.0 l Calibration Testing 0 / Not Done- 0.0 -j l ..................................................................................................................................... ; l l- ACCEPTANCE DATE: 08/23/89 l Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .Duk e Po.eer Company
. Unit........................ 0CONEE 2
.NSSS......................... Babcock & Wilcox Application.........
Component.................... VALVE F met i on. . . . . . . . . . . . Utility Ccaponent Id........ 2CC 11 Sys t em. . . . . . . . . . . . . . Component Cool i ng Water BW j Start Date...... 06/21/89 utility System...... CC'
-Stirt Time...... 20:50 cut of Service Hours...'.118 Data Start Date. 09/09/74 In Service Date..... 09/09/74 -
Discovery Date.. 06/21/89 Restoration Hours...... 118 Accepted Date.... Out of service Data.. . j l End Date. . .. . . . . 06/26/89
= End T ime. . . . . . . . 18:00 Safety Class....... 4-Report Date..... 08/14/89 trput Date...... 08/21/89 Mode................ Operating.
' System Status................E Train /Chamel in Service (OPC/SSC)
S: verity Levet...............J - Immediate Internet Env........ Ast> lent Temperature Over *180F L Fallurs Symptom. . . . .. . .. .... .C
- Demand Fault -Secondary coolant or Treated Water
'fatture Mode.................F0 Failed to Open External Env........ Ambient Temperature .10F to +120F Failure Detection............A - Operaticut Abnormality Insulated
- Cat.st Category. . . . . . . . . . . . . . . F - Mai ntenance/ Test Ing Supplier............
Caus1 D:scriptinn............AM
- Previous Repatr/ Installation Status Supplier Id.........
'S[ \ Effect................C - Loss of one or More irsin/ Channel FunctioManufacturer........ Crane to Pk f f ect. . .... . .. . . . .. . . .G Resulted in No Signi f icant Ef f ect Mfr Modet'Id....... 123
, Corrective Action....... ..... AG - Repair Ceeponent/Part M i r Mode l N o. . . . . . . 123- A . , Docurentat i on. . . . . . . . . . . . . . . .Z
- None of the Above - Mfr Serial No.......
~ LER Report Nuft)er.. . . . . . . . . . . Mi r St ardard.. . . . . . .
l 1 J
^~
WESTINGHOUSE CLASS 3 System Affected by failure..,WBs Conponent Cooling Wster 8W Drawing No. . . . . . . . . . Cet 245 257 Failure Description Warrative..... 2CC 11 IS THE DISCNARGE CHECK VALVE ON COMPONENT FOOLlWG PUMP '2A' . Engineering Ccdes TH VE LOULD NOT OPEN AND ALLOW FLOW THROJCH THE VALVE . WHEN THE PUMP WAS ST ARTED DISCHARGE PRESSURE ON THE PUMP WENT TO 140 PSI BUT wo A. Type................ Check FLOW WAS PA15ED THROUGH THE VALVE . B. operator............ None C. Function / Application one Way Flcw Ccusa of Failure Narrative..... D. Body Material....... Carbon Steet THE VALVE MAD BEEN ASSEMBLED INCORRECTLT . A PREVENTAflVE MAlWTENANCE E. Body Manufacturing M Cast LORK REQUEST WAS USED 10 REB'JtLD VALVE . WHEN VALVE WAS REASSEMBLED , F. Nominal inlet Slee ( 4 to 11.99 IN TIE DISC VASN'T FROPERLT ALIGNED Wl1H SEAT . WHEN TkE INLET SIDE OF ThE G. Site (Inlet)........ 4.000 IN VALVE BODY WAS 10Rt.1XD TO THE OULET SIDE OF THE VALVE BOOT , M. Design Pressure..... 150.000 PSIG MISALIGNMENT CAUSED THE DISC TO BIND AGAINST THE SEAT Ak0 PREVENTED THE J. Design Teenperature.. 225.000 DECF VALVE FROM OPENING . 1 Time Operating When Reactor is Critical.. 100% Corrective Action Narrative..... % Time operating When Reactor is shutdown.. 100% VALVE FLANCE BOLTS WERE REMOVED . TH15 RELEASED THE BINDING OF DISC AGAINST THE SEAT . A PIELE OF PlPING ON THE INLET SIDE OF VALVE WAS Hours Out REr.3VED So DISC CCULD BE HELD IN PROPER AllCNMNET WHILE VALVE HALVES ( Testing Performed frequency / Period of Service itLET / CUTLET ) WERE TORQUED TOCETHER . AFTER THis WAS C04PLETED AND " - " " " - " " " " " * " " - - " - - " " - - MOVEMENT OF DISC VERIFIED , THE INLET PIPING WAS TORQUED BACK INTO Check Testing i / Annust 0.0 PLACE . F metional Testing 0 / Not Done 0.0 calibration Testing 0 / Not Done 0.0 0 I O
WESTINGHOUSE CIASS 3 uclesr Plant R3tlebility Dsta lystem Generet acport Fort Rstph L. Hmter, Jr. Report Id: NPPG00AA Job kuter: 9345 GtstinghouseElectricCorporation Run Date: 06/30/92 R m times 16:08 Introdxt iont The cttached report was generated by your query of the NPRDS date base. A summary of your query is listed belou. QUERY: You s3lected the following search cordition(s): Selected Conponent is VALVE Selected VALVE Type is Check Selected Unit 10 is BRUNSWICK 1 Selected Systems are Reector Core isotation Cooling CE, SL5pression Poot Support CE, ard High Pressure Coolant Injection GE . Find Utility Ccaponent ids that are equel to any one of the following: E41 F076 E41 F077 E51 F063, and E51 F064 Selected Marmif acturer is Velan inc There were 6 records meeting the search condition (s). ( DISPLAY AND SORT: You satected to run general report 5: Caponent Master Failure Report (w/ Unit Information) You chose to sort the report by: Sort Sequence Field Name CPRG05AA Nuclear Plant Rettability Date System - Failure Master Report Run Date: 06/30/92 Job Ntseer: 9345 ACCEPTANCE DATE: 12/03/90 Ut ili ty . . . . . . . . . . . . . . . . . . . . . . Carol ine Power & Light Ccupony Uni t . . . . . . . . . . . . . . . . . . . . . . . . . BRUN SWI C3: 1 ES$3......................... General Electric Application......... Component.................... VALVE Function............ Ut i l i t y Conpanent I d. . . . . . . . . E41 - F 076 System......... .. ... High Pressure Coolant Injection-CE t- D at e . . . . . . 09/17/90 Utility System..... 1E41 k g il me...... 12:00 Out-of-Service Hours... 439 Data Start Date. 04/01/77 In-service Date..... 03/18/77 Discovery Date..10/01/90 R estorat i on Hours. . . . . . 115 Accepted Date.... Out-of Service Date.. Erd Da t e. . . . . . . 10/05/90 l End Time........ 19:00 Safety Class....... 2
WESTINGHOUSE CIASS 3 Report Dzte..... 11/09/90 t rput Date. . . . . . 11/10/90 Mode................ Opercting System Status............... 5
- System in Test Sever i ty L eve l . . . . . . . . . . . . . . .K Deg raded I nternal Env. . . . . . . .
Fal' e Sywptom.. . . ..... . . . . .B Out of Speci f icat ion External Env........ Tenperature / Humidity (Cntrid) Fa. s Mode.................F0
- Failed to Cpen Anblent Tenperature 10F to +12 Falture Detection............C - Survelt tance Testing S@pl i e r . . . . . . . . . . . . Uni t ed E ng rs & Cons t ru:t or s I nc Caus) Ca t egory. . . . . . . . . . . . . . .K Unknown Sw ptier Id........ 1E41*F076 Cause Description. . .. ... .. ...BE
- Dirty Manufacturer........ Velan inc BG Corrosion Mfr Model Id....... 20348 System Ef f ect...... ..........E System Fmet ton /Operat ion Unaf f ected Mfr Model No........ WS 2348 2TS Plant Ef fect.................G . Resulted in No $lgnificant Ef fect Mir Serial Lo.......
C:rrec t i ve Ac t i on. . . . . . . . . . . . AG
- Repa i r Conponent / Par t Mfr Standard........
Docunent a t i on. . . . . . . . . . . . . . . .Z - None of the Above Drawing No. . . . ... . . . FP 9527 6409 LER R epor t Nuu5er. . . . . . . . . . . . System Affected by Failure...SFC High Pressure Coolant Injection CE Engineering Codes Fciture Description Narrative..... DUtttG PERIODIC TESTING . THE WlGH PRESSURE COOLANT INJECTloN VACUJM A. Type................ Check BREAKER LINE CHECK VALVE ( 1 E41 F076 ) WOULD NOT OPEN AT THE SPECIFIED B. Operator............ None PRESSURE OF 1. $ PGJWDS PER SouARE INCH , UNIT 1 WAS AT 0 PERCENT C.Furiction/ Application VectaJa Relief Poutt ON DISCOVERY DATE . D. Body Material....... Carbon Steet E. Body Manufacturing M forged Causs cf Failure Narrative..... F.Nominat Inlet Site ( 2 to 3.99 IN THE FAILURE WAS DUE To SLIGHT SCALE BUILDUP ON THE VALVE INTERNALS G.$lte (Inlet)........ 2.000*lWCH WHICH CAUSED THE VALVE TO STICK . THE ROOT CAUSE OF THE FAILURE WAS H. Design Pressure..... 600.000 PSIG - UNKNouN , THE FAILURE RESULTED IN NO EFFECT ON THE STSTEM OR PLANT J. Design Tenperature.. 310.000 DEGF CPERATION . 1 Time operating When Reactor is criticat..100% Cterective Action Narrative..... 1 Time Operating When Reactor is Shutdom..1001 THF 'VE INTERNALS WERE CLEANED AND INSPECTED . THE CASKET ( PIECE / PAk. JF THE VALVE ) VAS REPLACED LIKE IN KIND . THE VALVE WAS CHECKED Nours Out FOR FROPER OPERATION AND LEFT IN SATISFACTORY CONDITION . TAW 90 ARGM1 Testing Performed frequency / Period of service Check Testing 0 / Not Done 0.0 Functional Testing 1 / Month 0.0 calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 12/03/90 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . Carol i na Power & L i gh t Cenpany Unit........................ 8RUNSWICK 1 NSSS......................... General Electric Application......... Ceeponent.................... VALVE Function............ Ut i l i ty Cenponent I d. . . . . . . . .E41 F 077 System.............. High Pressure Coolant Injection-CE Stcrt Date...... 09/17/90 Utility System..... 1E41 St:rt time...... 12:00 Out of service Mours... 435 Data Start Date. 04/01/77 In-Service Date..... 03/18/77 Disecvery Date.. 10/01/90 Restoration Hours... .. .111 Accepted Date.... Out of service Date.. . Erd 0:te........ 10/05/90 End T i me . . . . . . . . 15 : 00 Safety Class....... 2 Report Date..... 11/09/90 i nput D a t e. . . . . . 11/10/90 Mode................ Operating Syst em Status. . . . . . . . . . . . . . . .B - Sys t em i n T est Sever i t y L evel . . . . . . . . . . . . . . .K - Degraded internal Env. . . . . . . . Falture Sprptom..............s Out of Specification External Env........ Temperature / Nualdity (Cntrld) Fa l t ure Mode. . . . . . . . . . . . . . . . . F0 - Fa iled to C1:en Ancient Tenperature 10F to +120F Failure Detection.. .. . .......C Survel t t ance Testing Si. cpl i e r . . . . . . . . . . . . Uni t ed Eng rs & Const ruc t ors I nc Ce 's t egory. . . . . . . . . . . . . . .K - Unknown Suppt ler Id. . . . . . . . 1E41- F077 1 Cruw Descr i pt i on. . . . . . . . . . 8E - D i r t y Manufacturer........ Velan inc 3G - Corrosion Mfr Model Id....... 20348 Syst em E f f ect . . . . . ........E - System function / Operation Unaffected Mf r Model No. .. . .. . . W8 2348 2Ts Pttnt Effect.............. ..G - Resulted in No significant Effect Mfr Serial No. ... .
. ~~~ ~ .~ . . - . . ~ . , - - . ,
k A-52'- WESTINGHOUSE CLASS- , Ctrrective Action....,.'......AG
- Repelr Component /Part ' Mir Stend2rd........
J Document at ion. . . . . . .. . . . . . . . .!
- kone of the Above Drawing No.......... FP 9527 6409-LER Report Ntmeier. . . . . . . . . . . .
P M Affected by failure...SFCi
- Migh Pressure Coolant injection CE
( f Engineering Codes-lFl.areDescriptionNarrative......- DURING PER100!C TESTING , THE NIGN PRESSURE COOLAN' INJECTION VACUUM A. Type................ Check
- BREAKER LINE CHECK VALVE ( 1 E41*F077 ) WOULD NOT OPEN AT THE SPECIFIED B.0perator............ Wone' PRESSURE OF 1. 5 POUNDS PER SQUARE INCH . UNIT 1 LS AT 0 PERCENT C.Fmet t on/Applicatlan Vacutan Rollef
- POWER ON DISCOVERT DATE . D. Body Materiet........ Carbon Steel E. Body Manuf acturing M Forged Cause of Falture Narrative..... F. Nominal Intet Site ( 2 to 3.99 IN
- THE FAILUR! WAS DUE To SLIGHT SCALE BUILDUP ON THE VALVE INTERNALS - G. Site (intet)........ 2.0t?O IWCN WHICH CAUSED THE VALVE 70 STICK . THE ROOT CAUSE OF THE FAILURE WAS H. Design Pressure..... 600.000 PSIG UNKNOW . THE FAILURE RESULTED IN NO EFFECT ON THE STSTEM OR PLANT J. Design Temperature.. 310.000 DEGF -
OPERAfl0N ,
% Time Operating When Reactor is Critical..100%
Ccerective Action Narrative..... % Time Operating When Reactor is Shutdown.. 100%- TME VALVE INTERNALS WERE CLEANED AND INSPECTED . THE CASKET ( PIECE / PARTS OF THE VALVE ) WAS REPLACED LIKE INCIND . THE VALVE WAS CHECKED Nours Out-FOR PROPER OPERAfl0N AND LEFT IN SAflSFACTORT CONDITION . TAW 90 ARCP1 Testing Perforand Frequency / Period of Service . Check Testing 0 / Not Done 0.0
' Fmettonal Testing i / Month = 0.0 Calibration Testing 0 / Not Done 0.0 -
ACCEPTANCE DATE: 03/29/91 _ Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . Carol ina Powe r & L i gh t Cospany [
...................... BRUNSWICK 1 '
l- ...................... General Electric Appticatlon......... l~ C t.................... VALVE ' Function............ l- ' Utility component Id.........E51 F063 System.............. Reactor Core Isolation Cooling GE Stcrt Date...... 09/22/90 - Utility System..... 1E51 Sttrt Time...... 12:00 Out of service hours... 2093 Data Start Date. 04/01/77 in Service Date..... 03/18/770 Disecvery Date..10/06/90 Restoration Hours...... 1769 Accepted Date.... Out of Service Date.. End Data. . . . . . . 12/18/90 End Time........ 17:00 Safety Class....... 2 Report Date..... 12/28/90 input D a t e. . . . . . 12/29/90 Mode . . . . . . . . . . . . . . . . S t ancR>y cond i t i on System Status..... . . . .... ....F Train /Channet in Test l $1 veri ty Level . . . . . . . . . . . . . . .K - Degraded = Internal Env.'....... Secondary Coolant'or Treated deter. Failure Symptom. . .. .. . . . .....B . Out of Speci f ication External Env........ Teeperature / Hualdity (Cntrid) . Falture Mode................ 0R
- Fall to operate as Required Ambient Temperature .10F to +120F Failure Detection............C . Survelltance Testing Supplier............ United Enges & Constructors Inc Causa Category...............K . Unknown Supplier Id........ 1E51 F063 Causs Description........... 3E
- Dirty Manufacturer........ Velen inc System Effect................e Degraded System Operation Mfr Model Id....... 2034B Plant Ef f ect. . . ... . . . .. .. . . . .G - Resulted in No Signif icant E f f ect Mfr Model No........ WB 2348 2TS Cerrective Action... .. ..... .. AN - Replace Part(s) Mfr Serial No.......
Documentat ion. . . . . . . . . . . . . . . .Z - None of the Above Mfr Standard........ LER R epor t Nuvber. . . . . . . . . . . . Drawing No.. . . . .. ... FP 9527-6409 4 System Af fected by Falture...CEA - Reactor Core Isolation Cooling GE Failure Description Narrative..... Engineering Codes DURING PERIG)lc TESTING . THE REACTOP CORC ICOLATION CDOLING IURBINE l E[ 6 VACUUM BREAKER ( 1 E51.F063 ) WOULD NOT OPEN kt t . $ POUNDS A. Type................ Check P .ARE INCH GAUGE ( PSIG ) . THE VALVE DID OPEN AT 6 PSIG . UNIT 1 8. Operator............ Mech (Diff Press Open/Sprn l
.. WAS AT 0 PERCENT POWER ON DISCOVERY DATE . C. Function / Application One-Way Floc l
t D. Body Material....... Austenitic Stnts $tt Othe Cause of Failure Narrative..... E. Body Manufacturing M Forged l:
WESTINGHOUSE CLASS 3 THE FAILURE WAS SUSPECTED TO BE CNSED BT DIRTT VALVE I::TERIALS . THE F. Nominal Intet Slas ( 2 to 3.99 IN FAILURE RESULTED IN A DEGRADED SYSTEM WITH NO $1GNIFICANT PLANT EFFECT G Size (Intet)........ 2.000 INC-
- TWi$ YALVE Alt 0WS FOR VACLAJM REllEF OF THE TURBINE ExMAUST LINE 10 H. Design Pressure..... 1500.000 PS!G TME 10EUS A SLOW OPENING CREATES PRESSURE BUILDUP . HIGH TURBINE J. Design Tegerature.. 310.000 DEGF .
EU PRESSURE CAN TRIP THE TURBINE . THE ROOT CUASE OF THE FAILURC L'AS usiKNOWN . 1 Time Operating When Reactor is Critical... 0% 1 Time Operating When Reactor is Shutdoun... 01 Ccrrsctive Action Narrative..... THE VALVE INTERNALS ( PIECE / PARTS OF THE VALVE ) WERE CLEANED AND Nours Out ikSPECTED . THE SPRING ( PIECE / PART OF THE VALVE ) WAS REPLACED LIKE Testing Performed frequency / Period of Service
"""""""". """""""" ~~"""
IN EIND . 1HE VALVE WAS LEFT IN SATISFACTORY CONDITION . TAW 90 ARMW1 Check Testing 0 / Not Done 0.0 Functional Testing 1 / Month 0.0 calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 03/29/91 Utility...................... Carolina Power & Light Co m any Unit......................... BRUNSWICK 1 ESSS......................... General Electric Application......... Component.................... VALVE Fmetton............ Utility Co g onent Id.........E51.F064 System.............. Reactor Core Isolation Cooling GE Start Date...... 09/22/90 Utility Systas..... 1E51 Start Time...... 12:00 Out.of Service Hours... 20SS Data Start Date. 04/01/77 in. Service Date..... 03/18/77 Discsysry Date..10/06/90 Restoration Hours...... 1764 Accepted Date.... Out.of service Date.. End D at e . . . . . . . . 12/18/90 End T ime. . . . . . . . 12:00 Safety Class....... 2 Report Date.....12/28/90 Input Date...... 12/29/90 Mode................ Stan
- y condition Syst em S t a tus . . . . . . . . . . . . . . . . F . T r a i n/Ch anne t i n T e s t Sived ty Level . . . . . . . . . . . . . . .K . Degraded Internal Env........ Secondary Coolant or Treated Wat Fat Sygt om. . . . . . . . . . . . . .B Out of Spec i f i cat i on External Env........ Tegerature / Hualdity (Cntrid)
Failure Mode. . .. . . . . .. . . . . . . 0R . Fall to operate as Requi red Ambient Temerature .10F to +1207 fciture Detection............C . Surveltlance Testing Stwtier............ United Engrs & Constructors Inc Causa Cate9ery...............K . Unknown Supplier Id........ 1E51.F064 Causa Desc ri pt ion. . . . . . . . . . . .BE . D i r ty Manufacturer........ Velan Inc Syst em E f f ec t. . . . . . . . . . . . . . . .B . Degraded Syst em operat ion Mfr Model Id....... 20348 Plant E f f ect.. . .... . . .. . . .. ..G . Resulted in ho significant E f f ect Mfr Model No........ W8 2348 2TS Ctrrect i ve Act ion. . . . . . . . . . . . AG . R epa i r Corporwnt/Part Mfr Serial No....... Docurenta t i on. . . . . . . . . . . . . . . 2 . None of the Above Mfr Standard........ LER Report Nu,eer............ Drawing No.......... FP.95274409 9 System Affected by Failure...CEA . Reactor Core Isolation Cooling GE
- Fsiture Description Narrative..... Engineering Codes DURING PERICOIC TESTING , THE REACTOR CORE ISCLATION COOLING TUR81NE EXHAUST VACUUM BREAKER ( 1.E51.F064 ) WOULD NOT CPEN AT 1. 5 POUNDS A. Type................ Check PER SQUARE INCH GAUCE ( PSIG ) . THE VALVE DID CPEN AT 6 PSIG . UNIT 1 8.0perator............ Mech (Diff. Press Open/ Spen UAS AT 0 PERCENT POWER ON DISCOVERY DATE . C. Function /A;ptication One.Way Flow D. Body Material....... Austenttic Stnis Stt-Othe Caus3 of failure Narrative..... E. Body Manufacturing M Forged THE FAILURE WAS SUSPECTED TO BE CAUSED BY DIRTY VALVE INTERNALS . THE F.Neranat Inlet Size ( 2 to 3.99 IN FAILURE RESULTED IN A DEGRADED SYSTEM WITH NO $1GNIFICANT PLANT EFFECT G.slae (Intet)........ 2.000 INCH
. THIS VALVE ALLOWS FOR VACUUM RELIEF OF THE TURSINE EXHAUST LINE TO H. Design Pressure..... 1500.000 PSIG THE TORUS . A SLOW OPENING OF THE VALVE WILL CREATE HIGHER PRESSURE . J. Design Tegerature.. 310.000 DEGF THE TUR81NE WILL TRIP ON HIGH PRES $URE IN THE ExMAUST LINE . THE ROOT CAUSE OF THE FAILURE WAS UNKNOWN . % Time operating When Reactor is criticat... 0%
% Time Operating When Reactor is shutdown... 0%
Cor. Ive Action Narrative..... THE VALVE INTERNALS ( PIECE / PARTS OF THE VALVE ) WERE CLEANED AND Mours Out
!NSPECTED . THE VALVE WAS LEFT IN SATISFACTORY CONDITION . TAW 90 ARMU1 Testing Performed frequency / Period of Service j
................. ................ .......... 1
WESTINGHOUSE CLASS 3 z .t m ............................................................................................................................. g N ACCEPTANCE DATEt 01/31/90. Ut il i t y. . . . . . . . . . . . . . . . . . . . . .Carolins Power & L i ght Conpany Unit......................... BRUNSWICK-1 7555.............'............Ceneral Electric Application......... Conponent.................... VALVE function............ Ut il i ty conponent id. . . . . . . . 1 CAC X 20A System.............. Suppression Pool $@ port CE Start Date...... 08/02/89 utility System...... ICAC Start Time...... 12:00 Out of service Hours... 3312 Data Start Date. 04/01/77 In Service Date..... 03/18/77 Disemry Date.. 08/17/89 Restoration Hours... ... 2964 Accepted Date... 03/25/87 Out of service Date.. End Dets. . . . . . . . 12/18/89 End Time........ 12:00 Safety Class....... 2 Report Date..... 01/16/90 Input Date...... 01/16/90 Mode................ Stant y condition System Status. .. . .. . .. . .. . . ..F - T rain / Channel in Test
- $;ver i ty Level. . . . . . . . . . . . ...K - Degraded Internal Env........ Air Failure Symptom............. 8 Out of Specification External Env........ Tonperature / Hucidity (Cntrld)
F ailure Mode. . . . . . . . . . . . . . . . 0R - F all to Operate as Requi red Anblent Teterature -10F to +120F F ailure Detection. .. .. . ......C Surveillance Testing $@ plier............ United Engra & Constructors Irc Cause Cat egory. . . . . . . . . . . . . . .F - Maintenance /T est ing S @ plier Id........ 1CAC X 20A cause 0:scription............ AM - Previous Repair / Installation Status Manufacturer........ General Precision inc " System Ef f ect...... ..........D Degraded T rain / Channel Mfr Model Id........ Plant Ef f ect. ... .... ...... ...G Resulted in No Significant Ef f ect Mfr Model No........ DVG WO LD 240 193. Corrective Act ion. ... ... .... . AH . Replace Part(s) Mf r Serial No....... Docunentat ion. . . . . . . . . . . . . . . .Z None of the Above Mfr Standard........ O (
\
w LER Report Number. . . . . . . . . . . . Drawing ko.......... FP 6597 System Affected by Failure...SAA - $@pression Pool S@ port GE Failure Description Narrative..... Engineering Codes DURI%G MAINTENANCE TESTING , THE SUPPRES$10N PODL VACULM BREAIJiR CHECK VALVE ( 1 CAC X 20A ) DID NOT OPEN WITHIN TECHNICAL SPECIFICATIONS A. Type................ Check LIMITS . UNIT 1 WAS AT 100% POWER ON DISCOVERT DATE , R. Operator............ Manual C.Fmetion/ Application Vacuum Relief Caus2 of f ailure N6erative..... D. Body Material....... Austenitic Stnis Stl Othe THE FAILURE WAS DUE TO A STRIPPED MAGNET BOLT AND A BROKIN MAGNET ( E. Body Manufacturing M Forged P!ECE / PARTS of THE VALVE ) . THE FAILURE WAS DUE TO PREVIOUS F. Nominal Inlet Site ( 20 to 39.99 IN MAINTENAkCE , G. Size (Inlet)........ 20.000 IN H. Design Pressure..... 62.000 PSIG Ccrrective Action Narrative..... J. Design Tenperature.. 350.000 DEGF THE MAGNET AND THE BOLT WERE REPLACED LIKE IN KIND THE VALVE WAS TESTED AND LEFT IN SATISFACTORT CONDITION . TAW 89 AS$K1 % Time Uperating When Reactor is critical... 0%
% Time Operating When Reactor is shutdown... 0%
' Hours Out Testing Performed Frecuency/ Period of Service Check Testing 0 / Not Done 0.0 Fmettonal Testing 1 / Month 0.0 O Calibration Testing 0 / Not Done
.q).............................................................................................................................
0.0
WESTINGHOUSE CIASS-3 uclear Ptar.t Reliability Data System General Report f ort R:tph L. Hmter, Jr. Report Id NPRG00AA - stinghouse Electric Corporation - Job Nunter 9356 Run Date: 06/30/92 Run Tisae 16:26
Introductions
the Cttached report was generated by your query of the NPRDS data base. A sutmary of your query is listed below. QUERY: fcu colected the following search condition (s): Selected Cone: rent is VALVE S3tected VALVE Type is check S:lected Unit 10 la FARLEY 1 S;lected Systems are Main Feedwater Systee W and Conponent Cooting Water-W Find Utility Component ids that are eqJat to any ore of the following Q1P17V263A, 01P17V2638, and N1N21v504A Sitected Manufacturers are Anchor / Darling Valve Co and Kerotest Mfg Corp in:rs here 3 records meeting the search condition (s). DISPLAY AND SORT: e You satected to run general report 5: Corponent Master Failure Report (w/ Unit Information) You chost to sort the report by: 1 Sort ! Sequenee Fieid Name l l NPRGOSAA Nuclear Plant Reliability Data System Falture Nanter Report Rm Date: 06/30/92 Job Nuibert 9356 1 ACCEPTANCE DATE: 02/25/88 Jt ili ty. . . . . . . . . . . . . . . . . . . . . . Southern Nuc lear Operat i ng Conpany !Jnit.........................FARLEY1
~4SSS......................... Westinghouse Application.........
LOcaponent.................... VALVE Fmetion............ J t i l i t y Cr*ponent I d. . . . . . . . . N I N 21 V504 A Sys tem. . . .. .... . . .. . Main f eedwater System W Star
- Csta. . . . .. 12/15/87 Utility Systera...... CFW 2 Sta ime...... 12:00 Out-of Service Hours.. 108 Data Start Date.12/01/77 In-Service Date..... 12/01 Jiscevsry Gate..12/19/87 Restoration Hours...... 24 Accepted Date... 03/28/85 Out of Service Date.,
ind Octa. . . . . . . . 12/20/87 Ind Time........ 00:20 Safety Class....... 4
. . - . . ., ~ - . . - . . .
WESTINGHOUSE CLASS'3 - neport Date..... 01/11/88 _ - t rout Ost s. . . . . . 01/11/88 . .Modef............;.. Operstingi
' sys_ tee $tatus. . .. . .. . ... . . . . .E Train /Channe t in Service (OPC/$8C) --
~
. Seve ri ty L eve l . . . . . . . . . . . . . . . J
- I mmed i a t e ' ~ Internal Env........ Aelent Temperature Over +180F -
F Sympton. . . . . . . . . . . . . .C j Demand F aul t i Condensate / Nigh Purity Water: , f _ Mode.................F0.* Fai led to Open ~ Eaternal Env........ A2ient Temperature .107 to *120F
~ Fat uro Detection............A Operational Atriormality - Air-
'Cause Category...............K . Unknown'. - s@p t i e r . . . . . . . . . . . . Anchor / Da r l i ng va l ve to
- Caus) Description...........~.B8 Mechanicat Damage / Sinding -Supplier Id.........
- System E f f ect. . . . . . . . . . . . . . . .D '
- Degraded T ra in/ Channel ' Manuf acturer........ Anchor, / Darling Valve Co ,
Plant E f f ec t... . ... .~... .. ... .G
- Resulted in No $lgnificant E f f ect Mfr Mode l~1d........
-Corrective Action............AA - Recalibrate/ Adjust Mfr Model No....... 2211*3 Document at ion. . . . . . . . . . . . . . . .Z
- None of the Above Mfr serial No....... 2787 4 1.A LER Report Ni.suber............ Mfr standard........ ANsl 331.1 71 System Af f ected by f alture...HHF = Main feedwater System *W Drawing No.......... U160810.
Failure Description Narrative..... WITN UNIT STARTING UP AFTER SHORT MAINTENANCE OUTAGE ,'THE 2A MAlu Engineering Ccdes 1 FEEDWATER PLMP DISCHARGE CHECK VALVE WOULD NOT OPEN . A. Type... ............. Check Cause'of Falture Narrative..... B. Operator............ None-
-EXACT CAUSE FOR FAILURE WAS NOT DETERMikED . THE VALVE WAS MECHAhlCALLY C. Function / Application One Way Flou
- AGITATED AND EVENTUALLY OPENED . D. Body Materlat....... Carbon Steet.
E. Body Manufacturing M- Cast.- Corrective Action Narrative..... F.Ncuminal Intet $lte ( 12 to+19.99 IN. MECHANICALLY ACITATED VALVE . VEP!FIED FLOW THROUCK VALVE AND RETURNED G.$ ire (Intet)........ =18.000 IN. # VALVE TO SERVICE . M. Design Pressure..... 1700.000 PSIG> J. Design Tamperature.. 400.000 DECF 1 Time Operating When Reactor is Critical..[100% 1 Time Operating When Reector la shutdown... -$1--
'. Ql Hours Out -
Testing Performed- -Frequency / Period: of Service Check Testi_ng 0 / Not Done- 0.0 Functional Testing- 1 / Month- 0.0 , Calibration Testing _0 / Not Done. 0.0 ACCEPTANCE DATE: 07/06/84
' Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Southern Nuc l ear Ope ra t i ng Conpany Unit.........................FARLEY 1-CS$$......................... Westinghouse Appticatlon.........
'. C omponent . . . . . . . . . . . . . . . . . . . . VAL VE - Funetlon............
' Utility. conponent ld........ 01P17V263A Sys t em. . . . . . . . . . . . . . Component Coo t i ng Wat er W
$ tart 0:te...... 01/29/88 Ut il i ty Sys tem. . . . . .' CCW '
Stert Time...... 12:00 -Out+of servicr Hours.... 2217 Data Start Date. 12/01/771 In service Date.....12/01/77 l Dise:rt:ry Date.. 04/29/88 Restoration Hours...... 45 Acewt sa Date... 03/13/85 out of. service Date..
.End Oste........ 04/30/88 %End Time........ 20:58' safety Class........ 3 Report Date..... 05/26/88 trput Date...... 05/24/88 Mode................ Operating Sys tem Shtus . . . . . . . . . . . . . . . . F * = T ra i n/Channe t i n T es t ' Severi ty L eve t . . . . . . . . . . . . . . .K + Degraded _ Internal Env........ Ant > lent Temperatura 10F to +120F .. F al ture synptom. . . . . . . . . . . . . .C - Demand Faul t Air Fallore Mode.................F0
- Failed to Open External Env........ AMant Teaperature 10F to +120F j m
.rF s
Det ect i on. . . . . . . . . . . .C
- Survel t l ance Test ing -
- Cut.-. t egory. . . . . . . . . . . . . . .H Wea r Out .
Secondary Coolant or Treated Water . Supplier............ Kerotest M*g Corp
' Csuss Descript ion. .... .... .. 88 Mechanical Damage /ginding Suppl i er Id. . . . . . . . . - Sys t em E f f ec t . . . . . . . . . . . . . . . .D Degraded T rain /Channet Manufacturer........ terotest Mfg Corp Plant'Effect....... .........C - Resulted in No significant Ef f ect Mfr Modet Id.... ...
WESTINGHOUSE CLASS 3 A-57 C:rrec t iv) Ac t ion. . . . . . . . . . . . AM R eplcce Per t(s) ' Mfr Model tto........ AL.D.9914x015 fiocunent at ion. . . . . . . . . . . . . . . .Z
- None of the Above Mfr $erlat ho....... ME4*13 L E R R epor t Nuee r . . . . . . . . . . . . Mfr standard........ A1ME SEC 3 71 System Af fected by Falture...W90 - Cormonent Cooling Water W Drawing No.......... U258646 l
)
Felture Description Narrative..... WITN UNIT IN REFUELING OUTAGE , DURING SURVEILLANCE TE$flNG , FOUND THE Engineering Codes i COMPOWENT COOLING WATER SURGE TANK VACUUM BREAKER DID NOT OPEN AT 8 l PSIC AS REQUIRED . A. Type................ Check l B. Operator............ None l Cause cf Falture Narrative..... C. Function / Application one Wey Flow F0uk0 THE VALVE WAS BINDING ON ITS SEAT . CAU$E FOR FAILURE WAS D. Body Ma ter i al . . . . . . . Carbon Steet ATTRIBUTED TO WEAR AND ASING . E. Body Manufacturing M Cast F. Nominal inlet $lae ( 1/2 to 1.99 IN i C rrective Action Narrativt..... G.Stae (Inlet)........ 1.000 IN I REPLACED VALVE DISC ASSEMBLT , VTRIFIED PROPER OPERAfl0N , AND RETURNED H. Design Pressure..... 1250.000 PSIG VALVE TO $ERVICE . J. Design Tecperature.. 300.000 DEGF
% Time Operating When Reactor is f:ritical... 1% I
% Time Operating When Reactor is $hutdown... 11 Hours Out Testing Performed frequency / Period of Service Check Testing 1 / Month 0.0 F metional Testing 0 / Not Dane 0.0 Calibration Testing 0 / Not Done 0.0
.............................s...................................................................................................
ACCEPTANCE DATE: 07/06/88 Uti . . . . . . . . . . . . . . . . . . . . 5outhern Nuc t eer Opera t ing Capany Unit................... .....FARLEY 1 NSSS......................... Westinghouse Application......... Ca ponent.................... VALVE Tmc t i on. . . . . . . . . . . . Ut il l " / Caponent Id. . . . . . . . .Q1P17V2638 sys t un. . . . . . . . . . . . . . Corponent Cool i ng Wa t er-W start Dste...... 01/29/88 Utility system...... CCW 3 tart Time...... 12:00 out of service Hours... 2218 Data start Date. 12/01/77 In Service Date.....12/01/Tl Discov:ry Date.. 04/29/88 Restoration Hours. ..... 46 Accepted Date... 03/13/85 Out-of service Date.. End DIts. . . . . . . 04/30/88 End T ime. . . .. . . . 22:00 safety Ctess....... 3 Peport 0:te..... 05/24/88 Input Date... ... 05/24/88 Mode................ Operating tyttein Sta tus. . . . . . . . . . . . . . . . F - T ra in/Channe t in T est . Sever i ty Level . .. . . . . . . . . . . .K Degraded Internal Env........ Ambient Temperature 10F to +120F F e l l urs $ ymptom. . . . . . . . . . . . . . C D eer.and F aul t Secondary Cootant or Tre*ted Water F al t ure Mode. . . . . . . . . . . . . . . . . F0 - F a i l ed to Open Externet Env........ Ambient Tenperature 10F to +120F Fci ture Detection. ... ........C Surveillance Testing Air Causs C:tegory. . . . . . . . . . . . . . . N . Wear out s e tter............ Kerotest Mfg Corp Caus2 0:scription............B8 - Mechanicat Damage / Binding Supplier Id......... System E f f ec t . . . . . . . . . . . . . . . .D Degraded T rai n/Charriel Manufacturer........ Kerotest Mfg Corp r e ? Effect.................G - Resulted in No Significant Effect Mfr Model Id........ C rrcctive Action. . .. .... . . . . AN - Replace Part(s) Mf r Model No... ... .. AL-D-9914x015 Docunentat i on. . . . . . . . . . . . . . . . Z None of the Above Mfr Serial No....... LER Riport N m ber............ Mfr Standard........ ASME SEC-3-71 System Affected by Falture...WSD - Caponent Cooting Water W Drawing No.......... U258646 Fel'
- Description Narrative.....
' W11. elf IN REFUELING OUTA0! , DURING $URVEILLANCE TESTING , FOUND THE Engineering Codes COMPONENT C001,1NG WATER $URCE TANK VACUUM BREAKER DID NOT OPEN WITH 8 DSIG APPLIED AS REQUIRED . A. Type................ Check B. Operator............ None
'A-58 WESTINGHOUSE.CLASSJ.3 Cause gf Fallste Narrctive..... C. Function /Applic tion One W;y Flow TOUNO IME VALVE SEAT WAS BINDING . FAILURE WAS ATTRIBUTED TO WEAR AND 0. Body Material.'...... Carbon steel-LAGIEC , -E. Body Manufacturing M Cast g~g F.hominal Inlet Site ( -1/2 to 1.99 lW'.
)IveActionWarrative..... C. Site (Intet)........ 1.000 IN R,4. ZED VALVE DISC ASSEMBLY , VER! fled PROPER OPERATION., AND RETURNED H.0esign Pressure.'.... 1250.000 PSIG.
VAtVI TO SFRVICE . -J. Design teaperature.. 300.000 CECF
% ilme Operating When Reactor is critical... 1%
% Time Operating When Reactor is Shutdown... -it Hours Out Testing Performed FrequeNy/ Period of Service Check Testing. 1 / Month 0.0 Functional festing. 0 / Not Done 0.0 Calibration festing 0 / Not Done 0.0 i ,
\ '
/N s
WESTINGHOUSE CLASS 3 A-59 ucts r Plant R5llability 0;t System General Report for R:tph L. Hunter, Jr. Report Id NPRc00AA ' stinghouse Etectric Corporation Job Nuntaer 9363 Run Date: 06/30/92 Run Times 16:34 '
Introduction:
The citached report was generated by your query of the NPRDS data base. A su nary of your query is listed below. QUERY:
-You sitected the following search condition (s):
Selected Component is VALVE
- Silected VALVE Type la Check, Selected Unit ID is FARLEY 2 Selected Systema are Nuclear Service Water-W and Ce@onent Cooling Water W Find Utility Ccuponent ids that are equal to any one of the fonLowing: Q2P17V2638, C2P1N2638, and c2P16v602 Selected hanufacturer is Kerotest Mfg Corp Ther3 were 2 records meeting the search condition (s).
DISPLAY AND SORT: You selected to rm general report 5 Corponent Master Falture Report (w/ Unit Information)
' tou ch se to sort the report by:
Sort Sequence Fletd Name NPRGOSAA kuclear Plant Reliability Data System - Failure Master Report Rm Date: 06/30/?2 Job N & rs 9363 ACCEPTANCE DATE: 05/24/89 Ut i li ty. . . . . . . . . . . . . . . . . . . . . . Southern Nuc l ea r Operat ing Coapany j Unit.........................FARLEY 2 NS$1......................... Westinghouse A;ptication......... Cceponent . . . . . . . . . . . . . . . . . . . . VALVE Function............ l1.UtilityCcaponentId........02P16v602 System.............. Nuclear Service Water W l Sttrt 0:te...... 04/01/89 1 Utility System...... SU l Stsr- 'ime...... 12:00 out of. Service Hours... 400 Data Start Date. 07/30/81 In-service Date..... 07/3 I Dis. ry Date.. 04/12/89 Restoration Hours...... 148 Accepted Date... 03/26/85 Out of Service Date.. End D:te, . . . . . . . 04/18/89 End time. . . . . . . 04:49 Safety Class... ... 3 Report D:te..... 05/02/89 Input Date...... 05/02/89 Mode.......... ..... operating l
q
-WESTINGHOUSE CLASS'3
~
- $ys tem Status................E T raln/Channet in Strvica (OPC/SBC) -
Aaclent Tenperature 10F to +120F -
~
3everi ty Level . . . . . . . . . . . . . . .K Degraded - Internet Env........
=Falture 5)aptom..............C Demand Fault- . Fresh Water ( Well / River / Lake );
s FF* *3 Mode . . . . . . . . . . . . . . . . . F 0
- F a l l ed to Open External Env........ Amelent Temperature r10F = to +120F 4 Detection............A y Operational Abnormality Air
~
- C.,s. Cat egory. . . . . . . . . . . . . . . H Wea r out - Supplier............ Kerotest Mfg Corp
'Cause Description......'......BD Aging / Cyclic Fatlove. $@ptler Id.........
- System E f f ect....... . ... .... .D i Degraded T raln/ Channel Manufacturer........ Kerotest Mfg Corp J Plant Ef fect.................G _ Resulted in No significant Ef f et t Mfr Model Id...~..... -
Corrective Action............ AA RecsLibrate/ Adjust - M f r Model N o. . . . . . . . ALD9912x01
- Docusantati on. . . . . . . . . . . . . . . .! None of the Above -- Mfr Serial No....... CS6 9 L L E t R epor t No"ber. . . . . . . . . . . . Mfr Standard........ ASME SEC 3 71 1
" System Affected by falture... WAD . Nucteer $ervice Water-W Drawing No.......... U209359 Fr.iture Description Narrative.....
VIT11 UNIT IN REFUELING OUTAGE DURING ATTEMPT TO ORAIN SERVICE WATER , . Engineering Codes FOUND THE SERVICE WATER NEADER VACUUM BREAKER WAS STUCK CLOSED . A. Type................ 'Checkm 1Caus2 6f Falture Narrative..... B.Operstor............ None.-
. . FOUND THE. VACUUM BREAKER WAS BINDING ON ITS SEAT FAILURE WAS C.Fmetton/ Application One Way Flow
[ATTRIBUTEDTONORMALAGING. D. Body Materiet....... . Carbon Steet E. Body Manufacturing M Forged Cterective Action Narrative..... F. Nominal Intet Sl e ( ' 2 to 3.99 lu : FREED VALVE SEAT , VERIFIED PROPER OPERAflDN AND RETURNED VALVE To C. Size (Inlet)........~ 2.000 lu SERVICE . H. Design Pressure..... 1030.000 PSIG :- - J. Design Temperature... 650.000 DEGF
- 3
% Time operating When Reacte- le criticat.. 1001
~
% Time Operating When Reactor is Shutdown..100$ -
l Hours out...
- Testing Performed- . Frequency / Period ~ of service 7
=!
Check Testing 0 / Not Done 0.0 Fectional Testing 0 / Not Done .0.0- T Callbration Testing 0 / Not Done 0.0 l 4 ACCEPTANCE DATE: 06/06/89 Ut l l i t y. . . . . .'. . . . . . . . . . . . . . . . Southern Nuc l ear Opera t i ng Conpany
'Unlt....................,....FARLEY 2 ESSS . . . . . . . . . . . . . . . . . . . . . . . . .Wes t i nghouse Application.........
Ceaponent . . . . . . '. . . . . . . . . . . . . . VALVE F me t t on. . . . . . . . . . . .
' . utility Conponent Id........ 02P17V2438 : System. . . . . . . . . . . . . . Component Cooling Water W -
. Start Dste......~.03/27/89- Utility System...... CCW St:rt Time...... 12:00 Out-of service Hours... 780 Deta Start Date. 07/30/81 'In-service Date..... 07/30/81
- Discovery Date.. 04/27/89 Restoration Hours...... 48 Accepted Date... 03/26/85 Out of service Date..
End Dzts.. .... . . 04/29/89
- End Time..... . .. 00:54 -Safety Class........ 3 Eteport Date..... 05/15/89 Input Date...... 03/15/89 Mode...............a Operstlic -
. System Status.. . .. .. . ... . .. ..F - T raln/Channet in Test Sever i t y Leve l . . . . . . 4'. . . . . . . J levnedi a t e Internet Env........ Anblent Tenpesture 10F to +120F Fol lure $pptom. . . . . . . . . . . . . .C - Demand Fault Secondary Coclan er Treated Water :
- . F a l t ure Mode. . . . . . . . . . . . . . . . . F0 F a i l ed t o Open External Env,....... Aaclent Tenperature -10F to +120F Fal ture Detect i on. . . . . . . . . . . .C - Surve l t t ance T est ing Air ,
C'nf ategory...............H Wear Out $@ plier............ Kerotest Mfg Corp
- l[j asc r i pt i on. . . . . . . . . . . . AD Norma t /Abnorma t Wea r Supptler Id.........
~
BG Corrosion Manufacturer........ Kerotest Mfg Corp 88 Mechanical Demoge/ Binding Mfr Model Id........ > f Sys tem E f f ec t . . .. . . . . . . . . . . . .D Degraded T ral n/ Channel Mfr Model No........ AL D-9914X013-i
WESTINGHOUSE CLASS-3 , Plent E f f ect.... . ....... . ....G Result ed in to Significant E f f ect Mfr Serial No....... CN18 16 lr. Oorrsc t i ve Ac t i on. . . . . . . . . . . . AG Repa i r Cc:yenent/ Par t Mir Stan$ard........ ASME SEC 3 71 Document at i on. . . . . . . . . . . . . . . 2 None o f the Above Drawing No.......... U209351
. lek Report NJuber............ .
Syf Affected by falture...WBD Ccunponent Cooling Water W Engineering Codes fatture Description Narrative..... WITN UNIT IN REFUELING EnJTAGE DURING SURVEILLANCE TESTING , FOUND THE A. Type................ Check COMPONENT COOLING WATER SURGE TANK VACUUM BREAKER WOULD NOT OPEN . S. operator............ None C. Function /AFplication one Way Flow Causs of Fat ture Narrative..... D. Body Materiet....... Carbon Steel FOUND THE VALVE DISC WAS STUCK IN THE SEAT AND THE VALVE WAS RUS1Y , E.8cdy Manuf acturing M Cast DUE 10 NORMAL WEAR . F. Nominal Inlet Site ( 1/2 to 1.99 IN G. Size (Inlet)........ 1.000 IN Corrective Action Narrative..... H. Design Pressure..... 1365.000 PSIG CLEANED VALVE AND LAPPED SEAT , COMPLETED TESTING SATISFACTORILY AND J. Design Teaparature.. 300.000 DEGF RETUlt%ED VALW TO SERVICE . 1 Time operating When Reactor is Critical.. 100%
% fime Operating When Reactor is shutdown..100%
Hours Out Testire Performed Frequency / Period of Service Check Testing 1 / Month 0.0 Functional Testing 0 / Not Done 0.0 calibration Testing 0 / Not Done 0.0 0 O
ACCEPTANCE DATE: 01/12/89 A-62 WESTINGHOUSE CIASS 3 Ut i l i t y . . . . . . . . . . . . . . . . . . . . .per t icnd Gener0l E l ec t r i c Conpany Unit.........................TR0JAN 1 NSSS......................... Westinghouse Application......... Mein Steam Isol Valve t.................... VALVE F me t t on. . . . . . . . . . . . s Conrxnent I d. . . . . . . . .CV 22 F6 Sys t em. . . . . . . . . . . . . . Main St eam-W cate...... 11/28/88 Utility System...... MSS Start T ime. . . . . . 12:00 Out of-Service Hours... 1 Data Start Date. 05/22/76 In Service Date..... 05/22/76 Disc:v:ry Date..11/28/88 Restoration Hours...... 1 Accepted Date.... Out of service Date.. End Date. . . . . . . . 11/28/88 End T ime. . . . . . . . 13 :00 Saf ety Class... .. .. 2 Report Date..... 12/12/88 Input Dat e. . . . . . 01/03/89 Mode................ Operating System St atus. . . . . . . . . . . . . . . .E T rain /Channe l in Service (OPC/SBC) Sever i ty L evel . . . . . . . . . . . . . . . J Ieredi at e I nt ernal E nv. . . . . . . . S t eam F a i luro Sympt om. . . . . . . . . . . . . .C D emand F aul t External Env........ Ambient Tenperature -10F to +120F Failure Mode.................F0 Failed to Open Su m lier............ Bechtel Gro m Inc Failure Detection............ A Operational Abnormality Sum lier Id......... Caus2 C0tegory...............K Unknown Manuf acturer........ Atwood & Morrill Co Inc / Xomox Caus) D:scription............BB Mechanical Damage / Binding Mfr Model Id........ AG Abnormal Stress M f r Model No. . . . . . . 12330 System E f f ect. .. . . . . . . . .. . . . .B Degraded Sys tem Operat ion Mfr Serial No....... Plant E f f ect. . . . . . . . . . . . . . . . .G - Resul ted in No Si gni f icant E f f ect Mfr Standard........ ANSI 831.1.0 Correc t i ve Ac t i on. . . . . . . . . . . . AG Repa i r Conponent/ Par t Drawing No.......... M123 001 009 Docunent a t i on. . . . . . . . . . . . . . . .Z kone of the Abov e LER Report Na cer............ System Affected by failure...HBC - Main Steam W Engineering Codes - FfWre Description Narrative..... A. Type................ Check ( )28VITHTHEPLANTHEATINGUP,MAlWSTEAMISOLAfl0NVALVE ,B. operator............ Pneumatic (Diaphrapn or C CLJ6 WOULD NOT OPEN FROM THE CONTROL ROOM . MAINTENANCE PERSONNEL C. Function / Application one Way Flow WERE ABLE TO OPEN THE VALVE WITH A SMALL ASS!$T FROM A PRT BAR . D. Body Material....... Carbon Steel E. Body Manufacturing M Cast Causi of Failure Narrative..... F.Neminal inlet site ( 20 to 39.99 IN THE FAILURE TO OPEN is BELIEVED DUE TO INTERNAL BINDING RESULTING FROM G. Size (Inlet)........ 28.000 IN THERMAL CYCLikG . THE VALVE PERFORMS PROPERLY WHILE THE PLANT IS H. Design Pressure..... 1095.000 PSIG OPERATI::G . IT IS VHEN THE VALVE IS HEATING L'P AFTER HAVING COOLED DOWN J. Design Teaperature. . 556.000 DECF THAT THIS PHENOMEkON !$ 06 SERVED . 1 Time operating Wh r neactor is Critical.. 100% C:rrective Action Narrative..... % Time Operating When Reactor is Shutdown.. 100% THE YALVE WAS CYCLED FROM THE CONTROL RocN SEVERAL TIME $ AND TINED FOR PROPER OPERAfl0N . Hours Out Testing Performed frequency / Period of Service Check Testing 1 / Quarter 1.0 Functional Testing 0 / Not Done 0.0 . Calibration Testing 0 / Not Done 0.0 f) v
WESTINGHOUSE CLASS 3 uctter Plant Reliability Data System
' Ceneret Report Fer: R3lph L. H mter, Jr. Report Id WPRC00AA stinghouse Electric Corporation Job k & rs 9915 Rm Date: 07/01/92 Rm Time: 16:04 IntrodJction:
The att:ched report was generated b/ your query of the NPRDS data base. ..A supunary of your query is ilsted below. QUERT: You salected the following search cordition(s): Selected Caponent is VALVE
- Estected VALVE Type la Check Sitected Unit ID is PEACM SOTTOM 3
$3lected System is Nigh Pressure Cootent Injection-GE Find Utility Crmponent ids that are equal to A0-3 23 018 Satected Manufweturer is Rockwell Int / Flow Control Div Th:re were 2 records meeting the search conditicri(s).
DISPLAY AND SORT: fou selected to run general report 5: O Ccaponent Master Falture Report (w/ Unit Inforaintion) You chose to sort the report by: Sort sequence Fletd Wane NPRG05AA Nuclear Plant Reliability Data System - Falture Master Report Run Date: 07/01/92 Job huiser: 9915 ACCEPTANCE DATE: 10/17/91 0tili ty. . . . . . . . . . . . . . . . . . . . . .Philadelphi a E lectri c Conpany
.Jnit.........................PEACM SOTTCH 3 fS$3.........................Ceneral Electric Application......... HPCI Disch to Fdwtr check Valve Component.................... VALVE F metton............
Jt i l i ty Component I d. . . . . . . . . AO 3 23 018 System.............. High Pressure Coolant injection CE Start Date...... 02/09/86 Utility System..... 23 Stcrt Time...... 12:00 out of service Hours... 456 Data Start Date.12/23/74 In-service Date..... 12/23/74 3Incovsry Date.. 02/24/86 Restoration Hours...... 108 Accepted Date...12/20/91 Out of Service Date.11/26/91 End e 'e........ 02/28/86 Erd s........ 12:00 safety Ctess....... 2 tesort Date..... 05/05/86 Input D a t e. . . . . . 09/02/91 rode................ Operating System Status. . . . . . . .. . . . . . . . F - T ra in/Charvie t i n Tes t Severity Level...............K Degraded Internal Env..... . Reactor or Prisury Coolant Water
A-64 WESTINGHOUSE CLASS'3 Fal ture 5yuptem.. .. . .. . . . . . . .B
- Out of Speci f icat ion External Env........ Anblent Temperature 410F to +120F f;lture Mode.................F0 Falled to Open Other P3 Det ect ion. . . . . . . . . . . .C
- Suwel l t erre T es t i ng Suml l er . . . . . . . . . . . . Genera l E l ect ri c Cons >any i
L.. / ategory...............N Wear out Sumlier Id......... Cause Desc r i pt i on. . . . . . . . . . . . AD + korma t /Abnor1aa l We a r Manuf acturer........ RockweL L Int / Flow Control Div systee E f f ect...... . . ... . . . . .D Degraded Traln/ Channel Mf r Model Id... ... . 970Y Plant Effect.................G Resulted in No significant Effect Mfr Model No....... 970 JMMNT Corrective Action............AG
- Repair Component /Part Mfr Serial Wo.......
Documentat i on. . . . . . . . . . . . . . . .Z Ncne of the Above Mfr Standard........ LER Report Wunber............ Drawing he.......... Mi U 68 system Af fected by Fallure...SFC High Pressure Coolant injection GE Failure Description Narrative..... Engineering Codes WITN THE L*!T $ NUT DOWN FOR REFUEllWG , THE NIGH PRESSURE COOLANT INJECTION TESTABLE CHECK YALVE WOULD WOT OPEN FULLY DURlWG STROKE . ( A. Type................ Check 3 23 G 8601742 & 8601658 ) 8. Operator............ Pneunatic (Diaphragm or C - C.Ftretion/ Application Dr.e Way Flow cause cf Falture Warrative..... D. Body Materlat. .. .. .. Carbon Steel THE CAUSE WAS DUE TO WCAR AND AGE . E. Body Marufacturing M Cast F.Neminat Intet Site ( 12 to 19.99 IN Corrective Action Narrative..... G. Site (Inlet).. . . . . . . 14.000 IN LAPPED AND BLUED VALVE SEATS , REPACKED AND VERIFIED PROPER OPERATION . H. Design Pressure..... 1700.000 PS!G J. Design Tenperature.. .00.000 DEGF
% Time Operating When Reactor is Critical..100%
% Time Operating When Reactor is Shutdown... 0%
Hours Out-Testing Performed Frequency / Period of Service Check Testing 0 / Not Done 0.0 Functional Testing 1 / Month 0.0 Calibration Testing 0 / Not Done 0.0 V
WESTINGHOUSE CLASS 3 ucteer Plant Reliability Data System General Report fort R:lph L. H eter, Jr. Report Ida WPRC00AA tinghouse Electric Corporation ' Job Nuters 9917 Run Date: 07/01/92 Rm Timet 16:12
Introduction:
The Cttached report was generated by your query of the WPRDS data base. , A sumery of your cFJery is listed below. QIKRT t You 6:lected the following search condition (s): Selected Conpanent is VALVE Selected VALVE Type is Check S:lected Unit ID is MONTICELLO 1 Selected System is Resichel heat Removal / Low Press Inject GE Find Utility Component ids that are ecpat to CST 98 selected Manuf acturer is Vogt , enry Machine Co There were 1 records meeting the search condition (s). DISPLAY AND SORT: You anected to run general report 5: Component Master Failure Report (w/ Unit Information) fou chos3 to sort the report by; Sort Sequence Fletd Name ORG05A4 kuclear Plant Reliability Data System
- Failure Master Report Rm Date: 07/01/92
[ Job Wueer: 9917 i ACCEPTANCE DATE: 09/14/87 Jt i l i ty. . . . . . . . . . . . . . . . . . . . . . Northern S t at es Power Ccripany Jni t . . . . . . . . . . . . . . . . . . . . . . . . .M0NT I CE LLO 1 ( 41SS......................... General Electric Application.........
'caponent.................... VALVE FeetIon............
l _ Jt t li ty Component I d. . . . . . . . . CST 98 $ystem.............. Resichel Hee
- Removal / Low Press Injec l
It'.rt D:te...... 07/13/87 Utility System...... B.3.4 l Itart Time...... 12:00 Out-of service Hours... 434 Data Start Date. 07/01/74 In-service Date..... 07/04/71 - ( )lscovery cate.. 07/13/87 Restoration Hours...... 434 Accepted Date.... Out of service Date.. i ind P-+e........ 07/31/87 Ind ........ 14:03 safety Class....... 2 l 1eport D te..... 08/26/87 Input Date. .. ... 08/26/87 Mode................ Standby Condition system Status................E Train /Chamel in service (OPC/ SCC) Eve c i ty L eve l . . . . . . . . . . . . . . . J - 1 svned i a t e Internal Env........ Artient Tenperature Over +180F
WESTINGHOUSE CLASS 3 l . Failuro Symptom............. 6 Out of Specification Condensate / High Purity Water F 29 tur3 Mode. . .. .. . . . . . . . . . . .F0 F ai l ed to Open External Env........ Ambient leeperature +10F to +120F Ff " ~'s Detection............J . Incidental Observation Radiation Fletd (At$a / Bete / Canna ( )ctegory...............M.Weerout Cc J Description............BE Dirty Supplier............ Rechtet Group Inc Supptler Id......... System Ef f ect..... . ... . .. . .. .D Degraded T rain / Channel Manuf acturer........ Vogt , Henry Machine Co Plant Ef fect.................G Resulted in No Significant Ef f ect Mfr Model Id........ C:rrec t i ve Ac t i on. . . . . . . . . . . . AG R epa i r Conysnent /hr t M f r Model No. . . . . . . . SW 7DS Documenta t ion. . . . . . . . . . . . . . . 2 NJne of the Above Mf r Serlel No.. .... LER Report Nw ber............ Mfr Standard. 4..... System Affected by Fellure...CFA Residaat Heat Recovel/ Low Press injeDrawing No.......... WX 8968 21 F:lture Description Narrative..... THE SYSTEM ENGINEER NOTICED LOW RESIDUAL HEAT REMOVAL DISCHARGE HEMER Engineering Codes PRESSURE . AN INVESilGATION REVEALED THAT CHECK VALVE CST-98 . THE PRES $URE STATION TO 808 CONTAINMENT SPRAT HEADER CHECK VALVE WAS NOT A. Type................ Check OPENING . THE PLANT WAS OPERATING AT 100% POWER . B operator............ None C.fmetton/ Application one Way Flow Caus2 ef Falture Narrative..... D. Body Materiet....... Carbon Steel THE CAUSE OF THE CHECK VALVE NOT OPENING WAS AN ACCLMJLATION OF E. Body Marof acturing M Forged
- CORROSION PRODUCTS WHICH INNIBITED FREE MOVEMENT OF THE VALVE DISC . F.Neminal Inlet Stre ( 2 to 3.99 IN G. Size (Intet)........ 2.000 IN Cterective Action Warrative..... N. Design Pressure... .. 275.000 PSIG THE CHECK VALVE WAS DISASSEMBLED , CLEANED , AND PEASSEMBLED . THE J. Design Teeperature.. 263.000 DEGF YALVE OPERATED SATISFACTORILY .
% time Operating When Reactor is Critical... 1%
% Time Operating When Reactor is Shutdown... 1% !
V Hours Out G Testing Performsd Check Testing Frequency / Period of Service 0.0 0 / Not Done Functional Testing 1 / Month 0.0 Cellbration Testing 0 / Not Done 0.0 N
WESTINGHOUSE CLASS 3 uc(6er Plant R; liability D:ta System General Report Fort Ralph L. Hunter, Jr. Report Id: kPRG00AA
'tInghouse ftectric Corporation Job kueer 9920 Rm Date: 07/01/92 Rm Times 16:21 Introduetion The ettsched report was generated by your query of the NPRDS data base.
A suunary of your query is listed below. CfJERT: feu a!!ected the following search conditicat(s): Selected Ccaponent is VALVE
- Selected VALVE Type is theek ,
l Selected Unit ILs are PALO VERDE 2 and DAVIS-BEESE 1 Selected systems are Dieset starting Air SW, Diesel Starting Alr CE, and Residial Heat Removal / Low Presa inject GE Find Utf tity Component ids that are equal to any one of the following: DA 24 and 2PDGAV066 Selected Manuf acturers are Control Components International afd Dresser ind Vtv 8 Inst Div / Ashcrof t TM There were 4 records meeting the search conditlan(s). DISPLAT AND SORT: O You selected to run general report 5: Ccuponent Master f ailure Report (w/ Unit Information) You chos) to sort the report by: Sort sequence Fletd Wome kPAG05AA Nuclear Plant Retlability Data System - Falture Master Report Run Date: 07/01/92 Job Number M20 ACCEPTANCE DATE: 12/09/87
? . Utttity......................Centerior Energy Corporation Unit.........................DAVI$ BESSE 1 MS$$. . . . . . . . . . . . . . . . . . . . . . . . 8sbc ock & W i lcox Application.........
Component . . . . . . . . . . . . . . . . . . . . VALVE F met i on. . . . . . . . . . . . Utility conponent Id.........DA 24 System.............. Diesel Starting Air BW Stir * *:te...... 10/23/87 utility system...... EDG sts .ee...... 12:00 Out-of service Hours... 340 Data Start Date.10/19/87 In-service Dete.....10/1 l-DiscoveryDate..10/23/87 Restoration Hours...... 340 Accepted Date... 07/30/91 OJt of-service Date.. End D:ts. . . . . . . . 11/06/87 Erd T ime . . . . . . . . 15 :30 safety Class........ SR
A-68 WESTINGilOUSE CLASS 3 Report D:te..... 11/16/87 input Date...... 11/17/87 Mode................ Standby condition Systee Status. . . . . . . . . .. . . . . .F Train /Channet in T est i ROy Level . . . . . . . . . . . . . . . J - Inunedi a t e Internal Env. . . . . . . . Conpressed Ai r l c i Externet Env........ Air - F( jsymtom..............C Demand fault Falfure Mode.................F0 Failed to Open Ant > lent Temerature 10F to +1207 Fallare Det ection......... . ..C Survel t lance Test ing Supplier............ Pacific Velves / Mark Controt6 Corp Caus) Category. . . . . . . . . . . . . . .K Unknown Su plier Id.. ... .... D138 223 111 Caus) Descr i pt ion. . . . . . . . . .. .BE D i rty Manuf acturer........ Control Conponents Internatione A3 Foreign / Incorrect Materiet Mfr Model Id........ Systen E f f ect. . . . .... . . .. . . . .C - Loss of one or More Tre ln/ Channel Funct ioMf r M<: del No. . . . . .. . SERIES 300/3682 7E X Plant Ef fect........ ........G Resulted in No Significant Ef fect Mf r Corial No...... 0406 2 Correct i ve Act i on. . . . . . . . . . . . AG - R epa i r Conponent/ Par t Mfr Standard........ ANSI Doctament a t i on. . . . . . . . . . . . . . . .Z k one of t he Above Drawing ko......... 12501 M2130 5 5 LER k eport Wtstper. . . . . . . . . . . . System Af fected by Failure...EECDAA Diesel Starting Air-BW Engineering Codes f ailurs Description Narrative..... ON 11 3 87 WHILE THE UNIT WAS OPERATING AT 80 PERCENT POWER THE A. Type................ Check POSTMAINTENANCE SURVEILLANCE TEST WAS BEING PERFORMED ON DA 24 . THE B.0perator............ Mech (Speng-Force Open/Dif EMERGENCY DIESEL CENERATOR AIR RECE!VER 1 1 INLET VALVE DA 24 FAILED TC C.Fmetton/ Application one-Way Flow FWCTION PROPERLT BT STICKING CLOSED DURlWG THE TEST . THis VALVE HAD 0. Body Material....... Carbon Steel REEN REPLACED EARLIER IN THE DAT , E. Body Manufacturing M Forged F. Nominal Inlet Size ( 1/2 to 1.99 IN ~ Cous2 of Felture Warrative..... G.51:e (Intet)........ 0.750 IN tJPON DISASSEMBLY THE VALVE WAS FOUND TO HAVE HEAVY OXIDATION AND H. Design Pressure..... 300.000 PSIG M0ISTURE IN IT . ROOT CAUSE IS UNKNOWN AT THl$ TIME , BUT THE SCURCE OF J. Design Tenperature.. 475.000 DEGF MotSTURE AND OXIDAfl0N l$ UNDER INVESTIGATION .
% Time operating When Reactor is Critical..100%
C y ] tve Action Narrative..... 1 Time Operating When Reactor is Shutdown.. 50% T( . CHECK VALVE WAS DISASSEMBLED , CLEANED INTERNALLY WITN ALCOHOL
, U)REASSEMGLED . THE VALVE WAS T!STED AGAIN PER SURVEILLANCE TEST Hours Out U00 FCUND ACCEPTA8L,E AND RETURNED TO SERVICE . Testing Performed Fremency/ Period of Service Check Testing 0 / Not Done 0.0 Functional Testing 1 / Honth 0.0 calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 10/06/87 Jt i l i ty. . . . . . . . . . . . . . . . . . . . . . Ar i zona Ptbl i c Servi c e Conpany Jni t . . . . . . . . . . . . . . . . . . . . . . . . . P ALO VE RDE 2 (S$$ . . . . . . . . . . . . . . . . . . . . . . . .Conous t i on Engi neer i ng Application......... ; opponent.................... VALVE F me t t on. . . . . . . . . . . .
Jt i li ty component I d . . . . . . . . 2PDGAV066 System. . . . .. ... . . ... Diesel Start ing Alr CE ttart Dete...... 02/21/87 utility System...... DG it rt Tisw...... 12:00 Out of service Hours... 99 Dets Start Date. 09/19/86 In-Service Date..... 09/18/86 Discovery Date.. 02/21/87 Restorat ion Hours... ... 99 Accepted Date... 09/18/87 Out of Service Date.. Ind Dete.. . . . ... 02/25/87 ind T ime. . . . . . . . 14 :30 Safety Class....... 3 teport Date..... 08/24/87 Input D a t e . . . . . . 09/18/87 Mode................ Standby Condition tystem Status................E Train / Channel in Service (OPC/S8C) P. veri ty Level . . . . . . . . . . . . . . J lemed i at e Internal Env........ Cocpressed Air te l lure Sy.rpt ca. . . . . . . . . . . . . .D - Atrictinal Charac t eri s t i c Externat Env........ Tenperature / Humidity (Not Cntrld)
'cl e Mode.................F0 Failed to Open Supplier...... .. .. .. Dresser ind VLv & Inst Div / Ashcrof t
!c Detection............F Audiovisual Alarm Sumlier Id..... ...
t egory . . . . . . . . . . . . . . .H Wear Out Manuf acturer........ Dresser Ind Vlv & Inst Div / Ashcrof t
!ause Descript ion. . . . . . . . . .BE - D i rty Mfr Model Id....... 5580 iys tem E f f ect . . . . . . . . . . . . . . .D - Deg r aded f ra i n/Channe l Mf r Model No. . . . . . . HANCoct 5580
- L ant E f f ec t . . . . . . . . . . . . . . . . .G - R esul t ed i n No S i gni f i c ant E f f ec t Mfr Serial No..... .
- or rect ive Ac t i on. . . ...... . AG Repair Conponent/Part Mfr Standard........ ASME ill 3
A-69 WESTINGHOUSE CLASS 3-Document a t i on. . . . . . . . . . . . . . . . Z N one o f t he Abeve Drewing No......... 13 N DGP 001 LER Report NLa6er............ System Af fected by Falture...EEDDAA Diesel Starting Alt CE Engineering Codes F lt o Description Warrative..... THE UNIT WAS IN COLD SMUTtG N CouDITION . A CNECK VALVE ON ThE A. Type................ Check DISCHAR] 0F DIESEL GENERATOR ( DG ) SfARTlWG AIR DRTER WAS STICKING 8. Operator............ None CLOSED NOT ALLOWING AIR TO G010 AIR RECE!VEC AND ALSO LIFilNG THE C.FunctioNApplication One Way Flow DISCHARGE PRESSURE SAFETY VALVE OF THE DG STARTING AIR COMPRESSOR . D. Body Material . . .. . .. Carbon Steel
!.Dody Manuf acturing M Forged Cause cf failure Narrative..... F.N Ainal Inlet Site ( 1/2 to 1.99 IN NORMAL WEAR OF SEAT AND DISC AND CONTAMINAfl0N IN VALVE . G. Site (Intet)........ 1.000 IN H. Design Pressure.. ... 265.000 PSIG Corrective Action Narrative..... J. Design Tenperature.. 200.000 DEGF DISASSEMBLED VALVE , CLEANED INTERNALS AND REWORKED SEATING SURFACES OF D!$C AHD SEAT AS REQUIRED TO ACHIEVE GOOD BLUE CHECK , REASSEMBLED X Time Operating When Reactor la Critical... 55 VALVE PER TECHNICAL MANUAL . % Time Operating When Reactor is shutdown... 5%
Hours Out Testing Performed frequency / Period of Service Check Testing 1 / Three fear 0.0 Functional Testing 0 / Not Dcne 0.0 Calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 08/23/88 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . . Ar i t ona Piht i c Servi c e Ccurpeny Unit......................... pal 3 VERDE 2 NS$ . . . . . . . . . . . . . . . . . . . . .Combus t i on E ng i neer i ng Application......... Component.................... VALVE ' Function............ Utility Component Id........ 2PDGAV066 System.............. Diesel Starting Air CE St:rt Date...... 09/29/87 Utility Systse...... DG St:rt Time...... 17:00 Out of service Hours... 26 Data Start Date. 09/19/86 In Service Dete..... 09/18/86 31scovery Date.. 09/29/87 Restoration Hours...... 26 Accepted Date... 09/18/87 Out of service Date.. End Data..... ... 09/30/87 End T ime. . . . . . . . 18:30 Safety Class....... 3 '4eport 0:te...... trpat Date...... 08/03/88 Mode . . . . . . . . . . . . . . . . S tanciry Condi t i on - System Status................E Train / Channel in Service (OPC/ Sac) Sever i ty Level . . . . . . . . . . . . . . . J I sened t a t e Internal Env........ Compressed Air Failura Syeptom..............E - Released Leakage External Env........ Tenperature / Nu'nidity (Not Cntrld) F*.fluro Mode.................F0 - Failed to Open Supplier............ Dresser Ind VLv & Inst Div / Ashcrof t Failuro Detection............H - Routine Observation Stept ier Id. . . . . . . . .
*ause Category...............K - Unknown Manufacturer........ Dresser ind Viv & Inst Div / Ashcroft
- ause Description........... 5F Stocked / Obstructed Mfr Model Id....... 5580 SE Dirty Mfr Model No........ MANCOCK 5580 lystem Effect................D - Degraded Train / Channel Mfr Serial No.......
' tant Ef fect.................G - Resulted in No significant Ef fect Mfr Stamtard........ ASME III 3
- orrective Action............AG - Repair Component /Part D rawi ng No. . . . . . . . . 13-M DGP 001 Jocumentit i on. . . . . . . . . . . . . . . 2 - N one o f the Above
.ER R eport husber. . . . . . . . . . . .
iystem Af fected by Falture...EED Emergency Power CE Engineering Codes tailure Description Narrative..... A. Type................ Check Ulf " S AT NORMAL OPERATING POWER DURING OPERAfl0N OF A DIESEL 8.00erator............ None IENL 4 STARTING AIR DRYER THE PRESSURE SAFETY RELIEF VALVE ( PSV ) JAS LIFil%C DUC TO THE STARilWG AIR DRYER DISCHARGE CHECK VALVE BEING C. Function / Application One-Way Flow 9_ D. Body Material....... Carbon Steel -iTUCK CLOSED . E. Body Manuf acturing M Forged F. Nominal Inlet Size ( 1/2 to 1.99 IN laus2 cf Failure Narrative..... G. Size (Inlet)........ 1.000 IN
WESTINGHOUSE CLASS 3 ^* T M CAUSE OF FAILURE OF THE DISCHARGE CNNCK VALVE WAS DETERMlWED TO SE' N. Design Prcn ure..... 265.000 PSIG CRUD BUILDUP INSIDE THE VALVE WHICH PLUGGED THE EQUALIZING NOLE . J. Design Tecperature.. 200.000 DEGF C Ivo Action Narrative..... % Time Operating When Reactor is Critical... - 5% T E WAS DISASSEMSLED , INTERNALS CLEANED AND REASSEMBLED , No 1 Time Operating When Reector is Shutdown... 5% DT R0 STEMS FOUND . Hours Out Testing Performed frequency / Period of Service Check Testing 1 / Three Year 0.0 Func,tional Testing 0 / Not Done 0.0 calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 02/13/89 Jt i l l ty. . . . . . . . . . . . . . . . . . . . . . Ar l s ona Pths t e Servi c e Cowpeny Jni t . . . . . . . . . . . . . . . . . . . . . . . . . PALO VE RDE 2 ($ $$ . . . . . . . . . . . . . . . . . . . . . . . . .Contua t i on Eng i nee r i ng Application......... kuponent.................... VALVE Finetton............ Jt i l i ty Component I d. . . . . . . . 2P0GAV066 System.............. Diesel Start (t.s Air CE Itert Date.... .. 01/14/88 Utility System...... DG -ltert Time...... 17:00 out.of. Service Hours... 2526 Data Start Date. 09/19/86 In Service Dete..... 09/18/86 af scovery Date.. 01/14/88 Restoration Nours...... 2526 Accepted Date... 09/18/87 Out of Service Dete..
!nd D:ts........ 04/28/88 Ind T ime..... .. . 22:50 Safety Ctess....... 3 -
toport D;te...... Input Date...... 02/01/89 Mode................ Stan
- y Condition lystem Status................E - Train / Channel in Service (OPC/SBC) lever i ty L eve l . . . . . . . . . . . . . . . J -I smed i a t e Internet Env........ Cupressed Air ti ture Synptom.. ... ....... ..E - Released Leakege External Env........ Temperature / Hunidity (Not Cntrtd)
Mode.................F0 Failed to open Supplier............ Dresser ind Viv & fnet Div / Ashcroft
' letection............J - Incidental Observation Supplier Id.........
stegory...............K . Unknown 'Manuf acturer........ Dresser Ind Vtv & Inst Div / Ashcrof t -
- ause Desc r i pt i on. . . . . . . . . . . 8E D i rty Mfr Model Id....... 5580 tys t em E f f ec t . . . . . . . . . . . . . . . .D Deg raded f re i n/Channe t Mfr Model No........ HANCOCK 5580
*t ent E f f ect . . . . . . . . . . . . . . . . .G Resul t ed in No Si gni f i cant E f f ect Mf r Serlet No.......
- or rec t i ve Ac t i on. . . . . . . . . . . . AG - R epa i r Cceponent/Pa rt Mfr Standard........ ASME III-3 locument a t i on. . . . . . . . . . . . . . . 2 - None of the Above Drawing No......... 13 M DGP 001
,ER R epor t Nunter. . . . . . . . . . . .
system Affected by failure...EEDDAA
- Diesel Starting Air-CE Engineering Codes tellur3 Description Narrative.....
IURING NORMAL OPERATION , THE STARTING AIR DRYER SAFETY VALW WAS A. Type................ Check
.lFTING EVEN THOUGH THE VALVE MAD BEEN VERIFIED TO BE SET AT THE B. operator............ None ImRECT LIFT PRESSURE . FURTHER TRQJ8(ESNO3 TING LED PLANT PERSCENEL 70 C. Function / Application One Way Flow USPECT A MALFUNCTIONING STARTING AIR DRYER DISCNARGE CHECK VALVE , D. Body Materiet....... Carbon Steet E. Body Manufseturing M Forged tause cf Fallure Narrative..... F. Nominal Inlet Size ( 1/2 to 1.99 IN 'ISCHARGE CHECK VALVE O!SC WAS FOUND STUCK TO THE SEAT WITN CIL REstDUE G. Size (Intet)........ 1.000 IN M. Design Pressure..... 265.000 PSIG J. Design Tenperature.. 200.000 DEGF orrective Action Narrative.....
ISCNARGE CHECK VALVE WAS DISASSEMBLED , CLEANED AND REASSEMBLED . % Time Oper ting When Reactor is Criticat... 5% PERA3tLITY TEST WAS SATISFACTORY . 1 Time Operating When Reactor is Shutdown... 5% Mours Out im ( ) Testing Performed F re<pency/ Period of Service Q) ................. Check Testing 1 / Three Year 0.0 Functional Testing 0 / Not Done 0.0 calibration Testing 0 / Not Done 0.0
WESTINGHOUSE CLASS 3 ^# uclear. Plant R (tability Dit3 Systesa General Report Fort Ralph L. Nunter, Jr. Reportald: WPRGOOAA- . Stinghouse Electric Corporation Job Nurcer: 9924' Run Date: 07/01/92 - Rm flee: 16:33 Intraiction: _ The attached report was generated by your query of the NPRDS date base. A sammary of your query is listed below. QUERY: You selected the followire search condition (s): Selected Cenponent is VALVE Selected VALVE Type is Check selected Unit ids are CALLAWAY 1 and SURRY 1 Selected Systems are Diesel Starting Air-CE, Dieset starting Air W, and Nuclear service Water W Find Utility Ccuponent ids that are equal to any one of the following: 1 EG140,1 EG142, and EF V 0076 Selected Manuf acturers are Sonney Forge Div / Gulf & Western and Velen Valve Corp There wre 6 records meeting the search condition (s). DISPLAY AND SORT: O-Tou selected to rim general report 5: Ccuponent Master Fa;',se Reprt (w/ Unit Informatf ori) You chose to sort the report by sort tequence Field Name (PRG05AA Nuclear Plant Reliability Data System a Falture Master Report Rm Date: 07/01/92 Job Wurber 9924 ACCEPTANCE DATE: 09/16/86 Jt i l i ty. . . . . . . . . . . . . . . . . . . . . . Uni on E l ect r i c Company Jnit.........................CALLAWAY 1 (5SS......................... Westinghouse Application.........
*capenent . . . . . . . . . . . . . . . . . . . . VALVE Function............
Jt i l i t y Corponent I d. . . . . . . . . E F V-0076 System. .. .... . .. . . .. Nuclear Service Water-W st:r* t t2...... 06/18/86 Utility System...... EF ltr. ase...... 06:00 Out-of-service Hours... 729 Data $tsrt Date. 04/09/85 In-service Date.....10/02 liscovery Dr.ce.. 06/18/86 Restoration Hours.. . . .. 729 Accepted Date... 03/25/85 Out of service Date.,
!nd Data. . . . . . . . 07/15/86 ind Time........ 15:00 safety Class....... 3
A
~ WESTINGHOUSE CLASS 3 "
A j LR'aeortDatei....08/19/86 . Input Date...... 08/19/86 - Mode................ Standby condition: Li r \$tetus...............'.E.* Traln/Channet in Service (OPC/SSC) t j- L evel . . . . . . . . . . . . . . .K '
- Degraded Internet Env........ Fresh Water ( Well / River / Lake ):
.Feh
( i Syupten..............D.*Abnormel Cherneteristic-4 Secondary Coolant or Treeted Water F e l lure Mode. . . . . . . . . . . . . . . . . F C
- F 6 t l ed t o C l ose - . Externet Env........ Temperature / Humidity (Cntrid)
F6tlure Detection............A
- Operational Abnormality. ' Supplier............
.Cause Category...............K
- Unknown S p lier Id.........
Cause Description............BE
- Dirty Manufacturer........ Velen valve Corp' i System Effact................D a Degraded Tretn/Chennet . Mfr Modet Id........
e Plant Ef f ect.................G
- Resulted in No significent Ef f ect Mfr Model No........ 309 01148 02TS ,
-' C* erective Action.......... .. AG
- Repelr Component / Port . Mfr Serlet No...... 22 '
I 0ccument e t t on. . . . . . . . . . . . . . . .Z
- None of the Above Mfr Standard........ ASME SECT !!!
LER Report Wus6er............ Dreving No.......... M 02EF01 B 6 3
^* -System Affected by failure... WAD-
- Nucteer Service Water W Falture Description Narrative..... Engineering Codes ESSENTIAL SERVICE WATER TRAIN 88' FROM 'B' AIR COMPRESSOR CHECK VALVE APPEARED TO BE STICKING SHUT , OR PARTIALLY $ NUT , RESTRICTING COOLING A. Type................ Check
' WATER FLOW THROUGH COMPRESSOR CAUSING IT TO RUN AT AN ELEVATED 8.0perator...........'. None TEMPERATURE , C. Function / Application One Wey Flow D. Body Material....... Carbon Steel
.-Cause of. Failure Narrative..... E.Sody kanufacturing M _ Cast CHECK YALVE INTERNALS DIRTY CAUSING VALVE TD BE STUCK PARTI ALLT OPEN . F. Nominal Inlet Site (' 2 to 3.99 IN- ..
G. Site (Intet)........ 2.500 IN Ctrrective Action Norrative..,.. H. Design Pressure..... 200.000 PSIG' s DISASSEMSLED VALVE , CLEANED INTERNALS AND REASSEMBLED YALVE USING OLD J. Design Temperature.. 200.000 DEGF
. COVER CASKET AND USING A LAYER OF GRAF0ll CN BOTN SIDES OF GASKET .
% ? Ice Oportting Whoi Reactor is criticat...- 0%
% Time operating When Reactor is shutdown... 0%
( Hours out Testing Performed Frequency / Period' . of Service : Check Testing 0 / Not Done 0.0 Fmettonal Testing - 0 / Not Donel 0.0 Calibretton Testing 0 / Not Done . 0.0 - 4
WESTINGi!OU6E CLASS 3 N3 ACCEPTANCE Daft: 10/29/90
)
Jtility...................... Virginia Power
.>i8t........................ 5Uttf 1 W$kl......................... Westinghouse Applicaticn.........
Camponent . . . . . . . . . . . . . . . . . . . .V AL VE F a tion............ Utility Component Id...... ..1*EG1 40 systo.. .... . .. . . . . . . Diese t " art ing Ai r v Stort D:te...... 09/15/89 Utility Sptem...... EG1 start Time......12:00 Out of tervice Hours... 14$6 4. ate Start Date. 02/23/89 vice Date..... 02/23/89 31scovery Deta.. 09/14/89 Restoration Hours...,.. 3444 Accepts) Dete... 10/18/90 out of. service Dete.. E nd D e t e. . . . . . . . . "/06/90 Ind T ime. . . . . . . . .E 00 Safety Close....... 3 toport 0:te..... 06/25/90 t rout Dat e. . . . . . 10/18/90 kode................ Operatire Sys tee S tatus.. . .. . . .... . . .. .F . f +eln/ Channel in f est Sevet'l t y l eve l . . . . . . . . . . . . . . .'( . Degr aded Internal Lev........ Compres. sed Air Fellure 5yaptum. . . .. ... ... .. . A Physical '/sul t f aternet Env........ Tenperature / Musidity (Not CntrLdl f a il ure Mode. . . . . . . . . . . . . . . . 90 F a i l ed t o Open Suppller............ Bonney f orpe Div / Gulf & Westem f ailure Detection............C . Surveltlance f tsting $ wplier 14......... Cause 4t egory. . . . . . . . . . . . . . . K . Unknoias Marufasturer........ Bonney Forge Div / Gulf & Western "suse Description.... . ...... 84
- Corroelon Mtr Model Id........
Sys t em E f f ec t . . . . . . . . . . . . . . . .D
- Degraded f re in/Cheme t Mfr Model No........ ADTO Plant Effect....... .......G = Resulted in No $lgnificent Ef fect Mfr Serlel No.......
Corrective Action., . . . . . . . AK + R epl ace Component ( a t Mf r St ordrd. . . . . . . .
)ocumentation. . .. . . .. ... . ... 2 None of the A:sove Drawing No......... 11448 FB 46A 1/2 L t t R ecot t Nudier . . . . . . . . . . . .
tysl f fected by f ailure...itBCM + Diesei Startire Air *U ' Engineerire Codes failure Description Narrative..... dlTN UNIT 1 AT 100% POWtt AND SURVtiLLANCE f tSTING IN PRocats5 , A.1ype................ Check FERAfirWS Pitt0NNEL FOUNO INAT AIR COMPRESSOR #1 DISCHARGE CHECK VALVE B. Operator.......... . Mech (Diff Press Open/Sprn l*tGG JAS STICKING ClostD . C.hsiction/ Application One.Wey Flow D.Sody katerial....... Cerban Steel teura cf f ailure Narrative..... E. Body Nereafecturing A Cast tuti / CORRO$10N IR34 CONDEN1ATION . ROOT CAU$t it UNKNOUN . F.kaminal Inlet Slge ( 1/2 to 1.99 IN C.81:e (Inlet)........ 0.750 JW
- orrective Action Narrative..... H. Design Pressure..... 250.000 PSIG CPLACtt THE CNiCK VALVE IN KIND . ( IVit$CW / LOSO . WOW 085740 , J. Design fenperature.. 120.000 DEGF
-R13 .4C1)
% time Operating When Reactor is Critical..100%
% Tlee Operating When Reactor is $hutdown..100%
Houre Out Testing Performed f requercy/Peric<l of Service Check festire 0 / Not Done 0.0 functional Testing 0 / Not Done 0.0 Collbration Testing 0 / Not Done 0.0 l
A-74 l WESTINGHOUSE CLASS 3 l l ACCtPTAWCt Daft: 10/29/90 V ......................virginio Power
.....................$UPtf i N1 ......................... Westinghouse Agptiestlan.........
Cantonent . . . . . . . . . . . . . . . . . . . .V AL Vt f unc t i on. . . . . . . . . . . . Ut i l i t y Corvorwnt I d. . . . . . . . 1 t Gi 42 sys t ee. . . . . . . . . . . . . . Diesel Star t ing A lt W lt:r t Date......11/04/87 Utility System...... (C1 ltart t ime. ... ...it:00 Out of.5ervice Mours .. 2256 Date Stort Date. 01/01/83 in tervice Date..... .C1/01/73
$lecovery Dete..11/07/89 testoretton Hours...... 2196 Accepted Date...10/18/90 Out of. Service Dete..
End Dat e. . . . . . . . 02/06/90 trd Time........ 12:00 tafety Ctess....... 3 toport Date..... 06/25/90 Irput D e t e. . . . . . 10/18/90 Mode................ Orerating lystem St atus. . . . . . . . . . . . . . . .f . T rain /Chennet in Test lever i ty L eve t . . . . . . . . . . . . . . . J . Imedi a t e i nt erna l i nv. . . . . . . . Conpr es sed A i r f ailure 5 ppt om. . . . . . . . . . . . . . A . Phys i c e t f aul t laternet inv........ Tenperature / fueldity (hot Cntrid) failure Mode.................f0 . failed to Oren Eurot t er . . . . . . . . . . . . S t one & Webs t er i nc f llure Det ect i on. . . . . . . . . . . .C turve i t t ence f est ing $4pt l er Id. . . . . . . . 1.t G 42 Coues Cat egory. . . . . . . . . . . . . . .K unkevaun Noruf ac t ur er. . . . . . . . Dortwy f orge D i v / Gul f & Wes t ern Coup D: script ion.. ... .. . .. ..BG . Corrosion Mfr Model Id........ t ys t en E f f ec t . . . . . . . . . . . . . . . .D + Degr aded f r e i n/Chome l Mir Model ho........ AD70 Plant E f f ect . . . . . . . . . . .. . . . ..G ** Resul t ed in he $ l eni f ic ent E f f ec t Mfr Serlet h0....... Corrective Action............AK . Replace Component (s) Mf r $ t endard. . . . . . . . A11M* A105N
)ocurent at i on. . . . . . . . . . . . . . . 2 . hore of t he Above Dr awing h o. . . . . . . . . 11448. f D 46A .
LER R esort kwewr . . . . . . . . . . . . System Af fected ty f ailure...ItEDAA . Elesel Starting Alt W
. Engineering Codes f ailure Description Warrative.....
dl?Wif 1 At 100% POWER p0 $UeVt!LLANCt ttttlWQ IN Pt0Gets$ , A . f we . . . . . . . . . . . . . . . . Check
/
( WS Pitt0NNtl f 0JWD THAT Alt Coefissue #2 DILChAkGt CHECK VALVE t.0perator...........,
~C.fmet ton /A H v.h(Diff Press open/Sprn
(\ 42 ) WAS STICKING Closto ( Loso / IVttitu . Wo# 087663 ) . f ptication the Way flow D. Body Meterlet....... Corbon Steel Cace of f ailure herrative..... t.pody Manufacturing M 403i CONT 0510N FROM CONDtW$ATION . F.Wominal Inlet Site ( 1/2 to 1.99 th G.slie (Intet)........ 0.750 IW Mrective Action Warrative..... H.Desler. Pressure..... 250.000 PSIG ttPLACED Tkt CHtCK VALVE . J. Design teeperature.. 100.000 DEGF 1 fine Operating When teettor is Criticat..100%
% Time Operating When Atactor is $hutdown.. 100%
Hours Out testing Performed Frequency / Period of service Check testing 0 / Not Done 0.0 functionet festing 0 / Not Dene 0.0 Calibration testing 0 / Wot Done 0.0 ACCEPTANCE Daft: 10/29/90 Jt i l i t y. . . . . . . . . . . . . . . . . . . . . .V i rg i ni a Power An t t . . . . . . . . . . . . . . . . . . . . . . . . . $Ut t Y 1 1158......................... Westinghouse ApptIcetlon......... C ongxnent . . . . . . . . . . . . . . . . . . .V AL VE function............ J Conponent Id. . . . . . . . 1 t G1 42 systern... . . . . . . . . . . . Diesel starting Alt W
$L ate...... 06/21/89 Utili ty System. . . .. . E G1 Itcrt ilme...... 12:00 Out of Service Hours... 4?B Date Start Date. 01/01/83 In service Date..... 01/01/73
)lscovery Dete.. 06/22/89 testoretton hours...... 416 Accepted Date... 10/18/90 Out of service Date..
!nd Oste........ 07/09/89
I wasuncnouss etAss a ^* 1 l I t rd f lee. . . . . . . . 08 : 00 $sf ety Class....... 3 R epor t D e t e. . . . . 09/21/89 frvot Date...... 10/18/90 Mode. . . . . . . . . . . . . . . . Ope r a t t re Syst* Status.... ............I
- T rairVChervel in servic e (OPC/$gC) levt L eve l . . . . . . . . . . . . . . . K
- Deg r aded Interrol Env........ Conpressed Air f a ilure s ympt om. . . . . . . . . . . . . .C
- Demord f aul t laterrest Env........ fewperature / Heldity (Not Cntrid) failure Mode.................P0
- Premature Opening suppl i e r . . . . . . . . . . . . S t one & Webs t e r t re F a i l ur e De t ec t i on. . . . . . . . . . . . N R out i ne Obs e rva t i on $ g (ler Id........ 1.tG 42 Cause C tegory.. ............A Engineering / Design Mansf acturer........ Donney .'orge Div / Gulf 8 Western Cause Description............ A8
- ForeiprVireperect Meterial Mfr Modet Id........
tys t em E f f ec t . . . . . . . . . . . . . . . .! S ys tem f urt t lorV0pera t ion (Vm 8 f ec t ed W r Model ho. . . . . . . . AD 70 Plant Ef f ect.................G
- Resulted in No $lgnificent Jf f ect t'fr serial No....... j Cor r ec t i ve Ac t i on. . . . . . . . . . . . AK
- R epl ac e Ccaponent ( s ) M f r s t orde rd. . . . . . . . Alf M A10$W Doe mentatico................!
- None of the Above Drawing ko......... 11448 F6 44A Ltt Report Number............
System Af fetted try Fellure...ttBDAA
- Diesel Stortire Air W Engineering Codes f ailurs Description kerrative.....
WifH UWlf 1 IN COLD $HUfD0uk DURlWG RoutlWI WALKDouW , AN OPERAf0R A.1ype................ Chec k f(UND THAT THE #1 EM;tGtWCf Dit$tt 82 Alt COMPRt$$0R WA$ RUWWING AND 8.0perator............ Mech (Diff Prese Open/$prn 17] AIR CCMPRES$0R RiLif f VALVE WAS LIfflWG . FURTHtt INVt$flGAfl0N C.f metton/ Application One Way flow atVtAttD THAT THE #2 Alt CCMPRE$$0R DistNARCE CHECK VALVE ( 1 tG-61; ) D.Stxfr Meterlet....... Certson Steel dAS STUCK IN THE CLO$tD PO$lilow . ( LL / PJL to 0828T2 , 89 091 t. Body Meruf acturing M 6C1 ) F.kominel Intet $1 e ( 1/2 to 1.99 th G.$lte (Inlet)........ 0.750 IN Caus) sf f ailure korrettve..... M. Design Pressure..... 250.000 PSIC CisPECT IMPROPER DESIGN AND BUILD UP OF MolsfuRE IkSIDE THE VALVE AND J. Design Temperature.. 100.000 DECF LINE .
% Time operating When Reactor le Criticet..100%
' ort 've Action terrative..... % fise operattre When Reactor is shutdoun..100% 4tPL , CHECK VALVE LIKE FOR LIKt . Noure Out f esting Perfor1ned f reqJency/ Period of Service Check festing 0 / kot Done 0.0 Fmetional Testing 0 / Not Done 0.0 Collbration festing 0 / Not Done 0.0 0
^"' M !
WESTINGHOUSE CIASS 3 urloor Plant Attlebility Date System ' , General Deport ) F ^ " 'lph L. # eter, Jr. Report.lds_menG00AA tinghouse Electric Corpotetion Job kwebert 1107 ' ( km Date: 07/06/92. , R m fleet 16:18 Intradactlant I The Cttached report wee generated by your Saery of the WPRDS dets bees. ; A numery of your waery le tieted below. !
' MRY: -
'You attected the followitg eeerch condition (s): 1 i
Selected Ce g onent le VALVE Selected VALVE Type le Check Selected unit ids are BaumsWICC 2, CafSTAL RIVER UNif 3, and > DuANE AANOLD 1 find Utility Cogonent ids that are egaal to any one of the following: V32 0047, SW'356, f 41.Y60, and t$17040
$3tected Marsefecturere are Anchor / Darling Velve Co, Crane Co, _l Velen inc, and Velen Velve Corp Selected Systeme are Caponent Cooling Water *0W, Deector Core f eeletion Cooling GE, Dieset Starting Air *0E, and Nigh Preeeure l Coolent-Injectlon-QE N -
. TX.cs were 7 records meeting the search corufttlan(s).
OttPLAT AleD Sotis :
. You eclected to rts) poneral report 5: )
'Cemponent Meeter Failure Report (w/ unit Information) t
(: You chool to sort the report try - I sort l See.mee riend meme l;WP9005AA hucteer Plant Reliability Date System
- Failure Ms.ter Report Run Date: 07/06/92 Job h aber 1107 ACCEPTANCE DATE: 05/10/89 y
[ Ut i l i ty. . . . . . . . . . . . . . . . . . . . . .Ca rol i ne P' owe r & L i gh t Cwpany
- Unit.... ................... 84UNSWICK 2 ,
kSts . . . . . . . . . . . . . . . . . . . . . . . . . Gene r e t E l ec t r i c Application......... C?# h t.................... VALVE function............ _ Uih C omponent Id. . . . . . . . .t 41 V60 . System.............. l'igh Pressure Coot ent injection 4t f Start Date...... 10/15/88 Utility System..... 2t41
. Start 11me...... 12:001 Out of. Service Hours... 4491- Date Start Date. 10/01/83- In Service Date.'.... 11/03/75' Discovery Date.. 12/01/88 Reetoretton Hours...... 3375 Accepted Date... 12/19/84 Out of service Date..
- - - - + , ..
.- ~ - . . -- . _ . . .. . . . . -
WESTIllGHOUSE CIASS 3 ^~77 Erd D:te........ 04/20/89 E nd f lee. . . . . . . . . il: 13 Safety Ctess....... 2 Report Date..... 05/04/89 Irvut Date...... 05/04/89 Mcde . . . . . . . . . . . . . . . . S t ardtry Cord i t i on Syst em Status. . ... . . . . . .. . .. .f . T reln/Chame l In f est le ty level...............J
- lemedlete Internal Env....... 8eactor or Primary Coolant Water f a n re lyspt em. . . . . . . . . . . . . .C
- Demand F aul t Externet Env........ Temerature / MLnidity (Cntrid) f a i l ur e Mode . . . . . . . . . . . . . . . . . F 0
- F e l l ed t o Open Aetdent femerature .10F to +120F j failurs Detection............C
- Survelliance testing $ w ller............
Cause C:te9ery...............K
- Unknown s e llee Id......... j Cause Description............As
- Forelen/ incorrect Material Maruf acturer........ Velen inc tt
- Dirty Mfr Model
)
Id....... 20348 j sys tem E f f ect. .. . . . .. .. . .. .. .C . toss of one or More Tra ln/Chamet f uncti oMir kdt No. . .. . . . . W8 2348 215 l Plant Ef fect.................G Resulted in No Stonificant Ef f ect Mfr serial No....... i Corrective Action............AN
- Replace Pert (6) Mfr Standard........
Document a t i on. . . . . . . . . . . . . . . . ! . N one of t h e Above Drawing No......... 9527*FP 6409 LER toport Ntaber............ System Af fected by f ailure...sfC
- Migh Pressure Coolant injection GE Engineering Codes failure Description Narrative.....
2*E41.Y60 . DISCMARGE CHECK VALVE FOR THE HPCI ( MI PRESSURE COOLANT A.fype................ Check INJECTION ) BARCMETRIC CONDEN$ER VACULM PtHP , WWILE PERFORMING MPCI S.0perator............ Platon OPERA 81LiiY PERIODIC TE51, ANNUNCI ATOR A014 3 DID NOT CLEAR AS C.Fmet t on/ Application One Way flow REQUIRED , INDICAtlNG ikAT THE VALVE WAS NOT OPEN . UNif 2 WAS AT 100% 0.Sody Materiet....... Carbon $ teel POWER Od fME Di$COVERY DATE . E.Sody Manufacturing M Cast F.Nominel Intet size ( 2 to 3.99 IN Cause af failure Narrative..... G.slie (Intet)........ 2.000 IN TO VALVE WAS STUCK IN THE SEAT DUE TO RUST DEPosif$ AROUND INE Dist M. Design Pressure..... 150.000 P$1C IIJIDES AND WATER IN THE VALVE 800f . J.Deelen Temperature.. 390.000 DEGF Corre tive Action Narrative..... 1 ilme Operating When Reactor la Criticat... 0% DI .MBLED VALVE , FREED DitC AND REMOVED . CLEANED DISC AND foUND A % fime Operating When Reactor la Shutdown... 0% GRCOVE IN SEATING SURFACE . CLEANCD VALVE INTERNALS AND BLUED NEW DISC 10 INB@ Y SEATS . REA1SEMBLED VALVE AND LEFT IN SAfl5FAC10RY WORKING Noure Out CONDiflON . TL 88 $$Bf1 Testing Performed f reqJency/ Period of Service Check Testing 3 / Day 0.0 Fmettonal festing i / Duarter 0.0 calibration Testing 0 / Not Done 0.0 l 6 O l-
I WESTINGHOUSE CLASS 3 i
~
ACCEPTANCE DATE: 11/02/87 A-78 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Caro t t ne Power & L l ph t Compny ; unit.........................taUNsWICK 2 ' Nets.........................Generst Electric Application......... Campenant . . . . . . . . . . . . . . . . . . . . VALVE f me t t en. . . . . . . . . . . . Utility Component Id........,E51.f 040 System.............. Reactor Core lootetton Cooling of Start Date...... 09/18/87 Utility system..... 2E51 Start Time...... 12:00 Cut.of.servlee Hours...151 Date stort Date. 04/01/76 in service Date..... 04/01/76 - ! Diocevery Date.. 09/18/87 Restoration Hours.......iS1 Accepted Date.... Out.of. service Dete..; [ Erul Dete........ 09/24/87 End flee..... . ..19:00 Safety close.......
-l 2 =!
- Report Date..... 10/01/87 f rout Dete . . . ,WW/87 Mode. . . . . . . . . . . . . . . . s t ensby cond i t i on System Statue................A
- System in Service (OPC/she, Sever i t y L eve l . . . . . . . . . . . . . . . J
- j amed i a t e Internet Erw........ Secondary Coelant or f reeted 'Weter f ailuro Symptom. . ... ... .... ..C . Demand f ault Externet Erw........ Temperature / Nuoldity (Cntrid) f a i lure Mode . . . . . . . . . . . . . . . . . f 0 . F a i l ed t o Open Asblent Temperature .10F to e120f Fellure Detection............A
- Operational Abnormality Swptier............ United Enero & Constructore inc i Cause C:t egory. . . . . . . . . . . . . . .K . Ur*nown $g plier Id........ 3E51 7040 -*
- Cause Description........... 88
- Mechanical Demope/gf rufing Maruf acturer........ Anchor / Dertirg Velve to System Ef f ect.. ... . ...... ....A . Loss of one or More $yeten Funct ione Mfr Nedel Id........ t Plant Ef fect.................G . Resulted in No $1pnt ficent E f f eet Mfr Model No........ DWG.N0 BWB 532158 Corrective Action............ AG
- Repelr Camponent/ Port Mfr Serlet No....... ,
l totion................Z . done of the Above Mfr Standerd........ L sort 8naber. . . . . . . . . . . . Drouins No.......... FP 9527 6311 L. Af fected by f ailure...CEA
. Reector Core tooletion Cooling GE l
FCiture Description Narrative..... . Engineering Codes' WNILE TRTING TO RUN THE REACTOR CORE 190LAfl0N COOLING TURBINE , if
- TRIPPED TWICE CW NIGN EXNAUST LINE PREstuRE . SUSPECT THE EXNAUST CHECK A. Type................ Check VALVE 1.E51.F040 70 SE STUCK CLOSED . REACTOR AT 100% POWER ON THE 5.0perator............ 16ech(Diff.Prese Open/Sprn DISCOVERT DATE . C. Function / Application One Way Flow-D.sady Material....... Cerben Steel--
Cause of failure Norretive.....- E.Sody Manufacturing M Cast i . 1 E51.F040 ETUCa: Closed DUC To SCORED VALVE DUIDES PREVENTING IT FROM F.Nominet. Inlet Site ( 4 to 11.99.IN OPENING , - G.stae (Intet)........ 8.000 IN~ N.Deelen Pressure..... 150.000 P$1G Corrective Action Narrative..... J.Deelen Tegerature.. 1267.000 DEGF-MACHINED TWE VALVE DutDES FOR 1*E51*F040 TO REMOVE SCORING AND FREE UP
? - T:3 VALVE DISC . RESULTS WERE SATilfACTORT . ( PP ) 87 BEKJ1 I flee Operating When Reactor le Criticoli..r DE l- I Time Operating Wen keector le Shutdown.v. 01 -
l:
.Noure Out Testing Performed Fregaency/ Period of service 1 Check Testirg 0 / Not Done . 0.0 fmettonal Testing .1 / Month. . 0.0 Calibration Testing 0 / Not Done 0.0 -
ACCEPTANCE DATE: 02/11/92
\ j Ut i l i t y. . . . . . . . . . . . . . . . i. . . . . F l or i de Powe r Corpor at i on . Uni t . . . . . . . . . . . . . . . . . . . . . . . . .CR Y ST AL R I VE R UN I T 3 '
CS$$............s........... 8ebcock & Wilcon Application......... y z______ _ .__ - I w - =. .-, .- = ,u_- . . - - - . . - -
A-79 WESTIllGi!0USE CLASS 3 C wgunent . . . . . . . . . . . . . . . . . . . . V At yt i W t10n............ Ut il i t y Component I d. . . . . . . . .tW 356 Sys t ee. . . . . . . . . . . . . . Consonent Cool i ng Wa t e r BW ltert Date...... 05/21/85 Ut ili t y S rs tes. . . . . . sW Out of service Mours... 528 " stort tien...... 12:00 Date start Date. 03/13/77 in Service Dete..... 03/1 08 ery Dete.. 06/11/85 t e s t or a t i on Hour s . . . . . . 36 Acc ept ed Det e. . . . Out of service Dete., t ri, s t e. . . . . . . . 06/12/85 (nd flee........ 12:00 Esfety Class....... 1 toport Dete..... 06/21/85 I rgaat D e t e . . . . . . 06/25/85 Mode................ Operating $ ys t ee S t a tus . . . . . . . . . . . . . . . .! 1 re t n/Charew t i n se rvi c e (OPC/50C ) lever i ty Leve l . . . . . . . . . . . . . . .K Degraded Internal inv........ Amelent forgwroture 10f to e1207 f e l t ur e lyspt os. . . . . . . . . . . . . . C
- Demord f aul t Secondary Coolant or f reeted Water f a i l ur e Mode . . . . . . . . . . . . . . . . . f 0
- F e l l ed t o Cpen laternet inv........ Temereture / Hueldity (kot Cntrid) f a i lure De t ec t i on. . . . . . . . . . . . N
- R out i re Otn e rva t i on Other Cause Category...............M = Weer Out $@l l e r. . . . . . . . . . . . C r ere Co Caus e Desc r i pt i on. . . . . . . . . . . . AD W or sie l / Ateerme t We e r s p lier Id.........
88
- Mechanical Donege/Birv$ lng Manufacturer........ Crane to Sys t em I f f ec t . . . . . . . . . . . . . . . .D Degraded f r e i n/ Channel Mfr Model Id....... 147 1/2 Plant E f f ec t........ .. . . .... .G tesulted in ho significant E f f ect Mfr Model Wo....... 147 1/2 Correc t i ve Ac t i on. . . . . . . . . . . . AH
- R epl ac e Por t ( s ) Mfr serial No.......
Docunent et t on. . . . . . . . . . . . . . . 2 None of t he Above M f r s t orderd. . . . . . . . L f t R epor t huser . . . . . . . . . . . . Drawing No.......... System Af f ected try f el ture. , , WEB
- Craponent Cooling Water ed felture Description terrative..... Engineering Codes THE INDU$1RI AL C00 Lit IktET ChtCK VALVE TO THE VtWilL Afl0N F AN MOTOR 5 ,
5W 356 , APPEAtID TO St $1UCK $ HUT ALLOWikG WO COOLANT FLCW 10 THE A. Type................ Check RLACTOR BUILDikG FANS . TMt PROBLEM WAS Dist0VtetD DualWG A RifUELIWG 8. operator............ kone CHUfDOWN $Y AN Cett.ATOR Pitf 0eMlWG A ROVIINE INSPEC110W . C.f uret ion /Applicat ion One Way flow D . t ody Me t er i a l . . . . . . . Certon $ teel Cause of failure herretive..... E.tody Manuf acturing M Cost INI CK VALVE WAS NOT STUCK $ HUT BUT WJULD STICK WHEN CloslWG DUt to f.Nominet inlet Elte ( 4 to 11.99 lN A WOWN HlhGI AND MlNGE Dj$C PIN . 'G.$lte (Intet)........ 10.000 IN M. Design Pressure. ... . 200.000 P$1C Corrective Action korretive..... J. Design tenperature., 100.000 DEGt iMt WlWGE AND WINGE DISC PIN Witt atPLACED .1NE PO$f MAlWitkANCE itti attutis WEtt EAlltf ACTORY . % fine Operating When teatter le Critical..100%
% Tlee Operstirig When teactor le shutdown..100%
Hours out festire Performed frer.pency/ Period of nervice Check testirq 0 / Wot Done 0.0 f met t onal Test ing 0 / Not Done 0.0 Calibration Testing 0 / Not Done 0.0 ACCEPTAhCE DAf t 05/05/14 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . l ows ( L ec t r i c L i gh t ord P owe r C ostany Unit.........................DUANE ARNOLD 1 klSS.........................Generet tiectric Application......... Component . . . . . . . . . . . . . . . . . . . . V AL VE funttlan............ Ut i t i ty Congonent Id. . . . . . . .V32 0047 sys t em. . . . . . . . . . . . . . D i ese t s t ar t ing Ai r GE start Date...... 08/16/85 Utility systen..... 24.01 start ilme...... 12:00 Out-of service Mours... 5376 Date stort Date. 12/31/E3 In service Dete..... 02/27/74 Discovery Dete.. 09/16/85 testoration Moors...... 6644 Accepted Date... 01/03/85 Out of service Date.. E nd *
- e . . . . . . . . 03 /28/26 inr. e........ 12:00 safety Class....... 2 seport Date..... 04/10/86 I rput D a t e . . . . . 04 /10/ 86 Mode................ Operettrq S ys t em S t e tus . . . . . . . . . . . . . . F f r e i n/Chame l i n T es t Sever i t y l evel . . . . . . . . . . . . . . . J t wedi a t e Int ernal inv. . . . . . . . Anblent T emer a t ure +120f to *180f
, _ _ . . =._..m. ._ . .
WESTINGHOUSE CIASS 3 Failuro Spupt em. . . . . . . . . .. . . .C . Demand F aul t . Compressed Air f a i l ure mode . . . . . . . . . . . . . . . . . F 0
- F a i l ed t o open f aternet Erw........ AaR> lent f esperature +120F to +160F F lturo Detection............C
- Survelltence festing Air fm Ca t egory. . . . . . . . . . . . . . . F Me l nt enanc e/ T es t f rg s o plier............ Sechtel Gro w inc
) Description.....~......St* Dirty-
. S(splier Id......... NO DATA FOUND..
AD + Normel/Abnormel Wear Manuf acturer........ Velen valve Corp ' System E f f ect. .. .. . . .. .. . ... .!
- System imet ton /Operst len Unaf f ected -Mfr Model Id........
Plant Effect.................G
- Resulted in No Significant Effect Mfr Model No........ No 2340 Corrective Action............AG
- Repelr Component /Part Mfr Serlet No....... .75"*teD*CK 600SW Decument a t i on. . . . . . . . . . . . . . . .Z
- N one o f t he Above Mfr Stenderd........ ANSI B31.1 CAT LER R epor t Ntadier. . . . . . . . . . . . D rawing No. . . . . . . . . . Vt WDR
.,8yetem Affected by failure...ItADAA
- Diesel Storting Air *GE Felluro Description Narrative..... Engineering Codee DURING ltti DN STAND $f Olt$tL GENERATORS , STARflNG Alt TANC CNICK VALVE SilCES SNUT . A.fype.... ........... Check-8.0perator............ leech (Of f f Press Open/Sprn Cause cf Fellure Norrative..... C. Function /Aalication Cate*Wey flou -
VALVE il DIRff FROM WoeMAL Ust . D.tody material....... Carbon Steel E.Sody Manufacturing M forged
' C;rrective Action Narrative..... F. Nominal;jnlet $lte ( - 1/2 to 1.99 IN > . CLEANED VALVE $AfitfAC10RtLY . C. Site (Inset)........ 0.750 IN N.Deelen Pressure..... 275.000 PSIG J.Deelen temperature.. 400.000 DEGF X flee Operating When Reactor la Critical.. 100%i 1 flee Operating When Reactor is Shutdown..100% .
Noure Out festing Performed Fregaency/ Period of Service i
" Check festing 0 / Not Done 0.0 Functlenal festing 0 / Not Done 0.0-Collbration festing 0 / Not Done 0.0 t t i
WESTINGHOUSE CLASS 3 A-81 l O
, ACCEPTANCE DATE: 04/05/91
- Jt i l i ty. . . . . . . . . . . . . . . . . . . . . .Nor t heas t Ut i l i t i es l Jni t.. . . . . . . . . . . . . . . . . . . . . . . .C0NNE CT I CUT Y ANKEE 1 fist.........................Uestin0 house Application.........
j ;cgonent . . . . . . . . . . . . . . . . . . . . VALVE Fme t t on. . . . . . . . . . . . Jt i t i t y Component I d. . . . . . . . . N$
- btV 38 Systas.............. Main Steam-U ltert Data...... 05/24/88 Utility Systes...... W$$
Itart Time...... 23:00 Out of service Hours... 41 Data start Date. 09/19/84 In service Date..... 09/19/84 l Ilscovery Date.. 05/24/88 Restoration Neurs...... 41 Accepted Date... 03/06/91 Out of service Date. 05/26/88
- ird Date........ 05/26/88 l ind T ime. . . . . . . . 16
- 00 Safety Ctans....... 2
. teport Date..... 06/30/88 Input Date...... 03/06/91 Mode . . . . . . . . . . . . . . . . S t en.tsy Cordi t i on lystes St:tus................E - Traln/Chamel in Service (OPC/SBC) -
l teve
- L eve l . . . . . . . . . . . . . . . J I sned i a t e Intemet Env........ Steam
'a ll . Synytm. . . . . . . . . . . . . .C Demard Faul t External Env........ 'a llur@ Mode. . . . . . . . . . . . . . . . . F0
- F ai led to Open supplier............
. la t ure Det ec t i on. . . . . . . . . . . . A Oper a t i cna l Abnorma l i t y Sw ptier Id.........
t
- aus e C:t egory. . . . . . . . . . . . . . .K Unknown Manuf acturer........ Rockwell Int / Flow Control Div l :aus: Description........... 88 Mechanical Damege/ Binding Mf r Mcdet Id.. . . . . . 3668
A.32 WESTINGHOUSE CLASS 3 Sys t em E f f ec t . . . . . . . . . . . . . . . .D . Degraded I taln/Charine t Ef r Mode t b. . . . . . . 3668 Plant E f f ec t . . . . . . . . . . . . . . . . .G . Resul t ed in #o $ l gni f ic ent E f f ec t Mfr serial No....... Cor rec t ive Ac t i on. . . . . . . . . . . . AK
- R eplace Component (s ) M f r S t arderd. . . . . . . .
D- t e t t on. . . . . . . . . . . . . . . . ! Wee of the Atnve Drawing No......... 26012 $N 1 L sor t ktete r. . . . . . . . . . . . System Af fected by Fellure...HSC - Mein Steam-W Engineering Ccdes felturs Descrlption Warrative..... A MON REfURN VALVE WHICH $UPPLit$ $fEMI f kUM THE F3 $f TAM GthERA10R 10 A.fype................ Check f;3 18R2f TURBlWE WAl FOUND TD 81 $1UCK CLO$ED WHILE UllNG THE B. Operator............ Merust ATHOSPHERIC DUMP . C.Fmet t on/Applic at ion (he Way flow D.Dody Meteriet....... $teet Not Carton or $tnts Cause af felture Warrative..... E.sody Meruf acturing M forged li l$ LNKNOWW WHY THE VALVE WAS STUCK CLO$tD . F.Wominet Intet $lte ( 2 to 3.99 lW 0.$lte (Intet)........ 3.000 IN Corrective Action Warrative..... H.Deelen Pressure..... 1500.000 PSIG T!3 VALVE WA$ QJT 0U1 AND REMWED FRON SERVICE AND A NEW valve WAS J. Design Temperature.. 850.000 DECF WELDED IN PLACE . THE VALVE WELDS WERE IWSPECTED AND HYDto$1AflCALLT TESTED . I Tise Operattre When Reactor is Criticat..100%
% Time Operating When Reactor Is shutdown.. 75%
Hours Cut festing Performd F re<peney/Perled of Servlee Check testing 0 / Not Done 0.0 Functionet festing 3 / two Years 0.0 Cellbration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 06/17/89
,m
\
(
/
~) . . . . . . . . . . . . . . . . . . . . . .Ducpesne L l gh t Company Un d......................... BEAVER VALLEY 2 WS$$......................... Westinghouse A@ticetion.........
Component . . . . . . . . . . . . . . . . . . . . VAL VE F me t i on. . . . . . . . . . . . Ut i l i t y Conpanent I d. . . . . . . . 2E GA 131 System. .. ..... . . . .. . Dieset Stort ing Al t W Start Date...... 03/01/88 Utility Systes..... 36 Start Time...... 08:00 Out of $ervice Wours... 77 Date Start Dete.11/17/87 in Service Date..... 05/04/87 Discovery Date.. 03/03/88 Restoration hours...... 37 Accepted Dete... 07/22/87 Out of+$ervice Date.. End Dets........ 03/04/88 E nd T ime . . . . . . . . 13 :00 lefety Ctess... ... 3 Repor t Det e. . . . . 03/30/09 Irout D e t e. . . . . . 04/17/89 kods................ Operating Setem status................L
- f retn/Channet in service (OPC/$BC)
Seve r i t y L eve l . . . . . . . . . . . . . . . J I med i a t e Intemat Env........ Conpressed Air felture tymptos..............C Demand Foutt Anblent f esterature *10F to +120F F e l t uro Mode. . . . . . . . . . . . . . . . . F 0
- F e l l ed t o Open Externet Env........ Anblent Te@erature 10F to *120F Fel turo Detection............J Incidentet otaservation Air cause Category...............K-. Unknown $wpt i e r. . . . . . . . . . . . Colt Ird inc cause 0:scription........... 98 Mechanicet Damage / Binding $ w ptier Id......... 11908224 System E f f ec t . .. . . . . .. . .. . . . .C Loss of one or More f re in/Cherrwt Fmet icMaruf acturer. . . . . ... Vogt , Henry Machine to l Pl ant E f f ec t . . . . . . . . . . . . . . . . . F R esul t ed i n Demoge t o other E cNi pment Mfr Modet Id........
Cor rec t i ve Ac t i on. . . . . . . . . . . . AG
- R epe l r Corponent /Po rt Mfr Model No........ SV 12324 Documentation................!
- Wone of the Above Mfr Seriet No.......
LER Report We ber............ Mfr stenderd........ ASME 3 System Affected by Fellure...EESDAA Dieset Storting Alt W Drawing No.......... RM 72A*12 F' )Descriptionkarrative..... LJ AN INCIDENTAL OG$ERVATION OPERATOR DISCOVERED THAT THE W0 . 2 Engineering Codes l EMERGINCY DIE $tL GENERATOR Alt COMPRE$$0R WAS RUNulWG CONTIN 73JS8.Y . l REllEF VALVE WAS LIFilhG AND CCMoRES$0e WAS SMOKING Nii WAS ON LINE A.1ype................ Check At 100% POWER At THE 11ME OF FAltuRE DISCOVERY . s. operator............ None
WESTINGHOUSE CLASS 3 ^# C.Func t ion /Applic;t ion one.Wey Flow Cause tf Falture Narrative..... 0.sody Material....... Cerbon Steel CoMPatSSOR DISCNARGE CHECK VALVE ( 2EGA*131 ) WAS STUCK CLOSCO . ROOT t. Body Maruf acturing M Cast CAUSE (MNOWN . TNil CAUSED DAMAGE TO AIR CEMPRISOR DUE TO EFCES$1VE F.Nominst Intet Site ( 1/2 to 1.99 lN " El G AND CYERNIATING G. Site (Intet)........ 0.750 IN i N.Deelen Pressure..... 425.000 PSIG Corrective Attlen Narrative..... J. Design Tenperature.. 110.000 DEGF ortNED CHECK VALVE .
- Tlee Operating When Reactor la Criticat.. 100%
% Time Operating When Reactor le Shutdoun.. 100%
i Hourn out Testing Performed freq;ency/ Period of Service Check Testing 0 / Not Done 0.0 Functional Testing 1 / Month 0.0 Collbration Testing 0 / Not Ocne 0.0 ACCEPTANCE DATE: 05/25/88 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Georg i o Power Company Unit.........................NATCM 2 NS$$.........................Coneret Electric Applicellen......... Ccaponent.................... VALVE F metton............ Utility Component Id.........P42 F04TA System.............. Reactor tido. Closed Cooling Water.GE St:rt 0:te...... 02/2T/68 Utility System...... P42 Start Time...... 12:00 Cut.of. Service Mours... 388 Date Start Date. 09/05/79 in. Service Oste..... 09/05/79 Olocovery Date.. 02/27/88 Restoration hours...... 388 Accepted Date... 04/02/85 Out of. Service Date.. trd Dete.........ll3/14/88 End N me........ 16:00 Safety Clete....... 3 Re, Date..... 04/25/88 f rput Date...... 04/27/88 Mode................ Operating Systee Status................E . Tretn/Chernel in Service (OPC/SBC) Sever i ty L eve l . . . . . . . . . . . . . . . J
- t oened i a t e Internet trw........ Condensate / Nigh Purity Water F lluro $pptca..............D . Abnormel Characterletic Externet Erw........ Temperature / Hunidity (Not Cntrid)
Felture Mode.................F0 . Failed to open Aablent Temperaturr .10F to +12CF Failuro Detection............A . Operational Abnormality Splier............ Generet Electric Cuspany Cause Category...............N . Wear out $@ptler Id......... Cause Description........... 85 . Mechanical Demoge/ Sinding Manuf acturer........ Welworth Co AD . Normal /Abnormel Wear Mfr Model Id....... 5341 System Ef fect................E
- System Function / Operation Unof fected Mfr Model No........ FIG. 5341 Plant Ef fect.................G . Resulted in No Signi" ment Ef fect Mfr Serial No.......
Corrective Action............AN . Reptoce Port (s) Mfr Standard........ Document:t ion. . . . . . . . . . . . . . . .Z . None of the Above Drawing No.......... M26054 L E R R eport Nueer. . . . . . . . . . . . System Affected by Fallure...WBA . Reactor SLdo. Closed Cooling Water G Engineering Codes felture Description Narretise..... DURING A REFUELING OUTAGE , OPERATORS WHILE PERFORMING A SURVEILLANCE A. Type................ Check itST ON THE RfACTOR BulLDING CL0$tD COOLING WATER SYSTEM STARTED THE 2A S.0perator............ None PUMP AND DISCOVERED THE DISCRARGE PRESSURE AND FLOW DID NOT CHANGE IN C.fmetton/ App llcation One.Way Flow T O STCTEM . THEtt WLRE NO SIGNIFICANT EFFECTS ON PLANT OPERATIONS . 0.Sedy Materiet....... . Carbon Steel E. Body Manuf acturing M Cast Cause cf Felture Narrative..... F.Nominet Intet Site ( 4 to 11.99 IN ' THE CAUSE OF FAILURE WAS ATTRIBUTED TO THE PUMP DISCHARGE CNECK VALVE G. Site (Inlet)........ 10.000 IN BEING STUCK OR BINDlhG ON ITS SEAT DUE TO WORN NINGE HANGER AND Plks . N. Design Pressure..... 150.000 PSIG J.nesign Teeperature.. 200.000 DEGF Coe give Actice Narrative..... THE VALVE WAS DilASSEMBLED . CLEANED , AND NEW A MINGE MANGER AND PINS % !!ae Operating When Reactor le Critical.. 100% WERE I STALLED . THE VALVE WAS FUNCTIONAL TESTED PER PLANT PROCIOURE % Time operating When Reactor is Shutdown... 0% AND RETURNED TO SERVICE .
WESTINGHOUSE CIASS 3 Hours out f est f rig Perf ormed F regaerry/ Period of ferylce Check festing 2 / three Year 0.0 F a ticoat festing 2 / Three Year 2.0 Collbration Testing 0 / Not Done 0.0 ACCEPTANCE Daft: 08/28/87 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Sout hern Ce l l f orni e ( d i s on C ornperry unit......................... TAN Owortt i kl1$...................... .. Westinghouse Application......... Comporwnt . . . . . . . . . . . . . . . . . . . .V AL VE Fmetton............ Ut i l i t y Component I d. . . . . . . . .CCWO24 S ys t em. . . . . . . . . . . . . . Corporwnt Cooling Wa t er.W 5 tert Date...... 06/27/86 Utility System...... CCW tiert Time...... 12:00 OJt.cf. Service Nours... 7940 Date Start Date.11/01/84 in. service Date..... 01/01/68 Discovery Date.. 06/27/f4 Restoration Hours...... 7940 Accepted Dete... 01/29/85 Out.cf. service Dete.. End D:te........ 05/24/87 E nd f i sw. . . . . . . . 08 : 00 Safety Ctess........ $t septrt Dete..... 07/28/87 tr5vt Date...... 07/28/87 kode................ Operating systene s t atue. . . ..... .. . ... . .F . Treln/Cherral in f est tes.r l t y L eve l . . . . . . . . . . . . . . . J . l evned l e t e Internet Env........ f ai l uro s ynpt ce. . . . . . . . . . . . . .D
- Abnorme l Cha r ac t e r i s t i c taternal Env........
F al lurs Mode . . . . . . . . . . . . . . . . . F 0 . F e l led t o own Swpller............ Felluro Detection............I . In service inspection Sw ptier 1d......... T29 3.C32 Causs Cat egory. . . . . . . . . . . . . . .K . Uriknown Marsif acturer........ Crane Velve Prod / Crane to Fr Charmen Cause Desc r ipt ion. . . . . . . . . . . . AD . Norma t / Abnormal Weer Mfr Model Id........ Bt . Dirty Mfr Model No....... 147 1/2LU System E f f ect. . . .. . ...... ... .t . system Fmet t on/Operet t en Unaf f ected Mf r Serial No...... 7290 3 C32 P f f ect... .. .. . ... .... . .G . tenutted in No significant E f f ect pfr Standard........ ASME 1.26 3
.t ve Actlan. .. . . . . ..... AH . septoce Part(e) , Drawing No......... 517F.312 Document e t t on. . . . . . . . . . . . . . . 2 . Norw of t he Above Ltt Report hunter. . . . . . . . . . . .
System Af f ected try Felture...WBD
- Coripctent Cooling Wete*.W Engineering Codes felture Description Narrative..... A. Type................ Check VIIN LMIT Af 0% POWER , OPtRAfl0NS SU$PECTED THE TMERMAL SARRItt 8.0perator............ None EMERGENCY SUCTION CHECK VALVE MAY MAVE FAILED DURING THE IN SERVICE C.f met torvAsplication One.Wey Flow Itti 0F ANOTHER VALVE . D. Body Meteriet....... Certon steet E.Sody MarrJfecturing M Cast Cause 5f failure Narrative..... F.Ncainst Inlet $lge ( 2 to 3.99 IN INVE$flGATION FOUND DISC WAS STUCK To SEAT . PULLCD D!$C OFF SEAT WITH G.llte (Intet)........ 3.000 IN A NARD PULL SY MAND . THE NINGE PIN AND DISC ARM WERE CAKED WITH DEBRIS N. Design Pressure..... 150.000 PSIG BUT NO OTHER ABNORMAL CONDifl0NS . CAUSE : NORMAL WEAR . J. Design feeperature.. 500.000 DECF C:rrective Action Narrative..... % flee Operating When Reactor is Critical.. 10%
REPLACED CASKETS AFitt CLEANlWG VALVE INit#NALS . RETURhtD 10 $ttVICE . 1 Time operating When Reactor is shutdown.. 10% Nours out Testing Performed freq;ency/ Period of service Check f esting 0 / Not Done 0.0 Functional Testing 2 / Three Year 0.0 Callbretton Testing 0 / hot Done 0.0
WESTINGHOUSE CLASS 3 A-85 uclear Plant tellability Date System General Report for: Ralph L. M eter, Jr. Report *lce NPRGOOAA estinghouse Electric Corporation Job W e r 1430 Rm Date: 07/07/92 Run ilme: 09:55 Int redaction: The atteched report teas generated by your qJery of the NPRDS data base. A sumary of your qJery is listed below. QUERY: You satected the following search cordition(s): Selected Co m onent is VALVE Selected VALVE Type is Check Selected Unit ids are PAllSADES 1 and FITZPATRICK 1 Selected Systene are Containment $ prey CE and Essential Service Mater GE fird Utility Comonent ids that are egJet to art / one of the following: CK ES3401, CK ES3404, CK ES3405, and 46ESV 19A Selected Maruf acturers are Rockwell int / Flow control Olv, Velan Velve Corp, and Vogt , Henry Machine Co The** were 5 recorde meeting the search condition (s). DISPLAY AND SORT: You selected to rm generat report 5: Component Master f elture Report (w/ Unit Information) You chose to sort the report by: Sort Sequence Fletd Name WPRG05AA Nuclear Plant Reliability Date System Fallure Master Report *Rm Date: 07/07/92 Job Number: 1430 ACCEPTANCE DATE: 04/15/91 Utility.. .................. Consumers Power Cog any thit......................... PALISADES 1 RSSS. . . . . . . . . . . . . . . . . . . . . . . . .Concus t i on Eng i neer i ng App llcation......... Ccaponent . . . . . . . . . . . . . . . . . . . .YALVE Function............ Utility Com onent Id.........CK ES3401 Sys tem. . . . . . . . . . . . . . Cont alment spray-CE Str Dete...... 08/20/86 Utility System...... ESS . St. Ilme.......?2:00 Out of service Hours... 2313 Data Start Date. 07/01/74 In-service Date.....12/3 31scovery Date.. 09/20/86 Restoration Hours......1581 Accepted Date... 01/13/92 Out of service Date.. End Date........ 11/24/86 l Ind T ime. . . . . . . . 21:54 Safety Class....... 2 l
WESTINGHOUSE CLASS 3 M Report 0:te......C2/%J7 _ input Dete...... 04/09/91 Mode . . . . . . . . . . . . . . . . Ope r a t i ng l System $tatus. . . . . . .o ... . . . . .F
- Traln/Channe t in Tes t C [
- y Level...............J * !smediate i nt e rne t Env. . . . . . . .
F[ ] Symptcan..............C
- Demand fault E x t e rne t E nv. . . . . . . .
f a i lur e Mode. . . . . . . . . . . . . . . . 70 F a i l ed t o Open saller. . . . . . ... . . . Becht el Grow Inc Falturc Detection............A
- Op.erational Abnornellty supptler Id.........
Oeuse Category...............F
- Melntenance/ Testing Manufacturer........ Vogt , Henry Machine to teuse Description............ At . Foreign / Incorrect Material Mfr Modet Id........ i I
SE
- Dirty Mf r Mode t No. . . . . . . . E 48217 tr
- Blocked / Obstructed Mfr Serlet No....... 559 157907 tystem E f f ect... .. .. . . .. . . . . .C
- Loss of one or More T ro tn/ Channel Fmet toMf r standerd. . . .... .
8 tant Ef fect.................G Resulted in No SignI 6 teent E f f ect Drawing No. . . . . . . . . . M 204 10
- orrective Action............ AG
- Repelr Cenpanent/Part
)oewent:t i on. . . . . . . . . . . . . . . . Z
- None o f t he Above LE R R eport Number. . . . . . . . . . . . Engineering Codes System Af fected try Falture...SCD - Contaltiment $ prey CE A. Type................ Check Failure Description Norretive..... 8.0perator............ None THE REACTOR WA$ $ NUT DOWN . OPERATOR $ FOUND DURING THE PERFORMANCE OF A C.Fmetion/Amilcation One Way flow NYOROSTATIC TEST THAT 10 DINE REMOVAL NADH TANK DISCHARGE CNECK VALVE 0. Body Meterlet....... Carbon Steel CE E13401 STUCK CLOSED WHEN SYSTEM PREstuRE WA$ APPLIED TO THE VALVE . E. Body Manuf acturing M forged TCRE WAS W EFFECT ON PLANT CONDITION $ . F. Nominal Intet site ( 2 to 3.99 IN G.llte (Intett........ 2.000 IN
*euse cf Felture Warrative..... H. Design Pressure..... 16.000 P$lG TU $USPECTED CAUSE !$ THAT A F0ft!GN MATERIAL ( APPEARED TO BE CAULK ) J. Design Tenperature.. 110.000 DECF 4CCLMULATED SETWEEN THE BCDY OF THE VALVE AND THE GATE DURING A TWO 90NTN PERIOD WHEN THE LINE WA5 ORAINED FOR REPAIRS TO ANOTHER VALVE . % fine Operating When Reactor is Critical.. 1001 X Time operatiris When Reactor is shutdown..100%
lvt Action Narrative..... i I C{]/E T y WAS DISAttEMBLED AND CLEANED 4ElWG OSURVED . AFTER CLEANING , THE VALVE WAS PRESSURE TESTED AND WITN $0ME Testing Performed SMAlt. Frequency / Period AREAS O Houre Out of service
*aaa""*"" aaaa""- """~a RETURNED TO SERVICE .
Check Testing 0 / Not Done 0.0 Functional Testing 1/ Two Yeare 8.0 Cattbraticel Testing 0 / Not Darw 0.0 ACCEPTANCE DATE: 04/15/91 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Conseer s Powe r Company Unit.........................PAtisADES 1 NS$$ . . . . . . . . . . . . . . . . . . . . . . . . . Contus t i on E ng i neeri ng Application......... Camponent . . . . . . . . . . . . . . . . . . . . VALVE Function...........e Utility Component Id.........CK E55404 Sys t em. . . . . . . . . . . . . . Cont a l ement Spray-CE Start Dete...... 05/17/89 Utility systen...... Ess Stirt Time...... 12:00 Det of service Hours... 3802 Date start Date. 07/01/74 In service Date..... 12/31/71 Olscovery Date..10/15/89 Eestoration Hours,..... 190 Accepted Date... 01/13/92 out*of service Date.. End Date........ 10/22/89 End T ime.. .. . .. . 22:55 safety Ctess....... 2 Report Date..... 06/29/90 input Dete...... 04/09/91 Mode................ Operating Systee Status................F Traln/Channet in Test l severity Level...............E Degraded Internal Env........ F a i lure $yuptos. . . . . . . . . . . . . .C Demand F aul t External Env........ F a i lurs MMe . . . . . . . . . . . . . . . . . F0 F ai l ed to Open $4 w ller............ Vogt , Henry Machine to ! Fal M Detection............C - Surveittence Testing Sumlier Id......... Ci, i
'h t egory. . . . . . . . . . . . . . .C Manuf ac t ur i ng De f ec t Manuf acturer........ Vogt , Henry Machine Co C b b scription............A8 Foreign / Incorrect Meterlet Mfr Modet Id........
i 8E Olrty Mfr Model No........ E 48319 BF Blocked /0bstructed Mfr serlat No....... 681 157907 syst em E f f ec t. . . . . . . . . . . . . . . .C Los s of one or More T ral n/ Channel Funct i oMf r $ t erv3ard. . . . . . . . Plant Ef f ect... . . ... .... . ....G Resulted in No $lgnificant E f f ect Drawing No. . . . . . . . . . M 204 - 18
WESTING 1100SE CLASS 3 A-87 Cirr;ct ive Act ion. .. .... . . . .. AH
- Replace Port (4)
Doewent a t i on. . . . . . . . . . . . . . . . D
- F a i l ure R epor t ed t o CorTonent Manuf ac t ur e F
- Failure Analyste Perforced tr.gtneering Codes
'tL . ort Nater............
Systere Af fected by f ailure...bCD + Conteltvnent sprer*Cf A.1ype................ Check 8.0perator............ Manuel felture Description korretty ..... C.f met t on/Applic a t ion tvwaWey flow REACTOR WAS IN COLD SHUfDWW . WHILE PERFORM!kG A $URVilLLAhtt it$f FOR D.tody Meterlet....... Carten $teet
$fR0Kl%G THE 10Dikt t!MOVAL VALVil , if WAS OBittVt0 THAT lColkt E.lody Manufacturing M forged t!MOVAL $0DIUM NYDROXfDE MAKEUP TAkK f*103 CHECK VALVI CK*f53404 WAS F.Ncntnet Intet $1:e ( 2 to 3.99 th $ fuck CLO$tD . THE CLOSE 10tttANCE BODY GUIDED DISC CHECK VALVE hAD TO G 81:e (Intet)........ 2.000 lW B1 MCChAWICALLY AGITAf!D TO OSTAIN FLOU . THE REDUNDAWT f*103 PIPlWG N. Design Pressure..... 16.000 PSIG ftAIN ft$f WAS $AfflFAC10RT . THERE WAS WO (FFICT ON J.Dtsign fenperature.. 110.000 DEGF Cause of Felture terretive..... % flme Operating Uhen Reactor is Critical.. 1001 PLAuf OPERAfl0W . Ol$ ASSEMBLED AND INSPicitD IME VALVE . THE 1 Time Operating When teoctor is shutdown..1001 MAWF Ativett atPatttNTAtlVE AND ENGlkittihG REVitW Af f diputtD THE CAU$E OF FAILUet 10 A COM8thAtl0N OF : 1 ) DIAMETRICAL CLEARANCE SETWEtW THE Houre Out DISC A D SCcY WAS Lt$$ 1 NAN t[Cteet!WDED DUE TO AN OVittlZtD DISC ; 2 ) festing Perforewd frequency / Period of Service fut IKgCDT stat AND Dist stAf WERE PlfftD ; 3 ) RU$f AND A $ MALL AWJUWT ***************** **************** **********
OF DIBRIS WAS FOUND INSIDE THE VALVE VNICH CAUSED Check festing 0 / kot Done 0.0 Functional f esting 1/ Two Years 1.0 Carr$ctive Action herrative..... Calibration festlnC 0 / Not Done 0.0 BlWDING . REPLAttD THE DitC , GROUND AND CLtAkED INE EI AT AND PERFORMED A BLUE CHECK . AllEMBLED AND TORQUED THE VALVE . REVISED THE CHECK VALVE IkSPECfl0N CUIDillkt$ 10 IWCLUDE MANUFACTUREft itCOMMEWDED TOLERANCEE FOR Dl AMEf tl CAL CLEARANCES . INSPECTED ALL OTHtt SIMILAR VALVil FOR GtWERIC PR08LEMS . $UCCi$tFULLY COMPLifED THE SURVEILLLANCE fit' 7 VEtiff opt #Alltiff AND REtVRNED TO SERVICE . l l l l O
WESTINGHOUSE CLASS 3 A-88 O ACCEPTANCE DATE: 02/07/91 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .Consuners Power Cecpany Unit.........................PAlllADES 1 Witt . . . . . . . . . . . . . . . . . . . . . . . . .Cenbust i on E ng i neer ing Application......... Conpanent . . . . . . . . . . . . . . . . . . . . VALVE F me t t on. . . . . . . . . . . . Ut i li ty Ccaponent Id. . . . . . . . .CK t B5405 Sys t em. . . . . . . . . . . . . . Contelnment sprey CE 5 ste...... 08/31/90 Utility System...... ESS
$( jime......12:00 Out.of. service Hours... 3339 Date start Date. 07/01/74 In service Dete.....12/31/71 Dis..very Date.. 01/01/91 Restoration Hours...... 399 Accepted Date... 01/13/92 Out.of tervice Dete..
End D:te........ 01/17/91 E nd f lee . . . . . . . . 15 :08 sa'ety close....... 2 Report Dete..... 01/28/91 trput Date...... 01/28/91 Mods ............... Operating System St atus. . . . . . . . . .. . . . . .F
- T rain / Channel in f est S;ver i ty L evel . . . . . . . . . . . . . . .K
- Degraded Internet ?nv........
F e l l ur e $ ppt ers. . . . . . . . . . . . . .C
- D emand F out t Enternet Env. . . . . . .
F e l lure Mode. . . . . . . . . . . . . . . . .F0
- F e l l ed to Open Sumlier. . .... . . .. . . Vogt , Henry Machine to Fellure Detection............C = Surveillance f esting $ w iler Id.........
Ccuss Cat egory. . . . . . . . . . . . . . . A
- Eng ineer i ng/ Des t en Manufacturer........ Vogt , Henry Machine to cause Description............AA . Foreign / Wrong Part Mfa Model Id........
BF = Stocked / Obstructed Of r 64cce t No. . . . . . . . E 48319 Itt . Dirty Afr Serlet No....... 682 157907 lystem E f f ect. . .. . . . . . . .. . ...C
- Loss of One or kore f re tn/Chanrwl f unc t ioMir Standard. . . .. .. .
Plant Ef f ect.................G
- Resulted in ho Significant Ef f ect Drawing No.......... M 204 1B Correct i ve Ac t i on. . . . . . . . . . . . AG
- Repo l t Ccaponent/ Port Docunent a t i on. . . . . . . . . . . . . . . .D
- F e l l ur e R epor t ed t o Conponent Manuf ac t ure F
- Failure Analyslo Perforsed Engineering Codes
- LER Repor t kucer. . . . . . . . . . . .
System Af f ected by f ailure...tCD
- Containment $ prey CE A. Type................ Check 8.0perator............ Merust Fallure Description Warrative..... C. Function /A@lication One Wey Flow REACTOR WA1 IN COLD $HUTDOWW FOR REFUEllWC . UNILE PERFORMlWG A D. Body Meterial....... Carbon Steel SURVEILLANCE itti FOR STROKikG TME 10D!WE REM 3 VAL VALVES , IT WAS E. Body Maruf acturing M Forged N, TNAT THE ICD!bt REMJVAL $0DILM MYDROXIDE MAKEUP TAkt T 103 F.Wominal Intet site ( 2 to 3.99 IN D ct VALVE CK Et3405 WAS STUCK CLO$ED . THE CLOSE TOLERANCE 82 T G. tite (Inlet)........ 2.000 lh GUIDED 015C CHECK VALVE MAD 10 St MECHANICALLT AGITATED TO OsiAIN FLOW H. Design Pressure..... 16.000 PslG
.1::E REDUNDANT 1 103 P!PikG 1 RAIN TEST WAS SAfl5FACf 0RT . J. Design tenperature.. 110.000 DtGF Cause of Felture Warretive..... % time Operating When Reactor is critical..100%
WESTINGHOUSE CLASS 3 THERE WAS WO (FFtCT ON PLANT OP[tAfl0N . Dl1A$$tMSLED AND INSPECit0 THE % fime opercting When Reactir is shutdom...iDDR
' VALVI . Tkt MANUF ACTURI A StPillENI AllVE AND ENG1htttlWG REVlf W ATTRitVTED TWE CAust OF FAILURE 10 A CCMalNATION OF : 1 ) YtNDOR DillCW Nours Out DI$r GUIDE CLEARANCE AND / OR MACNikt Flkl$N WA$ thADEQUAf t j 2 ) Testing Performed Frequency / Period of Servic Di IN tnt $tlitM WHICN CAUSED BlWDikG 1 3 ) WRONG APPLICAf!ON . ."""."."".. ..""""."." .. "......
Dtball IN TNb $f$lfM KAT REQUlt! THE U$t OF A $WikG CHICK Check festing 0 / hot Done 0.0 - F mettonal festing i / Two veers 1.0 C rrective Action kerrative..... Calibration festing 0 / Wot tune 0.0 VALVE . CLEANED TN! ELVE lWittNALS AND PERFORMED A BLUE CHECK . AlstMsLt0 AND TORQUtD THE VALVE . ItVISED tnt CHECK VALVE INSPECTION GJIDEllWES TO lbCLUDE MANUf ACTUt[R RfCCMMENDED TOLERANCtl FOR DIAMETRICAL CLEARANCES . CCMPLETED THE $URVEILLANCE TE$f 10 YtRIFT OPERABILITT , INSFCCTfD FOR EXf tRNAL LEAKAGE AND RETueNED THE VALVI 10
$ttVIC1 .
..........a.........................................................................................................................
ACCEPTANCE Daft: 01/23/91 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . hew Yor k Power Aut hor i t y Unit........................, FIT 2 PATRICK 1 N5tl......................... General Electric Application......... Conponent . . . . . . . . . . . . . . . . . . . .VALyt function............ Ut i l i t y Corinnent I d. . . . . . . . 66t sw.19 A Systese.............. Essentist service Water GE Start Date...... 01/03/90 utility system..... 046 S tir t T im. . . . . . 12:00 Out of. service Hours... 2524 Dets start Date.10/01/TT in service Date..... 07/28/75 Discovery Date.. 04/03/90 Restoration Uours...... 376 Accepted Date... 05/07/90 out.cf. Service Date.. End Da t e. . . . . . . . 04/18/90 End T ime. . . . . . . . 16: 00 Safety Close....... 1 Report Date...... Input Dete...... 07/31/90 Mode................ Operating Wyst em st atus. . . .. . . . . .. . . . . .F
- Tre tn/Chamel in Tes t Se e lty Level...............J . lopedlete Internal Env........ Teeperature / Numidity (Not Cnt fa e $ p pton..............C Demand Fault Aablent Temperature .10F to eilt failure Mode.................F0 Falled to Open Fresh Water ( Well / River / Lake f ailure Detection............B
- In. Service Inspection Externet Env........ Teaperature / humid *ty (Cntrid) taus e Ca t egory. . . . . . . . . . . . . . . A Eng i neer ing/ Des i gn Air CG u Descript ion. . . . . . . . . . . .EE . D i rty suppller............ Stone & Webster Inc Bf Blockad/ Obstructed Swpller Id. . . . . . . . . VCS 60t System E f f ect...... ... .... ...C . Loss of Orse or More f rein / Channel Fmet toManuf acturer....... . Velen Velve Corp Plant E f f ect.................G . Resulted in No significant Ef fect Mfr Model Id........
Cor rec t i ve Ac t i on. . . . . . . . . . . . AG . R epa i r C onponent/Pa r t M f r Mode l No. . . . . . . . W8 2343 21Y Documnt a t i on. . . . . . . . . . . . . . . 2
- W one of t he Above Mfr Serlet me.......
Lt t R epor t Wusbor . . . . . . . . . . . . Mfr Standard........ ASME System Af f ected by f ailure...WAA . Essential service Water GE Drawing No.......... fs 18N 6.38 12 Failuro Description herrative..... , DualWG $NLFfDCWN OP(RAfl0N WNitt CONDUCTlWG AMERICAN SOCIETT OF Engineering Codes MECHANICAL EWGlWEERS ( ASME ) IN. SERVICE TESTING . EMERGENCY $ttvlCE WATER ( ESW ) SUPPLY CNECK VALVE IN 'A' ELECTRIC BAT UWIT COOLtR WAS A. Type................ Check FOUND STUCK CLO$ED , FOULED WITN pem AND $1LT . TNi$ WOULD PREVENT tsW B. operator..,......... None FLOW TO THE COOLER IN THE CVENT of EMitGEkCY SUT NAD WO EFFECT ON C.Fmetion/ Application One Wey flow , WORMAL PLANT OPERAfl0N . D. Body Met er i al . . . . . . . Carbon $ teel E.Sody Manufacturing M Forged cause of Fallure kerrative..... F.kaninst Inlet Site ( 2 to 3.99 IN IWVESTIGATION REVEAltD THE LACK OF SYSTEM FLOW AND INFREQUENT U$E OF G. Site (Inlet)..u.... 2.000 IN TNIS VALVE NAD PROBABLY CAU$ED THE ACCUMULATION OF MLD AND SILT ON TNi$ N. Design Pressure..... 100.000 PSIG VALyt . THE FAILURE l$ ATTRIBUTED TO POOR SYSTEM DESIGN . J. Design Tecperature.. 80.000 DEGF tk etive Action Narrative..... % fine operating When Reactor is Critical..100% CLEANCD AND FLU $NED VALVE . RET!$ FED THE VALVE AWD RETURNED IT TO % Ties Operating When Reactor is shutdown..100%
$ERVICE .
Nours Out
WESTIliGil0USE CLASS 3 Testire Perforted freg m ey/ Period of service Check Testirg 3 / Dey O 7tsetIonal itsttrq Calibration Testirg 1 / Arvust 0 / Hot Dore 0.0 0.0 0.0 O - 9 O
WESTIllG1!OUSE CIASS 3 u: lear Plant reliability Data 3rstem Cerwral acport fort ph L. M mter, Jr. Report Id WAC00AA Westinghouse Electric Corporation Jc6 Number 1$05 km Date: 07/07/92 aun ilme 10:28 1ntrodxtIan: the attached report was generated by your query of the NPRDS data base. 4 summary of your cpery is listed below. cur.tts fou selected the following search condition (s): Selected Ccaponent is VALVE Selected VALVE Type is Check find Utility Component ids that are equel to any one of the f:ltowing: 2*CN*181, 2CD0043, CK*CC941, erd 056*1F081 Selected Manuf acturers are Crane Co, Crane Velve prod /Crare to fr Chapman, and RockwelL Int / flow Control Div Selectsd Unit ids are Pall 8ADES 1, ZION 2, LIMERICK 1, and SURRY 2 Selected systems are Component Cooling Water *CE, Nigh Pressure Coolant Irijection-GE, Condensate W, ard Chemical 8 Volume Control *W , there were 4 records meeting the search condition (s). 31$ PLAY AND $0Ris fou selected to rm general report 5: Ccaponent kaster f elture Report (w/ Unit Information) fou chose to sort the report by tort se< pence field Name 4PtG05AA Nuclear Plant Reliability Data System
- falture kaster Keport Rm Detas 07/07/92 Job Nusber 1505 ACCEPTANCE DATE: 04/14/87 Jt i l i t y. . . . . . . . . . . . . . . . . . . . . . Consumers Power Cenpany Jni t . . . . . . , . . . . . . . . . . . . . . . . . . P Al l tADE S 1 (S$' . . . . . . . . . . . . . . . . . . . . . Contus t i en E ng i neer i ng Application.........
- capu. amt . . . . . . . . . . . . . . . . . . . . VALVE function............
Jt i l i t y Cenpanent I d. . . . . . . . . CK CC941 Sys t em. . . . . . . . . . . . . . Corrponent Cool ing Wat er CE Itart Date...... 12/04/86 Utility System...... CCS St:rt flee...... 16:20 Out of service pours... 1157 Data Stort Date. 02/14/84 In service Date..... 02/14/84 )iscovery Date.. 12/04/86 Restoration Nours...... 1157 Accepted Dete... 01/13/92 Out of service Date..
WESTINGHOUSE CLASS 3 EM Dete.. . . . . . . 01/21/87 trd f lee. . . . . . . . 21:15 safety Ctess....... 3 Dete..... 04/01/87 1rgut C a t e. . . . . . 04/01/87 Mode................ Operating Status.... . . . .. . ......! 1 rein /Chernet in service (OPC/$BC) lever i ty Leve l . . . . . . . . . . . . . . . J I medl e t e internet inv........ F e l lur e syvpt em. . . . . . . . . . . . . . C
- Demord f w l t E x t e rna l i nv. . . . . . . .
F e l l ure Mode . . . . . . . . . . . . . . . . . F 0
- F e l l ed t t. Open SurpL ler. . . . . . . . . . . . Secht el Croco Inc f a i l ur e D e t ec t i on. . . . . . . . . . . . A
- Ope r e t t ora l Atnorme l l t y k4 plier Id.........
Cause Ca t egory. . . . . . . . . . . . . . .N
- Weer Out Manufacteter........ Crone to cause Desc r i pt i on. . . . . . . . . . . . AD + Nor1he t / Atnorme t Wea r Mfr Model Id....... 123 50
- Aging / Cyclic Fettpue Mf r Modet ko.. . . . . . 123A S ys t em E f f ec t . . . . . . . . . . . . . . . .C L os s of Ore or kor e I t a l n/Chenne t f unc t i m f r les h l bo. . . . . . .
Plant Ef f ect.................G
- Resulted in No llentf f cont E f f ect Mfr $tr uard... ..
Corrective Act ion.. .... ..... . AH Rept oce Part(s) Dravirig No........., N.209 3 Document a t i on. . . . . . . . . . . . . . . 2 N one of the Atwe Lt R R epor t Nrertnr. . . . . . . . . . . . System Af f ected ty Felivre...WBC
- Concorwnt Cooling Water CE Engirweing Codes failure Description Norrative..... A.fype............. Check REACTOR WAS IN COLD SHUTDOWW . WHEM STARilkG COMPONENT COOLING WAftR B.0perator............ None FWP P 52A VNILE THE AMPS WERE VERY LOW AND THERt WAS N0 fLN , C.F metton/Applicetlen One Wey Flow OPERAfl0W5 PtRSONNEL NOTED THAT THE C*MP0htNT COOLING WAf tR FWP D .S ot.ty Me t e r i e l . . . . . . . Carbon $thet DISCHARGE CHECK VALVE CK CC941 WAS STUCK IN THE CLOSED P051 TION . 1HERE t. Body Manuf acturing W Cast WA$ No (FFECT ON PLANT OPitA110N . F.Ntalhet inlet $lte ( 12 to 19.99 IN G.ll te (Inlet ). . . . . .. . 16.000 IN Cause of failure korretive..... H. Design Pressure..... 150.000 PSIG RENOVED AND INSP(CTED IME VA(Vt $ TAT , DISC AND MINGE PINS . If WAl J. Design Temperature.. 140.000 DECF DitCOVERED INAT THE PIN $ WLRE DEf tRIORAT[D AND THE PIN Molt $ MAD L 'CE OF NOTABLE WCAR ON TkE TOP SIDES . THE CAust OF THE FAILUtt it I flaw Operating Wnen Reactor la Critical.. 1001 ED TO NORMAL AGING AND WEAR . ,1 time Operating When Reactor le Shutck)wn... 01 Corrective Acti9n Narrative..... Hours Out CLEANED INE VALVE INitRNALS AND FLANCES . REPLACID THE HlWGE PINS AND f esting Perforced Fre@ency/ Period of Service CAtKETS . BLUE CHECKED THE FLAPPER SEAT , CLEANED AND INSTALLED . '"""**'"' * " ' " * " " " ' " " '
- LUBRICAf tD THE PINS AND EN$uet0 THE CLAPPER WAS FREE AND THE PINS kAD A Checit Testing 0 / Not Done 0.0 C000 fit . PERFORMED A MYDRostATIC TEST 10 VERIFT THERE WAS Wo LEAKACE Fmettonal Testing 0 / Not Done 0.0
. YttiflED THE DISC WAS FREE TO PlVOT IN THE VALVE BODY , REINSTALLED Calibration Testing 0 / Not Done 0.0 AND RETURNID CK CC941 10 SERVict .
ACCEPTANCE DATE: 05/22/86 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Comonwe a l t h E d i son Cornpeny Unit........................ 210N 2 W$$$......................... Westinghouse Appl i c a t i m. . . . . . . . . Ccaponent . . . . . . . . . . . . . . . . . . . . VALVE F me t t on. . . . . . . . . . . . Ut i l i t y Copponet I d. . . . . . . . 2CD0043 S ys t em. . . . . . . . . . . . . . C ondens a t e W start Date...... 02/20/86 Utility System...... CD Stort T ime. . . . .. 12:00 Out of service Mours... 24 Date Start Date. 10/C1/74 In $ervice Date..... 09/19/74 Dlacovery Date.. 02/20/86 Restoration Hours...... 24 Accepted Dete... 04/16/84 Out of service Dete.. trd Date........ 02/21/86 E nd 11me . . . . . . . . 12 : 00 tafety Ctese....... 4 Report Dete...... Irvut Date. . . . . . 04/29/86 Mode................ Operating System $tetus. ... ... .... . .. . .t Tretn/ Chemet in service (OPC/stC) Sever i ty L evel . . . . . . . . . . . . . . .J I medl et e Internal Inv........ Anblent Tenperature Over +180F f $ rupt om. . . . . . . . . . . . . . C Demand F evl t Condensate / Nigh Purity Water F- e Mode.................F0 - Failed to Open Esternet Env........ Tenperature / Heldity (Not Cntrld) Felture Detection............H - Routine 00servation Anblent lenperature *10F to +120F Cause Category...............H a Weer out Suppt ler. .. ... . .. . . Westinghouse E lec Corp / Hagen Cause Descr ipt ion. . . . . . . . . . . .B F - Bloc k ed/Obs t ruc t ed Suppd er Id......... BG - Corrosion Manuf acturer........ Crane Velve Prod / Crane to Fr Chapman
WESTINGHOUSE CLASS 3 A-93 System E f f ec t. . . . . . . . . . . . . . . .C L oss of One or More t rain / Channel Fme t i caf t Mode t id. . . . . . .. Plant Ef f ect........ .. ... . . . .G sesult ed in ho $lenificant E f f ect M f r Model No. . . . . . . 16L323A C;r* 't i ve Ac t i on. . . . . . . . . . . . AG
- R epe l r Cosponent/Pa r t Mir lerfel ko.......
0 06 .t e t t en. . . . . . . . . . . . . . . 2 b ore of the Af *e M f r S t aMard. . . . . . . . LER Report htm6er............ Drawing ho.......... M 506 System Affected by failure... pt Condensatt f ailure Description kerretive..... Engineering Ccdes WifN UN!! ! AT FULL POWER , $NIFT PER$0NkEL RECElVED lWDlCAfl0W THAT fr'At WASW'T ANY FLOW THRCUGN THE 2A CONDENSATE IKo$1Et PLMP CHECK A. Type................ Check VALW 2CD0043 WITN THE PUMP RUNNtWG , AN IWDICAfl0N 1NE VALVE WA$ $1UCK 8.0perator............ hone CLOSED . C.Fmeticrg/ Application One Way flow D. Body Ma t ee l s t . . . . . . . Carbon Steel Cause cf failure Warrative..... E. Body Manuf acturing M Cast VALVE DitC WAS STUCK CLOSED W'fM C0tt0$10N . F Nominal inlet $lte ( 12 to 19.99 IN G.81:e (inlet)........ 16.000 IW C frective Action herrative..... N. Design Pressure..... 720.000 PSIG OPENED VALVE FLANGE . JACKED DISC OPEW AND REMADE FLANGE UP U$1WG J. Design Teeperature.. 850.000 DECF , OrlCthAL CASKET . 1 Time Operating When Beactor la Critical.. 75%
% fine operating When Reactor is Shutdown... 0%
Noure Out festire Performed freq;ency/ Period of service Check festing 0 / Not Done 0.0 Fmettons! Teeting 0 / Not Done 0.0 Collbration Testing 0 / Wot Done b.0 ACCEPTANCE DATE: 03/25/87 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . . Ph i l ade l ph i e E l ec t r i c Company Unit......................... LIMERICK 1 NS$$.........................Generet Electric Application......... Compment . . . . . . . . . . . . . . . . . . . . VALVE F me t t on. . . . . . . . . . . . Ut i l i t y cononnent I d . . . . . . . . 056 1 F 081 Systes.............. High Pressure Coolant injectlon GE Start Date...... 08/03/85 Utility System..... 056 Start Time...... 12:00 out of service Mours...1685 Date Start Date. 02/01/86 In $ervice Dete..... 08/26/83 Discovery Dete.. 09/19/85 Bestoration Nours...... 568 Accepted Date...10/29/85 out of Service Date... E nd Da t e. . . . . . . . 10/12/85 E nd 11me.. . . . . . . 16 :30 $efety Class....... 2 seport Dete..... 03/18/87 Irput Da t e. . . . . . 03/18/87 Mode. . . . . . . . . . . . . . . . $ t ardy Condi t i on i System Statue.. . .. . . . . . .. . . . .F Tra ln/ Channel In f est l Sever i t y L evel . . . . . . . . . . . . . . . J
- Inmedi at e Int ernet Env. .. . . ... Ai r l Failure Sywptom. . . . . . . . . . . . . .C
- Demand F ault Externet Env........ Amblent Tenperature +10F to +120F Fa i lure Mode. . . . . . . . . . . . . . . . 70 F a i l ed to Open Surpt ier. .. .. . .. .. .. Secht el Grote Inc i F:lluro Detection............C
- Surveillance Testing Surst l er I d. . . . . . . . .
Caus2 Cat egory. . . . . . . . . . . . . . . N Wear Out Manufacturer........ Rockwell Int / Flow Control Div Caun3 D:sc r i pt i on. . . . . . . . . . . .B F B l oc k ed/Obs t ruc t ed Mfr Model Id....... 838Y BG Corrcston Mf r Model No........ M1475 3 FIG 838YT1 Sys t ee E f f ect . . . . . . . . . . . . . . . .D Deg raded T ra ln/Chenne l Mf r Serial No. ...... Plant E f f ec t . . . . . . . . . . . . . . . . .G R esul t ed in No $l gni f i c ant E f f ect Mfr Standard........ ASMElli 2
- Correc t ive Ac t i on. . . . . . . . . . . . AG R epa i r Copponent/ Par t Drewing No.......... PID M 56 Document a t i on. . . . . . . . . . . . . . . 2 N one of t he Above LE' mrt Ntaber............
Syswa Af fected by f alture...$FC Nigh Pressure Cootent injection GE Engineering Codes f ailurs Descrlption karrative..... A.1ype................ Check INE PLANT WA$ AT 19% POWEk WHILE PERFORN!WG A SveVEILLAWtt TEST ON THE B.0perator............ kone NIC:t PRES $URE COOLANT INJECil0N ( NPCI ) SYSTEN WHEN THE HPCI C.Fme t t on/ Asplic a tion One Way Flow
WESTING 110USE CLASS 3
$APCMittlC CONDIN$tt VA(RM FU4P Di& CHARGE CHECT VALVE 0561F081 $1DCE D.tody Me t:r t e ! . . . . . . . Certa:n Steel IN TO CLD500 PollfloW CAullWG THE VACLAN PUMP 10 TRIP . MAFNO 85075TT t. Body Manuf acturing M Cast ,q F.Nominst inlet 51 e ( 2 to 3.99 IN C )f Failure Narrative,.... G.slie (Intet)........ 2.000 1N b VALVE INitRNALE WERE CORRCE>tD . N.Deslon Pressure..... 940.000 PSIG J. Design Tenperature.. 700.000 DEGF Co#rective Action Narrative.....
CLEANtD INitRNALS , INSTALLED AND LAPPED NEW PLUG IN CHICK VALVE X Time Operating Een Re6* tor is Critical... 0% 056.iF081 . 1 ilme Operating When Reactor is shutdoun... 0% Noure Out Testing Perfor ed Fremency/ Period of service Ched Testing 1 / Month 0.0 Fmettonal Testing i / ouarter 0.0 Collbration festing 0 / Not Done 0.0 ACCtPTANCE Daft: 04/17/89 Ut i l i t y. . . . . . . . . . . . . . . . . . . . . .Y l re i nt o Powe r tkilt.........................SURRY 2 N$$8......................... Westinghouse Application......... Congenent.................... VALVE function............ Utility Component Id........ 2.CH.181 $ystem.. .. ... .... . . . Cheelcel & Volune Contf ol.W
- St:rt Dete...... 01/23/85 Utility system...... CN st:rt Time...... 12:00 out of. service Hours... 15983 Date start Dete. 01/01/23 in. service Dete..... 05/01/73 Discovery Date.. 01/23/85 Restoration Neurs...... 15983 Accepted Date... 04/16/89 Out of service Date. 11/20/86 End D:te........11/20/86 C M me........ 11:00 safety Ctess....... 2 f rout Date...... 07/24/87 Mode................ Operating C
) Dete..... 07/23/87
- 8,...J 8tatus. . ....... .. ... . .E . T raln/Channet in Service (OPC/stC) tever i t y L eve l . . . . . . . . . . . . . . . J . Ismed l e t e Internet Erw........ Hydrogen F e l luro Syept om. . . . . . . . . . . . . .C . Demand f aul t Externet Erw........ Temperature / Nunidity (Not Cntrid)
F:lluro Mode.................F0 . Felled to Open Sgptier............ Westinghouse Elec Corp / Nogen f a iluro Det ect i on. . . . . . . . . . . . A . Operat i onal Abnormal i t y twpt ler Id... . . .. . 1.C58 Cause Ca t egory. . . . . . . . . . . . . . .K
- Unkrewn Manuf acturer........ Rockwelt Int / Flow Control Div Caus) Descr i pt ion. . . . . . . . . . . .BE
- D i rty Mfr Model Id....... 3674 AD . Normel/Abnormat Weer Mf r Model No....... 3674F316J System E f f ect.. .. .. ... .... . . .t . Degraded System Operation Mf r terlot No....... DWG.#C.464947 Plant Effect................ 0
- Resulted in No $lgnificant Effect M f r S t arde rd. . . . . . . . AS TM A182 Cor rective Action............ AK
- Replace Component (s) Drevire No.......... 11548 888 Document at im. . . . . . . . . . . . . . . .Z
- None of the Above Lt R R epor t Numbe r. . . . . . . . . . . .
System Af f ected by f ailure...PCG . Chemical & Volume Control.W Engineering Codes Falluro Description Warrative..... A.1ype................ Check VITN UNIT 2 AT 50% POWER , AN OPERATOR TRYING 10 ADO NYDROCIN TO THE B.0perator............ None VOLtME CONTROL TANE FOUND THE CHECK VALVI ( 2*CH.181 ) . IN 1NE FLOW C.Fmetton/Applicotton One Way Flow PATH , STUCK CLostD . ( RING , WO : 012751 , 85 001 . 4C2 ) D.tody Meterlet....... Austenttic stnts stl.316 L. Body Manufacturing M Forged Cause of Fellure Narrative..... F. Nominal Inlet $lte ( 1/2 to 1.99 IN UNINOUW . SUSPECTED 10 St DEPOSITION of EXTRANEOUS MATERI AL / VEAR OF G. tite (Inlet). . ... . .. 1.000 IN CCCK VALVI INTERNALS . M. Design Pressure..... 25.000 PSIG J. Design Tenperature.. 110.000 DEGF C ive Action korretive..... R v f2D VALVE AND PIPE . 1 Time Operating When Reactor is Criticot... 51
% Time Operating When Reactor is Shutdown... 0%
1 Hours Out Testing Performed frequency / Period of Service
.- - - . . . ~ . . ..-. .
WESTINGHOUSE CLASS 3 A-95 Check festing 0 / Wot Done 0.0 fmettonal Testing 0 / Not Done 0.0 Calltration Testing 0 / Not Darw C.0 O' O
WESTINGHOUSE CLASS 3 uclear Plant tellability Data systee ! General Report stph L. Meter, Jr. Report Id krtG00AA Wetttrap.ouse Electric Corporation Job Nwter 1520 km Detes 07/07/92 k m Tiset 10:41 Introductlen: The attached report was ponerated try your gaery of the hPRDS date bene. A sumery of your cpery is listed below. QUERY: You selected the following search condition (s):
$etected Component is VALVE Selected VALVE Type is Ched Selected Unit 10s are ROBINSON 2 and $URRY 1 Selected Systeem are Dieset starting Alr W, Condensate W, ard Main fechster System W Find Utility Corponent ids that are equal to any one of the followlrst FW 1A,1 EG142, erd C 27,*
telected Maruf acturers are* Atwood & Morritt Co Inc / Xceox, somey Forpe Div / Gulf 8 Western, and Vogt Henry Machtte to a re 4 records soeting the search condition (s). , Ol$ PLAY AND $0R13 You selected to rm generet report $1 Conponent Master Fellure Report (w/ Unit Information) You c. hose to sort the report try: . Sort Se< pence fletd kame kPkG05AA mucteer Plant Reliability Data system
- f elture Master Report Rm Date: 07/07/92 Job Nunber 1520 ACCEPTANCE DATE: 11/21/89 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . .Ca r ol i na Power & L i gh t Ccapany Unit.........................R00Ik$0N 2 WS$$......................... Westinghouse Application.........
Cc-wwnt . . . . . . . . . . . . . . . . . . . .V ALVE F me t t on. . . . . . . . . . . . v Cceponent Id.........C 273 System.............. Condensate W [ ft . Date...... 09/30/89 utility system..... 3070CMV start Time...... 12:00 Out-of service Moors... 263 Data Start Date. 01/01/60 In-service Date..... 03/07/71 Discovery Date.. 10/08/89 Restoration hours.......t3 Accepted Date... 11/02/89 Out of service Dete.. E rd ca t e . . . . . . . . 10/11/29 trd flee........ 11:00 $afety Class....... 4
A-97 WESTINGHOUSE CLASS 3 Seport 0;te..... 10/30/89 fr4ut D:te...... 11/07/89 Mode................ Operating Sys t ee S t a t us . . . . . . . . . . . . . . . .F ~ T ra ln/Cheryw l in f e s t Severi t y Level . . . . . . . . . . . . . . . J
- lonedl e t e internal inv........ Condensate / Nigh Purity Water Fe i s ymp tas. . . . . . . . . . . . . . C
- Demord F aul t f a t e rna l E rw. . . . . . . . Anti t ent t enper a t ur e 10 F t o + 120 Fal w o Mode.................F0
- Failed to Open insulated f ailure Det ect ion. . ... . . . . . . .C
- Surveillorce tes t ing $wil er. . . . . .. . . .. . tbesc o tyse inc t ause C a t egory. . . . . . . . . . . . . . .K
- Urtrxwn $qpplier Id.........
Cause Description............tG
- Corrosion Manufacturer........ Vogt , Henry Machine Co System E f f ect.. ..... .. . .. . .. .C
- Loss of the or hore f reln/Charinel func t ioMf r Model id. . . . . . . .
Plant Ef f ect.................G
- Resulted in No $lgnificant Ef fect Mir Model No. ... ... . E4$270 R10 Correc t i ve Ac t i on. . . . . . . . . . . . AG
- R epe l r Cceconent/Pa rt Mfr Serfel No.......
Document a t ion. . . . . . . . . . . . . . . 2 . None of t he Above M f r $ t erderd. . . . . . . . Ltt Report Wudaer............ Drawing No.......... G-190197 $N.2 System Af f ected ty f ailure...NNE
- Condmeate.W Felturo Description Narrative. ... Engineering Codes f3 PLANT WAS IN A COLD $NUTDOWN CONDlfl0N WHEN Suevt!LLANCE ftSilNG CVEAltD CONDENSATE PLMP$ $tAL WAf tt $UPPLT CHECK VALVE C 273 APPEAf tD A.fype................ Check TO Bt STUCK SNUT . A CACE WAS ttMOVED DOWNSit!AM OF VALVI C 273 DN THE B. Operator............ None SEAL laitt ilNE AND THttt WAS NO FLOW 10 EMERGE . C. function / Application One Wey Flou D.tody Meterial. . .. .. . Carbon Steel Cause cf Fallure Norrative..... E.gody Maruf acturing M forged C~ 4 CK VALVE C 273 WAS STUCK IN THE CLostD Postil0N WifN CORR 0510N AND F.Nominst inlet $lge ( 1/2 to 1.99 IN RU$f . G.$lge (Inlet)........ 1.000 IN N. Design Pressure..... 100.000 PSIG tverective Action Narrative..... J. Des 19n fesperature.. 150.000 DEGF REMOVED INE TOP OF THE CHECK VALVE , CLEANED .ALL VALVE INTERKALS ,
INITALLED A ktW GASKti , REINSTALLED INE TOP OF THE CHECK VALVE AND 1 flee Operating When teactor le Critical.. 100% LIFT YME VALVE IN $Af!SFACTotlLT OPERAllNG CONDif!DN . WORK REQUEST % fine opernting When Reactor le thutdown... 0% MK 81 . KND . Noure Cut Testing Performed frequency / Period of Service Check Testing 0 / Not Done 0.0 Fmctional Testing 0 / Not Done 0.0 Calibration testing 0 / Not Dans 0.0 l 9
WESTINGHOUSE CLASS 3 A-98 I 1 s W ACCEPTANCE Datt 10/30/89 t A ......................sebrask e Pubtle Power Dis t rict g 46.).......................CODPtR1 Applicellen......... Main Steam Safety /AD$ Pipe Vec trk NS$8.........................Generel (Lectric ime t I on. . . . . . . . . . . . Copponent....................VALvi tys tes. . . . . . . . . . . . . . Mai n S team CE Utl Li ty Component Id.........M1 CV.26CV Ut ility Systee.... . . Ms Start Date...... 04/20/68 in service Dete..... 05/21/83 OJt*of service mours... 1656 Date Start Date. 01/01/64 5t:rt ilme...... 12:00 Accepted Dete... 06/12/89 Out.cf.$ervice Dete.. 016covery Date.. 05/04/88 Restorstion Hears......1332 End Da t e. . . . . . . . 06/28/88 tafety Class....... 2 tess ilme........ 12:00 Mode. . . . . . . . . . . . . . . . Ope rat ing Report bete..... 09/26/88 trout Dete......10/11/89 System Statue................G
- Treln/Chemel in Melntenance Int ernet tm . . . . . . . .
Seve r i t y Leve l . . . . . . . . . . . . . . . K . De s reded f a t ture Synyt om. . . . . . . . . . . . . . A
- Phys i cal f aul t External Em........ Redletion fleLd (Neutron / Comma) titrogen f ailure Moce.................M0 . Poeti during Test (rg/Surveittance/Inspec failurs Detection............D Preventive Melntenance S e tier............ GPl Controle Suppl i er 10. . . . . . . . . LD 240445 Cause Cat egory. . . . . . . . . . . . . . .N
- War Out Manuf ac turer. . . . . . . . CFt Cont rols Caus) Description............lG - Corrosion 3rstem f wstleryt$eration unaf f ected Mfr Model 1d........
System Ef fect................t
- Resulted in No Significant Ef f ect Mf r Model No........ LD240 445 Plant (f fect.................C Mf r ler t al No.. . . . . . 7903*0680 7 Corrective Action............AN + Replace Pert (s)
Dor,unent a t i on. . . . . . . . . . . . . . . .! None of the Above Mir Standard........ Drest ra me.... . . . . . . LD240 4A$ tui ttR Report Niamer............ tystem Affected by failure...CCA kein Steam *GE Engineerine Codes {Oe Description karrative..... L , A ECHLDULED OUTACt . A PitytutAf!VE MAlW1EkANCE ACil0N ITEM WA$ A. Type................ Check Pf1704,M10 AND TMt MAIN $1EAM RttlEF VALVE ( MStv ) DISCMARGE PIPikG
- 8. Operator.. ......... none VACULM 8tf AK!A CHICK VALvf I CV ) MS RV 26 vAs Fouu0 to RE DAmaGto .
C.f unction / Applit ation Vecuura Relief 17$ itAvil RIOe , BumPtt AND suMC viet PLAttlCAtt1 OkFoeMED .1HL D lody Mat eri et . . . . . . . Austenttic Stnis $tt*316 0*tRAll0N of 1Mt COMPCstaf Wat AFFtCffD , so CTMit 5tS71w3 Of f.t wy Manufacturing M Cost COMPONENTS Wtti AFFECitD .
WESTING 110USE CIASS 3 ^~" 7.:orrinal intct life ( 4 to 18.99 IN Cause of f ailure Narrative..... C.slae (Inlet)........ 10.000 13 UPOW IRAMihAf tta Of ins VACVUM $ttAr.tR'$ STAT AND Dilt CONIACI SL'ATACES N.Dee lgn Pre 86ure... . . 625.000 Pil0
, A '"G: of RVST WAS f cuwo . f >t 5fAf AWD 011C FAILtD TO C#th J. Design leaperature.. 500.000 Df1F IMm FLY DVI to INE BONDikG Ef f ECT Of Imt 20$1.1kt NiCM ACCitttAflCN CAU$t0 Wf h if Dl0 OPlu RESULi[D lh f 0RCtl plCM INa>CN 10 % fime operstfre When teettor le Crititel..103% &f f 0tM THE it Wtl
- STC# Of fMt VACVUM Sl( AKf 8 WIN II (MPikGtD OW TM( 1 flPe Opertting Wher) Reett0f it $hutdtwi.. 10%
INittlO of TNC DitchARGE PIPt . houre CMt Corrective Attlan 86erative..... Testing Performed Freguercy/ Period of lervice A PRivt';f AtlV! MAluf thAwCE ACfivilf RA$ $(IN IkttRfD TO Al&UAt ik&T f Mt ................. ................ .......... Cowf ACT $UtfActs of TN! VACLtJM St! AKik'$ $CA1 AND DllC Akt CLEAWID Check testtrg 0 / Not Done 0.0 l (rtif ttfutLik0 CLff ALE , TPC Msty was P(fuegith(D Wif u REPLAttMiki furstional festing 0 / Not Done 0.0
#AAf 8 AND THE MttV PRtytuf Afivt MINf tkANCC ITEM WAS COMPLif tp Calibration festfrq 0 / Not Done 0.0 SAfl$f ACf 0 tilt . ( hCe 88116 )
I O
A-100 - WESTINGHOUSE CLASS 3 ! w ieer ,ient e:n ehin ty :ia erste. . General eeport
.f
- f. " '*.Lph.L. M eter, Jre ~
Ieport=1di NPeG00AA
) tinehouse tiectrI6 Corporation - Job her 7940 ;
Am Dets 09/08/92 Sun fine 10:00 ; Intradations , i the ettsched report was generated by your query of the keeps data base. s eunnery of your spery la (Isted below. } i auteYs feu s: letted the followin8 search condition (s) Selected Co yonent is VALVE , telected vatyE twat la check - telected unit 30 le sea m outF 1 Selected $rstes is Mein Steam CE -! find Utility Component ids that are equel to any one of the followin8s N1821f 037M, e182tf 0377, N1821P078A, and hip 21F078u Selected Manufacturer is Atweed & Merriti Co inc / Xerms
'here were 5 recorde seetins the seerch condition (s). .
?
P 4ND $04f: ,
,0
'ou selected to run seneret report 5:
Cosponent mester Failure toport (w/ unit lefonnetten) , i vu chose to sort the report in's $ sort Secpence field Name IPes0$AA sucteer Plant Reliability pote 8retam f ailure Master Report am Date: 09/04/92
-Job nunters 7940-ACCIPfastE Daft 02/21/91 1 ]tilltr......................EntereyOperettoae, Inc.
Ini t . . . . . . . . . . . . . . . . . . . . . . . . 0 RAND GUL F 1
'StS t. . . . . . . . . . . . . . . . . . . . . . . 0enere t i t ec t r i c Appliestion......... Main Stoem $efety/ ADS Pipe Vec $rk -
.enpenent....................vatvf f mction............
! 't lli ty Component ' Id.'. . . . . . ..k1821F078u S ys t em.'. . . . . . . . . . . . . Me in s t oom- CE , Utility systee..... 821 F Ltert D:te...... 01/18/90 4 tert time...... 12:00- Out of.$ervice hours... 6438 Dete stort Date. 07/01/85 In* Service Date..... 06/16/82
'[ out of*$ervice Dete..-
T y Date.. 10/04/90 Kesteretton pours...... 204 Accepted Date... 07/16/90 A i........ 10/12/90 safety Ctess....... 3
.nd f l ee . . . . . . . . 12 :00
'eport este..... 10/18/53 Input Date.......t2/27/90 Po0e................ Doeroting lysten Status....'...........f'* .' .
1 rein /Chennel in Test i l l
. . - , . - - . ,: - . . - - , . ~.. . . . - . . - . - . - , - _ - - - ,_ ,.
WESTINGHOUSE CLASS 3 A-101 Severity Level...............t . Degraded Int ernet E nv. . . . . . . . St eam f ei t urc Sympt om. . . . . . . . . . . . . .t . Out of Speci f i c a t i on Ancient Tenperature Over +*.80F fall- tode. . . . . . . . . . . . . . . . . f 0 . f a i l ed t o Open External Env........ Air Fall. 4 tt
- on. . . . . . . . . . . .C . Survel t lanc e t es t ing Ancient tenperature +120F to +18s
- aus) CCt every. . . . . . . . . . . . . . .K
- Unk nown Supplie r. . . . . . . . . . . . Bechtel Group Inc
*ause Description.. ........ . . AE . Lttarication Problem supplier Id........ 13972 Sptee E f f ec t. . . . . . . . . . . . .. . .E . System f unctice/Opere t t on Unof f ect ed manuf acturer........ Atwood 8 Morrill Co inc / komos at ent E f f ect. ... .. . . . . . . . . . . .C
- Resulted in ko S igni f icant E f f ect ufr Model id........
*errect ive Ac t i o% . . . . . . . . . . . AC . R epai r Ccroonent/Part Mfr M Wel ho........ 13972 01.M Saceantat i on. . . . . . . . . . . . . . . 2
- None of the Abov, afr Serial ko.......
LER Report utster............ Mfr Standard........ AN$1 831.1 System Af f etted by f elture...CCA . Main steam.Ct Drawing ho......... 964$*M 1077C Felturo Description karrative.....
)VRikt $URVEILLANCE TESTING , $AFETT / RELIEF VALVE DISCHARGE LINE Engineering Codes VADADI BREArtR 7078W 010 tof FULLY OPEN LNCER TME REQUIRED T0tQHE .
fMERE WAS NO $1GN]FICANT EFFECT 04 THE PLANT WHICH WA$ SWuTDOWW . THE A.1ype................ Check tiACTOR PRESSURE W$$tL $APETY / RELIEF VALyt $7$ TEM WAS NOT CtGRADED B.0perator............ None IT INIS FAlLURE $1NCE TH!$ t$ CNLY ONE Of 20 SAFETT REL!tF VAls.1. C.Foriction/Amtication Voeuta Relief
- 0. Body Ma t er i al . . . . . . . Carbon Steel
*aus) Sf f el,ure harrative..... E.Sody Manufacturine M Cast ikt (*Act CAust OF THE FA! LURE OF SAFETT / REl.lEF VALVI DISCHARGE LikE F ucainal Intet $13e ( & to 11.99 IN WAcuum tiltarER F078W WAS NOT CITERMINED . SVT 15 SUSPtCTED TO 88 DVt 70 G. Site (Intet)........ 10.000 lu .ACK OF LuttlCATION . N. Design Pressure..... 530.000 Psla J.teslgo Terrperature.. 480.000 DECF CorrectisJ Attice Narrative.....
IT.E SAFETY RELIEF VALYE DISCHARCE LINE VACUUM BREAKER F078W WAS 1 fire Operating Wen teactor is Critical..100% WltlCATED AND ERIRC] stb . THE SURVEILLANCE ft$T WAS $UCCEtsFULLY 7 Time 0pecating When keector is shutdown.. 10% CD# 0 t Wo26560 ) hours Cut Testing Performesi Frequefty/ Period of Service Check testing 0 / Not Gene 0.0 Functional fee *.ing 2 / Three Year 8.0 Calibration Testing 0 / Not Done 0.0 ACCLPTANCE DATE: 06/14/89 ut ili ty. . . . . . . . . . . . . . . . . . . . . . tnt e rgy Oper a t i ons , . nc. Unit.........................CRAND GUtf 1 N333.........................ceneral Electric Application......... Main Steam saf ety/ ADS Pipe Vac trt Ccreponent . . . . . . . . . . . . . . . . . . . .V ALVE Function............ Utility Conpanent Id.........N1821F037M syst em. . . . . . . . . . . . . . Main stese CE utttity System..... 521 Stirt 04te...... 03/11/89 start flee...... 12:00 out.cf service pours... 741 Data start Dete. 07/01/85 In. service Date..... 06/16/82 Discovery cate.. 03/25/89 Restoration Nours...... 417 Accepted Date... 07/16/90 Out of-service Date.. End 0:te........ 04/11/89
$afety Class....... 3 Ervi Time........ 09:00 Report Date..... 0$/11/89 Irput Date...... 0$/23/89 Mooe................ Operating System Status.. . .... . .... . ...F Traln/Chamel in Test leveri ty Level . . . . . . . . . . . . . . .K . Degraded internal Env........ Steam Ancient Tenperature Over +180F F a l t ur$ S ywpt em. . . . . . . . . . . . . 8 . Out o f Spec i f i ca t i on
/ellure Mode. . . .. .... . . .... . 0R . F all to Operate os sequired External Env........ Air Fall"=e betection............C . Surveillance Testing Acclent Tenperature +120F to +180F ategocy...............M . Wear out ' $w plier............ Decntet Group Inc Ces trusa Description.. ....... 33 . Mechanical Damage /tinding suoptier id;....... 13972 AD NormsL/Abr. cams l Weer Manuf 6cturer . . . . . . . . Atwood & Morel ll Co Irc / Xcmos AE Lubrication M olem aft Mocel Id........ l S ys t em E f f ec t . . . . . . . . . . . . . . 0 . Degraced Train / Channel mfr Model No........ 13972 01-H Plant Effect........ . .... 4 Resulted in No $lg9t ficant Ef f ect Mfr Serial No.... .
... u .. .. .. . ... . . .
WESTINGHOUSE CLASS 3
~
Replect Pertte) lif r sterd:rd. . , . . , . AN$1 $31.1 Cirrective Action............AN Dr awing No. . . . . . . . . 9M5.M.1077C Docment ati on. . . . . . . . . . . . . . . 2
- hone of the Atove L port W e er............
t tffected try felture...CCA
- kein steam-CE Engineering Codes f ailure Description Narrative.....
SAFEtt RELIEF WALVE 01tCMARCI LINI VACyt.et 8REAEIR VALYE F037M REDUIRD A.fype............... C' It EEC!tstyt 10aQUE TD OPtn untLE PgRFORMING A $VRYllLLANCI f tST . TMtRE 3.0perator............ .e * . WAS ho E!CNIFICANT EFFLCf CN THE PLANT , WHICM WAS $NVT DOWN FOR C. Function / Application secWe Redef REFUf LibG OUTAGE 3 . D. Body Meterial....... Certon Steel I.lody kanufacturing M Cost Csas3 sf felture Warrative..... F.Nominst Inlet $lte ( 4 to 11.99 IN THE btFFICULTT la OPta!NG 1AFETT RtLIIP VALVI Di$CMARCf LINE VACUUM C.$lte (Inletb....... 10.000 la DREAAtt VALVE FJ37M WAS CAUSED ST F'!CMAxlCAL elh0lWC OF THC VALVI H. Design Pressure..... 550.000 PSIG PACKlCC AND LACK OF LUSRICAT!ON OF 1Hf VALV1 $TtM . J. Design Te m ereture.. 480.000 DEGF 1 Time Operating When Reactor is Critical.. 100% CIrrective Action Narrative..... REN. cat 0 SAFEtt RiLIFF VALVI DIschARCC LIN! VACULM BREAK.IR vaLvf FQ37M 1 Time Operating When Reacto; ls Shutdown.. 101 Amo LusRICAftD twt VALVE SMAF1. NO RETEST WA5 REQUIRED . ( MMS. ) Mours Cut festing Perforewd Frequency / Period of Service Chect Testing 0 / Not Done 0.0 F mettonal festing 2 /1hree fear 4.0 . Cetteration festing 0 / set bone 0.0 ACCEPTANCE DAT[I 02/07/&& U'? Qv......................Enterey Operations, Inc. J ( ......................CRAND CULF 1
- Application......... Main $ teem $afety/ ADS Pipe Vec Brk d_.........................GeneretElectric Caponent....................YALVE Function............
Ut t t i ty Ce@onent I d. . . . . . . . .k1821F037M tystem.............. Main Steam CE utility Systen..... 821 start Dete...... 06/27iM 12:00 .Out of service houes... 3764 Data Start Date. 07/01/&5 in. service Date..... 06/16/82 st:rt Time...... Restoration Mours...... 104 Accepted Date... 07/16/90 Out.cf. Service Date.. Disccvery Date..11/27/85 End Dite........ 12/01/85
$af ety Ctess....... 3 Erd f lee. . . . . . . . 08:00 I nput De t e . . . . . . 01/31/ 86 Mode................ Operating Report Dats..... 01/29/86 S ys tem 5 t a tus. . . . . . . . . . . . . . . . F - T ra t n/Ch ame l in T es t Severi ty Level . . . . . . . . . . . . . . .K . D egraded Internal Env... ... . . Steam Astlent Teeperature Ovec e180F f ai lure Septom. . . . . . . . . . . . . 8 - Out of spec i f i c at i on Fet ture Mode .. .... .... . .. .. . 0R Fall to Operste as Required External Env........ Air Survelllance festing Ambient Tenperature e120F to +180F Fciture Detection............C Bechtel Group Inc Caust Category...............M . Weer Out tu @ lier............
Cause Description............st . Mechanical Osmage/strding suppt ler Id.... ... . 13972 80 Aging /Cyctic Fatigue Mamfecturer........ Atwood & Morritt Co inc / xanoA tystem E f f ect.... . . . . . . .. . ...D Degraded Traln/ Channel Mfr kodel Id........ Mfr Model no........ 13972 01.H Plant Ef f ect. ... .. . ... . . . . . ..C . Resutted in No $10nif i cant E f f ect C rrect i ve Act i on. . . . . . . . . . . . AG . R epa i r Component /Pa r t Mf* Seelet #4....... Decumentation............... 2
- hone of the Abov, Mf r $thodard. ... . ... ANsl 831.1 Dreutng No......... 9643 M 1077C LE R Report huter . . . . . . . . . . . .
System Affected by failure...CCA . Main Steam.CE Engineering Codes F O p Description marrative..... kj tuRvilLtAuCE TESituG OF TME MAIN STEAM SAFETT / eELIEF VALVt DISCMARCE LINC vsCUUM BREAKER Cutcr VALVE FC07M , THE TORQUE VALUE A. Type................ Check thEeE VAS h0 B.0oerator............ None
$7ECIFIED f oe Movl4C ikt VALvt bist uAS EXCEEDID C. Function /Aoptication Vecu m AeLief 11CNIFICAnt EFFECT ON t>t UNtt . THE UMit uAt tN C0t3 $4WiDouN FOR A D.lody Materiet....... Carton Steet SCMf DULED OJTAct .
s c. r c, ' m .;. i ., . = c, r r ., < r wae a.c..; t. i . a n c e n a
. . WESTINGHOUSE CLASS 3 E. Body Manufacturing M Cast j Ceuu cf Fellure Norrative..... F.Nominst inlet $13e ( 4 to 11.99 IN 122 STitrtNC of THE VACwM BREAEER CHECK VALUE WAS ATTAIBUTED TO C.Slae (Inlet)........ 10.000 IN ' >A '.D YALVE PACKING DUt to (XTENDED PERICDS OF NON M0YtMENT OF tnt N. Design Pressure..... $$0.000 PS10 VAlts 0!SC . THE CulCK YALYt Att IhtTAtttD TO PRtytNT SIPHON!kt OF J. Design Temperature.. 480.000 DECF SUPPRES$10N POOL WATEF. INTO Tkt SAf tTT / RELIEF VALVI ( SRV ) DISCNARCE Likt AFTER SRV ACTUATION . X Time Operating When RetClor 18 Celtital..1001 X Tlee Operatinw When *esctor is thutdown.. 107, corrective Action Narrative.....
fME Malt STEAM SAFEff / RELIEF VALVE DISCHARGE LINE YACVUM SRIAKER Nours out CCCC VALYC WAS CYf.uD SEVERAL TIMES MAirJALLY LJWTll THE YALYt Cl$C Testirig Performed Frequency / Period of $trvica ROTATED FRIELY Flft$7 WAS SATISFACTORT . (M58211 ) " " * " * " " * " " "" "*"."." - " " ~ - Check Testing 0 / het Done 0.0 Functional Testing 2 / Three Year 8.0 Collbration Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 11/13/90 Utility......................Entergy Operations, Inc. Un i t . . . . . . . . . . . . . . . . . . . . . . . . .GRA ND GUL F 1 Ntst.........................Ceneral tiectric Application......... Mein Steam Saf ety/ ADS Pipe Vec Brk Ccaporent . . . . . . . . . . . . . . . . . . . . VALVE Function............ Utility Component Id.........W18217078A Systee.............. Main $ teem-CE Start Dste...... 01/18/90 Utility System..... 821 stiet Time...... 12:00 Out of-service Mours... 6408 Data start Dete. 07/01/85 in service Date..... 06/16/82 Discovery Date.. 10/04/90 Restorstion hours...... 204 Accepted Cate... 07/16/90 Out ofatervice Date.. End Dats. . . . . . . . 10/12/90 End Time........ 12:00 Safety Class....... 3 tepm Date.....10/18/90 t rout ca te. . . . . . 10/27/90 Mode................ Operating Sys Status.. .... . . .. .. . ...F Train / Channel in f ut Seve r i ty Leve l . . . . . . . . . . . . . . .t D eg raded Internal Inv........ $ team Folture Synptos............. 8 Out of Specification Ancient Tenperature Over +180F F ai lure Mode . . . . . . . . . . . . . . . . . F 0 . F e l l ed to Doen External Env........ Air Failure Detection............C . Survelttance Testing Anblent Temperature *120F to +180F Caus) Category...............r . unknown S wotter....-........ Sechtet Group Inc Caves Description............AE Lubrication Problem succtler Id......... 10 14066-Syst em E f f ect . . . . . . . . . . . . . . . .t . Syst em f unct i on/Operet t on bns f f ect ed Manufacturer........ Atwood & Morritt to inc / Romon
# tant 1ffect..... ...........C = Resultad in No significant Ef fect Mfr Modet 1d........
Cterect i ve Ac t i on. . . . . . . . . . . . AG R epe t e Cenponent/Pa rt Mfr Model No........ 14066-01 M Document at i on. . . . . . . . . . . . . . . . ! None of t he Above Mf r Serial No. .. ... . 6=14066 LE R R epor t ambe r. . . . . . . . . . . . Mfr Stardard........ ASME Systeve Af fected by Fat ture...CCA - main Steam CE Drawing No......... 9645.M.1077 (siture Description Narrative..... DURING SURVEILLANCE f tSTING , SAFETY / RtLitF VALVE DISCMARCI LINE Engineering Codes YACUUM 3RLAKER F07BA DID MOT FURY OPEN UNDER THf REQUIRED TORQUE . THEat WAS No SIGNIFICANT EFFECT ON THE PLANT WNICM WAS $NVTDOWN . THE A. Type................ Check REACTOR PRESSURE YtSSEL SAFETY / RttltF VALVE STSTEM WAS NOT CICRADED 5. Operator............ None BT 1Xtt FAILURE SINCE TN!$ is ONLY ONE OF 20 SAFETY RELIEF VALYt3 . C. Function / Application Vacuun Relief
- 0. Body Meterial....... Carbon Steel Cs.s3 sf Fellure Warrative..... E.Sody Manuf acturing M Cast THE E c c7 CAUSE OF THE FAttuet CF SAFETY / RELIEF WALVE DISCHARGE LINE F. Nominal Inlet Site ( 4 to 11.99 IN YACUUM SREAJtER 7078A WAS NOT DETERMINED , SUT 15 SCSPECTED TO SE DUE 10 G. Size (!nlet)........ 10.000 IN LACK OF LUS21 CATION . N. Design Pressure..... 550.000 PSIO J. Design Te m erature.. 480.000 DECF Cc .ive Action Warrative.....
THE SAFETT RELIEF VALV1 DISCHARGE tlME VACUUM BREACER 7078A WAS 1 Time Coerating uhen Reactor is criticat..100% LueticATED AND EXECERisto . TPE SURVElLLANCE TEST WAS SUCCESSFuut 1 Time Operating uhen Reactor is shutdown.. 10% C04PLETED ( nc26559 ) Hours Out
-WESTINGHOUSE class 3 .
NO Testine P2rfccmed F regaency/?Celod - cf s:rvics Check Testing O'/ Not Done. 0.0 Functionet festing 2 / Three Year 8.0 - 0 / Not Done 0.0
.,J....................................................................Cettbrationfesting ACCEPTAliCE DATE: 11/13/90 . Ut il i ty. . . . . . . . . . . . . . . . . . . . . .Ent er gy Opera t i ons, Inc.
Uni t . . . . . . . . . . . . . . . . . . . . . . . . . GRAND OUL F 1 WS$$......................... General Electric App ((tation......... Main Steam Safety / ADS Plpe Vac trk Component . . . . . . . . . . . . . . . . . . . .V AL VE function............ Ut l H ty Comonent Id . . . . . . . . . N 1821 F 037F tyctem.............. Main Steam Gl~ Stort Dite...... 01/18/90 Utility System..... 821 St;rt f lee.... ..12:00 Out of service hours... 6408 Dets $ tert Dete. 07/01/85 Ina$ervice Date..... 06/16/82 Discovery. Dete..10/04/90 Restoration Noues...... 204 Accepted Dete... 07/16/90 Out of $ervice Dete.. Erd Dite........ 10/12/90
. E nd T ime. . . . . . . . .
- 2 :00 safety class....... 3 Aeport Date.....10/18/90 Input Date...... 10/27/90 Mode................ Operating Sys tem Sta tus. . . . . . . . .. . . . . . .F T reln/ Channel in f es t Seve r i t y L eve t . . . . . . . . . . . . . . .K - Degr aded Internal Env........ Steam f;lture Sygtem..............g - cut of Specification Aelent Tegerature Over *180F f *.i tura Mode. .. . . . . . . .. .. . . ..F0
- Fa iled to open External Env. .. . .... Air
-fciture Detection............C . surveiltence festing Ambient Temperature e1207 to +180F Causs Category. . . . . . . . . . . . . . . M = Wea r out $wpller.. ... .. .. ... Sechtel Grc@ inc ,,
Caust Description............Af = Lubrication Problem supptler Id......... $0 14066 AD = Normel/Abnorset Wear manufacturer........ Atwood & MorriLL Co inc / Nomon System E f f ect.. . .. .. . .. . . .. ..E - System Fmet t on/Operet ton Unaf f ected Mfr Model Id........ Plant Ef fect.................G Resulted in We $lgnificent Ef f ect M f r Model No. .. . . . . . 14066 01*H Corrective Action............AN
- Replace Part(s) Mir Scrist No...... 8 1&O66 stat ion. . . . . . . . . . . . . . . 2 . None of the Above Mfr Standard........ A5ME l
rt hunber . . . . . . . . . . . . Drawing No......... 9645 M 1077C system Affected by failure...CCA
- Mein Steam GE Failure Description Narrative..... Engineering Codes Dut!NC SURVEILLAsrCE TISTINC , EAFETY / RELIEF VALVE 01sCHARGE LINE Vacuum ttEAAER F037F Dl0 eit FULLY OPEN UNDER THE REQU18ED TJtQUE . A.T we................ Check THERE WAS NO SIGNIFICANT IFFECT ON TNE PLANT WNICH WAS SNUTDOWN . THE 8.0perator............ None REACTOR PRfSSURE VESSEL SAF(fY / RELIEF VALVE $TSTEM WAS NOT DEGRADED. C. Function /Ap0Lication Vacuun tellef ST TNIS FAILURE $1NCE TMit IS ONLY ONE OF 20 SAFETT RELitF VALVES . D.loor Meterial....... Carbon Steel E. Body Manufacturing M Cast causs af f ailure Narrative..... 7. Nominal Inlet $12e ( 4 to 11.99 IN
-THE (XACT CAU$E OF TNF FAILURE OF $AF!TY / RELIEF VALVE DISCHARCE LINE -0. Site (Inlet)........ 10.000 IN VACUUM SREAKER P037F WAS NOT DETERMINED , BUT !$ SUSPECTED TO SE DUE To M. Design Pressure..... 550.000 Ps!G PACICING WEAR AND / 04. Lact OF LURRICATION . J.Deel9n teg erature.. 480.000 DEGF' - Corrective Action Narrative..... % Time Operating When Repctor is Critical.. 100% - ThE SAFETY RELIEF VALVE DISCNAACE LINE VACUUM SR!AKEe FC377 WAS % Time operating When Reactor is shutdown.. 101 REPACKED AND LUBilCATED . TNf SURVE!LLANCE TEST WA$ $UCCES$ FULLY COMPLETED . ( WO2AS$7 ) Nours out Testing Perforced - Frequency / Period - of Service Check Testing 0 / Not Done C.0 F metional Testing 2 / Three Teer 8.0 Calibration Testing 0 / Not Done 0.0 h'
V
-A-105 WESTINGHOUSE CLASS 3 i uctccr Ptrvnt Roll <bility Date systeen l Ceneret Report For' *tph L. Nunter, Jr. Report !d: NPRC00AA
.stinghovee Electric Corporation Job Numert 7958 am Date: 09/08/92 am fleet 10:1T Intretisetton:
The ettsched report was tenersted by your query of the WPRDS date base. A suury of your query is listed below. QUEti You estected the following search cordition(s): Silected Ceirponent Is VALVE
$3tected VALYE Type is Check Estected Unit ID is CR.AND CULF 1
$3tected Systee is Main Steam CE Selected Mamf acturer is Atwood & Morritt to inc / Monox Fird Utility Coaponent ids that are equel to any one of the followinst mil 21F037W, N18217037R, N1821F037U, and mis 21F078a There were 4 recorcas meeting the search condition (s).
31$PLaf AND SORT: You sstected to rm seneral report 5: Ceeponent Master Failure Report (w/ Unit Information) fou chose to sort the report by: Sort Secpence Field Name WPRGCSAA huclear Plant Reliability Data System - Failure Master Report Run Date: 09/08/92 Job uumbert 7958 ACCEPTANCE DATE: 04/21/86
'Jt ili ty. . . . . . . . . . . . . . . . . . . . . . tnt ergy Ope ra t i ons, I nc.
Jni t . . . . . . . . . . . . . . . . . . . . . . . . .CRAND GUL F 1 (3$$.........................Ceneral Electric Application......... Main Steam Safety / ADS Pipe Vac trtt Caiponent....................YALVE Function............ Jtility Cceponent Id.........N1821F0758 sys t ern. . . . . . . . . . . . . . Ma i n S t eam- CE st:rt Date...... 07/27/85 utility System...... B21 Ster
- Time...... 12:00 Out of tervice Hours... 3368 Data Start Date. 07/01/85 in service Date..... 06/1
-Dis ry cate.. 11/27/BS Restoration hours...... 128 Accepted Dete... 07/16/90 Out-of Service Dete..
End Date.........12/02/85 f nd T ime. . . . . . . . 08 :00 safety Class....... 3 Rcport Date..... 02/25/84 Input Date...... 03/24/86 Moce................ Operating System Status...............,F . Train /Channet in Test
A-106 WESTINGHOUSE CIASS 3 Se ve ri t y Leve l . . . . . . . . . . . . . . .K Degr eded Interrot fev........ $t:em Ancient 1eoperature Drer *180F f e l t ur) tyept oro. . . . . . . . . . . . . . I Out of Speci f i c a t i on
!a l lure Modo . . . . . . . . . . . . . . . . 0R
- F a l l t o Ope r a t e a s # coul red Externat inv........ Air Fe Detection............C * $wevelttance Testing Antsient Temerature +120F to *180f
;e . tegory...............N . Weer out $ +ptier............ sechtel Crou0 Inc isus, Description............st + Mecnonical camese/ finding $w@He r 16. . . . . . . . 13972 80
- Aging / Cyclic Fetis. Ma of acturer........ Atwood & Norrllt Co Inc / Xceca S ys t es E f f ec t . . . . . . . . . . . . . . . 0 a Degraded f rein / Chemet Mfr Model Id........
Mfr Model No........ .t972 01 M Plant Ef f ect.................G
- Resulted in No $lonificent Ef fect terect i ve Ac t ion. . . . . . . . . . . . AG R epe l r Corponent/Part Mfr serial No.......
Docusenta t i on. . . . . . . . . . . . . . . 2
- None of the Above Mfr Standard........ ANil 531.1 Drawing No......... 9645-M 1077C LE R B eput $6srbe r . . . . . . . . . . . .
tystem Af f ected by Falture...CCA Main Steam-GE Engineering Codes silur3 Description Narrative.....
.iURING BURYllLLANCE 11$TIMO 07 MIN STEAM $Af tf 7 / RELitF VALVE A. Type................ Check DISCMARD LINE VACUun BREAKER CMEcs: VALVE F0784 THE TORout VALUE 8.0perator............ None setClF1E0 FOR MOVING 1pt VALVE DISC VA$ EXCEEDED TWERE WAS NO C. function /A@tication Vectam Relief $1GelFICAh11FFECT ON TME PLANT . THE UNIT WAS Smut DOVu FOR A D.tody Meteriet....... Carbon Steet $CHEDULED PLANT (11 tact .
- E. Body Marsif acturire M Cast Cause e,f felture Narrative..... F.N einal Intet $fte ( 4 to 11.99 IN I THE STICKING OF TMt VACLAM 3Rf AKER CHECK %ALVE WAS ATTRISVTED TO C. Site (Intet)........ 10.000 (N H. Design Pressure..... 550.000 PSIG l NARDENED VALVE PACKING 00E T0 EXTENDED PtRICO3 OF NON MOVEMENT OF TME J:0esign Te m ereture.. 480.000 DECF .
I VALVE DISC . IME CMtCK VALVES ARE INSTALLED 10 PetVIN1 SIPMON!NG OF suPPR15310N POOL WATER INTO THE SAFETT / RELIEF VALVE (SRV ) DISCHARGE 1 Time Operatine When Reactor is Critical.. 100% LINE AFTtt EAV ACTUAfl0N .
% Time Operating When Reactor le shutdown.. 10%
i C:rrective Action Narrative..... Nours Out T[ M STEAM SAf tTT / BElltF YALVE 0!$ CHARGE LINE VACUUM SREAKER frequency / Period of $ervice r ; Testing Performed C%,JALVE WAS CTCLED $tVERAL TIMES MANUA LL Y UNTIL THE VALYC D1$C - - ~ " " -
"--~~""' " - " . . " - " "
RCTAito FREELT . RETEST WAS $ATISFACTORT . ( M18210 ) 0.0 Cneck Testing 0 / Not Done Functional Testing 2 / Three Year 8.0 Cattbration Testing 0 / Not Done 0.0 ACCTPTANCE Daft: 02/07/84 Ut il i t y. . . . . . . . . . . .. . . . . . . . . .Entergy Operat ions, Inc. I Unit......................... GRAND GULF 1 A@tication......... Mein Steam Saf ety/ ADS Pipe Vac set usS5.........................Generet Electric F metion............ Cogonent . . . . . . . . . . . . . . . . . . . . VAL VE i Sys t es. . . . . . . . . . . . . . Ma in s t eam-CE I utility Co,ponent Id.........N1821F03h1 Utttity System..... 821 St:rt Date...... 07/27/85 In service Dete..... 06/16182 Out of tervice pours... 3044 Data Start Date. 07/01/83 f tert Time. . .. ..12:00 Accepted Date... 07/16/90 Out of servics Date.. Olsc:very Date.. 11/27/25 Restoration Mours...... 104 l trd Date........ 12/01/85 Safety Class....... 3 End T ime . . . . . . . . 08:00 Operating Report Date..... 01/29/E4 Input D e te. . . . . . 01/31/ 86 Mode................ l system statue................F f rein /Chamet in Test
- Degraded Interne t Env.. . .. . . . Strom l
leverity Lev 4t...............K Ancient fewperature over *1807 f ci turo $ywotom... .. . . . . . .. . .s Out of Speci ficat ion Externet Env........ Air F llur3 Mode.... ... . . . . . . . . . 04 - Fel t to Operate es Recuired Molent Texperature +120F to +1807 F al turo De tec t ion. . . . . . . . . . . . C - surve i t t ence Tes t ing r set t er . . . . . . . . . . . . sechtet Group Inc M C:tegory...............M hear out
; i Sipptter (d......... $0 14064
! ) Description... .... ... . .Bs - Mechanical Demoge/ Binding
$0 Aging / Cyclic fat 10ue manuf acturer . . . . . . . . Atwood & Morri t t Co inc / temex Mfr Model Id.... ...
System Effect...... ........ 0 Degeeoed Train /Chanret 14066 01-N Mfr Modet No....... P l ant E f f ec t . . . . . . . . . . . . . . . . . C Resulted in No Significant Effect Mfr Seriet No....... 2-14066 Correc tive Action. . . . . . . . . AC - Rep. sir Ccr'ponent/ Par t
WESTINGHOUSE CIASS 3 Docunent a t i on. . . . . . . . . . . . . . . . Z N one of the Above Mfr Standard........ ASME LER Report Nwber. . . . . . . . . . . . D rewins ho. . . . . . . . . 9645 M-1077C System Af f ected by f ailure...CCA Nein Steam-CE Fat Description korretive..... DURon SURYtILLANCE TESf!NC OF THE MAIN ST!AM SAFEff / RELl[F VAlyt Insineering Codes G. DitCRARCE LINE VACUUM SREAKER CktCK VALVE F037U , Tkt TORQUE VALUE A. Type................ Chect SPICIF!!D FOR MOVING THE VALYC DISC WAS EXCitDED . THERE WAS NC 8. Operator............ Mone llCalFICANT EF'ECT Om ThE UNii . THE UNIT WAS IN COLD SHUTDOWN FOR A C.hnet t on/ Application vacuun tellef SChCDULED OtrTAGE . D.sody Materiet....... Carton Stet l E.tody MmNf acturing M Cast Cause of Falture Warretlw..... F.Nominat Intet Site ( 4 to 11. W IN THE $11CKING OF THE VACUUN BREAKER CNECK VALVE VAS ATTRIBUTED TO C.Stae (Intet)........ 10.000 IN MARDENED VALVE PACKING DUE TO EXTENCED PERICOS OF NON*MOY! MINT OF THE H. Design Pressure..... 350.000 PSIG int CMECK VALVE DISC . THE CNECK VALVES VERE INSTALLED TO PREVENT J. Design f orgerature.. 680.000 DEGF SIPHONikt CF SUPPRES$lon POOL WATER lATO TMt SAFITY / REL!!F VALVI ( SRY ) DlSCWARCC LINE AFilR SRV ACTUATIDM . X fime Operating when Reactor is critical.. 100%
- 7. Time Operating When Reacter is shutdown.. 10%
Cort etive Action Warratin..... INE F.AIN STEAM SAFETT / RELl!F VALVt DISCMAaCE LINE VACUUM BREAKER Hours Out CHECC VALVE WAS CYCLED S!v!RAL TIMt3 NANUALLY UNiil THE VALVE DISC Testing Performed frequency / Period of Service
- - ~ ~ ~ - " " - ~~~a~~" -"-~."
RCTAftD FREELT . RETEST WAS SAtl$ FACTORY . (M58211 ) check lasting 0 / Not Done 0.0 Functionet testing 2 / Three Year 8.0 Calibration Testing 0 / Not Done 0.0 ACCEFTANCE CAft: 02/07/86 Utili ty. . . . . . . . . . . . . . . . . . . . . .Intergy Operat i ons. I nc . Unit . . . . . . . . . . . . . . . . . . . . . . . CRMD CUL F 1 NSL ......................Ceneral Electric A; plication......... Main Steam Safety / ADS Pipe vac 3 Couponent . . . . . . . . . . . . . . . . . . . .VAtVE Rnction............ Utility Ccaponent Id.........N1821F037R S yst em. . . . . . . . . . . . . . Ma i n S t ese-CE Start Date..... . 06/27/85 utitity System..... 821 start Time......12:00 Out of Service Mours... 3764 Cate Start Date. 07/01/85 In Sarvice Date..n. 06/16/82 olecovery Date..11/27/85 Restora t i on Mours. . . . . . 104 Accepted Date... 07/16/90 Out of Service Dete.. End Dete. . . . . . . . 12/01/85 End T ime. . . . . . . . 08:00 Safety Class....... 3 Report Date.... . 01/29/86 Imut Date...... 01/31/66 Mode . . . . . . . . . . . . . . . . Ope ra t i ng System Status. .. . . .. .. .. .. . ..F Train /Channet in Test Severity Level...............K Oegraded Internal Env........ Steam F a l t ure Symptam. . . . . . . . . . . . . . t Cut of Spec i f i ca t i on Ancient Terrqmreture Over +180F F e l t ure Moce . . . . . . . . . . . . . . . . 0R F a l l t o opera t e as R equ'i red External Env........ Air Falture Detection............C - Surveillance Testing Ancient Teaperature +120F to e180F Cause Ce t tsory. . . . . . . . . . . . . . . N . Wea r out Sql .er . . . . . . . . . . . . Sechtel Creup inc Cause Description........... 98 . Mechanical Damage / Binding S g Ller Id......... 50-14066 BD
- Aging / Cyclic Fatigue Manufacturer........ Atwood 8 Morrill to inc / Xomes Sys tem E f f ect. .. . . . . . . . . . . . . .D - Degr aded T re i n/ Channel Mfr Modet Id........
Plant Ef f ect.. . ... . . . . . . . . .. .C - R esulted in No Signi ficant E f fect Mfr Model No........ 14066 01 M Corrective Action.... ........ AC Repai r Corponent/Part Mir Seriet No....... 1 14066 Document a t ion. . . . . . . . . . . . . . . 2 - None of the Above Mf r S tariderd. .. . . . .. ASME LE R R eport Nwtaer. . . . . . . . . . . . Drawing No.. . ... . .. 9645 M 1077C System Af f ected by Failure...CCA - Main Steam-CE Failure Description Narrative..... Engineering codes Due"'t SVRVilLLANCE TESTING OF THE MAIN STEAM SAFETY / RELIEF VALVE DI. (Ct LINE VACUUM BREAKER CMECK VALVE FC37R . THE TCaQUE VALUE FOR A. Type................ Chect Movim3 TME vat.VC blSC uAS EXCEEDED . THERE WAS No SICMIFICAuf EFFECT Ch 8.Operster............ None in! U%If . TME UNIT WAS IN COLD SHVfDOWN FOP A SCHEDULED CUTAGE . C. Funct i or./ Appl ica t ion vactasn Relief 0.Becy Material....... Carbon Steel
A-108-WESTINGHOUSE CLASS 3 E.sody ManufCcturing N Cett , Cause Cf fatture Eccretive.....
. F.kominst Intet $(se ( 4 to 11.99 IN . Int STICEtNG OF THE VACUUM DREAttR CMECK VALVI WAS ATTRIBUlto TO _
DARDeutD VALVE PACKING DOE TO EXTfNDED PERIODS OF NON MOVEMENT OF THE_ G. Site (Intet)........ 10.000 IN
' N.casign Pressure. . . . . ' 550.000 P$1C l[ ) Disc . TME CMICK VALYts ARE INSTAktt0 To PRfYENT SIPMON!NG .
J.0641pn f07 e@erature.. 480.000 DtGF-
' Q $$10N POOL WAftR INTO THE SAFETT /RELiff VALVE ( SRV ) DI$tMARCE
' Ll'3 Af fit $4V ACTUAT10N .
% Time operating When Reactor Is Criticot..100%
- % lim operating When aeactor ts shutdown.. 10%
Corrective Action Norretive..... 1:1 m lN STEAM SAftTT / relit 7 WALVE DISCHARGE LINE VACUUM SREAtfR Noure out CHECK VALVI WA$ CTCLtc SEVERAL TIMES MANUALLY UNTIL THE VALVC DISC frequency / Period of Service Testing Performed ROTATED FitttLT . REf tsi WAS SAfitFAC10RT (M58211 ) ................ ........... Check festing 0 / Not Done . 0.0 Functional Testing 2 / Three Year 8.0 Calibration Testing 0 / Not Done 0.0 i ......................-............................................................................................................. ACC1eTANCE DATE 02/07/86 ut t t i ty. . . . . . . . . . . . . . . . . . . . . . tnt ergy Oper a t ions , I nc. l' : Uni:.......,s................ GRAND GULF 1 Application......... Mein Sttem lef ety/ ADS Pipe Vec Stk RStl......................... General Electric Cogonent.................... VALVE Function............ S ys t em. . . . . . . . . . . . . . Ma in Steam CE Utllity Comonent Id......... Mis 21F037N Utt tity system...... s21
- Start Date...... 07/27/85 In service Date..... 06/.16/s2 out of. service sours....
- 4 Data start Dete. 07/01/85 stCet Time...... 12:00 Accepted Dete.'.. 07/16/90 - out.cf.$ervice Date..
l Olscovery Date..11/27/85 Restoration Nours...... 104 ! Ind D at e. . . . . . . . 12/01/85 Safety Ctess.'...... 3 l ' End Time........ 08:00 Operating toport oste..... 01/29/86 Input Dete...... 01/31/66 Mode................ u Statue... ... . .. .. . . .. .F - Tra f n/ Channel in Test Internet Env........ Steam
- v. Ity Levet . . . . . . . . . . . . . . .C . Desceded Aselent Teeperature Over +1807-F a l ture $)ept om. . . . . . . . . . . . . .B . Out of spec t f t ca t i on laternal Inv.....,., Air F a l t ure Mode . . . . . . . . . . . . . . . . 0R . F e l t t o Oper a t e as R equi red Asblent Temperature 412CF to +1807 .,
Failure Detection... .........C . Surveit tence Testing l Caus) Ca t egory. . . . . . . . . . . . . . .N . Weer out supplier............ Beentet Cro w inc Supptler 1d........ 50 14066 j Cause Description............la . Mechanical Demoge/tinding 80 Aging / Cyclic Fatigue Mamfacturer........ Atwood & Morritt Co lac / Xomon
. Degraded Traln/Channet M f r Mode t 1d. . . . . . . .
System ENect................D Mfr Modet ko........ 14066 01 N Plant Ef f ect................ 0 . Resutted in Ne slenificant Ef f ect CIrrect ive Act i on. . . . . . . . . . . . AQ
- R epe ( r comonent/P o r t Mfr serial No....... 9 14066 Mfr Standerd........ AsME l' Documentat t en. . .. .. . . . . . . . . . 2 hone of the Above Drawing No......... 9645 M 1077C LER Report u mber............
System Af fected by Feiture...CCA . Mein Stese-CE-Engineering Codee Felture Description Narrative..... DURlk0 SURVEILLANCE f ttflNG OF THE MAIN STEAM $AFETY / RElltf VALVE 0!$ CHARGE LINE VACUUM GREAKER CNECK VALVE F037N , THE TORQUE WALUE A. Type................-Check B.0perator............ None
- j. SPECIFIED FOR MOVING TMt VALVE OttC WAS EXCEEDED TMERE WAS NO C. Function /Appt{ cation' VacWW Relief l l SIGNIFICANT EFFECT ON tnt UNIT . THE UNIT WAS IN COLD SMUTDOWN
- 0. Body Materie FOR A -.. Careon st ot
- t. . ...
SCNEDULED ouTACE . E.tody Manufacturing M Caet
~ F.hominet intet Stae ( 4 to 11.99 IN Cause of Falture herrettve.....
G. Site (Intet)........ 10.000 lW-THE STICKlWG OF THE Vacuum SREAKER CNICK VALVI WAS ATTRIBUTED M.TO Design Pressure..... 550.000 P$1G l MARDENED VALYT PACKING DUE TO EXTENDED PER100$ OF h0N* MOVEMENT OF TMt J.Dedgn Te@erature.. 480.000 OtGF LV1 OlSC . THE CMECC VALYt$ ARE INSTALLED TO PREV!NT SIPMONING OF
'REss!ON Pook WATER INTO TMt $AFETY / RELIEF VALVE ( SRV ) Di$CHARCE
% Time Operating When Reactor (s Cr{ticat.. 100%
ADOL tev ACTUATION .
% Time Operating When Reactor is Shutdown.. 10%
Ccerective 4 tlen Narrative..... Mours out Tsf MAIN STEAM SAFETT / REllEP v&LvE DiscHARCf LINE VACULM SREAKER I
A-109 WESTINGHOUSE CLASS 3 CntCE CALVE WAS CTCLt0 SEVERAL TIMt$ kANUALLY WT!L THE VALvt DISC Testing Perf orined F requerwy/ Period of service 201 Aft 9 1REELY , RETEST WAS SAfttFACfolt? . (K58211 } ................. ................ .......... Check Testing 0 / Not Done 0.0 Functional Testing 2 / Three Tsar 6.0 Cetibration Testing 0 / Not Done 0.0 0 O
A-110 WESTINGHOUSE CLASS-3 uclear Plant R: liability D;te System Generet Report ph L. lheiter, Jr. Deport ld: NPt000AA tinghouse Electric Corporation Job Wueer: 7963 Rws Cates- 09/08/92 atei ilme - 10:23 Introd;ction: The attached report we generated br your cuery of the WPRDS date tase. a sweeery of your query is listed below. WKET Tou selected the following search condition (s): Selected Cosponent is VALVE 5 elected VALVE f p is check l Selected Unit ID la CRAND GJLF $ telected 5'ystem is Main steam CE i Selected Marmsf acturer is Atwood & MorrlLL Co IN / Xceen , find Utility Conpanent ID* that are ogJet to err one of the following: W1821F078C. N1821F0780, if1621F0781', and M1521F078R
-ThJre were 4 records meetin0 the search condition (s).
I' Di LAT Amo $0RTs Tou selected to rts) gmeral report 5: Component Master f ailure Report (w/ Unit Information) tou chose to sort the report by: Sort Sequerce 7letd Name kucteer Plant Rollecility Data system felture Master Report Run Date: 09/08/92 1 NPRCOSAA Job suber 7963 I ACCEPTANCE DATE: 04/21/86 i i Ut il i t y. . . . . . . . . . . . . . . . . . . . . .Entergy operat i ons, Inc . teil t . . . . . . . . . . . . . . . . . . . . . . . . .CRAND CUL F 1 Application......... Meln Steam Safety / ADS Pipe Vac trk - E1$$ ........................ General Electric l Function............ Corponent . . . . . . . . . . . . . . . . . . . . VALVE ! sys t em. . . . . . . . . . . . . . Ma i n s t ears r4 titi l i ty Cenconent Id. . . . . . . . .W182 t f 07Br utility system..... 821 Start Dete.. . . .. 07/27/85 out of service Hours... 3068 Data $ tert cate. 07/01/85 In tervice Date..... 06/16/82 Time Averyc......12:00 ate.. 11/27/81 Restoration Hours...... 128 Accepted 04te... 07/16/90 Out of-service Date.. Errj Cate........ 12/02/85 Saf ety 0L ess. . . . . .. 3 End t ime. . . . .. . . 08:00 Input Dete... ... 03/24/66 Mace................ operating Resort Oste... .. 02/15/ea System $tatut................f Train / Channel in Test
WESTINGHOUSE CLASS 3 ^~III severi t y Leve l . . . . . . . . . . . . . . .E . Degraded Internal Env........ Steam f ailure System. . .. . . . . .. . . ..t . Out of speci f ica t ion Ant >f ent Teeperature Over +180F 7;il'
- Mode. . . . . .. . . .. . . . . . 0R . F a ll to Operate as RegJl red External Env........ Air F:lt 0ctection... ....... ..C Surwill ence f esting Ancient Teeperature +120F to *16 Caus e Cat egory.. . . . . . . . . . . . . .H
- Wear Out Supplier............ Bechtel Group Inc Cause Description........... 88 . Mechanicet Dosage / Binding Supplier 1d........ 13972 80 . Aging /Cyclie fatigue Maruf acturer........ Atwood & Morrit t to Inc / Xenos system E f f ect. .... .. .. .. . .. ..D . Degraded Tra in/ Channel Mfr Model Id........
Plant Ef fect.................Q
- Resulted in No $lentficant Ef fect Mfr Model No........ 13972 01*M Correcti n Action............AG . Repelr Co m onent/Part Mfr Serial No.......
Document at ion. . . . . . . . . . . . . .. 2 . k one of the Above Mfr Standard........ ANSI B31.1 LER Report N e bet............ Drawing No. ... ... . . 9645 M-1077C $ystem af f ected by f eiture...CCA . kein Steam.Gt f ailure Description Norrative..... Engirwering Codes DuRING $URVIILLANCE 7ttTINC OF MAIN STEAM 1AFETY / Rttttf VALVE DISCNARCE LINC VACULM BREAKER CHECK VALVE f 078K . THE T0t0Ut VALUE A. Type................ Check SPECIFitD FOR MOVING THE VALVE DI$C WAS EXCEEDED . THERE uAS No 9. Operator............ None SIGNIFICANT *FFECT DN THE PLANT . TME LNIT WAS Snc DOWN FOR A C.f met ton / Application Yac w s Rellef StilEDULED PLAh' CUTAGE .. C. Body Material....... Carbon Steel E.tody Marmef acturine M Cast cause cf f ailure herretlw..... F. Nominal Inlet size ( 4 to 11.99 IN fut STICK!hG OF THE VAMM SRIAK!R VALVE WAS ATTRIBUTED TO NARDENED C.113e (Inlet)........ 10.000 IN VALVI PACKlkG DUE 70 EXTENDEC Pfal005 of NON. MOVEMENT OF TNI VALVE OlsC N.Desico Pressure..... 550.000 pslG . THE CNECK VALVit ARE INSTALLCD TO Pit!V!NT SIPMONING OF $UP9tESSIGN J. Design Tenperature.. 440.000 DEGF PQ0L WATER INTO THE EAFETT /RILIEF VALYE ISRV ) 015CPAAct LINE AFTER 3RV ACTUATI0a . % Tlase Operating When Reactor is Critical..100%
% Time Operating When Reector is shutdown.. 10%
Ctr 8ve Actico Narrative..... THE waN STEAM SAFETT / RELIEF VALYE 015 CHARGE VA*ULM BREAKER CNICK Nours Out - VALVE WA5 CTCLED SEVERAL TIMC$ MANUALLY UNTIL THE VALVE DISC ROTATED Testing Performed Frequency / Period of Service
............~.. ..........
FREELY . RETEET WA$ $ATitFACTORY , ( MS&210 ) . . . . . . . . . . . . . . . . . Check Testing 0 / set Done 0.0 Fmettonal Testing 2 / Three fear 8.0 Calibration Testing 0 / Not Done 0.0 ACCEPTANCE DATEt 04/21/86 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . .Ent ergy operat i ons , I nc. Unit......................... GRAND CULF 1 k s$$. . . . . . . . . . . . . . . . . . . . . . . . . Gene ra l E lec t ri c A mticaticn......... Main steam Safety / ADS Pipe Vac trk Copponent . . . . . . . . . . . . . . . . . . . . VALVE Function............ Utility Comrment Id.........NIE21F075C System.............. Main steam CE Utility system..... 821 St:rt D:te...... 07/27/85 Out-of.5ervice Hours... 3068 Osta start Dete. 07/01/81 in. service Date..... 06/16/82 $ tir t T isie. . . . .. 12100 Olscovery Date.. 11/27/85 Restoration Mours...... 128 Accepted Date... 07/16/90 Out of service Cate.. End Osto........ 12/02/85 Safety Class....... 3 End T i me. . . . . . . . 08 :00 Irput Date...... 03/24/86 Mode................ Operating Report Date..... 02/25/86 system status. .... ..... .. . ...f . Tra irVChamel in T t Seve r i ty L evel . . . . . . . . . . . . . . .K - Deg raded Internal Env........ Steen Armient Temperature Over +180F Failure Sygtem............. 8 Out of Specification fel tur3 Mode.. . . . . .. .. .. . . .. 0R Fai t to Operate as Rewired External E nv. . . . . . . . Ai r Anolent Terrperature +120F to *180F fain"ro Detection............C . survelltance Testing 11t eg ory . . . . . . . . . . . . . . .M - We er out supot ter.. ... . . .. . . . sechtel Group Inc Ca-Cavas 01scription..... . .. ... 8B 86echanical Demoge/8inding Suppt t er Id. . .. . . . . 13972 BC - Aging / Cyclic Fetigue Manufacturer........ Atwood & Morritt Co inc / Xomox
$ystee Effect......... ..-.. 0 Degraded frein/Channet M f r Mode t I d. . . . . . .
.......G . Resulted in ho Significant Ef f ect Pfr Model No........ 13972 01.M Plent Effect.........
Cerrect ive Act ion. . . . . . .. . . . AG
- Rece i r Cor@onent/Part Mfr $erial No.......
A-112 WESTINGHOUSE CLASS 3 Mir Stendard........ AN11 831.1 Doceent a t i on. . . . . . . . . . . . . . . . ! None of the Atove Oreutne ko......... 9645 M 1077C LE r t h untw r . . . . . . . . . . . .
$ \f f ected t>y F eiture.. .CCA - kein stese ct Engineering Cc6 s Isilure bestription Warrative.....
DURlNG suRVEILLauCE TE$11NG OF MlW STEAM WETT / RILIEF VALVE A. Type................ Check Cl& CHARGE Llkt VACUUM BREAKER CHECK VALVE f 07BC , THE Toegut VALVE B.0perator......... .. kone SPfClf!ED TOR MOVlWC TME VALVE D!tC VAs EXCEEDED . TkEREC.WAS NO / Application Yacuum Relief function
$1GalFICANT EFFECT cm int UNIT . TML PLANT WA$ $ NUT DOWN FOR A 0.lody Materiet....... Carbon steel StutD'AED PLANT CUTACE ,
E.Sody Manuf acturing M Cast F. Nominal Inlet $lte ( 4 to 11.99 IN Cause of faitu*e marrative..... C.Stae (Intet)........ 10.000 IN TRI Sf!CKING OF TME VAcuuH &aEAtER CMECr VALVE WAS ATTRl4VTED TO H. Design Pressure..... 550.000 Ps30 RARDENED VAL,VE PACKING 00E TO f.XTENDED PERitt$ OF kON.McVEMENT CF 1ME J.Desig9 Towperature.. 450.000 DEGF '~' VALVY DISC . Tut CHECK VALVES ARE INSTALLED TO PREVENT $1PHONikG OF
$UPPREt$10N PQ0L WATER INTO THE SAFETT / RTLIEF VALVI ( SRY ) DitCMARGE % time Operating When teactor is Cri LINE AFTER SRV ACTUAflow . % Time Operating When Reactor is $hutdoun.. 10%
Corrective Action Warrative..... Mours out THf MAIN $1EAM SAFETT / RELIEF VALVE DISCWARGE LIWE VAQJUM BREPerform Testing ACER d fre @ency/ Period of Service CHECK V M E WAS CTCLED sEVERAL TIMES MANUAL U UNTil --.....---..... INE VALV! Di$'C . .. ............ kOTATED FREELT . RETEST WA$ SATISTACTORT . ( M58210 ) 0 / Wot Done 0.0 Check Testing functionel Testing 2 / three Tear 8.0 . Calibration Testing 0 / Wot Done 0.0 ACCEPTANCE DATE: 04/21/86 9..y......................Entereycperations,Inc.
. . . . . . . . . . . . . . . . . . . . . . .CR AW0 CUL F 1 Main steam Saf ety/ ADS Pipe Vac Brk Acolication........
NSSS......................... General Electric Tmetion............ Conpanent . . . . . . . . . . . . . . . . . . . .V ALVE System.............. Main Steam.CE Utility Cmponent Id..... ....N1821f 0780 utility system..... 521 Start Date...... 07/27/85 Data Stort oste. 07/01/85 In. service Date..... 06/16/82 start Time...... 12:00 Out of service Hours... 3068 Out of.$ervice Date.. Accepted Date... 07/16/90 0(scovery cate.. 11/27/85 Restoration Mours...... 128 Erd D a t e . . . . . . . . 12/02/85 saf ety Class....... 3 End T ime. . . . . .. . 08:00 Mode................ Operating input Date.......C3/24/86 Report Date..... 02/25/86 Systee Status.. ..... ....... . .f Traln/Charewt in Test Inte net Env. . . . . . .. Steam Seve r i ty Leve t . . . . . . . . . . . . . . .E - D egr eded Anblent Temperature Over +180F F ailure Sycptoc..... .. . .. . . . 8 . Out of Specification External Env. ... .. . . Ai r 0R . Fait to Operste as Rewired Aabient Tecperature +120F to +180F Failure Moce................ f ailure Detection............C . Survelltance Testing Cupot t er . . . . . . . . . . . . Recht 4 L Group I rc Cause Category......
- Veer Out
........N Supplier Id......... 50 14066 Cause Cescription......... .. 88 . PechaMcat Demage/tinding manufacturer........ Atwood & Morritt Co inc / Xomon Bo . Aging / Cyclic Fatigue Mfr Model Id........
sys tem E f f ect . . . . . . . . . . . . . . . 0 - Degreded T r ain/Ch anne t Rfr Model ho........ 14066-01.M 0 - Resutted in ho significant Ef f ect Plant Ef f ect................ Mfr serial No....... 10 14066 Corrective Action........ .... AG - Repef r Cortonent/Part afr sten o rd........ Aswt None of the Above Dewing mo. . . . . . . . . 9645.M 1077 Do. mentation... . . . . . . . . . . . . .Z LER Report kustar. . . . . . . . . . . .
- main Stea+ CE system Af f ected ty Failure...CCA Engineering Code $
ure Description Narrative..... DutikG SURVEILLANCE TESTikG OF MAIN STEAM $AFEttA./ Type... RELIEF.... VAivt ...... Check DISCHARGE LINE VACWM BREAKER CHECC VALVE FOR780 THERE WAS NO
. TME. ......
8,Cogrator... 10eQUE NoneVALut soECiflED FOR McVlhG THE VALVt Ol$C WAS EXCEECED C.f ur etion/ Apot tcat ion Vacwm kellef 51Gh1FICANT EFFECT C4 THE PLANT . THE UNIT WAS $ HUT FOR A.... Carbon Steel C0wmaterial. C. Body SCHE 0utED PLANI GUTAGE .
WESTINGHOUSE CLASS 3 ^~l13 f.Boey Manufacturing M Cast Cause cf failure herrattve..... F.kominal Intet Slae ( 4 to 11.99 IN TMF *1CKlh4 0F TME VACUUM Btf AKER CHECK VALVI WAS ATTRIBUTED TO C. Size (Intet)........ 10.000 IN MAi 40 VALVE PACKIhC DUt TO EXTENDED PtRICol 0F NON MOVEMENT 07 THE h. Design Pressure..... 550.000 PSIC VALV! DISC . THE CMICK VALVtt ARE Ih5fALLED TO PREVENT SIPwCNING OF J. Design fe m erature.. 480.000 OtCF-SUPPRE$$10N PQ1 WATER INTO TM( $AFETT / RtLitf VALVE ( SRV ) DIS MARGE LINT' AFTER $RY ACTUAf tcu . 2 Tire operating When Rear. tor is Celtical..100% 1 Time Operating When Reactor is thutdown.. 101 Corrective Action Norrative..... TNC MA!N STEAM LINE SAFETY / RELitf VALVE O!SCNARGt 1,1N! VACUUM RREAKER Mours Cut CaECK VALVE WAS CTCLED $tVER.AL TIMES MANUALLY UNTIL Tht VAtVE D!sC Testing Perforned Frequency / Period of Servlee
" " - " " + + " * " " " * " " " " " * **""-~-
RCTATED FRttLY . RETEST WAS SATISTACTORT . ( M58210 ) Check Testing 0 / Not Done 0.0 Fmetional Testing 2 / Three Year. 8.0 Collbratten Testing 0 / Not Done 0.0 ACCEPTANCE DATE: 04/21/66 Ut i l i ty. . . . . . . . . . . . . . . . . . . . . .E nt er 0y Opera t i ons , I nc. Unit.........................CaAND GULF 1 A mtication......... Main Steam safety /AD$ Pipe Vsc Brk Nt$$.........................Cenerst Electric Cwponent.................... VALVE function............ Utility Corponent Id.........N18217075A System.............. Main $tsam CE Utility system..... 321 start Detc...... 07/27/85 start Time...... 12:00 out.of- h evice Mours... 3063 Cate start cate. 07/01/85 In-service Date..... 06/14/52 Olscovery Date.. 11/27/83 Restoration Mours...... 128 Accepted oste... 07/16/90 out of service Date.. End Date........ 12/02/85 safety class....... 3 Erwi T iee. . . . . . . . 08 :00 Input Date...... 03/24/86 Operating cate..... 02/25/86 Mode................ Ri Synem status.. . . ... . . .... .. .F Trein/Chamel in Test , Severi t y Leve t .s . . . . . . . . . . . . .K - Dei; reded t r terne t Env. . . ..... Steam f at ture $pptom............. 9 Out of Specification Ancient Tv@erature over +180F f al ture MMe..... .. . . . . .. ... 0R
- Fai t to operate es Required Externet Env........ Air Ambient Tegerature +120f to C80F.
f al tur2 Detect ion...... ......C
- Survei ttance Test ino Cause Category...............N Wear out Suppl i er. . . . . . . . . . . . Bachtel Cro@ Inc Caust Description............aa . Mechenleat Dennage/ Sinding supplier 1d......... $0 14066 to Aging / Cyclic Fatigue Manuf acturer........ Atwood & Morritt Co Inc / Xomor .
System E f f ect. . . . . . . .. . . . . . . .D - Degraded T rain / Chemet Mf r Model 1d. . . . . . . . Plant Ef f ect.................C - Resulted in No SIgnificant Ef f ect M f r Mode l N o . . . . . . . . 14066 01.M Corrective Action............ AC Repelr Coeponent/Part Mf r Serial No....... 15 14066 , Mf r S tarde rd. . . . . . . . AsME Docunent a t ion. . . . . . . . . . . . . . . 2
- None of the Above LER Report Number............ Drawing No. .... . ... 9645.M.1077 l
! System Af f ected by Failure...CCA Main steam CE 1 1
- 7:ltura Description Narrative..... Engineering codes 00RlWG SURVEILLANCE TESTING OF MAIN STEAM SAFETT / RtLIEF VALVI 0!$CMARCE LikE VACUUM BREAXER CHECK VALVE F078R , TNE TOR 2K VALUE A. Type................ Check 8.Operatoe............ mene $PECIFIED TOR MOVING THE VALV1 DISC uAs EXCitDED . THERE WAS NC SICN!flCANT If f ECT ON THE PLANT . TMt UNIT WA3 $MUT DOWN FOR A C. Function /Amlication vacum Relief l
D. Body Material......, Carbon $ teel
$C7.EDULED PLANT CUTAct .
E. Body Manufseturin0 M Cast Caust of Falture Narrative..... F.soninct Inlet $13e ( 4 to 11.99 IN TME STICKINC OF TMt VALVE WAS ATTRl8UTED TO MAR 0fMED VALVI PACKING DUE C.$lte (Intet)........ 10.000 !N M. Design Pressure..... 5$0.000 Ps!G TO 8XTEN0E0 PERICOS OF NON+ MOVEMENT OF THE VALVE DISC . TME CHECK J. Design fe m erature.. 480.000 DEGF t $ ARE INSTALLED TO PREVENT SIPMONinG OF $tW9RES$10N POX WATER ikTO TMt $AFETT / RELIEF VALVf ($RV } 015CHARCt LINE AFTER SRV
% Time operating when Reactor is critiest.. 100%
EftlATION .
% Time Operating unen Rea tor is shuteown.. 10%
corrective Action Norrative..... Nours out
.T"E MAlk STEAM SAFETT / RELIEF % ALVI DISCHAact LINE VA:WM $4 TAKER
_ . . ..... -. _ .. .__ _ _-.~.__.. - . _..--_ . - _ _ _ __ _ m
^
/A-114?
' WESTINGHOUSE CIASSt3- -
~festing Performed. Frequency /Peried! ' of Service:
' CalCE VALVE WAS CTCtED $fvtitAL 11MES MAmuALLY UNflL" THE VALVE DtSC - ....+ ..+....-- .......
...a....... **. - ,
, FREELT _. REf t$1 ms $AllSFActoltY .:( M58210 ) .
'. Check iestirg:-.; O / Not Dane. ' O.0 -
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WESTINGHOUSE CLASS 3 A-115 ucteer Plant Peliability Data system Gmeral Report Frr . ph L. Hunter, Jr. Report Id: NPEGOCAA Westinghouse Electric Corporation Job Nud>er 7966 R m Date: 09/08/92 km Time: 10:39 i introdxtlan The cttached report was Generated by your query of the hPtos data base. A swenery of ycur query is listed below. QUttY: Too selected the f attowing search condition (s): Selected Casponent is VALW Selected VALVE Type is Check S:lected Unit los are 206lK$0E 2, GRMD GULF 1, and CroPEt 1 selected systems see Main Steant CE ard Main Feedwater System-W Find Utility component 104 that are equal to any one of the following: N1821F078U, FW 1A, and Ms CV 26CV
~5 elected Manufacturers see Atwood & Morritt Co Inc / Xosm and GPE Crntrols The+ tes 3 r eercs swering the search condition (s). ,
DISPLAY AMD totT: You G:lected to run general report 5: Conpanent Master f ailure Report (w/unf t information) tou chos) to sort the report by: Sort Secpence Ffold home (PRG0$AA Nuclear Plant Reliability Data System Falture Master Report Rm Date: 09/0G/92 Job Nustert 7966 ACCEPTANCE DATE: 04/21/56 ut i l i ty. . . . . . . . . . . . . . . . . . . . . .Ent ergy Opera t f orr , Inc. Un f t . . . . . . . . . . . . . . . . . . . . . . . . . C2AND GUL F 1 4c ,reral Electric A;pt f cation......... Main Steam Safety / ADS Pipe Vac trk N$1S....................... Ccapenent . . . . . . . . . . . . . . . . . . . .vALW Function............ Utility Ccrponent Id.........W1821F078U System. . . . . . . . . . . . . . Main Stese-CE St 12te. . . . . . 07/2 7/85 Utility System...... B21 out of service Mours... 3068 Data start Date. 07/01/83 In-service Date..... 06/1 - Star . T ime. . .. .. 12:00 testoration Houts...... 128 Accepted Det ... 07/16/90 Out-of Service cate.. Discovery Date..11/27/85 f,nd D te. .. .. . . . 12/C2/85 safety Class....... 3 End Time.........C8:00 Operating 2epart C:te..... 02/25/86 Input cate...... 03/24/86 Mece................
A-116 WESTINGHOUSE CLASS 3 l t I System Status. . . . . . . .. . . . . . . .F - T raln/ Channel in Test sever i ty Leve l . . . . . . . . . . . . . . .K Deg raced internal inv........ Steam Mblent Tegerature Over +180F i f Syapten.. . ... . .. . .. ..$ . Out of Speci f icat ico F . Moce . . . . . . . . . . . . . . . . 0R F a l l t o opera t e a s R equ i r ed Ex t ernal E nv. . . . . . . . Ai r Arblent Tegerature *120F to +180F Falture Detection............C - Survelt tance Testing Cause Category...............N
- Weer Out Sweller............ Sechtel Oroup Inc Cause Desert? tion............ta Mechanicet Damage / Binding Sun tler 1d........ 50 14066 BD - Agirig/ Cyclic Fatigue Menuiacturer........ Atwood & Morritt G Inc / Komos Deg reded T r a ln/Chenne l Mfr Model Id........
Sys tes E f f ec t. . . . . . . . . . . . . . . .D Resutted in Ne lignificant Ef fect Mf r Meet No.. . . . . . 140M 01.M Plant Ef f ect.................C Correc t i ve Act l en. . . . . . . . . . . . AG Repe l r Corponent /P a rt Mfr Serial No...... 16 140 M Document a t i on. . . . . . . . . . . . . . . .! kone of the Above Mfr Stancard........ ASME Drawing No. . ... . ... 9645 M 1077 LER R eport Nurber . . . . . . . . . . . . System Affected by failure...CCA - Main Steam CE Engineering Codes Failure Description Warrative..... DuRING SURVEILLANCE TEST!NG OF MAIN STEAM SAFETT / RELIEF VALVE A. Type................ Check DISCNARGE Laut VACUUM BREAKER CHECK VALVE 7078U . THE TORQUE VALUE S. operator............ None SPECIFIED FOR MOVING THE VALVE DISC WAS EXCEECEO . TMERE WAS to C. Function / Application Vacuum Relief SIGulFICANT EFFECT ON THE PLANT . THE t*lf WAS SWUT 004 FOR A 0.Sody Meterlet....... Carbon Steel SCHEDULED PLANT QJTACE . E. Body Meruf acturire M Cast F.komin61 Inlet Site ( & to 11.99 !N Caus* sf fatture Warrative.....
- TEE STICKlWG of THE Vacuum EREArER CHECC VALVE WAS ATTRIBUTED TO G.81:e (Intet)...... . 10.000 IN M.betion Pressure..... 550.000 PSIG MARDENED VALVE PACCING Duf 10 EXTEh010 PERIODS OF NON* MOVEMENT of THE J. Design Teaperature.. 480.000 CEGF VALVE DISC . THE CnECK VALVES AAE INSTALLE3 TO PREVENT SIPWONikG OF SUPPR($$10N POOL WATER INTO THE SAFETY / RELIEF VALVE (SRV ) DISCMARGE 1 Tise Operating When Reactor is Critical.. 100%
L? AFTER SRV ACTUAT!ca .
. 1 TIME Operating When Reactor is shutdown.. 10%
[ ) , C W tive Action Narrative..... Mours Out THE MAIN STEAM SAFETY / PJLIEF VALVE DISCNAkCE LINE VACULM SRf ACER Fre< pen:y/ Period of service Testing Performed CHECK VALVE WAS CTCLED SEVERAL T!NES MANUALLT UNTil THE VALVE -~ ". DISC ROTATED FREELT .. RETEST WAS SAT!SFACTORY . ( MS82101 0.0 Check Testing 0 / Not Done Functional Testing 2 / Three Year 8.0 Calibration Testing 0 / Not Done 0.0
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. TITLES ~ AND ABSTRACTS 7
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Ask at t h e dt. s:k for assist.ance iri changing the d i sc. . IMPORTANT KEYS - pr ess t he s.e keys a L Jiny t i nie t-o begio a new 1uncLion. RESTART F7 To begin a new session or t.o erase .1 previous ses;.ivo FIND F2 To sear ch f or subject terms or author names SHOW F4 To display each retrieved record PRINT F6 To print out selected referenres INDEX F5 l o br ow..e the database i ndm HELP F1 Explains. commands or system prompi.s GUIDE F3 io learn abouL the N11G da Latute O TO SEARCH NTIS G Step 1 Write down your t.opic In a sentence or two De Exact! St.ep 2 Divice your topic into two or .t.hrse mea n i nel f u ) conceris and think of all the specific terms or phrases _which describe each concept.. Use the NASA Thesattrus to help choose terms. GLep 3 Press F2 (FIND) and 1.ype a n a ] ] t he ter ms and phrases which describe your first concept, u v i nej Lhe word "OR" bet.woen each te rin . Example: highway materials or concrete or cement Press ente- (4J) t.o t>egi n t he sear ch and then wait, for t.he computer to finish processing. Repeat this s tep f or ereh < rirent l. in your cear ch Glep 4 Combine the concepts to narrow your cearch. Type in ti.e se t. numbers that the compu ter has ast.t9 nod to voter- final concepLs arid conneuL them W 1 1.h f.he word "AND" l~ Example: tt5 and #9 ( riol e : I q >e l tt tmf.o e eat h numbei ) Ptes.s enter t<J) to i n .a i n I.hr u . o ch o.J lhen u.itt leir ihe computer to f tijsh ru s-m .iseg 3
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Press F4 (CHOW) Press [PgDn] for the next' screen or Press [Ctr1]+[PgDn] for the next record To change the display of records, press [D] Options and follow the . instructions in the window. Press (Fl] for HELP. Press F2 (FIND) to return to searching.- NOTE: The computer always displays from your last search resul t. To see records from another search, press F2 (FIND) and the number of the search you would like to see. (e.g.82) TO MARK As you view your search results, you can mark those records which you would like to print, download or reshow. Position the cursor on the desired record wi th the arrow keys. If the highlight on the bottom of the screen is on MARK RECORD, press enter. Asterisks will display on the record. If the highlight is not on MARK RECORD, press [M]. Asterisks will display., To UNMARK a record, position the cursor on the record. If the highlight is on UNMARK RECORD, press enter. The asterisks will be removed. If the highlight is not on UNMARK RECORD, press [U). The asterisks will be removed. TO PRINT Press F6 (PRINT) or [P] from the menu. Press [C] if you want to change print options. Press [Fl] for help. Press enter [ ENTER] to accept changes to print options. Press [S] to start printing Press F2 (FIND) to return to searching. SEARCHING HINTS To search for: Example: a word in the title field specifically, builuings in ti a word in the subject field specifically buildings in de varioue endings on a word root robot
- reports b author turns-sr in au repor ts b{y report number nasatm89412 reports by date of publication 1989 in py a number in the report 1066 a search result you already have #6 To stop a search in progess, press [ ctrl]+[ break]
TO FIND THE_ MATERIAL IN THE LIBRARY Check the AN field of the record (should be directly after the title). Most technical reports in the Engineering Library ate on microficb Technical reports ate filed in alph.4 num-ric i>rder by this acced number (N.AD,PB etc). If a particular report. is not avcii1able .i t tho 1 i t , Jir y , an order request may be submitted. All reportr. are oi dat ed on microfiche and become par L of t.he 1ibr<try's colJrction. I 1. - r e - no chcir ge ior orders, which gener a l 1 y take several week t, o r i v< 4
1 WESTINGHOUSE CI. ASS 3 l-C M , DOC. n Il verPla_tter 2.01 NTIS 1983. 1984 1985 (#1-13) Y , . No. Records Re qu e s t _. 1: 649 CHECK 2: 1834 . VALVE
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1 of 10 M.o r k 'e'd in earch: #3 T1 .TITL E:xFail ure LTestli ngvof . Acti ve SolarCEnergy Components. AN ACCESS 10NaNUMBER:aDE84013024XSPP;- . OM- + - AU ~ P ERSON A L IAUTHORS':ff'a'r,r;i n g t o,n jR. B . - C S C0R POR A T E ._,.S OURC E.:4 Pie,r.T orme rh'S ol a r.; .E n e r g y . Re s e a r c h I n s t . , Golden CO. F u n d e r'.: .D'e Fa'r tmeii t%gfMelr*47$Wa s hi n~g t'on , ~ DC . .' - R E PORT D AT E/P AG I N AT I ON &O tt1 F04 W71 p' ' - 1 PY PUBLlCATION YEAR:.s.1984 pdf.a>3,' _. . . 0 -
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- DE DESCRIPTORS:
- Solar-Heating-Systems;-Drain-Down-Systems; Failures,;
F r e e z i n g '; <T e s t i n g- ;' .The'rmal-C yc 1 i n g ;'-V a l v e s- F ' " " ~- '
.DE DESCRIPTORS:p,Solari)Raplqq gg ..p sb w /;l Dx!. DENT,1 FJ ERS: A ERDA/j!j4DS,01.gpg,s iM./M .@4v;WWgg%t,emsk .W- wn Siyfg.; gr% a 3, 8 c alghdu s t r i a lg ciNilg-and-ma r in e-egg i n e e r i ng- A i rm -
( jn 1di'SUBJECTJCATEGORIEg3 t'i onYg heIiiDin'g .149 htii@ g epany$n M eWtb1atMhg'k1DA M W ~ C'NN' M' T l Ene r g y-con ve.r si on-n on p riop~ul sive-'Conve rs i on'-t ec hni que s : (10 A) ; 7 $
- l s En o r g y ' Sol a r-en e r gy9(97Nt14M; WW.'*'e&9W'<f%G'WWtt+"s-W r PW m r**
Ene r g y-Hea t i ng-and-c ool i ng-s}s t[emo g(9 7y) ; , . m. -
'3 : q B u i l d i n g-i n d u s t r y - t e c h rLo l. o g y - A r c. h i t e,c, t u r a.1 - d e s i g n,- a n d_ ,e n v i r o nme n t a l engineering
.(898);;-
. 4 i m . w w 3 % w m m e . % ,.r se w ..y. p t w W M y s % s; I n du s t r i a l'n 'a' d-mec ha n i'cil ensi dec r i n g-Qu al i ty-c on t 'r ol-and reliability (948)
CC SUBJECT CATEGORY CODES: 13A, 10A, 97N, 97J. 898, 948, 10, 13, 89, 94, 97 AB ABSTRACT: Component and. system. reliability of ac ti ve solar energy systems continue to be a major concern;of~ designers,, manufacturers, insta'11ers,-and consumers.'Six test loops were constructed and the Solar Energy Research Institute, in G o l d e n . . .C o l o r a d o". s t o < t h e rm a l.l yN cc y c l e active solar energy l system.
- components. Drain valves, check valves, air vents, vacuum breakers, tempering valves, and polybutylene pipe were included in the testing. The test methods l and results are discussed in this repor.t.' Test results show poor. reliability of I
some of the components an d l i mi t e d ' p e r f o'rma n c e 'f r om o t he r s . The results' lead to a_better understanding'of certain failures in the field and present designers with realistic e x pec t a ti ons for these components. Recommendations are given to s improve component reliability and for further testing. (ERA citation 09:045765) AG AGENCY SOURCE CODE: DE i CA CORPORATE AUTHOR CODE: 056095000, 9506687 i RN REPORT NUMBER: SERITR2532187 CN CONTRACT / GRANT NUMBER (S): Contract: AC0283CH10093 UD UPDATE DATE: GRAI 8502, l \
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/\2 of 10 Marked sn Search: #3 TI TITLE: EDE Coal Li quef ac ti on Process Development. Fhese V. Final Technical Fr;grets Report, t .lume !!. Engineering Research end Dev*lopment and Hybrid E' o i 1 + r frcgram.
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WESTINGHOUSE CLASS 3 l l ander:-Department of Energy. Wa s hi n g t o n , DC. ('-REPORTDATE/ PAGINATION: Jun 84. 151p. PY PUBLICATION YEAR: 1984 Cl COUNTRY OF I NT E L L E CT U A L, OR I GI N : UNITED-STATES LA. LANGUAGE: ENGLISH - PR NTIS PRICE CODES: PC AOS/MF A01 _AV.AVAILAplLITY NOTE: U.S. Sales Only. P o r t i on s . a r e il l'egi ble
* , microf'iche products.
DE DESCRIPTORS:
- Coa l-Li quef ac tion-Pl an t s ;
- Coal-Liquids; eeExxon-Liquefaction-Process;
- Residues-; Coal-Liquefaction; . Coking-;
' 'Combu s ti on-; Design-;' Economics-;. Engineering-; E x p e'c ime n t a l - Da t e.; , , s.
-Gosification-;' Hydrogen-Production; Hydrogenation-1 Material-Balance;
* .iMote ri al s-Testi ng; 7Pa rti al;0xi dati n-Processes; Pilot-Plants; Solid-Wastes;
-Vo1Ves-b Waste-Water'; Yields-DE~DESCRIPTORS:
- Coal-Liquefaction-Plants;
- Coal-Liquids; 1.oExxondLiquefaction-Process;
- Resi due s .
.;OI DJID ENT.I Fs l,ERS : c ER D A/C l o,4 05g.4Mp;h,A, _ . .
. . 4. x , 4
' *pSC;SU B'J ECT* C AT EGORI ES':~W og.ulsi on u n d-f u el s- F u e l s ( 21 D ) ; .- + % * /
1 r.*gp MthemijtYly Ch V emi e al'- e'n'gi b ErIrigf(;75fi;W G
, Eneggy-Fuel-con ve r si on pr ece s se s 4(97F) ;
?+14' Q -
Chemi s tr y-Indu s t ri al -c hemi s try-and-chemi cal p roc es s-en gi ne e r i ng (99B);. En e r g y- Envi r onme n t al - st u di e s : ( 97R);
- f
* 'En vi r onmen t al dp ol l u t i on-a nd-con't'r ols (68) o - '" . ,% CCjSUBpECTs. CATEGORY 7 CO.D,ES: @ Dy7,AQ.g f.;g998,,97R, 68, 7..21, 97.s 99.q,.o vA B STR ACT.: ATwo . ma evaluated, requirements for.
4, I B.q$h.0.mme d J ,, gy1,r.c M,uj i ,a}[sga 1 ne(j tti2 nbp 1,a o rrp t e . we a t1etedfJheifir;s't$ e comp tim yppd e e.i.g nse he.S s
+ coalpinf~aronce-through coal $liquefacti'onimode. The second study design *ef f ort WW16 e t e d %eq6i'rvme rrt s*fe r% REDS $'iEn'tW6p e r a ti n cj"on" Wy omi n g'c o a$Mn Wh'e" v a e u um bottoms)re,ycle liquefaction mode.; Cost. reduction and l aboratory guidance studi,e s we re c o n du c t e d ,i n 's e v e r a,1,, a r o n s . . A va ri ety of studies evaluated
%dif f e ren t_ bot toms pr ocessing.ger(dAbydr,oge,n:manuf actu r e options: -(1.)2 vacuum
~
' f r' a c tl on a t i'o n , (2) b o t t om s "p r o'c e ss}n g ' e c o n omi c studies, (3) partial o x'i d a t i o n testing, (4) FLEXICOKING development, (5) technical evaluation of alternative bottoms processing opti ons, (6),the. hybrid boiler predevelopment program, and (7) the uhybrid boilet deve,lopmentxprogram A number of studies;were-carried out to de veTop engi neeri ng technol ogy f or the liquefaction section of the process.
Bottoms. processing engineering, technology was chiefly concerned with.the FLEXIC0 KING option, al t hou gh some tests on atomization of molten vacuum bottoms for combustion in a hybri d boiler are also reported. Materiels and environmental engineering technol ogy developmen t covered a-broad range of subjects. Studies on envi ronmental c o n't r ol of air and noi se emissions,' wasteweter treatment and sol.id waste disposal are reported. Development of construction materials covered corrosion rack and c o r r o si on probe studies, and i n spe c ti on of operating equipment for corrosion and erosion. Other technology development studies covered block and check velves, pumps, control valves, instrumentation, and heat exchangers. (ERA citation 10:000004) AG AGENCY SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 051756000, 9502276 RN REPORT NUMBER: DOEET10069T95, FE2893128 rN CONTRACT / GRANT N UM E: E R ( S ) : Contreet F C 05 77 ET 100 E.9 J UPDATE DATE: GRAI 8505,
)k3 of 1.
Marked in Seer:n e' TI TITLE: Comperison of NUFIFE-II and SAF IV F r e d i .m t e d and ExperimenteTi, b t e r r o r. e c Dvnero : tructurel Rewone-t f .: r 9-rmen stender, P r o h ' - rr 4A 'h l 6
WESTINGHOUSE CLASS 3 f"% ( nder:. Department of Energy, Washington, DC. V)EPORTDATE/ PAGINATION: 1983.~28p. P Y - PU BL I C A110N --Y E AR: 1983 -- NT DESCRIPTIVE NOTE: American Societ) cf_ Mechanical Engineers pressure vessel-end piping conference, Portland, OR, USA, 19.Jun 1983. , em Cl COUNTRY 20F I NTEL L ECTU AL - ORI GIN : UNITED-STATES s l j; LA LANGUA90: ENGLISH ,. 7 i' - PR NTIS PRICE CODES: PC A03/MF A01 # bc ff". or AV AVAILABILITY NOTE: Portions are illegible in microfiche products. , DE DESCRIPTORS: *BWR-Type-Reactors;
- Loss of-Coolant;
- P i p e s'- ; y e Prima ry-Cool an t-Ci r cui t s ;; Rea c tor-Sa f e t y ; S t r e s s - An'e 1.y si s ; H y d r e,u l i c e - ;,,_ g Heat-Transfer; Computer-Calculations; comparative-Evaluations. ,u DE DESCRIPTORS: .* BWR-Type-Reactors;
- Loss-of-Coolant;
- Pipes.; ./4
- Primary-Coolant'-Circuits.% , -
UE ID IDENTIFIERS: ERDA/220900-; ERDA/210100 . V-SC SUBJECT CATEGORIES: Nu c l ea r -sc i e nc e-a nd- t e c hnol ogy-Rea c to r-engi nee ri ng-a ndf operation (18,1) L ,;._,,g j ., , u,,,,q%..,a,.4 4 4,g, c
'Me pi p e c s-fha i t t inni;;s i ciiuS ta lM -i and-valves,(13K);
ndu s t r i a l-ci v i l an A d-ma
? .
r i :nskiU%WBWkf e -e n gi n e e'dri ng@ Nuclear-science-and-te;chnology-Reactor-engineering-and-nuc. lear power ple.nts ,.1L. (77H) L: 53_~ , r - 3 CC SUBJECT CATEGORY-CODES: 181, 13K, 77H, 13, 18, 77 ; AB ABSTRACT:,This papers presents comparisons between two+ computer cSde' ""# p r e di c t i o n s j a n d . e x p_e;rj m,e n t agme a s u r_eme n.t s o f the structural: response;ofya pipe {
. lino /checkgva l v e 4.s y;s t em ;.s u b j e c t e d .t o. l oa di n g, f r om < eN1 o s sio f s f.e e dwa t e r? r , ak.
ansient.sThe.p a e .t he" foiu sto(i VG p'ehna,na S t aEda'rd eP r ob1' mSt To 0 pTr 4efMMH'$ 1i n'g .-i ~s sys t emi s'"dimif ? t he t 'wa s mo r is'k t o r 3 afety Program 4beingeconductedsin the Federal Republic o f fr G e r ma n y..' Thel- $ wo v a isl e b i 14 tipof-bt h'e@rb xp'e rime n t a 1:*'da t e e o f f e r e d cEG9n d *G Sahu ni qu o N ppN t'u n i t y4 to evaluate _two s.t r u.c t u'r a l .c o d e s ' p r edi c ti ons , to compare.them-with each otherp. cnd to compare thel,r; predictions with the actual measured.value's of '
;g. .
o c c e l e r a t i o n . a n d .,f j s p,1.a c e m e n t .j A 9 thermal-hydruelic.ac o d e,, , SO L A ;LO,OP,.,3.c ompu t e d a;,. . the hydraulic' behavior of the~systemi The nydraulic' forcing fun'ctions'were f_ calculated and placed into the structural codes, NUPIPE-Il and SAP IV. It was ~ concluded that both computer programs provided comparable, realistic _prodictions of the piping system dynamic response to a blowdown load. (ERA + citation 08:043906) "
"~~
AG' AGENCY SOURCE CODE:'DE a, , , a
-CA CORPORATE 'JTHOR CODE: 046580000, 9507781 RN REPORT NUMBER: EGGM20082, CONF 83060716 CN CONTRACT / GRANT NUMBER "(S): _ Contract: AC07761001570 UD UPDATE DATE: GRA1 8401,
.4 of 10 TI-Marked i ii [ Search: #3 TITLE: Periodic Large-Amplitude Thermal Oscillations Occurring in a Buoyant Plume.
AN ACCESSION NUMBER: DE83014812XSP
' AU PERSONAL AUTHORS: Ores-J.J.; Kasza-K.E.
CS CORPORATE SOURCE: Performer: Argonne National Lab., IL. ander: Department of Energy, Washington, DC. PORT DATE/ PAGINATION: 1983. 6p.
! PUBLICATION YEAR: 1983 NT DESCRIPTIVE NOTE: American Nuclear Society winter meeting, San Francisco, CA, USA,-30 Oct 1903.
Cl COUNTRY OF INT EL L ECTU AL ORIGIN: UNITED-STATES
-LA LANGUAGE: ENGL!SH rr - tre c .
~ ai 7
.. . . _. . .. . . . . , , . . . . . . . . ..., . . . , . m. , . . ,
WESTINGHOUSE CLASS 3
/ =draulics-; Leaks-; Nozzles-; Pipes-; Reactor-Safety; Test-Facilities; rhermal-Stresses; Valves . "
DE DESCRIPTORS:
- Power-Reactors;
- Primary-Coolant-Circuits. .
ID IDENTiflERS: ERDA/220900 . SC SUBJECT CATEGORIES: Nu c l ea r - sci e nc e-a nd- t e c hnol og y .Rea ct o rvengi n ee r.i ng-a nd . operation (181); ~
, ^eT T',$"~ d ?b
~ *s N u c l e a r - s ti'en c e - a n d - t e c hn ol og y -Re a c t o r - e ngi n e e r-i n g? e nd-fiuc 14 ower p;1ahts M (77H) .
CC SUBJECT CATEGORY CODES: 181, 77H, 18, 77
~'
AB ABSTRACT: Reactor events such as N-1 l'o'o p ope ra t i on ii n%.c'onj'ufc't'i'oNwi t h e y leaky check valve in the down loop can cause flow ttA6e Woi v e h t eld.4Yo@ pr o th'e reactor outlet nozzle / piping region and to be b a c k - f l u s he d :.i n t oNt h'enrie a c t o r w t out1et p1enum. The p r e e e d i n gf r,e sul,tls j i n a _ t empo r a t u r efdif f e r e3c{eJjb;eitwie'e n . pi pe t inflow and plenum. Thi s t emper atu r e -di f f e renc e /cau se s ' buoyancy 4.orce skwhi ch i f-large enough can cause: a' pipe' backflow and r e c i r c u l a t i'o n" To o pV*a n d"ah h e r m a l " plume in the plenum. Both phenomena'.are being studied becauserthey"7can! produce undesirable pipe, no zzl e., and p_l enum4wajd.ct he rma lgdi stQb y " ' " c e , . gig un de si r abl e t he rma l ;st r e s se sMThi,hsppspe r Mdi scu s se sysome :e e
*l urWf is
-(ERA citatio 08:051.282% M4MMi@
. 42l.h .
^ " v- ' *A _
., d ).,-d A & M
,1 N
AG AGENCY sos M ': CODE: DE CA CORPORATE AUTHOR CODE: 0019600007 0448000
, ' %YMgM$Mi?
Q " RN REPORT NUMBER: CONF 03104770 Sum- "' ~ O
- JN CN CONTR ACT/ GRANT NUMBER (S): ' Contra ctr W31109 ENG38 > PW "Wpfe'9ht.. a UD UPDATE DATE: GRAl 8402,.p.n y.y:M ;3 7 .. % aa s-h.Ajigygg[t.- .f
- F'
- W.MM ## -M
,. 9. $Wk.S$ i M$,.$.a Mep!$bNs p W R.l W b.55 h D )y$ g h % . *Ah7 h.
.hTI uhde m. % e.s.wM* tin'rke #in
. . I
- - ~ . . . w Jew i eareh 3 TITLE: L i qui d-Bl oc ki ng chec@VM1Ve'. Patent Application M @ d N1 N ' '
M. '" AN - ACCE SS10N' NUMBER:' DE8'3 0180414XSPot 'v'W *" " * *v'M*r"MA64M.MM AU PERSONAL AUTHORS: Merrill-).T.M a ,
. . . .' ~-
CS CORPCRATE SOURCE: Performer: Department-o.f Energy., Wa s h i n g t orQ 2 DC .-{;;,M M.
. REPORT DATE/ PAGINATION: Filedg27pSepg.82.,10p.
. .-r,
,,g'.y.w q* *v g~g . , c.c PY PUBLICATION YEAR: 1982 '
'" ' ~ "'
' ~ ' ' '
CI COUNTRY OF INTELL ECTUAL ORIGINIDNITED-STATES LA LANGUAGE: ENGLISH -- , PR NTIS PRICE CODES: PC A02/MF A01 = ,y.t W ee - AV AVAILABILITY NOTE: Thi s Government-owned invention available'for U.S. li cen sing and, po s si bl y , for f o r e i,g n . l i c e n s i n g . Copy of application 'available.. NTIS. DE DESCRIPTORS: ' Valves-; De si gn-; Gas-Ficw; L i qui d- Fl ow. DE DESCRIPTORS:
- Valves . .
ID IDENTIFIERS: ERDA/420200-; + Patent-applications. ID IDENTIFIERS:
- Patent applications.
SC SUBJECT CATEGORIES: Mechani cal-i ndust rial-ci vil-and ma rin e engi nee ri ng-Pumps-filters pipes-fittings-tubing-and valves (13K); Industrial-and-mechanical engineering (94); Gove r nmen t-i nven ti on s-f o r-l i c e n si n g-Mee .oni ca l-dev i ce s-and equipment (90A); Manufacturing-technology (41) CC SUBJECT CATEGORY CODES: 13K, 94, 90A, 41, 13, 90 AB ABSTRACT: A liquid blocking check valve useful particularly in a pneumatic ystem utilizing e pressuri ed liquid fill chamber is disclosed. The valve : icludes a floatable ball disposed wi t hi n a housing defining a chember. The housing is provided with en inlet aperture disposed in the top of seid chember, and en outiet operture disposed in the bottom of Yaid chember in an offset relation t ci seid inlet aperture and in communicetion with a catewey sa de va l l section .f said h :,u s i n g . (ERA citaticn 04:054463) Aa AGEnc, ;OUM E /EE- c' E. DE r - - - 8
WESTIliG110USE CIASS 3 i l
/~'N
( l UPDA1E DATE: GRA) 8405, U'
\
6 of 10 l Marked in Search: #3 i Tl TITLE: Componen t : Reli abili.t y Te st i ng .. ..
. ...;t -
AN ACCESSION NUMDER: DE04004496XSP - ja , ,g . . . _ . . AU P E RSON4L) AUTHORS : Fa r ri ngton-R. D . . , " o,; m .* y..- y t. ~ 4.
- CS CORPORATE SOURCE: Performert, Solar Energy'Research Inst., Go den, CO.
Funder Department of Energy. Washington, DC. - - REPORT DATE/ PAGINATION:= Mar 34. Op.s i.
- C m .,, ;g ., .
PY PUBL 1 C AT10N WE AR 31984 P c,Hy w <* n . v i. 4 t h i % '*- -
. s .
. o ,_ .
NT DESCRIPT1VEnNOTE:tAnnual meeting-of the1Ameriven. Solar Energy Society. Ansheim...CA..USAn.54Jun 1984.a.:., a ~ + ~ w . u .. . ,e. C1 C O UN T R Y <0 F CI N T Ell' E CTUNL".'OR I G I N EUN I T E D- ST A T E'sb., g, .r..3i'. LA LANGUAGE:'ENGL'ISH* ~<*s"-
'""4 ** " * ~a' M * -
PR NTIS PRICE CODES:,PC A02/MF. AO,1* .
,, ,,,, M :g (*e .
AV AVAILA0,1LJT c a m il l> 9 D)lt a XmJio i r41.J,o h a J r.o d,u cAs . ,0,rj g i .n a l a o o p y ' a y a ijl? e b'1k,JdN,0, T IMor, ,t.4, na Dt. ' DESCRI PTORS rc* :ypti13sgoog S dle r.tde a t;spe x yeust,ed,$'uien,y ng-SystemedD es.,J W ,y.WyNy fahlur@.es- h 'e:b m.y :q o . g
/ r.4 P o r f o r ma n o e.-T e o tin g ;,, P,4 p e s - ;L R e l .1 a b i l i.t y, .l.,lT h eyma hC.y o,1,i .n g 1; V a i v e s - 1 V o n t a . ,
DE DESCRI PTORS p*Soler-Heating-Syst ems. " P q$W t*- o 7 << ' , ID IDENTIFIER $1 ERDA/140901 . - P. < SC SUBJECT CATEGORIES:' Mechanical-industrial-civi1-and-marine-engine / ring-Air-6 o o n di t i,op 5.h e a ,t.,i n g ,,1.i.g ht i n,g ,a n d y e n,t,41 a t,Q g j,Q{A),;ig.,g y up . . g., ,
,i Energy-So rene r gy ((9,7N.) NWe gqrpm wo 3
'gg
,/ ergy-He6 h g - a n,d - c 901,i n g - s y s t e m s.Q9 7, J )g ;
( ]f, SUBJECT @ATEGORhC00ES 2W,3 AD.97N ,4970,%14 y;.dm., ygg/fpQ .w ,g(. :,W. m ,- , s . db , s *. s y,q,. y eQf,j,.j,W we AD ADSTRACT: C omp o ri e n i e nt d s y s t em ' r e l i a b i l,i iyG g:} e c tTv e s ol'a r e energy. systems
- c o n t i n u e s' it'o% e*a Nnel o r' "c o n c e M tif4d e s i g rie'r's @m'ahf%her e rsWh s t al l e rW ' a n d O 8
consumers. Six testj. loops'were c o n s t r u c t e d ','a t) t h e { S ol a rnEnergy Research Institute in G'o l d e n [ Col [o r a do , to t h e rme 11 y[ c y,5f,e;a cj,4, v e . s ol a r energy system components,.,. Drain,,velves. check valves a ai r.iw a pw v.a cu umg r be a k e r e , . t emp e r i ng 4 volves. and' pol ybutylene pipe were i nc l u d e d 'i n' t he ' t e s t i ng .'T e s t re sul t s show " poor reliabilty of some of the components and limi ted perf ormance from others. Tho results lead toa better u nd e r s t a n di n g o f . c e r.t.a i n . f a i l u r e s in the. field and prosent designers with r e a l. i s t i c expsetationseforrthese components. (ERA ~ citetion 09:028173) M~~l AG AGENCY SOURCE CODE: DE . .. . .. . .. .. , g,6 ' L,g ' 4 ., y , , x , CA CORP 0" ATE AUTHOR CODE: 056095000, 9506687 PN REPORT NUMBER: SERITP2532299 CONF 04062210
- CN CONTRACT / GRANT NUMBER (S)
- Contract: ACO283CH10093+ '
00 UPDATE DATE: GRAI B420, *7
- l 7 of 10 Marked in Search: #3 Tl TITLE: Shutdown Heat Removal: Safetv Water Tests.
AN ACCESSION NUMBER: DE02008064XSP CS CORPORATE SOURCE: Performer: General Electric Co., Sunnyvale, CA. Advanced Reactor Systems Dept. F',a n d e r : Department of Energy. Washington, DC. DATE/ PAGINATION: 9 Jul Bl. 32p, (')EPORT PUBt! CATION YEAR: 1981 (M 1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-iTATES LA L A N G u t, G E : ENGL1SH PD NTls FRl(E CODES: PC AO~./MF A01 DE DL%CRIPTORS: .Lmftr-type-reactors; . L o s t - o f - f i c. w ; . Rhr-systems;
.T*tt-facilitier: Fee tor tefatv: A f t e r - hee t -: After-heet-removel. g e < i r r 1, , . , , , , , . ..
n
WESTIliGHOUSE CLASS 3 i ( : SUDJECT CATEGORIES: Nucl ea r -sci enc e-a nd-t ec hnol ogy-Reac t o r -engi neering-
' operation (181);
Nuclear-science-and-technology-Reactor-engineering-and-nuclear power plants (77H) ,
.CC, SUBJECT CATEGORY CODES: 4181p77H. 18, 77
'. AD" ABSTRACT: This. specification establishes the r e qui r eme n t s -t'. .de si gn the SAFETY'WATOR TESTS to be constructed in the H, y d r a u,14 c l T e st Fa. i t y -(HTF) at the GE San Jose site. The test is an 1/8th scale model of a large loop type breeder reactor or a 1/14th scale model of,a large pool type. b r 'e'e d e r reactor end uses; water as t h e vt e s tif,1 u.i d . . I t -s t rnu l'a t e e _ S treeder reactor system with a O'.5 MW heated coreiwith'an7up'pereend allower pl enum. .a pri ma r y l o.op wi t h. 3 00 gpm' flow rote and four auxil.iary*-cooling systems'(DRACS) that are to be irnme r s e d v_g 1 v e %.. . . ;. yi,n; t h e .u.
: -UD %,0Npl ACT/GR ANTrNUf10 Eft P D. A T. ; E f D A T E 5.G ptra(S l4. c t :g. AT0376S 'h fb' 71b 3 2 (WME'J@y ' ' *,+ emM .o R A I 183 0 2 , W.h drW'/.e W"rthW r c - 7 (, y , - <. g.. . .. , . a . we . ,. , . w ..e w . .. . ~ .,~.m . ... .n... =. . .. n. . p j ..+,1, r. A 8 of 10-t.#. ,.y w - .. . 'Mf Marked.in jSearch: #3 ' 'T !*T ITL E':Pl an t Ma i n t es nes/T*r ai ni ng ff a nu el', (RADL" Item 2-37):~Section 4. c Wo.1 v,e n'4B o o k ;2,.gf 2 . y 0 4,M'.3,Mo}1,a r4T.h e rma ljC e n t r a l - R e c e i v e r ..,P,i l o t gP.l a n t , " Sol a r- re pri,1:i.t i e s De s i gn /,I nt egr,e t4cnuMA qp: X , ' e. : 'r . , + <qw . + '1 ;; . t/ 'thACCESSAON N.UMD ER:' DE82 039ffig'q/gg -Qj,;gpk,; p.,3.Jg,, , g * . he CORPOR ATEDSOURC E t e*0e rf omero+1c DonnelkEDou gl a s .. A s t r onau ti c s -Co4 , dun' ting Beach, CA. .'.' ' ' J s.'AM.% a W ~ - "Tu n d e'ri$ D e p"a'r t'm e ntF6'&Cn d r*gNHIsNh@o rO,D C"."'N " L -+* **P'**"' REPORT.DATE/ PAGINATION: Julg81. 595p.,g . c, ,PY; PUBLICATION YEAR:_ 1981 _ , ,, _ d g ;D;. . . , 7 C i g COUN T R Y< ,0 F .I NT E L L E CTU"A'L#0Fti LIN' :%Uf,(lj E D .ST AT E s t. , .r wu ; .. LA LANGUAGE: EN G L I S H ' ' * ' " ~ PR NTIS PRICI CODES: PC A25/M'F A01' DE DESCRIPTORS: *Barstow-solar pilot-plant; Valvos-; Relief valves; Sol enoi ds-; Specifications-t Trops-; M o t o,r s, .1
- M a n u a l s .
DE DESCRIPTORS: *Barstow-solar pilot plant. .
ID_IDENTirlERS: ERDA/140702'. *.f35.c .
. .s .. .
SC SUDJECT CATEGORIES: Energy-conversion-non propulsive-Power-Sources (100);
Eno r g y-Sol a r - ene r gy (97N)
CC SUBJECT CATEGORY CODES: 1.0 8 , 97N, 10, 97 AB ABSTRACT: The valves i n c l u'd e mo t o r' 'o p e r a t e d v a l v e s . other solenoid valves, safety-relief velves, checl and stop cheek velves, pressure regulator rupture discs, and trapt. The valves are listed, and many are i ndi vi duall y described and specified. (ERA citation 07:042926)
AG AGENCY SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 030394000, 4035600 RN REPORT NUMBER: SAN 049992Sec4Dk2, MDCG9705Sec4Bk2 CN CONTRACT / GRANT NUMDER(S): Contract: ACO3795F10499 UC UPDATE DATE: GRAl 8306, 9 of Merhed in Search: x3 Tl TITLE: I r. t e g r e t e d Twe-5tsge Liquefection: Start Up of Integrated FDU.
Quarterly Technical Frogreet R e p.. r t , April 1, 1900-June 30, 19EO.
AN M C E S0lON IHIMb E R
- D E C O l M 7 E f t F W f [ A f fm A L AUTHOR' thindler-H.D '
- h-n-).M l F+tt Y- 3.D, 10
WESTINGilOUSE CLASS 3
[slande r : Department of Energy. Washington. DC.
hdEPORT DATi/PAGlHATION: Mar 02. 91p.
PY PUDLICATION YEAR: 1902 NT Df'CRIPTIVE NOTE: Portions of document are illegible.
C1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES
- LA LANGUAGE: ENGLISH .
PR NTls PQ4CE CODES: PC AOS/MF A01 - -
DE DESCRIPTORS: *Tal processt
- Coal-extracts;"* Coal-liquids;--Ef' liquefaction; Coal-Proceas-development-units; Hydrogenation-1 Deeshing-; Lc-fining-i Hydrogen ;
Consumption fates; Experimental-data.
DE DESCRIPT0RSt *Tal processi
- Coal-extracts;
- C o a l-Ti q u i d e . .. _c, ID IDENTiflERS: ERDA/01040S .
SC SUDJECT.. CATEGORIES: Chemi st r y-C hemi c a l-engi ne e r i ng (7A); 'g Pr opul sion-and-f uel s-Fuel s '-(21 D);
Chemistry-Industrial-chemistry-and-chemical process-engineering (998);
Energy-Fuel-conversion-processes (97F)
CC_. SP D)(CJAC AR GO& COD E S : 7A. 2,10 jf 9 D . 9 7 F,,,7.,21.,97, 99 g
+ ADe < ABSTRACFthThie~ program combines a .re search study on Ca tal ytic Expanded Ded-H y M p r o c7s'e'lifg^L o f . Co'a1, Extracts (Task 1).mndrthet. operation of en Integrated '6 Two-S t a gejl;i que f a c t i on Process Development Unit _(Task 2). The two taska are t o, run c on-cur rentl y. Two runs of the Parametric study of Task I were c ompl e t e d. 'c All units of'the Integrated PDU started up with the.first stage, short-contact i' time r eac tor . using f or eign posting solvent in t hi s the$rter. qu The i n t e r r up t ed f o r. abo u t, ona. mon t h..t o replace feed lines, p a r am e t g[i c s,,S,4,u,d y , wa stransfpr M;ines+andicheck volves that had'become corroded. All Task 2 u ,
O't,opez5tio'ng.this qu a r t e r . . S ho r t - c o n,t a c tjtj m,e 4( S CT) ,r un s with Hoppers ;;
Vr eo s6ts*@(beel ven t and r e ac t or ou t'l e t+t empe ra tur e - of 860 e xp 0 F were made
~
with no , operating difficulty. The coal space rate was varied between 111 and v 247 pounds'86fecoal+f eed"pe r -hour pe r ecubie f'ont oft reac tor ' wi t h no -e ff ect on#
conversion. which,was 91 +- 2% of moisture, ash-free (MAF) coal. Hydrogen c on s ump t i.on,,v a r i ed, f r om 0. 6 to 1.9% of MAF coal.,Preasphaltene content of the extract in.c,reased with coal space rate f. rom 29t to3 44% o f. . t h e soli ds-f r ee ,
extract ~The deasher successfully deashed the SCT' extract and provided a low-ash feed to the LC-Finer. The LC-Fining yields from this extract agreed well with runs made under the preceding contract with SCT extract made at Wilsonville and deashed by Lummus. The LC-Finer also had no diffievity hydrotreatfikg' extract that had by passed the deosher. Per pass ~ 8SO exp 0 F+
conversions in.the LC-Finer were 3S to 49 vol.,. %. (ERA citation 07:049000)
AG AGENCY SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 064097000, 95042SS RN REPORT NUMBER: DOEET14804T3 CN CONTRACT / GRANT NUMBER (S): Contract: AC2279ET14804 UD UPDATE DATE: GRAI 8308, NP ( 10 of 16)
Marked in Searct: #3 Tl TITLE: Licensee Event Report Analysis for Selected Safety System Valvee.
AN ACCESSION NUMBER: ID01S70T22XSP AU PERSONAL AUTHORS: Hubble-W.H.; Miller-C.F.
CS CORPORATE SOURCE: Performer: Idaho National Engineering Lab., Idaho Fall s.
r under: Department of Energy.
(tYjPORT DATE/ PAGINATION:
PUBLICATION YEAR: 1979 1979. 710p.
Cl COUNTRY OF INTELLECTUAL OR I GI N : UNITED-STATEI LA L ANGU AGE : ENGt15H FR NTl; FRICE CODET: FC A95/MF A01 DE Di-:hIF10R -
.fwr'-typ -ree:+cr., .Fw, -t cr-t ee:tcr. ,
))
WESTINGHOUSE CIASS 3 f.b' h o
/ :cactor protec' 0
svttems:
- Values .
D IDENTIFIERS: e /I20900-; EhDA/210100 ; ERDA/210200 . a SC SUDJECT C A f t- tS: Nuclear-science-and-technology-Reactor-engineering-and-operation (181);
Nuclear-science-and-technology-Reactor-engineering-and-nuclear power-plants "
(77H) ,' ....,,,
CC SUDJECTpkATEGORY CODES: 101, 77H, 18, 77 ,
AB ADSTRACT: Thi s anal ysi s utilized the US Nuclear Regulatory- ommission's Licensee Event Report (LER) file to estimate LER-based f a i l u.r e rates (LER rotes) for selected safety system valves iti operating nuclea} power--plants. In.
general, the selected safety systems included Pressu'r.ined. Water. R.eactot JPWR)N and Dolling Water Reactor (BWR) Emergency Core Cooling System (ECCS) valves, s' ,
PWR Auxiliary Feed Water System ( AFW) valves, and PWR and DWR. Primary,y Sofety/ Relief valves. L E R r' a t e s w e r e calculated for. remote actuated valves 4,e (i.e., motor-operated, hydraulic-operated, air-operated, e t c . ) 'in both' t he ECCS and AFW systems for failure modes of fail-to-open and fail-to-close. LER rates
, we r e, also cal ulated for, rever,se, leakage of check valves,tnfbotht,,he,Ep,CSandE AFW eystems, amend LER rates ~were calculated for two'exemplecasesrofiprimar,yT rolief. valves f a i l i n g- t o-open' a nd t f a'i li n g-t o- r e se n t . Ho u'r l y ILERfrates% ere M.C T
calculated for primary relief /sofety val ves which opened prematurel y. 3n. each k calculations, aggregate LER rate were calculated for both PWRs and BWRs. and a'n overall LER rate was calculated for all valves in the particular c e l e u l a t i o n . .
(ERA citation 05:001003)- > i- - -
1 ..j'. ~ 4
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- N p . s... ?. :.A Jf
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elverPlatter ? . fL1, NTIS 1980(#14-?6). 1986-19ro(al-211 s
No. Records Request 1: 1262 CHECK 2: 1281 VALVES . v -A.
3: 41 8
,, CH EC K r'V A L V E St( Semad DM EO b (t.t:: %. . u. .e..-sy. . . . . -
1 of 9
, M.a r k 'e'd in Searci. 3 TITLE: Light Water Reactor Pressure 1 s'o l a t i o n Valve Performance Testing.
TI Research rept. '
%'-' '..- f re v AN ACCESSION NUMBER: NUREGCR5515XSP *.
AU PERSON AL AUTHORS:- Neel y-H.H. ;- Jeanmougin-N.M. ; 4 Corugedo-J.J., p
. . 7,,, ,y CS CORPORATE SOURCE:- Perf ormer: Energy Technology Engi n ee ri ng Cen t e r ,*Canog a ~" '
f Park, CA.
Funderf Nuclear Regulatory Commission, Washington,. DC. Div. of Engineering. , (a REPORT DATE/ PAGINATION!' Ju1/.SO. 73p., ,
. . a 4. p w* ' $643.a W , p W , eq PY PUDLICATION YEAR Q1990'W 4
~T %%'7*$gh 7 ? %fNf.T NT DESCRIPTIVE' NOTE " Al so' available f r om S u p t . ' o f " Do c s"."S p o n s o r e d h b y JNGo'l e dt '
Rogulatory Commission, Washington, DC, Div.Lof. Engineering..
.. J,i, j,, , . . .i C1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES m*e "" UP' *d.t.
^ ' ^
LA LANGUAGE: ENGLISH .
PR NT!S PRICE' CODES:"PC A04/MF A01 " ' "~ * ' b- -
DE DESCRIPTORS: Performance-tests; Leakage .;m D e g r a d a t{o ry.,;i c h e c k - v a l v ee' i, pp
'Gote-valves; AcounLtic;moni tor:i ng; Failure-;< Li f e-c ycleate sti ng.a p r pqqy4
.DESCRIP. TORS: *Nu t
/]d
( IDENTIFIERS: 0h d_cjear h U-wa tpower;plantyi,;,7Valyes.)
e r- r e a c t o r s '. v * *+ - - ' g,g"'glp
- g s,g g'g g ,.p.g$ * *
- w*' -
SC SUDJECT CATEGORIES:' Nuclear-science-and-technology-Reactor-engineering-ande
"*nu c l e a r - p owe r pl a h t's"t (f77H )M W-M F '% . e *meM4titw Ah % Meta "--- 4 CC SUBJECT CATEGORY CODES: 77H, 77 -v ^-
AB ABSTRAr': The Light Water Reactor Valve Performance Testing Program was ,
initiated ,
the;..NRC..to evaluate leakage as-en indicatjoncofavalve. condition,3 p r ovi de input to'Section XI of the ASME Code, evaluate motor signature testing to measure valve operability, evaluate acoustic emi ssion moni tori ng f or condi tion and degradation and in service inspection techniques. Six typical check and gate volves were purchneed f or testing at typical pl a_n t conditions "
(660 F et 2250 peig) for en assumed number of cycles f or a 40 year plant lifetime. Tests revealed that there were variances between the test results and the present statement of the Code; however, the testing was not conclusive. The lifecycle tests showed that high tech acoustic emi s si on een be utilized to trend small leaks, that specific motor signature measurement on gate valves can trend and indicate potential failure, and that in-service inspection t ec hni que s for check v a l v e s, w a s shown to be both feasible and an escellent preventive maintencoce indicator.
AG AGENCY SOURCE CODE: NUREG CA CORPORATE AUTHOR CODE: 060308000 RN REPORT NUMBER: ETEC0001 UD UPDATE DATE: 9020 3 Marked in Secrch: #3 ji TITLE: Action P1ans for M o t c. r - O p e r a t e d Valves and Cheet Velvn .
AN ACCESSION NUMBER: N U R E' G 13 r. 2 X S P AU FERSONAL AUTHORS: Scarbrough-T.G.
C'. CORFORATE SOURCE: Ferformer: Nuc1eer R
- r) u l e t o r y r o rnr.. i 3 e i o n . Wa>hington, DC.
Office of Nucleer Recctei Regulatson REPCG7 b A T E / F A r, ! N A T I ON : lun %. 3, r, n
..r 16
a _ _ . _ . _ _ . -- m & &_ a y & g , 4 y g & g,. , es WESTINGHOUSE CLASS 3
' , LANGUAGE: ENGLIEH PR NTIS PRICE CODES: PC A03/MF A01 .3 _ u DE DESCRIPTORS: Requirements-; Standards-; Inspection-; Problem-solvin,g!
Performance-evaluetion.
DE DESCRIPTORS:
- Re a c t o r- s a f e t y;,-
- C hec k -va l ve s .u . .._,,; ,, g h .,f 4 g ,,
ID IDENTIFIERS:
- Mo t o r - o p e r a t e d- v a,1 v e s . . . .
=. .,, @ . g g SC SUDJECT4 CATEGORIES: N u c l e a r - s c i e n c e - a n d - t e c hn o l o g y ' R e a ola nuclear-power plants (77H) "
CC SUBJECT CATEGORY CODES: 77H, 77 - .
AD ADSTRACT: The proper performance o f . mo't'o r - o p e r a t e d - v a l v eh(fiO V s )
velves i s necessary for t he s a f efop'e r a t i on),o f; e nu o4Ad r .p owe .r.o rg3,rtt b.J e m .Ql;e s'
have been' experienced with these valvestior many. years.1Currenffy,gthe]U"$.
Nuclear Regulatory C ommi s s i.onp(NR,C)9a n d,.t he n u c l e a r ,,i n du s tr.yxhagelmanunibe r o f, ; ,
. octivities under way t o p rn'i-d e#a s s u r a tic 4~ t ha t. MOV a ~e n d fo @c k'Oa1 Ge e'MED.1 successfully perform thei r saf ety-f uncti ons when needed. 'Ihe-Mechanica1o Engineering Branch (EMEB) of the-Office.of Nuclear Reactor Regulation l.4;as been, cosigned the r e spon si bj l iut y;@fyge dhet1 eck -4RCs act,i iegpn % { {rl4rW gii, ,[~
industry
- activities responsibility. EMEB has prepare r e g a r d i n,g yM,0 , Jn d 'l.5 h,,qg T o, ne$
)' v ae l v'e j proper performance of these' yelves..T,hrough the .
action'p,la,n,s,6 M NR "
s4aff will have an organiz ed approach. to* resol veythe operability of MOVs and check.Veh es-in a ttimel y^ manner, h c on ce rn s prega rdiggg,.yt,, ", y y W g-
;f AG AGENCY SOURCE CODE: N U R E G wM '- ' O ' '~ - r e v.W.vrN. >b .o
.C A CORPOR AT E . AUTHOR COD E : .s04 41,000354.g.1, g,Q. . ,, ,,4,. ,44,g gg Q.
-UD UPDATE DATE: 9010 m A .>g. ypwg q,. ww.,4 g g4 ~*
a-g, ,
- +
2 Au o ':. : . .s.M,.7:.. .d% Ah%,_ M.. Q..,:.%lH 9Q .a m s (m , .~ .- . . c .... ._ *'
jd.ith.. is,l,j. ~ *, ., f . . . i.b. m.b4 'eH aFkIef*, ilrijSSa r c h : .#3
' T!"^TITL E i Ev al u a ti on tof ?ChshMf awe 4 Mon it' orsi ng SMe t'hodov&ky.Qf,UMd@b a AN ACCESSION NUMBER: DE900024 , y,..sd gi, . .4g AU PERSONAL AUTHORS: H a y n e s D- .H - ,0 G,2 X S P .. ,. % .7...,:
CS CORPORATE S O U R C E : P e r f o rlme'r,:da hR i,d g e . ,N a t i,o n a l ,, L a b .,, hTA.Qi Funder: Department of E n e r g y , Wa s h i n g t o n , ' DC . ' -
er d Q '
REPORT DATE/ PAGINATION: 1989. 31p. ^ "~ '
" "~"
PY PUBLICATION YEAR: 1989 , , ,,,,, , ,m NT DESCRIPTIVE NOTE: 17. wa te r geac t o r - s a f e t y i n f o rma ti on-mee ti.ng.n Roc k vill e..
MD, USA, 23-25 Oct 1989, Por ti ons of thi s document are illegibTE in misrofiche products.
C1 COUNTRY OF INTELLECTUAL ORI GIN : UNITED-STATES s . . ,b. , ,,. . . . , ( ,.gg, gg.. '
LA LANGUAGE: ENGLISH - -
PR NTIS PRICE CODES: PC A03/MF A01 ~
.. w .
Ut DESCRIPTORS: Ac ou s t i c- Emi s s i on-Te s ti n a ; Design-; Leaks-; Magnetic 4Fl u x ;
Reactor-Safety; Research-Programs; Technology-Assessment; Ul t ra soni c-Te sting.
DE DESCRIPTORS: *Nuc l e a r- Powe r-Pl an t s ;
- Valves;
- Aging;
- Reactor-Monitoring-Systems.
ID IDENTIFIERS: ERDA/220400-; ERDA/220900-; ERDA/220200 .
SC SUBJECT CATEGORIES: Nu cl ea r-sc i enc e-a nd-te chnol ogy-R e ac t o r -en gi ne e r i ng-a nd-nuclear power plants (77H);
Nuclear-science-and-technology-Reactor-materials (77J);
Energy-Selected-studies-in nuclear-technology (97Q)
"C SUBJECT CATEGORY CODES: 77H, 77J, 97Q, 77, 97 -
3 ABSTRACT: Check valves are used e x t en si vel y in nuclear plant safety syt is and t,alance-of plent (BOP) systems. Their failures have resulted in significant maintenonce etforts and, on occasion, have resulted in water hammer, ove r p r e t su r 3 : e t i on of low pressure syttemt end damage to flow s y s t e rn c on.p o n e n t s . Consequently, in recent years check valv.r have received
- en e i h r a t l e a t t - n t i o r, bi the Nuclear Reguleter. C omm e r i o n (URC) and the 17
r... .. . . . . . . . . . r.... ......
WESTIliGHOUSE CLASS 3 l
p
( > evaluating several developmental and/or commercially available check val ve Ediagnostic monitoring methods; in particular', those based on measurements of ecoustic emi s si on , ultrasonics, a.nd magnetic flux. These three methods were found to provide different (and compl ementary) diagnostic information. The c ombi na t i on of. a cous t ic 4emi s si onawitt hce s.t he r sul tra soni c. or magne t i c fiux moni t oring yi elds;a emoni toring4 system t h a t-'s'u c c e e d s ' i n : p r o v i, d i ..sen si t i vi t y to detect a 115.ma j o'r c h e c k s v a l v e do p e r a t i n g i c o n d i-t i o n s C 41 D,t hT e e' bods are"still '
under development and should 1mprove in many r
'espects as a resu t of further testing and evaluation. 10'refs., 19 figs.t 1 tab.- .,
AG AGENCY 50VRCE.40DE: 3DE*W h*. ~?be'c> ~ a CA CORPORATE AUTHORnCODE 50$1I310000, 4832000 " d ' 2 C -~ - , . .
RN REPORT NUMBER:PCONF8910222M 4 ' "
CN C ON TR A C T/ GR ANTjNU,H,B E R,( S)MC on t r a c ty A C 058 40R 214 00j. y t g,W - .,
UD UPDATE DATE: J9 OO l ' ee + T.wM N - - .+ + h - -m ~*N 4 p .m .. < ,;-. . m :.; a , - .' .- -
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valves. r Ab a l r.e p'oM s c'hTTMsMirfo' U/,;.,.$4L'.. lit?.hDy$
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AN AC C ESS 10N 'NUMD.ER fT] B A 0 8832 71 X S P W Y j ' /,rf B*~* % '^MM w -
AU PERSONAL AUTHORS:tGronenberg-R. ,- ;*.1' ' " *% . 'c .
t CS CORPOR ATE
- SOURCE:"Pe rf orme r-: 4 Stu t t ga r t > Uni'vW(Ge rman'y i F?R. ) F ~1 n s[. "f ue r '
l Hydraulieche eSQomur,ihofna%ohFenMmwh,y@.@ppdM'@f4dt,hWa%% < * .# y l
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DE D E S CR I P TORSetomp.u t e r,i z edy.6 t mu l a t i on ). Ha thema ti c a ) -mode l s ; v compu t. s t i on- ;
~
Literature-surveysl'Dampinga;' Steady-state;" Estimations . ,
DE DESCRIPTORS:
- D yn'ami c- c h a r a c t e r i e t i c e ; *Non-return-valves.
ID 1DENTIFIERS:
- Foreign-technology;
- Fluid-dynamics.
SC SUBJECT CATEGORIES: Ma n u f a c,t u r. i n g- t e c hnol.o g y-To ol i n g-ma c h i n e r y -a n d- t ool s (41J);
- I ndu s t ri al-and-mec ha ni c al-engi nee ri ng-Hydrauli c-and pneuma ti c. equ i pmen t m (941);
l Phy si c s-Fl ui d-me c han i c s (46B) l CC SUBJECT CATEGORY CODES: 41J. 941, 46D, 41, 46, 94 .
I AD ABSTRACT: Within the reported project ,the dynamic behaviour of non-return valve s wa s systematically investigated. The~ a'im was to suppl y designers and applicators of hydraulic installations with criteria to assess the behavior of the non-return valves. The main stress was laid on check valves. The investigations were carried out e xpe rimen tall y and by way of numerical s i mul a t i on s . In the calculation dimensionless characteristic values were used, which were improved from steady stete measurements. The force occurring during l the closure of the non-return val ve was determined and investigations in a damping equipment were carried out. With the results of these investigations it is po s si bl e to estimate qualitatively and quantitatively the influence of ifferent parameters of the non-return valves. ( c, r i g . / R H M ) . (T1B: FR 1398.)
,opyright ( c ') 1988 by F12. Citation no. 88:083271.)
AG AGENCY SOURCE CODE: TFF!Z CA CORF OR AT E AUTHOR CODE: 02E510000 CN CONTRACT / GRANT NUMBER (5): Contract: E M F T 0 0 Wi > D 5 UD UF DhT E DATE: 8909
! l8 .I lw a .s. g ,-w,
. WESTINGliOUSE CLASS 3 f .wer Plant Systems. Final rept. Sep 87-Apr 88.
W N ACCESSION NUMBER: Nbr.EGCR5159XSP
/,U PERSONAL AUTHORS: Kalsi-M.S.; Horst-C.L.; Wang-J.K.
CS CORPORATE SOURCE: Performer: Kelsi Engineering, Inc., sugar Land, TX.
. uf.unc e r t Nucl ea r Regula to r y nCommi ssion , tWe shi n g t on , DC. Office of Nuclear
'4RogulatoryfResearch. 3 .Nd ,3 9u ' e- -
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- PY PUBLICATION YEAR: 1908 NT DESCRIPTIVE NOTE: Also available from Supt. of Docs. Spon sored by Nuclea r e iR6gul'e'to r.yi Comm.i.s si on ;-We s,hi ng' ton. LDC. Of fic e of Nuclear Reg 01 story Research.
QC1 '0CO.UNTRYh0 F '1 N T E L L ECTU A Ljio,R!!11N :
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4A .
- N u c l e a r 'p[oke KBg,E[J,,C &T.E G.0 RJ.,E S,: ,1Nu
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g.'e s ' ;' -
, .,1 u r e f o fji.s wi.n g c h e c k valves and.[resulting
,gABi
$dema'g ABSTR e ?t of 'plACT:a n t. e.Degrada qui pme n t ti:h'a ons !,andy/
ll,e a)dato aineedyto develop a method t'o pre. dict
'spo r'f o rma n c e ' a n d degr ada ti on3of;the s e: val ve s 'i n . nuc l ea r power plant systems. j The
" Phos'e t"I* i n4e s ti gat'i ont de v elop'e dNnet ho'd s .whi c h ca n be used'to4 predict the y..c,tc b ii3 t i.t yi.o fs t.h e o h efc k @ a lg3 MMeplep d i p i n gi.d i a t u r b a n c e s s o u c h ..a s)41 b ow s ,.
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' h chi, eve yaut ul ls op,'eny. ethi he oss$troncithe magnitudeno) M isk*fyirequired motions
- d o v' it he s'e up s t r NMid 0sti/rti'~ric a es\wi t h f l.ow v e l oc i.t i e s b e'l ow full open kan"el oped wi thdi'tfo n d"'aiWSW%Td iMMWl%QWq'iT4(My*d a t'ahwhi tih~4~ 17JeVN d
-woor,and~ fatigue' damage.;Reduo'e % wir:elfound-to cause l i t tl e aor., no, p e r f o rma n c e
,,,[d o g r a d a t i o n . E1 bow 4 e f f e 6 t sMsVbMo',p si[de}e d when , l oc a t e d ;wi t hi n 5 di ame t e r s af..;t,h e,.c he diotences to c10k .diameters.,
va l ve ,y yhij eg[C1,e a rwa y; swi designs r@ c he were c ke veAagtug.bule found to be nc er.so porticularly sensitive to manufacturing tolerances and installation variabl es making them likel y candidates for premature. failure. Reducing the disk full eponing angle on t h e s e - c l e a ryaygd e s i,g n,s resulta i n > si gni f i can tJ,e r f o rmance improvement. , s "4 + -
.AG AGENCY., SOURCE. CODE: NUREG ODEl,..;'d,A v. .o ,
. . s.
CA CORPORATE AUTHOR CODE: 091'370000 RN REPORT NUMBER: KE11559 UD UPDATE DATE: 8818 s. ++ .
- 4. % . , .-
l 6 Of 9 Marked in Search: #3 Tl TITLE: Sellindge AC/DC Converter Station: Surge Ana l y si s .
t AN ACCESSION NUMBER: BHRA8804XSP l AU PERSONAL AUTHORS: Buttigieg-G.L.J.; Austin-K.
[ CS CORPORATE SOURCE: Performer: Bri ti sh Hydromechanic s Research Association, Cranfield ( Engl and) .
REPORT DATE/ PAGINATION: Jan 84. 20p.
DY PUBLICATION YEAR: 1964
. COUNTRY OF INTELLECTUAL ORIGIN: UN I T E D- K I N GDOM LA LANGUAGE: ENGLISH PR NTIS PRICE CODES: pct 45.00 l DE DESCRIPTORE: Fire-eefety; Cloturee-; Velves-; Accumulatort-;
l El ec t r ic-cenver t er s; Fumps-; Water-flow; Hydromechanics . jg i .- DE DE:CRIFTORi,
- r. . - . .
+ U n i t e d - F i n g d o rt ; +5urget-; +Futterfly velsee
WESTINGHOUSE CLASS 3 CATEGORY CODES: 97E, 500, 50, 97
)* SUBJECT bend ABSTRACT: The British Hydromechonics Research Association conducted 6 surge analysis of facilities at the Sellindge AC/DC Converter Station. The analysis was undertaken to determine suitable valve closure times in the event of an operator shuiting a butterfly velve against the flow from two pump units ,
following a false, fire alarm. The total system. includes a stora ~ e vessel, pumps, check valves. on accumulator, mains, bu t t e r f 4 y a'n d del T ' val ve s ," and "
sprinklers. Results of the analysis indicate'that a five-second~ valve closure would result in an initic1 head rise well wi t hi n- t he shut-valve pumping head.
if it-were.necessary to achieve a faster Val v e closure, then three seconds
- would be-theEsuggested minimum time. No operations pi.oblems s hou l.d be _ .-
encountered-during normal valve opening and subsequent start-up.
AG AGENCY . SOURCE.. CODE: TFBHR .m CA CORPORATEVAUTHOR. CODE: 004480000 Jf.5 RN REPORT NUMBER: RR2137 UD UPDATE DATE: .8817
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Marked in Se, rch:.w3 Tl TITLE:; Removal of Shippingport Station Primer,y System Components and ,o Piping. '
AN ACCESS 10N' NUMBER: DE88001859XSP .
AU PERSONALVAUTHORS:'LaGuardia-T.S.; Lipsett-S.M. -
7
.CS CORPORA , P e.r f o r me r : . .T L G . S e r v i c e s . ,I n c . -, , B r i d g e wa t e r . s.CT .
- q yFunder.NC.1. g SOURCE.:
evplendsWrecking Co., OH< W. . %4 . w s <- , <
.+ 9 i n d e rn.De,p'af rn@i t i o f ,E n e r g y y q).iPORT(DAT.E/FC1 NATION:-1987.37p.Washingto,nf D,C., A i - - 6-wS + - ,
R , . ,
,j ,
y PY PUDLICATIONLYEAR: 1987 -'
8
- o N T~.0ESCRI PJtVERNOT E :
- I nat e r n' t'i on a l d etsommif Ti on GgMsympoaium' Pittsburgh,-PA P" ,
- USA, 4 O c t ;1.9 8 7 . - .
Cl COUNTRY'-OF- INTEL L ECTU AL ORI GIN : UNITED-STATES
,. AV AV AI L'A'B'),Lil,TYj NOT E : Portions of t hi s ..d ocume n t, a r,w i l l egi bl e in microfiche , e, p r o d u c t s '.' ' '
LA LANGUAGE:'ENGLISH i PR NTIS PRICE CODES: PC A03/MF A01 l DE DESCRIPTOR$:-Occupational-Exposurei. Cutting-Tools; D e c omm i s s i o n i n g - ; -
De c on t ami nit'i o n - ; Demineralizers-; Evaluation-; Minimization-; Pennsylvania-;
Pipe s-;. Remova)-;. Val ves-; Water-Pumps.. 7t .
DE DESCRIPTORS: *Shippingport-Reactor.
ID IDENTIFIERS: ERDA/220500-; ERDA/210200-; ERDA/055002-; ERDA/510300 .
GC SUBJECT CATEGORIES: Nuclear-science-and-technology-Reactor-engineering-and-nuclear power plants (77H);
Nucl e a r-sc i ence-and- t ec hn ol ogy-Radi oac ti ve wa s t e s-and- r adi oa c ti vi t y (77G);
i Ene r g y-Sel ec ted- s tudi e s-i n-nuc l ea r -t e c hnol ogy (97Q)
CC SUBJECT CATEGORY CODES: 77H, 77G, 97Q, 77, 97 AB ABSTRACT: The primary eystem components within this workscope consist of the stainless steel raector coolant piping, check valves. reactor coolant pumps, steam generators, and reactor purification demineralizers and c ooler s.
The four reactor coolant pumps, the four check val ve s. and several sections of I reactor coolant piping were removed and shipped to a laboratory for l g 3etallogrephic examinetion. This paper describes the work performed, the teavy
( ) ggi ng preparations and procedures, the cutting tools used, component b r a i r. i n g / c a p p i n g techniques to prevent spills, contamination containment, cirborne control techniques. end lessons learned during toe removal of these i primary system componente. Summaries of crew si: e and c otopo s i t i o n . labor hours.
l d u r a t i o r, hours and radiotion +xposure to worLer5 ere prosiced cred diseuseed l brief1<. 6 fier IERA citation 1 :006-Ei ,
l r- ..i 20 L , . - - . .
_. .- - . __ - = .
WESTINGHOUSE CLASS 3 CONTRACT / GRANT NUMBER (S): Contracts: AC0676RLO1057 AC0684RL10421 UD UPDATE DATE: 0809
) 8 of 9 Herked in Search: #3 TI TITLE: Method f or Testing Fluid Control Valves. Patent. s%> .m y 1 AN AC C ES S LON NUMBER: ADD 0132845XSP ;.
e J he %f7;+ .t .
r AU PERSONAL AUTHOR $2 Corrine-G.G.; Hager-C.E.,
CS CORPORATE SOURCE: Performer: D e p a r t rne n t of the Navy. Washjngton, DC.
' REPORT DATE/ PAGINATION: Filed 22 Apr 81, p b't e n t e d 14 Jun 03.'4pffG'.',9r ,
PY PUBLICATION YEAR: 1981 9. ' . - . i rid!;,, 9,, Q .y . .j./
NT-DESCRIPTIVE NOTE: Supe r sedes P AT- APPL-6-25 6 327 A D- D00 0 73 8."* r "M.4 - .
3 C1 COUNTRY OF INTELL ECTUAL -ORIGIN: . UN!TED-STATES . .s..,, g . .. .g 4 AV AV AIL ABILITY NOTE :, Thi s ' Government-owned invention available@vf or-dl5.
i ne licensing and, po s si bl y , for foreign licensing. Copy of patent'available '*
Commi s s'i on e r of Patents, Wachington, DC 20231, $1.50. . efys. c. 4
. ,l Agt AN GU AG Ei .IN GL I SH ,. , , , , g ,,,w , p ,. s . ,3 q ,g .. g, y ggy4 ? C , . . . . g-
" PRf NT.1 S c P.R I C Ef COD E S : NottavaOlebleNTIS - +"
> N. , 47 - egg, , ~ . t 4 1 ;
DE- DESCRIPTORS: Control-system'steFluid-flow;' Indicators .o.Wis p I, y "> 4 DE DESCRIPTORS:
- Patents-;
- Cheek-velves;
- Fuel-systems. , t ,g g, %". ;,-
, ,]
ID'IDENTlF1ERS: PAT-CL-73-168- .
r+ w jf,p'y W /y L ',
SC SUDJECT CATEGORIFS: Manufacturing-technology (41); *1 "
" - eWne dw?.
I n du s t r i al pa n d-me c ha ni c al -engi ne e ri ng (94);
- a Gove r nmen t -i nve n ti on s.- f or.-1,i ce nsi ng-Mec h ani c a l -dev i c o s-and-e quipmen tif.90 A) og
- CCsSUBJECT Cr.TEGORYLCODES:o4 M .94k.90A,,'90 ..< e . % :# U S M' Q 4.. MS
'c A test apparatuPjor7 determining the",operab1MoonditionPof.
h./v'e; ABSTRACT:
ldc'on t r ol val ve s i s fresMcM Aben sor<l aMn'necTe d Etod3*ujS1?i$'N f or u {'
delivery of a test sample of fuel through the fuel. line todenreceiving: system i
'***f Fom*a " f 'u el su pp1 y
- s ou r c eFAU*14e as ' t t*on'e* Na7 ve -1 s% d i sp os'e r ih\'hh4Tbelbline"-"t #
between the sensor and thesfuel receiving system. A plurality.'ofisense liners (ofconnected from the sensor,to a flow , indicator and a p r e s s u r e(',i n,d i c a t o r such) that, simultaneous i n di c a t .i on - o f s t hem vi su a l:;f.l ow .i n di c a t o r..an d ,.the vi.su a l
~
f prossure indicator within respective predetermined limits upon e' delivery of the test semple of the fuel prior to delivery of'the fuel through the fuel line indicates that the fuel icvel control velve i* not properly operable..
AG AGENCY SOURCE CODE: GPN ~~
CA CORPORATE AUTHOR CODE: 001'840000, 110050 -
RN REPORT NUMBER: PATAPPL6256327 PATENT 4387591 UD UPDATE DATE: 0803
$ of 9 Marked in Search: #3 TI TITLE: Identification and Monitoring of Critical Components for Nucleer Life Extension.
AN ACCES$10N NUMBER: DE87010496XSP AU PERSONAL AUTHORS: DeBey-T.M.; Carlson-D.D.; Ducherme-A.R.; Herrison-D.L.
CS CORPORATE SOURCE: Performer: f adie National Lebs., Albuquerque, NM.
Funder: USDOE. Washington, DC.
Funder: Department of Energy. Washington, DC.
REPORT DATE/ PAGINATION: 1987. 13p.
oY PUBLICATION YEAR: 1907 DESCRIPTIVE NOTE: S ymp o s i um on aging and maintenance. Vienne. Austrie, 3 1 1967.
Cl COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH FR NT15 F RIC E CODE 5: PC A02/MF ACl CE DESCRIPTOR - r ailue-t-: Lif,+ine-; Lew-te-stur -Cecia- - i .1 e c + i e <. : 21
WESTINGl!OUSE CLASS 3 (m)) 1DENTlFIERS: ERDA/200200-; ERDA/?t0700 .
c~bC SUBJECT CATEGORIES: Nuclear-science and-technology-Reactor-engineering-and-nuclear power plants (77H)
CC SUBJECT CATEGORY CODES: 77H, 77 AB ADSTRACT: The US Department of Energy has a program to develop predictive performance monitoring and reliability / safety technology to enh.nce the operation 61 lives of nuclear power plants. A n. e f f e,t t i'v e efuip i mo ni t o1 i n g program can provide improved reliability and safety during a p ant's initial license term, thus providing valuable data,to support e u t e n d.i n g' 't h e life of a facility. Probabilistic risk assessment (FRA)-techniques were initially used to ~
help identify' components that were c r i,t i c a l 7t oi sa f eNbpe r a t i on . E qu i pme n t.-wa s identified for which it is important to maintain-initial reliability levels and for which it-would be important to i.mp r o v e, ar e l,i a b i l i t y levels. Of the equipment for which it is important to maintain initial reliability levels, three component types were further evaluated in t hi ss t u d y : swino-check valves, motor-driven centrifugal pumps, and motor-operated valves. Component failure end degradati.on mechanisms were d e t e rmip e d pa q qht h e n/,y e l a t e d ., t o p h y s i c a l w.
parameterspend. potential, measurement .t e'c hf 4 h%e~k?)IouY t yp e a l o f mon i t o r i ng we r e ,
found to have'the potential f o r wi d e s p r e a d,na p$19s a t~i on i n equipment moqitoring.
These are the use of ultrasonic probing, vibtAtion monitoring, infrared a
emission monitoring, and acoustic emi s si on moni to r i ng. Efforts are continuing by the US Department of Energy, in cooperation:with the US nuclear pgwer industry, to develop spec ^*ic monitoring-techniques. (ERA citation 12:036006)
AG AGENCY.SOURCEiCODE: DE -
w ec9g., A p , , . . . . .
CA CORPORATEcAUTHOR~ CODE: 060123000, 951!!100 t*MM N REPORTfNUMBER: . SAN 0071091C, CONF 870756)f M /ji; i (Q,A CONTRACT / GRANT NUMBER (S): Contract:'AC0476DP00789' UD UPDATE DATE: 8724 * -
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WESTINGHOUSE CLASS 3 1 - %2. DOC lve rPla t t er ?.01 NTis 1985(a14-26), 1986-1990(*1-21) t.
No. Records Request ;
1: 1262 CHECK
\ l 2 1281 VALVES +- - .a t- *GsWT 1 3: 41 ad d
. CHECK VALVI$' (.S m hs,f ? .M m .v- .M.x.".M
. .u . Mj . # e $,m. M, .') <T <- - - .-
' I of 10 i
? -
TI TITLE: Flight Worthiness of Fire Re s i s'Ia n ( H y d r a ul,i o : S y s t eme r Ma r k 'e'd in Search: #3 l
- 2. y i Component and Endurance Testing. F i n a l ~r e p t FJa n
- 01"-Dec-8 6 M 9 '!.; a Vol ume 46.e h*
AN-ACCES$10N NUMBER: ADA1000650XSP '
M V " i *
'M 'M" @
AU PERSONAL AUTHOR $: Je f f e r y-J . R. ; - Po how's k i}S yE J L'qP,i e r c e-N. J .;UWile lif t&J.^ A. ;
Yowng-R.E. ' ' .
" '4
>$4 "* o % 'w* ' *
- t* * *%e'd*P W i CS CORPORATE SOURCE: Pe r f o rme r": Mc D on n e'1 P A i r c r a f t"'C d r p . I'S t . i l oVi's',' dM O ." ' * !
Fundart Air Force Wright Aeronautical Ly bs . i i Wr i g h t - P a t t e r s o n y A F B P.,0Hf.7?,1 4 R E PORT . DAT E/P A G1 N AT 10N :;,3 0nDf e i96. o,2.63 PY PUBL1 CAT 10N-YEAR: P1986 M $jQ "%$ pMWh;&Gg7% gt,'g
' q. t l
NT DE SCRI PTIVE NOTE sc See al so: Volume ~1' AD#A1'57N'? %.g6'1 Y.# Y m.W W .. .~ ' . . . '"7 f
Cl COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATESj.~,6....s...m4W % dim ds .
4 '
LA LANGUAGE: ENGL1SH
- 5 PR NTIS PRICE CODES: PC A12/MF A01
.'.--/'t N ".".
N
- M bT W M M' N '
DE DESCRIPTORS: F i r e - r e s i s t a n c e ; ' A i rwo r t h i n e s s - FE ridu r a** n d~eG *en Toot-methods; u r ~$
1 Hoot ' tolerance; F Test.-and-evaluation l i g h t - c o n t r ol p;,sPe y forriersceaEkgin'eerihg s t e m s ;4'r;.,r *;fp retsfMW e p r o ph9 e4 me 1,1 u r e-He c ha h i e s ;IF l ops ;C on t r,ol, ,s u r f a c eigMQgyMQMR$dyp% j,9 ) j$
DESCRIPTORS: + H yd rauli c-equi pmen t';i+@ iter 1e f t equi pment*.M L , q 9 '#** ,
C SUBJECT CATEGORIES: Ae r onau t i c s-and 'a e r odynami c s- Ai r c'ra f t <(51ty T l '- Mc nu f ac t u~rh g- t e c hn o l o g y-To o1Wg Jrifa'c htn'#t$W naWF"*'97 rt Wo'I'tif* ,
I n du s t r i a l - a n d-me c ha n i c a l - en gi ne e r i n g-H y d r a u l i c- a n d pn e uma t i c-egu i.pmep;t.y(941 ) 4 CC SUDJECT CATEGORY CODES: 51 C c '41 J ,7,,9 41),n41 sc. 51., 9 4 y AB. ABSTRACT: T hi s documen t4,i se the,sec ondaof e.ctwodvolume s t whi ch>ma ke*mppthe
.;;"/.; ;=/,Jr 3 flight Worthiness of Fire Resi stant Hydruli .Hp a E Systems' final r ephr'i?.^ Th i s ,
document reports efforts involved in component procurement, analysis, qualification testing .the 750-hour endurance test, a na l y t i c a l mo de l- ~.~
verification, and results of the t e a r d own ., a r e '-i n c l u de d . Thef f o.11ow-onro'on t r a c t
- to pe rf orm^a study of pump pul sa tion attenuation and actuator s.tiffness'are roported in t hi s volume. Components procured for the endur.anceJt esteysetup a included an 8000 psi hydraulic pump, servoactuator, utility actualob, . filters, relief and check val ve s , and various required seal s. The results of the endurance test show that 8000 psi CTFE hydraulic s y s t em s a r e a p r a c t i c a _1. a n d f ocsible approach for next generation aircraft design. Two areas of concern, pump pulsations, and actuator stiffness were studied. Acceptable candidate solutions for both topics are included. Keywords: Fire resistant hydraulic system, Hydraulic system life-cycle costs.
AG AGENCY SOURCE CODE: 00DXA, D0DAF CA CORPORATE AUTHOR CODE: 014554000, 223100 RN REPORT NUMDER: AFWALTR842085VOL2 CN CONTRACT / GRANT NUMBER (S): Contract: F3361580C2074 UD UPDATE DATE: 0718
.k Maried in S e a r c ri : #3 T1 T17tE: velv- Lushing Weer in the Atwood-Morrill Co. Chact Val ve t . CV-3, CV-5. FC'V-:0;.
AN ACCE% ION 60MEEF: DES 6014459x5f 23 Ah r f E ' r.g ;. L - e. ui ers e- t o e .W i
WESTINGHOUSE CLASS i
/ PUBLICATION YEAR: 1977 CI COUNTRY OF INT ELL sCTUAL ORIGIN:- UNITED-ST ATES AV AVAILABILITY NOTE: Portions of. t hi s document are illegible in microfiche products.
LA LANGUAGE: ENGL1SHm . . v 't.nnmi . m, :,
P RDESCRIP.
DE NT I S P RTORS:
ICEC OD Eval a tiEon S.:'u
!qfFPl C ui A d-04 /M Fy f l ow;. Hi/}gDh-l;rP 4.n, r e s;su,, r e f 4Wgh - .
ie r a t u r e<;
Hydraulics-; Inspection-; Loading-; Primary-Coolant-Circuits;.R'epair-1 Wear .
DE DESCRIPTORS: eN-Reactor-;
- Bushings-;
- V a l v e sy . - ,
ID IDENTIFIERS: ERDA/220700f!fERDA/210300'*? ,' -
SC SUBJECT /4ATEGOR11S:hWuc.1 nucl e a r powe r pl ant s177H) m,ea g y. r3so,i W ~ e e* nc e-a ; - nd-t e c hnol og'yMeac to c-r-engineerj n.g-a CC SU B J E CT. C AT Je'po7G.W.,To E GORY 4 CODES; 7deM7.7H',$ ore'c o. r.Lu.
. . . - ,. . . - ~ + -o AD ADSTRACT: This r".d Lt h e "h i s t o r y of the primaril:1oop check volve ope r a t ion , ' i n sp ec t i'onPe valu a ti on-an d r epai r . It consi ders the result s of onelysis and life projections:es well.as;.a program to confirm these for subsequent;p.lanninggq ', en i ' ' ' eg ;apgepair d q i jj,on .g,;'
m y AG AGENCYfSOURCENCOD,E,, ,
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RN REPORT NUMBERi UN!WJL19 Z .'O . j [., . _ .
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CN CONTRACT / GRANT HUMBER(S) gContrect: PAC 0676RLOl857 ; +% -
UD UPDATE DATE: -8703 -m c. " i t ,
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;3 of 10
, S e a r cm h :.y #3 w TITLE: 'C1'o s eju t Nogi gE B *tCheok ;
hool l n g S y a tems s o f .iD'i ooel,3 Ge n e r:a *dpgnp3pD3)dn,i tyrus .%e o a lgVa l ve ;F ai,1 ut e' dis k.fBawj r e p t .+ 9 "J a nb9 5 -10f=M a N 8 6. 4 AN ACCESSION NUMBER: NUREGCR3963XSP M .
- e q r> <
' %mR v P AUt P E RSON A L"' AUTHOR $MWGy*WJ 28NDe'enURVS MH ennic.k~-A M ' M M W "t W - #
CS CORPORATE SOURCE:N e'rformer.:.mPARAMETER,minc.. E l m G r a v e!, ,.WI .< .s P
Funder: N u c l e a rt F, e g u l a t,o ry ,Commi s s i o n ,,;.Wa s hi n g t on , DC.,Offi,ceboh !nspection and .
E n f o r c e m e n t . n ... v ..u REPORT DATE/ PAGINATION': Nov-86.#
eis.m.ygws:s.s -v.r ep;pog.y .
44p."
m't.y ( ,;. y' 'y;. 4 n
' ~
PY PUBLICATION YEAR: 1986' NT DESCRIPTIVE NOTE: Sponsored by Nuclear Regulatory Commission, Washington, DC. Office of Inspection and Enforcement.+
1-C1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH , y4 ,
- s m .3 PR NT IS PRICE CODES: PC A03/MF A01 DE DESCRIPTORS: Evaluation-; Failure-; Electric generators; Nuclear power plants; Nuclear-reactor-safety.
DE DESCRIPTORS:
- Check-valves;
- C o o l i n g'- s y s t e m s .
ID IDENTIFIERS: ele-Bu11etin-83-03;
- Diesel generators.
SC SUBJECT CATEGORIES: Nuclear-science-and-technology-Reactor-engineering-and-nuclear power plants (77H)
CC SUBJECT CATEGORY CODES: 77H, 77 AC ABSTRACT: On March 26, 1984, IE Information Notice 82-00 was issued by the NRC to alert utilities to the check valve failures on diesel generator cooling systems at Dresden Station. On March 10 1983, IE Bulletin 83-03 was issued by the NRC to licensees of operating power facilities to report the failures at "resden and similar failures at Qued Cities, and to require use of effectiv sent for assuring the integrity of check val ve s in raw water cooling syste for diesel generators. In order to provide guidance for preparation of testing and insp*etion progrens. the bulletin was issued for information to holders of conttr utt'en permit 1. Because dietel g e r. e r a t o r t are used to generete emergency pones .
this potential pir o b l etu is ref+ty-related. Evelvetion of utility
-tpc *,,e NRC /IE in;e:tinn <
- t, o r t = t hew s ' t u -
te. th* t> u l l e ' i n con t.+ c' :--
24
WESTINGHOUSE CLASS 3 mainino areas of concern are identified and conclusions are drawn.
d AGENCY SOURCE CODE: NUREG
.CA CORPORATE AUTHOR CODE: 078381000 RN REPORT. NUMBER; PARAMETER!E151 ,,,
wUD. YUP DAT ErDAT.E,:g8704 ; . .
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. -# 4.
. .c. . .- :.- (. 4.of 10 TI Mar id in Search: #3 TITLE: 10 MWe Solar Thermal Central Receiver:P41ot Plant: Solar Facilities Design;. Integration.yM ant Maintenance /Traih'ing Manual (RADL.ltem: 2-37). Section 4.1 Va l v e t N B o o k V.3'r o f ,3. ' m @ Af -J . ' . - . . . , . . , ,
AN L4 ACCES$ 10N cNUMBER:t DE86000718XSP . s >
'! olo'oh'sCNT.Yn % % W.S I X Y M A~>:*CS.'CORPORATEJSOURCEdPerformer.:fM Huntington ,
B
- m i
Fundert' Department-of' Energy, Washington.-LC.
~
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R E,P,0RTvDAT E/P.AGIN ATI ON : Sep 82. 571p.3 , f
, J% "p BQ. .{y 0NyE A p 19 8 2, ,,g,aQn.;d,p m , ,. ;,,& ym., u .g..p.,, , as;; '
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f.
PR NTIS PRICE CODES: PC A24/MF-A011-DEJDESCRIPTORS: Maintenance-; Specifications-; Traps-;' Valves . #
, ,aDE,4 PES C R 3 PfoQ:M Ba qs t o w-S o,he ry.Pjgo 4
- ~ q,. a .v. q.sq, .3,., o 414,I D EN T I F,IIR SMERDA/.1407.02gtg.ppgcq,1;P,1pn t,.; , %.h> % y,.q w ,;e.g.,c w q
<dN.U B J E0Q{EJiog{E S :. ? E n eggy o n,v p aef~ sp--.-se n - n+o-.w n tp r o p u l lsc(108)l. ,1,v e - P o; NnforogryjBki<
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^1en- Q 71)C M . yk.A + e : 7 4 *
- +
4 -
e Al*C OM U B J E C TWC AT EGO RW4 COD EW#001*J83?N #97 I N 0797 mW.tW uH W1 + $ *&h e#W C
.AB 4 ABSTRACT:,.T.hKya l v_e s.jdo.cumen,teddi ncl ude : c hec k and stopocheck._ valves. manual volves~ pre ssur et regul a to r, rupture 4di sc s and t raps. Each valve i s -
i,i n'd i'v^i d;u a l' 'dd'e's c hi b e"d M~ n c.1,3d i.nii,'p*a dt s f]'.i. sis,c a n d., s p o c 10:051176) " ^ ' ' ' " *
AG AGENCY' SOURCE CODE: DE '
CA CORPORATE AUTHOR CODE: 030394000. 4035600 RN: REPORT. NUMBER:pDOESF1,0499T149pSJHP0236.-SAN 049982Bk3 Sect 4, MDCG9705Bk3 Sect 4' ww l CN CONTR ACT/GftANT.' NUMBER (S)L Contsrect :.' AC0379 SF 10499 ,
UD UPDATE DATE: 8604 c ,
5 c'f 10 Marked'in Search: #3 Tl TITLE: Vecuum Still Bottoms Viscometer.
AN ACCESSION NUMBER:'0E86002188XSP AU PERSONAL AUTHORS: Dinsmore-T.V.; Wilson-J.H.
CS CORPORATE-SOURCE: Performer:-Oak Ridge National Lab., TN.
Funder: Department of Energy. Washington, DC.
REPORT DATE/ PAGINATION: 1985. 31p.
PY PUBLICATION YEAR: -1985 NT' DESCRIPTIVE NOTE: American institute of Chemical Engineers annuel winter e eting, Chicago, IL, USA, 10 Nov 1905.
Cw COUNTRY LANGUAGE: ENGLISH OF INTELLECTUAL ORIGIN: UNITED-STATES
-PR NTis PRICE CODES: PC A03/MF A01 DE DESCRIFTORS: Calibration-; Coal-L i que f ec t i on: Coking-; Design-;
On-Line-Measurerdent-Systems; Folymerization-: Specifications-:-
T e rop e r e_ t u r e - C o n _t r. o l .
t r. c. t w i n 1r . .e. 3 , ; .3 . . 4 m , ; . 2 ;.. , . . 25
WESTIllG110USE CLASS 3
,emi s t r y-Chemi c al engi nee ring (7A);
ene r g y-Fuel-conve r si on pr oces se s (97F);
Chemi s t r y-Indu s t ri al-chemi st r y-and-chemi cal proce s s enginee r i ng (99D)
CC SUDJECT CATEGORY CODES: 21D, 7A, 97F, 998, 7, 21, 97, 99 AB AL* TRACT: A viscometer system that is capable of measuring VSB vi scosi t y on-line has been designed, constructed, and tested. The viscomejrrwill not ~ l only p r o v i-d e continuous on-line measurements,for p.roces'scont$1< purpose 1, but l
will also determine viscosity as functions of' temperature and shear rate. The '
latter results may be used to verify de s i gn-b a s e: i n f o rma t i on, f oF di r e c t coal liquefaction demonstration plants. The vis*cosities of Wilsonville samples of VSB and LSRC were de termined a s f unc tion s of s h e a r 'r'a t e - a n d , i n - t.h e case.4f LSRC, temperature. The VSD viscosity was found to be shear-rete sensitive, while .the LSRC viscosity was temperature sensitive. A 24-h test run was unsuccessful, apparently because the check valves in the pump pluggedi however, i all other mechanical, electrical, and electronic equipment operated i satisfactorily. The source of the plugging was thought to be degradation
. . p r odu c t s ., whi c h .s houl d, n o t cause difficulties in.the;piloty pl an t, whe re<J.r e s h - 4, va cuum' bot t oms feed'is always,available. In summe r,y . . t hef resul t s ob t ai ned i n f, o thi s- study ci ndi cate t he t i the 'vi scomet e r s y s t e m i s c r e a d y ~ t o " b'e ' t~r a n s p o r t.e'd t o 'a' plant such.as Wilsonville and operated on-line. 7 figs., S tabs. .(ERA citation:
11:004688) -
4 AG AGENCY SOURCE CODE: DE f
CA CORPORATE AUTHOR CODE: 021310000, 4832000 "
RN REPORT.NU,MBER: CONF 8511235e . ., s ,. , ,.4
.#. ~ ,
t
..CN CONTRACT /GRANToNUMBER(S):J. Contract: 1AC05840R21400s, n ! "
ee 9,- a
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- h; gre at 'nhys i r c h : ~ #3 i TI TITLE: Aging and Service Wear of Check Valves Used in Engineered I Safety-Feature Systems of Nuclear Power Plants.' Volume 1. . Operating Experience end. Failure ldentif.ication... Topical.rept. . . .. +- -
AN ACCES$10N NUMBER: NUREGCR4302V1XSP_
AU PERSONAL AUTHORS: Greenstreet-W.L.i Murphy-G.A.; Gallaher-K.B.;
Ei s se nberg-D.M.
CS CORPORATE SOURCE:-Performer: Oak Ridge National Lab., TN.
Funder: Nuclear Regulatory Commission, Washington, DC. Office of Nuc. ear Regul a to r y .Re sea rc h.
Funder: Department of Energy. Washington, DC.
REPORT DATE/ PAGINATION: Dec 85. 74p.
PY PUBLICATION YEAH: 1985 NT DESCRIPTIVE NOTE: Sponsored by Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Regulatory Research, and Department of Energy, Wa shi n g t o n , DC.
Cl COUNTRY Or INTELLECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH PR NTIS PRICC CODES: PC A04/MF A01 DE DESCRIPTORS: Maintenance-; Detection-; Degradation-; Wear-;
Cost effectiveness; Failure .
DE DESCRIPTORS:
- Nuclear power plants;
- C hec k -v el v e s .
'O IDENTIFIERS: Aging-; Monitoring .
SUBJECT CATEGORIES: Nuc l ea r -sc i e nc e a nd- tec hnol ogy-Rea; t o r engi nee r i ng-e.
operation (181);
Mechanical-industrie1-civi1 and-marine engineering-Fumps-fiiter! pipes-f i t t i ogt - t ut ing and 5 al ve 5 (l3K);
Nucieer-!cience end-technoiogy-Reactcr -ngineering end-r,uc!eer power plan'=
( ? ? H '.
,. - - . - . , . . . ~ _ -- .
,m
. .- .,.. .._f .........v.. . ee w w . t w .
WESTIliGHOUSE CLASS 3 1
i f lent Aging Research program. Thia program addresses the e va l ua t i on and [
identification of practical and cost-effective methods for detecting,'
monitoring, and assessing the severity of time-dependent degradationl(aging.and service wear) of CVs in nuclear plants. These methods are to provide capabilities for establishing degradation trends prior to failurecendaw '
.t t developing guidance for effective maintenance.;The repo r t exami e s;,f ai 1 u r e ..A modes and;4auses r e s u l t i n g f r om a g i n g a n d s e r,vi c e <.We a r-[ L'% T.v*- "- " ' ;
manufacturer-recommended maintenance and surveillance p racti ces. and measur able parameters (including functional indicators) fortuse in a s s e.,s s rn'g o p e r a t i o n a l readiness, establishing degradation t r e n d s', a nd de t ec ti ng i ncipTent.if ailure .
- The results presented are based on i n f o r ma t i o n d e r iYe'd f r om
- o~pe r a t i n cff; -e . $
experience records, nuclear. industry reports, ma n u f a c t u r e r - s u ppl i e d M*;.E t information, and. input. f r om pl an t operators.f
, y y. ._ $F$M;Fi.;
.y AG AGENCY SOURCE-CODE: NUREG, DE
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CA CORPORATE AUTHOR CODE: 021310000 : ~-
- 2 ' M :'".
RN REPORT NUMDER: ORNL6193VOL)
. .. , S j;k ' .y, ,y ,* ,
CN , CON TR A C T/GR A,N T.-N U 1B E R ( S ) L C on t r a c t 24 DEA.C05.840R21400 gn.png4ArJC UD UP D AT E!'DAT E :;8600 C i *,9
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TI TITLE: Loss of Power and Water Hammer Event at- S a n On o f r e , . Un i t' fMM ?:on
^
November'21, 1985. Technical rept.- v. - x- ""*^** '
T AN ACCESSION. NUMBER: _NUREG1190XSP4 M 9 4 r % g m yj. Q .1,Qj M g .
~ wed
- .CS .CORPORATEs SOURCE:< Perf orme r.:e Nuc4eatwRegula toryiCommi est onPWashhkton,5006 f 'PORTv PUBL1 D AT E /P A G IN AT10N : dele n.
CAT 10N YEAR:<1986W(86,$203'py/,4fd@@,,Q;ggg.@g 1 :Mg:q . _ .d Cl COUNT 8Y 0F INTELLECTUAL' ~ ORIGIN:
- + ~ 9 UNITED-STATES m ~.m ~ C w!"eM";-***% 4 " " UA A**P A * * *P'
"*M N
'l A - L A N GU A G E'.rSEN G L'I SH1 '"W MWhM8PN*WWOM*WWNMh*4 PR NTIS PRICE CODES: PC A10/MFsA01 . 74,n ; i..p . & , 9paf' e 5 DE DESCRIPTORS: Leakage-;, Damage-; Cheek-valves; Failure .' _;" ,, : . c ,
D E D E S C R I P.T OR S :-
- N u c l e a r:- r.e a c t o r - a c c i d e n t s q,p - . > . . .s z rnw M.Qeg7 a*
ID IDENTIFIERS: Water-hammer;' San-Onofre-1. reactor; PWR-type reactors; Feedwater-; Heat-sinks.
ID IDENTIFIERS: ' Outages . . -
SC SUBJECT CATEGORIES: Nuclear-science-and-technology-Reactor-epgineering-and-ope r a ti on (101); -
Nuclear-science and-technology-Reactor engineering-and-nuclea'r power. plants ..)
(77H)-
CC SUBJECT CATEGORY CODES: 181, 77H. 18, 77 AB ABSTRACT: On November 21, 1985, Southern California Edison's, San Onofre Nuclear Generating Station, Unit'1, located south of-San Clemente, California, experienced a partial loss of inplant ac electrical power while the plant was operating at-60 percent power. Following a manual reactor trip, the plant lost
- all inplant oc power for 4 minutes and experienced a severe incidence of water hamm r in the feedwater system which caused a leak, demaged plant equipment, and challenged the integrity of the plant's heat sink. The most significant aspect of the event i n vol ved the failure of five saf ety-rela ted c heck velve s in the feedwater system whose failure occurred in less than a year, without detection',- and jeopardized the integrity of safety systems. The event involved number of equipment malfunctions, operator errors, end procedural ficiencies. The report documents the findings and conclusions of an NRC ncident i nve st i ge ti on Team.
AG AGENCY SOURCE CODE: HUREG CA CORPORATE AUTHOR CODE: 044100000 OD UPDATE-BATE: Mii 26 s v
.-- ...: . ~ . -
i . 1 WESTINGIIOUSE CLASS 3
>11ector scaling Tests and the Ef f ect on Thermal Performance from Scale tiuild-Up.
AN ACCESSION NUMBER: DE86004419XSP AU PERSONAL AUTHORS: Bingham-C.E.; Farrington-R.B. l CS CORPORATE SOURCE: Performer: Sol a r. Ene rgy.,Re s ea rc h ,J n o t . , Golden,.C0.
Funder: Department of Energy, Washington, D C ; .; . r. * ': - -
~
s REPORT DATE/ PAGINATION: Jan 86. 29p. 't'# -
PY PUBLICATION YEAR: 1986
.- - ;,9.-c.
#- % f.
C1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATESr - .
LA LANGUAGE: ENGLISH, .. . N .fy/ . w ,%e >s PR NTIS PRICE _ CODES: 7PC A03/MF.A01 '*Wl
. " A '-. - - . . . , ,,,..:.-
DE DESCRIPTORS: Flat-Plate-Collectoral. Reliability-I Scaling-1
. -.y c , . 4WQg 1ar...t. '.
-Water-Heaters., w e n").p e <g g,i, T h e rma l -.E f f i c i e n c y'o. . .DE DESCRIPTORS:>=S www f.
ID IDENTIFIERS: ' ERDA/140907-l' ERDA/141000 . ' '+
SC SUBJECT CATEGORIES: - Energy-conve r si on-non propul si ve-Conve rsi on-tec hnique s .
( 1. O A) ; 4 gggg ';j g g 4; m ,p 1-and-mar no-Letigine Ho c h aindni,c a lNw,u ' '
s t r.i:al- c iI' { big,ggG44,$d iti 4h, A*Mi % @@'
Ener9y-Soler-energy.,(97N)1; ,,. . .% N,i.e. .; , .. .g..a.c.c . %,f ,c . .. l : .. a ,
Ene r g y-Hea ti ng-and-c ool i ng-s y s tems _ (970)W F' # : t'7tW ' 3 -
.CC SUBJECT CATEGORY CODES: 10A, 13A, 97Ni;97J',110,.13,:97M AB ABSTRACT: The objective o f "t hi s wo r_k kwa s wt o" de te rmi ne -how mu c h 's[. ale
~
o c c umu l a t e s, i p,,,7agfJ a t ; p l a t e ,.c o 1J e c t o ro.c a u q eyb,,b,y,ge pp.aj e d fj;11/ n gg a n d e d [ a i n i n g .4 L c b o r a t o r y .tt e s t i n g. 'o f p.s o.1 a r. ' d ome a t i c 34to ts,wat'er/4sys tem rc omp on e n t s ai n t F Yg1983 4 5 owed that.a si E6Etl.1'aie bn i sNe's uuS7bre'akerapo de b e
~
h c 1 v e s',va'i/fv e(rit'g n i f;i c a n t ve mo u ntoit;;of b on one side (such as when used a ss en i solationetval ')'. fra n d 'rt emp e r i n g "v a l v e s . .I n p a a c 51'e $*
eriYdicidrainy (
'* " F Y "19 0 C,4w e -t t e e t e d 'aWf 1 e t p 1 va t e co l l'e c'tb rdoT WtiPett%I'$bdeigYe aFo f O s de l e M occumulation caused by evaporation o f w a t e s.GT e s t,i n g pv e r- a c p e r i o d o f ~o n e y e a r:,
and 9733 cycles caused a 7% decrease i n ; c o l.l e c t o r c volume.because,of scale,
~
which i a e qu.i va l e.n t mt o . u n i f o rm s c a l i n g 4o f. ,045f.mm 9./h,3 rmm .. s c a l i n g , t hi c k n e s s would decreasethe heat removal factor'by'6% of' increase ~the ab 1rber plate temperature and overall heat loss factor U/sub L/ by 5 exp 0 C and 2%.
rospectively. This would result in a 13% reduction in the amount of energy collected. Homeowners in geographical areas wherenthe water has a high potential for scaling should not uso direct solar energy systems that .u s e conventional flat plate collectors.unle,ss>they treat.the water before it enters the system. (ERA citation 11:019540)
AG AGENCY SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 056095000, 9506607 RN REPORT NUMBER: SERITR2532604 CN CONTRACT / GRANT NUMBER (S): Contract: ACO283CH10093 UD UPDATE DATE: 8614 9 of 10 Marked in Search: #3 Tl TITLE: Simulation of LMFBR Pump Transients and Comparizon to LOF That Occurred at EBR-11.
AN ACCESSION NUMBER: DEB 5000089XSP 40 PERSONAL AUTHORS: Koenig-F.F.; Dean-E.M.
3 CORPORATE SOURCE: Performer: Argonne National Lab., IL.
Funder: Department of Energy, Washington, DC.
REPORT DATE/ PAGINATION: 19ES. 7p.
PY FU E-t i C AT 10N YEAR: 1965 NT DESCRIPTIVE NOTE: ANS/ENE feet reector sefety meetinc, knovville, TN, TA.
I1 A r: r 19 M .
,,.-r. . .. - - -
,.7 .... y
WESTINGHOUSE CLASS 3 m
DESCRIPTORS: Computer-Calculations; EBR-2-Reactor: Failures-; Flow-Rate; b)ydraulics-; P u rnp s - ; Reactor-Safety.
DE DESCRIPTORE: eLMFBR-Type-Reactors;
- Loss-of-Flow.
ID IDENTIFIERS: ERDA/220900-; ERDA/210500 .
SC-SUBJECT, CATEGORIES: Nu c l e a r.-s c i e n c e-a n d- t e c hn ol o g y -R e a c t o r - e ry g i n e e r i n g- a n d-
- oporation TlB1);. . . x'2 awe _
Mo c h e n i c a l? i n d u s t r i a l - c i v i l - a n d -ma r i n e - e n g i n e e r i n g? P uino's - ri l' th.. -
pipes fittings-tubing-and-valves (13K) '
El e c t r on i c s- a nd - el e c t r i c a l -en g i n e e r i n g- C omp.u t e r s: (9B); ,
Nucl e a r- sc i ence 4 ated- t e chnol ogy-Re ac to r-eng'i ne e r i ng-a nd- nucl e a r powe r pl an t s
( 7 7 H '; . .
..- ~
.n:n. U *f ,
^3~ ~X -
.- . . .r .
CC! SUBJECT CATEGORY C O D E S : ' 1911,713 K , t9 8 ,' " 77 H , 9, 13, 10, 77
. AB, jABSTR ACT :,i n e . l a r ge ';LMF;BR.gp] a n t de si gn i , a: numbe r . o f pumps in parallel will f eed nthe rcore i +1 t mu et bo rdemons t ra ted *t ha t"t he* pl ant can continue to operate wi th'the 1 oss of one 'of ' the pri[n not to have cheek valve nin the 1 o o p_ f r om ai ;- ri,,11 elf ,t ay; b'pr an d ec onomi c stendpoint./ pump's .' f I t' i s' d eS si mul i r aabl t ie on a have q eAco f.P,'a i,,1 o a s;,,o f,go n e . p ump .;i n w a . f o u r - 1 o o p .a
'_uded9to<d'eANrt$ine"#the Agen,(na d,e gqp1d,o)e),tni.e e n typ rkt'e'c'ti e,t hegoopeyd,e,rp:iorf;i U would ac'compeny'pumpl1oes.ipo'o12:p a e t 1.'o n?i.s Dt o k e'n'.",Thi s' a n a 1 y a i s' :wou l d b e The,two primary cen t ri f ugal,; pumps ai nsEBR-II.. feed tpe core and blanket plenums in two' parallel flow 1pathsWThe~1oss?o.F1one' pump will result in decrease core flow and' reverse flow through. theEdownipump'since no check valves arey present in'the system. F o'r' a'l a r g e( po'd1P'pl an t dt t h* f ou r p r i ma r y pump s , the loss of one
, pump).,wQ 4 ; al so ire sul ts.liurovense $1;owgthr.oughathe bdown ,. pump sif e h ec k v el ve s of-ed.1.o6di ode 39e re .rio tM nol udediNThe4e s0}t.Vnghfsl owit r ansi entahas be en model ed f or R,-;l) @. a'ry d " t.h'e.Q1 a r g el, p,1, o r3 t i S ci S,{,,Pa"9^*"*v"""'0N S P.i p40.9*a*r a mMER A ic i tj tio n2 x p AGENCYqSOURCE CODE':-'DE*y f .
CA' CORPORATE AUTHOR CODE: 001960000,"0449000 5 ' -
NTN" REPORT? NUMBER FCONFD50'41'Od N W W 9'** W *w% # M*** * '"' ' '
CN CONTRACT / GRANT NUMBER (S): L'. con t r a c tf:c W31109 E N G3 8 /
UD UPDATE DATE: 8515 .;, _ _ _: ,
, , , , . .. . . .... . .g.q9 v. ..p , g, ,e.s
< , -4 , u i s .,
10 of 10 Marked in 'aerch: #3 Tl TITLE: Component Reliability and Control System Testing.
AN ACCESS 10N NUMBER: DE05008792XSP 7, ,
AU PERSONAL AUTHORS: Farrington-R.B.
.CS CORPORATE SOURCE: P e r f o rme r,:.. Sol a r sEnergy.Research Inst., Golden, CO.
Funder: Department of Energy, Washington, DC.
REPORT DATE/ PAGINATION: Mar 85.' 9p.
PY PUBLICATION YEAR: 1985 '
NT DESCRIPTIVE NOTE: Solar buildings: realities for today -
trends for tomorrow, Wa s hi n g t on , DC, USA, 18 Mar 1985.
Cl COUNTRY OF INTELLECTUAL ORI GIN : UNITED-STATES LA LANGUAGE: ENGLISH PR NTIS PRICE CODES: PC A02/MF A01 DE DECCRIPTORS: Control-Systems; Pipes-; Reliability-; Testing-;
Thermel-Cycling; Valves-; Vents .
DE DESCRIP'iORS: *Soler-Heating-Systems;
- Solar-Water-Heaters.
ID !DENTIFIERS: ERDA/140901-; ERDA/140907 .
g^ $ SUBJECT CATEGORIES: Mechanical-industrial-civil-end-marine-engineering-Air-(tnergy-Solarenerg>jndi (97N); t i on i ng-he a t i ng-1i gh t i ng and ven t il a t i ng (13A);
[nerqy-Heating-end-ccoling-syatemy (97J)
(C SUBJEC7 C ATE GOM CODE 5: 13A, 97N, 97], 10, 97 Ab ABSTRACT: The Scist Energy Research In!t'tute ha! been invcIved in t e t *. i n c ective e.m m p an arit r e i t e r. i l i t y end centrol 1,ttem*. ii. tett Icept wart
WESTIllGHOUSE CLASS 3 I (N- better understanding of certain failures in the field and present design wi t h realistic expectations for these components. The seven SDHW control systems tested i ncluded t he rmi s t o r s switches, RTDs, IC sensors, and controllers. Serious reliability problems i r.c l u d e d sensor degradation or failure from high temperature . ar d controllers that did not meet specificatjons. As much as 50% of collected energy can be lost 6,ecause of s'e by 250%.
~
sensor depadation, and auxiliary energy r e qu,i r eme n t s ' c an -i ric '
(ERA citation 10:025479)
- AG AGENCY SOURCE CODE: DE -
CA CORPORATE AUTHOR CODE: 056095000 9506667 RN REPORT NUMBER: SERITP2532681 CONF 8503887 -3."- .. o CH CONTRACT / GRANT NUM9ER(S): Contract: ACO203CH10093 m U D,.U P.0 AT U;D AT E: 48618
. . u. . s . . u . .. . , < s
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*D e#[I th 9 $f F p MSAL 65.. ) 4' # W 3 e *% i', 4 e i,'g, , += - __4
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WESTINGHOUSE CIASS 3 MM A-C t)7. DOC 41verPlatter 2.01 NTIS 1985(#14-26). 1986-1990(#1-21)
& a am mg" ,w %.a wm seen ret oi .
l 2: 1766 VALVE
- cv4 g.c b l.' Dot ,9.r Aes 3: CN$ Z-CD.2.'DO C. A 62 CHECH VALVE
- 1262
. . . . T' O.%% i W !
4!
5: 1000 CHECK VALVE For % A a- rdent's o * ~
7" J 1
6: 31 CHECK VALVE Sea,r ch 7* 1262 CHECK ~~ W Ecv. VPolEN '
O WA E X ivA E 'c kP
-8 1281 VALVES CNCV VblV6 A T,9f 7+.NI s .MU M+ ! 1 ge% . W ; upp, 'M gre r4 %,mge,%,,,,f,wm$[
9: 41 CHECH VALVES gth 10: 41 m3 and #9 -
d i 11:
- 31. n3 and #6 ' St \6.Htt, - ~ s +M-o *'s~ w v*nc. +~
12: 1262 CHECK *
- A"*'M# '""
13: 1000 VALVE ? , h E &&h *
,. ,14:
1262 CHECK.,n., y, w ,y _,9 16: 1281'
.., p ,
,d .,, w g g;igist,: ./
16:
V A lb E S T " , f ' ' r , 7"?."M *" '19 E_ %
-21 ' ( CHEC Ky A L'V E ) en,otttCH Ett ?VAIVES3 ft@1W 4 '$,t'e % ^b"* h7 .
-l. m., g.4 O ..;.c,A A.,
a % [ ,'[ . ZilL >
3,g T1 TITLE: SOL A-LOOP' Anal ysi s of a Back Pressure C h e c k ' V_a " Mal rvk'e e ?dM: i'^W n$ h" a ch:'*16 '
AN ACCES$10N NUMBER:,,DE84012437XSP, - p..m;&,u . .wway.;M,Md~ " 6 -e"'*". .
1 AU PERSONAL 1 AUTHORS:.f Perf ortner;;.Travis-J.R.1 PQ@ %9 5 9 A$ i ..
'S CORPORATI SOURCE: . Los Alamos .Nationa1 ., w u ,ri-+ KM' 4
. u n d e r :P D e h a r tid el *,OoWEN'e' r g y e4/a's'h'1 Eg tlnQ$, { 16CNNf#[1. a b .',;.L ,4 REPORT DATE/PAGIGATION:>1984.;8p.. *t ** r mi<m % M e"4 (MM$,d', f ,M. ..
** PNTYm P U B L ! C AT 10N >Y E AR tt19 8 4 '~r*@W'*9""W"WGf!M#MMD"@@W*Y DESCRIPTIVE NOTE: ,;1AEA t e c h n i c a l . c onyni t t e e /wo r k s h o p jo n at h e*:use.sJe ft;c ompu t e r,-
codes f o r n u c l e a r r e a c t o r - s o f e t y. a n al y si s bV a r n a ,1 Bul g a r.i ai r.29 ;,Ma yf.3 9 8 4. -
.n C1 COUNTRY . O F. 1 N7IL L ECTU A Ls ORI. GIN :+ UN.lT E D . STAT.E S a ,wwmqst.*Qw s
WP AV AVAILABILITY NOTE: ' P a p e r "c o^py ofil y[. 'c op y 'd o e s n o t I p e rmi t 'mi c'r b ffc h el production, LA LANGUAGE: ENGLISH . * ~~ '
PR NTIS PRICE CODES: PC A02 y - -
'v >; * %K7 +?
DE DESCRIPTORS: Blowdown-i Computer-Codest Feadwater-i S-Codesi Valves .
DE DESCRIPTORS:
- Loss-of-Coolant;
- Nuclear-Power-Plants.- . Ner h a 10 IDENTIFIERS:-ERDA/220900 .
SC SUBJECT CATEGOR1ES: Nuclear-science-and-technology-Reactor engineering and-operation (181); -
j gy-E1 oc t r oni e s-a nd-el e c t r i c a l-e n gi ne e r i n g-C ompu t'e r s (98);
', c
-Nuclear-science-and-technology-Reactor-engineering-and-nuclear power plants (77H)
CC SUBJECT CATEGORY CODES: 181, 98, 77H, 9, 18, 77 AB ABSTRACT: The SOLA-LOOP computer code for t ran sient , nonequilibrium, two phase flows in networks has been coupled with a simple valve model to -
- analyze a feedwater pipe breakage with a back pressure check valve._Three tests
-from the Superheated Steam Reactor Safety Program Project (PHDR) at Kahl. West' '
Germany, are analy:ed, and the calculated transient back pressure check velve p havior and flui d dynami c s ef f ec t s are found to be in excellent agreement with'-
ge experimentally measured data. (ERA citation 09:030879)
A AGENCY SOURCE CODE: DE l CA CORPORATE-AUTHOR CODE: 072735000, 9512470 L RN REFORT NUMPER: LAUR841620 CONF 84051641 L
CN-CONTRACT /GRA4T NUMBER (S): Contract: W7405ENG36
.UDLUFDATE DATE: 1606 30
, , . _ . , _ . . . u, n_ . _ . _ _ _ 2. _ _ . _ _ _ _ _ _ _ _ _
. WESTINGilOUSE CLASS 3
('-nN 1 TITLE: Check Valve Closure Transients and the RETRAN Code.
ACCES$10N NUMBER: DEBS 703146XSP.
AU PERSONAL AUTHORS: Kobussen-J.A.; Myl ona s-R. ; Zheng-W.X.
CS CORPORATE SOURCE: Perf ormer : Ei dgenoe s si sc he s Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland).2 n e .' m tv.a * ' - 7
- 9. " ~." % . 92 .M REPORT DATE/ PAGINATION: Mar 6 4.. 2.1 p ; Q. . . . . -g PY PUBLICATION YEAR: 1984+ ' E ' a n " * * ' y e.*~ '
f*
Cl COUNTRY OF INTELLECTUAL ORIGIN: -SWITZERLANb ***
AV AVAILABILITY NOTE: U.S. Sales Only. . r- % '
LA LANGUAGE: ENGL1SH d W 4 ::."
- W * * , ^
?
PR NT!S PRICE CODES: PC A02/MF[Adl W . *N '*Lm s.s e ^ w DE DESCRIPTORS: ~
Bl owdown- t . Dampi rig- b,WM VFeedwa te r- 1. Ma t h'ema t i cal -Mo R-Cod e s ; Rup t u r e s- i S t eam Gene r e t,or s t'@iTran si e n t s-l%Wa t e r-Hamme r. 9,fM;.% .
l D E DE SCR I PTORS : e Compu t e r-Code s ; = PWR-Type-Re a c t o r sP* Va l.ve s - . w "' ^ ^ '
* ^ " "
ID IDENTIFIERS: ERDA/210200 .Q + 7 P "' ~ ~* '
ID IDENTIFIERS: ,. . f.! q ';
. 13., c .;3 . jy ,
g andt,-
- F o r e i g n - tcesan SC, SU BJ ECTcCATE GORI E S : .Nu c1, ear ic' e
4$Q d c hn o l o,g
.QQM y P {Mg;d:,t e cgn o '
l
. / epe ria ti o n K(3 9171;W ;',.h*y #VQMd h a n ie-e c'arigi l -iYa n e eu rsi tn rgi -*
a Pump l - c i ve tT i 15 i'1'ta bn. th
$ -tn p a s gl7* G't- A
. f,i t ti ng s-A ubi ng-a nd-val ve s (l'31();Y 1.h::g . . . . ;$t,.M/'. '/ /Jdd.bM b% .
El e c t roni c s-and el ec t r.i cal-enginele'rd ng-comput er s (90)i bim 4 MUNW
Nuc l e a r - s c i e n c e-a n d- t e c hn ol o g y.-fle a c t o'r-e ngfn'e e ri n g-and-nu cl e a r powe r f pl an t s .
(77H)/ a.
- M A.'"tWe FW eW C Cs S U D J E CTgC AT E GOR Y.rC,0D Wh 4 w*cb E S :d,B 9.BM.(w r*;tMWa r m
% pH,d'9.nt,3(,h10 07 M e A % p, . 4 .y
. ..- AB n.iAd STR ACT : .oThe rmai nM e edwa ts wededp i f Ds/PWR ~ - C f ' ej,Q$ '
( aha1eav,1) *# yc o n t a i n s Ra j.c h'er doe rkt cr' ave1 ehou 1 d cl'o ae
- a s +eoon%s@ .
)
a a '1%w"e9mi'nvls[ g$e@p@plyi **1'oNs*'p o .
wa t e r f r om yt h e- s t e am g en e r a t or ?onQ.%n' t he J o t he r c ha n d ?a *f m e t'[c}fd,si ng:7v a l v e " ?.
ch n *p r ' 'o'd U~d e "s'e % W p'r e s*s u r*eWMWi'eTtW(6t #
eWEIEE)gh),giy ,*, u,g, pig , N ~
'l o a d i n g to the, steam generato g Tohdi[minish.the a e v c e r i,t yz o f . t'h e[;p r e s s u'rle.
transients it has been suggesJed2that;,the damped' check v a l v e' mi g h O b e.'.a n
. o t t e r na t i ve. whe n e qu.i pi ng atpennai.nnf e edwa t e r-li ne . of va e PWR ep l an t!..nA ssubrau t i ne doscribing'the conventional ann'Dt*f[e',"a hd t h e ~ d amp e d p'1 u g ' t y p e c h'e c k~ Valve has been developed and implemented into the RETRAN code. The c h e c k .v a _1 v e model was tooted on a postulated feedline rupture of the Westinghouse designed KKB
? ( K e r,n k r a f t we r k Bernau) plant.qThelRET_RAN calculations performed _with the conv,entional, swing type check' valve, os actually built in the KKB7 plant, show a cvory good agreement with earlier..results'obtained with theslTCH-MLitT! FLEX code.
Shoul d, on the other hand, the KKB check val v e be replaced by a properly designed demped plug type check val ve . a RETRAN anal ysi s shows that_the pressure peaks can be suppressed almost completely. (Atomindex citation 16:064788)
AG AGENCY SOURCE CODE: INIS CA CORPORATE AUTHOR CODE: 010503000, 231A000 RN REPORT NUMBER: ElR$13 UD UPDATE DATE: 8607 3 of 5 Marked in Search: #16 Tl TITLE: Appendix S-FS-1: Experiment Operating Specification for the Semiscale Mod-2C Feedweter and Steam Line Break Experiment Series.
J ACCESSION NUMBER: DE85008017X5P AU F E R5 0N A L AUTHORS: Doucher-T.J.; Owea-W.A.
CS COPPORATE 50tiRCE: Performer: EG end G Ideho, Inc.. Idebo F e l l t. .
runder. Department of Energy, Wethington, M R E F OM DATEffAG] NATION: Jen 65. 101p pv 5"( t : r !. T i n N VEAF: 19qr 31 7
WESTINGHOUSE CLASS 3
/&
( kLANGUAGE: ENGLiSH ,
b/R NTIS PRICE CODES: PC A06/MF A01 i DE.DESCRIPTORS: Failures-; Feedwater-i Heat-Transfer; Hydraulics-; ,
Roactor-Safety; Re ac t o r -S a f e t y-Ex pe r irnen t s ; T e s t - f a c i l i, t i e s .
DE D E S C R I P T0RSharic e s-o f -Cool a n t ;nePWR-Type-Reactors; *' team-Lines.
- I D I DENTI F.l ERS:nER.DA/2SD900-;';ERDA/210200 . .-
SC SUBJECTwCATEGOR,lES:L Nuc l ea r-sc i e nc e-a nd-tec hnol ogy' R'esit dn ,k'i n e e r i n'g - a n d ope r a t i on '(101)'l ~
Nuclear-science-and-technology-Reactor-engineering-and-nucle'er+ '~
'ower-plants (77H); . W? %4.& @.I;- .
Energy-Selectedjstu, dies-in nuclear-technology ( 9 7Q )V."..: . . , . . . . _ , , . .
CC .SU B J ECTmC A'{E GO,RY/ CODE S i l101. 77H , 97Q, 10,- 77.,L97 -
(ofLthe AExpe riment Operating AB.
Spe ccA i f.iDSTRACTyT.Msgooume c a t ion d EOSMf drnt hd%enct ond vi s.e Appendi x ,S-F,S e x pe r'imerit > .j,fnWhie Fe edwa t e r and S t eam Li n .
Break -(FS)AseIru e Wit A contains' detailed information*on~ experiment operation and to meet the series-objectives ~
stated in the E Mo f a c i l i eyp t y .c on'fsciongur's ti on. ne gt.e c es.P,rso gsa r am .rt oy[o&Jeedwa em r[s t g m;
%,msin;j,9,S N Pe,r ngnt g,1 W n v e s t i,g a t e ~. ? r main .feeMi S,,e.a n teamtlineibreak.dtransients @ hearestrseries:consikt;s of o.x p e r i me n't a 'r'eli'$s eft.i n g , o fr'o 6 g e, o ff f e e dwa t e r1.l i rteha n d is t e a m l i n e bresk t ransi en t s taccompan.i ed by compoundi ng .f actor s.;90a tnTf romsthe se e xpe rimen t s will be e x ami ne d t o. ~identi f y;irnpor t ant ,p henomena , respective event severities, f a n c8 rocovery-procedurest with the< objective of;'providing~ data for benchmarking code c a l c ul a t i oppy,gT,ep offsetesheer ", Sg1 w(1,)fni,kmain,:s t e amM ne t down s t re a sam) gene 3
or mu l a t e 3 m ytg.a.n ste n t fi,ni,t i, e t,e d b y ; e . d o u bl e - e n d e d t
otrictor$ 9ee f
~%nhofdhe 'omm66 i o a t l'o nfr,e Tug %p'gr}o~maf a i 1 u r e (lc f f t h e ' c h e c k l v ed ri.I de va . 4e edil$a'inM iiS11EMi U15beOeen ted4pel'Iowing4 theTintact^"
l oop a t e am ; gen % rit5r,Wt o b b~1 oWIows un t i l ma'i ni'st'earys ol a ti on val v'e.- (HS I V)i * .
~+'W AG AGENCY S,00RCEbCODE6 DE; f. i 3.7 _ , x.4 f .M ,
<CA cCORPORATE l o s u9AUTHg r e N (rE R A*c'd it4ttobl 0 :,. 0f0 y Erl? )MW%nM s _.,.
~
RN REPORTJNUMBIfi 4EGGSEMI6703 ,0R[ CODE:g 0465,00000, z.%.c m .m. 950778,lg-w m m e,w Q ;,% ,
, .+, -
CN CONTRACT / GRANT?NUNDER(S)3":jcontract: A C077 61,0015 70 UD UPDATE DATE: 0514
+ b v. s cy- , g, ; 4 of~5 Marked in Search: #16 11 TITLE: Development.of Seal s f or a GeothermalyDownhole Intensifier. Progress Report.
AN ACCESSION NUMBER: DE05010124XSP AU PERSONAL AUTHORS: Captain-K.H.i Harvey-A.C.; Caskey-0.C.
CS CORPORATE SOURCE: Performei: Foster-Miller Associates, Inc., Wa l t h a m', MA.
funder: Sandia National Labs., Albuquerque, NM.
Funder: Department of Energy. Washington, DC.
-REPORT DATE/ PAGINATION: 1985. 7p. :
PY PUBLICATION YEAR: 1985 1 NT DESCRIPTIVE NOTE: International sympo sium on geothermal energy, Kailua Kona,
- Hl. USA, 26 Aug 1985.
- Cl COUNTRY OF INTELL ECTUAL ORIGIN
- UNITED-STATES l_ AV AVAILABILITY NOTE: Portions of t hi s document are ill egi bl e in microfiche l
I q ooucts.
) tANGUAGE: ENGL1SH
( R NT15 PRICE-CODES: PC A02/MF AO!
DE DESCFIPTORS: Ceramice-; Design-; Drilling-Fluide; Performance-Terting.
DE dei (R1PTOR5:
- Je t -Dr i ll s ; 45eale .
p 3D I D E N T l F 1 E R I. : ERDA/1509C,1 .
y s u E ) E c ' : t. T E r,0 R I E 5 E n-e p- c on v e r si on-n on p r opu l s i v. -< % v e r t i o n- t e c hni < ie+
) . - _. _ . _ _ _ _ _ . _ _ _ . _ _ -- ._ _. . - . - - -
. WESTIl!Gl!OUSE CIAS3 3 1
1 f sterials-sciences-Adhesives and-sealante (71D);
v nonufacturing-technology-Joining (41F)
CC SUDJECT CATEGORY CODES: 10A, 11A, 97F, 710, 41F, 10, 11, 41, 71, 97 AB ABSTRACT: A system using high velocity fluid jets in conjunction with e
. ' rotary diamond bit i ts cur entl y considered as the best candidate for reducing the cost of drilling geothermal wells. Technical, safety a n d, c, ofte
- c o n s i d e r a t'i o n s indicate that the required j e t, s u p p'.l y p r e s s u r e -jt Fi1 best bi- ,
ostablished by a downhols pressure intensifier. Key intensifier components are the c heck valve and plunger seals, which mu_st prevent leakage of'the
.>high pressure, high-temperature abrasive f 'l u i d (dril, ling mud). To achieve the
+roquired performance, novel-ceramic seals are c u r r eM l y bei n g devel ope d..-The
_ check valve seal includes a tapered polymeric plug and ceramic stop acting
, (ogainstia;. ceramic seat. The-ceramic-plunger seal is a variant of the
.4': stepped-joint piston ring and is designed to minimize contact pressure and
^ obrasive wear. Initial' testing of these seala in the laboratory shows
,oncouraging results; design ref,inement end further testing is in progress. 2 WJ,6f a . A.6 f2s i.g a . , ~3 ',t 3 a b s; ,.( E,R ta4.i . c., . , .,, . ...
' MGj,AEEN CYSOURC E l' COD E : 5 DE&Tff:r *M>gn;y10 M ,
; O 2 54 9 6) "' . . .' W.k,L ."/ ,
VACA9CORPORRTE AUTHOR CODE:301k995000,'9501280 - "M -
4,
.RN , R E PORT.. NUND E R : S AN D0500 49 CI.: CONF 85000128 (DCN CONTRACT / GRANT NUMBER (S): Contract:'AC0476DP00789 OD UPDATE DATE: 0518 f a - :m. ,e . < , . . y. .. . e f 4/ y .4,. a. np 5.r . %..engjywp e yvu-a , .y
. .* 5 of 5
# a. u p g.g + , . s.w w p; sig O m 4.c ,
. R ,,, Markediin Seerch: #16 s eTk-ITLPEr tQhe e s,srmal u r ,lp e" yCdrhauj ec k W a l v e e[c do sf/df ?a,7 e e dhWe't ; ~e ~r P,i p e B r e h k a g e' wi
- bAN' .hh ACCESSION' NUMBER:'DE85007703XSP
- T r *A ~
~ ~ ~ *t t -
**?AU*tPER' BON A t'* AUT HORS't*"TrWi WWrf?TIirYe?- H i DY" ~'N~"#"'"'*'"Y'& "O '
..CS. CORPORATE SOURCE: Perf'rmer:-Los,Alemos, o e National Lab., NM.
;;Funder: Department o f . Ene r g y , : Wa s h.i ng t on .f DC .
S.REPORTrDATE/ PAGINATION: 4 9 0 5%22 p .w.% . , . wy - . -
PY PUBLICATION YEAR: ~1985 NT DESCRIPTIVE NOTE: International sym'posium on fundamental aspects of gas-liquid flows, Miami..FL, USA, 17 Nov 1985.
-lcCl; COUNTRY f 0F INTELLECTUAL ORIGIN: UNITED-STATES _.
LA LANGUAGE: ENGLISH PR NTIS PRICE CODES: PC A02/MFaA01 DE DESCRIPTORS: Computer-Calculations; Damping-; Fluid-Flow; Hydr auli c s-;
Hydrodynamics-; Loss-of-Coolent; Mathematical-Models; Reactor-Accidents; Roactor-Cooling-Systems; Reactor-Safety; Ruptures-; Val ve s-; Water-Hammer.
DE DESCRIPTORS: *PWR-Type-Reactors;
- Blowdown .
1D IDENTlflERS: ERDA/220900-; ERDA/210200 .
SC SUBJECT CATEGORIES: Nu c l e a r -s c i e nc e-a n d- t e c hnol og y-Rea c t o r -et.gi ne e r i ng-a nd-operation (181); -
Nuclear science-and-technology-Reactor-engineering-and-nucleer power plants (77H)
CC SUDJECT CATEGORY CODES: 181, 77H, 18, 77 AB ABSTRACT: The SOLA-LOOP computer code for transient, nonequilibrium, i two phase flows in networks has been coupled with a dynamic check velve model. I Trensient back pressure check valve behevior and fluid dynamic effects in t' -
rm of the to celled water-hammer ere n ume r i c all y simulated for a f eed wat pipe breakage accident. Three tests from the Superheated Steam Reactor Sefety F r o g r a rn Froject (FHDR) cerried out near Frenkfurt. Wett Germany are enels: ed, end t he calculated trentient back pressure check s e l v e- behe<1cr a: n d fluia dynemics effect. ore icund to be in e cellent egtetment w1 th the expertru- s1 le f'ma .
.wetur-d det s. '
r-f= , .: <er, crp4 - , ,,,, . tr :nse_rc ,
33-
WESTINGHOUSE CLASS 3 rx l /t CONTRACT / GRANT NUMBER (S): Contract: W740SENG36 s
D~JD UPDATE DATE: 8520 M
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O O
WESTINGHOUSE CLASS 3 d 3-CD2. DOC, 1
i i ! ive rPlat ter 2.01 NTIS 198S(#1A-26). 1986-1990(#1-211 Qf .
No. Records Request .
1: 134 SWI N G 2: 1281 VALVES m & w C N Ma ~GM~Ne 3 3: 1 SW1NG V ALV E$ ( h. a.*, c.LukeA hm6 ME*M.t 13tt 8't 'M 2
, .~. , .sf d . ,- .
fw .- 1- u T -
i (1 of 1 M.p r IIe'd i n' S e e r c h : #3 TITLE: Identificatien and Monitoring oN Critih 11 Components.foriNuclear
~
i ~
T1 Life Extension. -
' t '" M'MMhd*
- VM$ v <!(
AN ACCESSION NUMBER: DE07010496XSP # : MVfWMM' M? * *M W.T AU PERSONAL AUTHORS: DeBey-T.M.; C a r l s o n - D . D 2q hD'u'C h a'rmeh A". R'.1 ;H a r%i s o'nfD . L .' ~
CS CORPORATE SOURCE: P e r f o rme r : S a n d i a - N a t i o n a l vL a b s .*,"Al b u q u e rqtfe *,* NM'." -*
Funder: USDOE, Washington, DC. *
' N "* * * " " " " ~ " " 7 Funder:- Department of Energy, Washington R E POR T .D A_T E/ P. A G I N /.T.! ONc : 1p 87p13 p ,p..M..[d, .6
_ ;.~. s chDMCgui'QM
. . o, , iw;p+*
Wyi, ' yy % g~ M/d""
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-PY PUDL'ICATIONME NT: DESCRIPTIVE NOTE: AR: *1987 7.y{Jon" a ganng
'Symposlum tnain enanc . .enna os .. / '3 ~ ~J 1987. . - u.; .m. 4. . . J
, .... . r.
CI COUNTRY OF I NTE L L ECTU A L ORI GIN :' ' UN IT ED-STATESTF.b3 ' h(.M'TW@$d
.hv.-r.9 M UH M-4rl.f -D.
J LA LANGUAGE: ENGLISH
~.<"',M *QW 7 N.' " T PR HTIS' PRICE CODES:
FailPC u rA02/MF*A01 e e ,;..Li *"7 f e. Pre time s supe $4; Stow 7{"N'f)o*olantfitd
- 8. ec
.DE DESCRIP, TORS: s P. %A e Mor9i t o ringp;. Pi pe s-; P r ima rlyhCool a n t Cimcu ht?s' yp W/4 Q s k - A a aa a sme n t,; , S e r vi e7 e - Li f.eyU S ,D,0 Ej](V,.a.%$;DPump' if; 95$ Re s e t'o re Q i DESCRIPTORS:
MM'I . ,,,
!a..
. 'P ID IDENTIFIERS: WERD Nue A l/ e2 a2 r0-P 2 owe 00- ; r-"EPR1 D a A/ n t 210700-e P* ft e Mria c tur** ompti n ev@
mM*Edb.WW$ 9N sty4d%..N.W P
' 0 S C tS U B J E CT*C'AT E GORl'E SV'N u c'1Ya'rW c i'e ri tie'O "n'W4EH.'M!d.%Y:N Ea Y T. M,., i T $rEs g a
.. % nN +
nuclear power plants (77H) o., ;s 5, W s ; .w. .g .r p
,, c;g:.
3M qd;.6 @a.* %l.;/ *c m . . hyt$gg CC SUBJECT CATEGORY CODES: 77H . 7.7 d AB w. A BSTRACT :,.T he = US. <De pa rtmen t ro f f En e r g y9h a s ve p ro g r.a m ht oyf e v el o p,r.,;P rpjdj e t i v e t performance monitoring and reliability / safety t,echnology'to_ enhance the operational lives of nuclear power plants. An eff9ttive equipment moni t ori n g program can provi improved reliability and safe'.y during a plant's initial liconse term, t h t, providing valuable data t o ; s u'hp o r t extending;the life of a^
facility. Probabilistic risk a s se s s.ne n t (PRA) t ec hni que s we r e , i ni t,i all y u se d to help i den t i f y c omponer,t s that were c r i t i c al ..t o safe operation... Equipment was -.
identified for which it is important to maintain initiel reliability levels and for which it would be important to improve re W bility l evel s. Of the equipment for which it is important to maintain initial rs l i abili t y. l e vel s .3t hre e:
component types were further evaluated in this study: swina-check'velves, motor-driven centrifugal pumps, and motor-cperated valves. Component failure and degradation mechanisms were determined and then related to physical parameters and potential measurement techniques. Four types of monitoring were found tc aave the potential for widespread application in equipment monitoring.
These are the use of ultrasonic probing, vibration monitoring, infrared emission monitoring, and ecoustic emi ssi on moni toring. Efforts are continuing by the US Department of Energy, in cooperation with the US nuclear power industry, to develop specific monitoring techniquas. (ERA citation 12:036806)
M AGENCY SOURCE CODE: DE
( A CORPORATE AUTHOR CODE: 068123000, 9511100 x/
RN REPORT NUMBER: SAND 871091C, CONF 6707561 CN CONTRACT / GRANT NUMBER (S). Contreet. AC0476DP00709 UC UFDATE DATE: 3704 35
~
WESTINGHOUSE CIASS 3 '
, lverPlatter 2.0) NTis 1985(114-26), 1986-1990(*1-21) v No. Records Request 1: 1262 CHECK ,
2: 1766- VALVEe y:. ~ a -
3: 62 CH E C K : V A L'V Egn:1. . .' Zn, '
4:
5:
1262-1000 CHECK VALVE
-4
+ v* mw'* ;M Mc W "_ h:j f 1 6: 31 CHECK VALVE r- ,
7: 1262 s CHECK;ri % :k;V.:,:g ...n W *,y .m .
8: '
1281 . V A L V E SP:%k'W W W W'N 6, 1/ - .
q .. _...r,.
9: 41- . CHECK 2VALVNSU.A / Y' @ ~ .: . O 10 :c, a> ,, '41 g 3pand)*9,3 M g Q g g g h $ d @ y Ng g 11 :- . z 31,~ #3 a nd 4644-+e ww/wW%h. + .w v. ae 12* 1262 CHECK- " ' ~ " "M'NM*' W W ' - '
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,ty . ,o p p ;.c 9 , p . % e g ;.0d y F.* MarkedM n* earch:-#22 JTT.1 1TL'EiinM' e t"a~1rl'udWVMi%yAMst'I'gd,FdiNMMlida'~i a tTeirTWn'ef GeMim6kt%r"a*c 1/i n g? N Lokeview TGS. .'+,.3 . .;.c, , ,6; o . n . . g;
.^.g ] g,y' g g. % m ., , , - -y, q AN ACCESSION-NUMBER:,MIC9003_531XSE, _ , <"e- 4 . .. .._E - ~.hm -
..AU PERSONAL AUTHORS.;pW.estwoodqH.h w; q :rp p,gesc.wwpu e ,% w .t,s u . p .
CS CORh0 RATE SOURCE: Performer: OntariofHydro,'TorontoP Research'Div.
REPORT DATE/ PAGINATION: u1989. 48p.
PY PUBLICATION YEAR: 1989 ~. .
C1 COUNTRY OF INTELLECTUAL ORIGIN: CANADA- ^ '
.; ~. "
- L__
LA LANGUAGE: EN GL I SH PR NTIS PRICE CODES: PC E07/MF'E01 n 9 ..i ,.
DE DESCRIPTORS: Steam-boilers.
DE DESCRIPTORS: *Steem power plants.
ID IDENTIFIERS: ' Inspection;
- Metallurgy;.*Weldmentsi
- Cracks,. .
SC SUBJECT CATEGORIES: Energy-El ec t ri c power produc tion (971);
Manufacturing-technology-Joining (41F)
CC SUBJECT CA1EGORY CODES: 971, 41F, 41, 97 AB ABSTRACT: In early March, 1989, a steam leakage in the vi cini ty of the west main steam stop valve caused a shutdown of Unit 3 at Lakeview Thermal Generating Station, i nsul a ti on removal and inspection revealed a large through wall ci rcumf erenti al crack adjacent to the wel d between a T piece and the main steam stop valve. Similar, but less advanced damage was then disclosed in the east main steam line and also in both east and west lines of the
'dentical Unit 4 at the seme locetion. All these sections were removed and t 3r metallurgical inve s t i gat i on, as were other suspect sec ti ons from these units and units 6 and 7. This report concerns the conventionel destructive ;
metallurgicel investigation which was carried out on the removed sections f r e rr.
{
failed, damag-d and su: Pct locotions to c ha rec t er i: e the damage mechar. ism in 1 deteil and tc investigete the reescn: for the damege.
4 (, AGENCs CO@iE f ME: r r g N 36
WESTINGHOUSE CLASS 3
[ \
) 2 of 2 w Marked in Search: #22 T1 TITLE: Test Results of N.C.B. (National Cool Board) Solenoid Ston Valve s.
AN ACCESSION NUMBER: PB06204328XSP ,_
"irAU,zP_ER$0N AL. AUTHORS :. Smi t h e on .J . H .- r -
ct.(CSdCORPOR ATE
- SOURC E : Pe rf orme r :- Bri ti sh. Hydromechani c s Research M ssociation.
*C r a n f,i e l d..M E n gl a n d ) .- .. . . ~
.- n' -
' REPORT DATE/P AGIN AT ION: c1982. 47p.
- -} 'I' PY PUBLICATION YEAR: 1902 M'C OCOUNTRY10F' INTELLECTUAL ORIGIN:: UNITED-TINGDOM 33t AFL AN GU.AG E.: ENGL1SH , , A _'~ . - t 'Q. ' ' V.'- .
tPRY:NT;1SrPRICE ? CODES:- PC ;E04/MF/JE04T , ,, t y , '. '
"Il@.QEXC,R iff03S :;jl e a k a g e - 1,g.L i f;egt e,s t s ;jop,o r a t i o n s - ; Orientation-;
- Wantamina ti on-;eCo r r osi on-re si stan c e:; p Da t a -.- .
*DE*DESCRI PT0RSC 4 Sol enoi d-valve s ;"** Tests .
61 D il D ENT I F 1 ERS :
- F o r e i gn- t e c hn ej'og y .; _.;,a W S. AE,CTygQT EG031 E,S.:6 $ohpn -4gd,u,gi,Q .c i vi 1 -a n d -ma r i n e prggj,n e e d n g-78,m
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t .- Lflya s,b o r,a ttest-f op Wgyd a ci1.i ;;:'y afv e st e1s( t-equi t i es-and- 13 K praen ) I M..t 2(148); p
,, M 3%u[.~e'c'turing-techno1ogy,f.(41N,. d h.d i N..... .
71 n d6s t"r'i cl - a n d-me c h a n i c a l -e n g,i n e e r:i n gf(9 4 ) l' I ndus t ri al-and-mec hani c al-engi nee ri ng-Nonde s t ru c t i ve-te sti ng (94J) #
^1C C 'S'U B J E CT ' C AT E GOR Y C O D E S - *13 K',V'14 B P- 4'179 4 4 '9 4 J , 13, 14, 94 4 .%),@BSTRACT:
A 3 T he,r e po r t sco.n,pa',ips' ' j egre suy syot,' ...a n d ..c ommen t s ,on e t e s t s .,
-. Woffgiedkout+onstwohsolenoid pur$r -
[ kil lMI.heyAej,thiw e dja[jjMU), .m)do'rjf.a,n Nez;i.g( a);pT c e r,,ol wi,tl.h; e xa t. i,o t h e,,N valr!a,1ve ,L (b)]se u sc hj
' (.f0%;)y' B HR A pa g r ete s -,e tr progremp(nnep% )MeOu r:i n g-t herp r og r am -some re
. JthRtheitesteprocedure e nd <.e ddi!ttone'1?pe r.':rma nc e c he c k s we r e egreed between
'4%)i RT$Wd NC B Wrfd* Fd d ifd %%DM$96YYin M'D ifrTiic[#t h'6"L'e?t4F61Tr'a m% i7n'e #d e ve l o p m e n t Mw h t; ki .wa s sn e e d e d o n t h e' v a l.v.el's[.yjIh e',p e s u l,t e 4 i n a n umb e r o f, i n t e r n.a 1 .a ,
~ modi f;i c a t i on s ' b ei n g ,ma d e .[j,l t nnu s t 4 b e 'emp h,a s i, z e d -t h a t , Jd u e to t hi s , ^ t he; resul t s 4 9,0 f.,4 e s t s c a r,r i e d a o u top r.(oJ4toyppe,,, yAf i gu aym o d i f..i c a t i o rp .1mieht notube occuratea fo,r'the cur' rent build s t a n de r d, ~o f d h e valve.'0, tails'of valve modifications are
' ' docur$en t ed in'the report.
~
AG AGENCY SOURCE CODE: TFBHR. a
, .CAJCORPORATE AUTHOR CODE: 004480.000: ;3g.g34, . _
RN4 REPORT NUMBER: RRI914 ~- : n t- ' .-
wuDyVPDATE DATE: 8617 j .u d y y .A g Q ; d .
c.t.. m x ..k.r -
m 37
WESTINGHOUSE. CLASS 3 0 V$ 5-CD2.Taoc (4.),M nik scwe, beense 4here are. h6 record s')
,' , a l ve r Pl a t t e r 2.01 NTIS 1985(#14-26), 1986-1990(#1-21) F10-Commends F 1
(
No. Records Request
#1: 1231 LIFT .
#2: 1281 VALVES _
- L'1FT> VALVES'C b e cita.m.& M.RT V KLV E 4' ~~ :'), ~k..
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38
. WESTINGHOUSE CLASS 3 silverPlatter 2,01 NTls 1990(#22-24), 1991(*1-23)
%. Records Request
; 279 CHECK y" 2 : 375 VALVE
- 3: 13 . CHECK VALVED
.~ og 93 Q
a. ' da ' . .
,, 7 , - M a3 d in S e a.r c h ; pI TITLE:~' APFIM char'acterization of the spinodal,decompositta T1 in duplex stainless steel s. .. _ ..
N NUMBER: DE91014256XSP .- -
,AN ACCESS 10.T
'AU PERSONAL AUTHORS: , Brown-J.E.; Smith-G.D.W.; P ump hy ey - P.. H . ; Miller-M.K. ~
~"
' CS' CORFORATEi: SOURCE: Performer: Oak Ridge National Ldb., TN.
.Funder: De p'a r tme n.t e o f. En e r g y , Washington, DC.
MR E P ORT 3 D AT.E7P A G I N AT.I ON f;.199Rh 10 p .
~
' P Y .P U B L I C AT I ON,jY E AR: 1991'T!
NT DESCRIPTIVE NOTE: International symposium on environmental degradation on np t e r.ia l s .j ninu c1,e a r. powe r systems -
water reactors (5th), Monterey, CA (USA),
r25.-297]A6ght19 S 1pASp o,n e o r e d ;byW0 e p a r t me n tt o f(En eitj y P.Wa s.h i n g t o n; , ;D C '.
CI' COUNTRY 40 v!NT.E.LL:ECTU ALCORI GINiiUNITE D-KINGDOMW
~ - . ;t s.. .'
- L YL'ANGU A'GF: JEN'GNiSH , ? !4 I - - >
4 -
PR ?NTIS PRICE $0 DES:M,PC; A03/MF A01. -", ";gt DE DESCRIPT,0RS:QAgi n g-;;r B r.i t t l e n e s s-; fFe rii t e s- ; Hardness-; lon-Microscopy; Mi c r o s t r u c t uf.e,,;;S hi ppigg po r t -Re a c t o r..t, Mee t i n g s . ~ /
DE DESCRIPTORS:..* Stain 1.eas-Steels.m - -
- I D?!.D ENTIFs! ERSTAEUB 360103 f EDB/360102'-;* h .4 a v
' K D k'I'D'EWTd 'Fh YR$ ?.%h ejsn*F t Wc 5ido 1 o ciy'.2W, pE D B / 210200T .,N.TOI'(ll "$- 1 x QSUB,3EC, N a t e r T al s,Q- s'cTe n c e s-Ma t e ry a l s -d e g r a d a t i.on - a n d- fo u l i n g ; ( 71 N N t**dU k97<~b'* ~t,og gppingergog,yndnnuclear power p)ents M}*f *.WJd?
CC SUBJECT 0 CATEGORY -CODES : 71 J , 71L , 77H,71,t77 ' '
AB.-ABSTRACT + An-atom probe f i el d i on- mi c rosc ope characterization of two CF3 s hs't eel-s~ wi t hP4 5 0a'ndY2 Si ul ume' p e rc'e'n't" f e r ri t e*a ge d 6a t4 0 0 ( d e g r'e e s ) C f o r ~ up to 10,000.h and service materials from the Shi ppi ngpo r t main and check velves aged for approximately 13 years at (app r ox ima t el y) 290(deg r ee s)C has been performed.
In eli these material,s, the f e rri te phese was found to have decomposed into an ultrefine sc al e -two phase microstructure ccrisisting of an iron-rich (alpha) phase and a chromium-enriched (alpha)(prime) phase. The sc al e of the decomposition in-the Shi ppi ngp o r t ' me te ri al s was much finer that than found in the CF3 material subjected to accelerated aging at 400(degrees)C. 20 refs., 9 figs., 3 tabs.
AG AGENCY SOURCE CODE: -DE -
CA CORPORATE AUTHOR CODE: 021310000, 4832000 RN REPORT NUMBER: CONF 9108083 CN CONTRACT / GRANT NUMBER (S): Contract: ACOS840R21400 UD UPDATE DATE: 9121 Marked in Search: #3 TI TITLE: Recent improvements in check val ve monitoring methods.
AN ACCESSION NUMDER: DE91010384X5F AUTHOR 5: Haynet-H.D.
V( 3CORPORATEPERSONAL SOURCE: Pe r f orme r Oak Ridge National Leb., TN.
Funder: Department of Energy, Washington, DC.
1991 40p {
REPORT DATE/FAGINAT10N l Fi PUELICATION VEAR: 1991 39 '
NT DESCFIFTIVE NOTE: Muc1-ei power r> i e n t and facil *v me,ntenanc- . + < r i c. e l
'3:
._a -c . gs; 7- .. ; , ,
, ., ..7 .
l l
. WESTINGHOUSE CLASS 3 l Energy, Washington, DC.
Cl COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES .
1 LANGUAGE: ENGLISH d NTis PRICE CODES: PC A03/MF A01 DE DESCRIPTORS: Acoustic-Emission-Testing; Aging-; Di a gnos t i c -Te c hni qu e s ;
Diesel-Engines; Electric-Generators; Feedwater-; Inspection-; Pumps-;
Reactor-Monitoring-Systems; Research-Programs; Specifications-; US-NRC;
' I,,Ul t r a s oni c -T e s t i n g ; Meetings . -
lDE DESCRIPJORS: *BWR-Type-Reactors;
- PWR - T y p e - R,e a c.t o r s.(: ,* Re a p fComponents;
- e V a l v e s .- - -
~
ID IDENTIFIERS: EDB/210100-1 EDB/210200 , . .-
3C; SUBJ ECT- C ATE G,0RI E S : N u c l e a r - s c i e n c e - a n d.-t e c h n o l o g y - R e a c t o'r e n g i n e e r i n g- a n d-jnucle a r powe r pl ant s: (77H)';p #
_.E n e r g y* S el e c t e d- s t u d i e s-i n-n u c l e a r - t e c hn ol o g y (97Q)g ; , ,.
' - ~
. jIndus t ri al-and-mec ha ni c al -engi nee ri ng (94);
Widd6sTri a$e'nd-me c ha n i c a l -engi ne e ri n'g -N o n de s t ru c t i ve- t e s t i n g (94J). *
[C C' S LIB'J E'CT% C AT E GORY . C O D E S : 77H, 97Q,.94, 940, 77, 94, 97 AB,: ABS. TRACT: .in support of the NRC Nuclear Plant Aging Research (NPAR)
- program;;f 0RNL' ha s ca rri ed out an[evoluation'of'three check _ valve' monitoring '
h*9 nim $ysMc bu's t i c:lemi s si or@ L1"t r e a s n i cKn s~p~e c t i on';f a n d ma g'ns ti el f3 u x"s'i gn a t unk .
e3
@,n_a ly'dt,sg M Fj A )p.5T hi,s wo r k ; h a syf o c u s s e d fo n$ e t e,rmi n i n g L: t h e;zc a p aeach ynsth'o b i,ti.t tosprovide diagnostic /infUrmation useful in determining e~0heck va1ve 5% ging^andtservice we a r 'ef f ec t s f (deg ra da ti on1 and undesi rabl e ope r a t-i ng7 mode s.
?l n --a d di t i o n , as ~ part of t he;'ORNL - Advariced Di a gnosti c ^Enginee ring "Re sea rch and '
eDovelopment. Center ( ADEC) ...two . novel ;noni nt ru si ve moni t ori ng me t h~ods /were dove.l oped 1( e x t e rnal a c a nd .de-mege t i c moni to ri ng) that provi de - seve ral- <
t o N c f*dVerTeRtDivFrO D Ep*2EEiNs',$$dtiiIt'$ r'h'e#!d
?nit's n tt'aiie h eoupie s f pt'h'~d o a l't'i os'.YN on e%f{ DaYd moli on ' df%h'e t hUi dh.hdkSNIlga] N e Q 4 ein gNMo'w eyir.);3% h'e%mb i,n e ido n '[o f$m c3 u s t i c y.~e mi a sj o n 1
. . . S.n tt o r,_i n.g (,w i,t h r o n e of they;otheryme thodsl provides the meansito~'determina vitaly g:ge.p e cMv a l v e 4op e,pp t i.o n a b.ido,rga.t&o n;Ai .s 4m pp er.d e s c r;ip e th s9 g .ejb e n ef4t sy ttd . -at Tlimi ta ti ons ^ a s soci a t e d wi t h ea ch me t hod an d includes recent laboratory:and
?,*f i el dst e s t"da t e ' t o ' i.11 u s t r a t e -t he c a p a bi l .i ti e s of these methods to detect 4 '
*~ simul.ated check valve'degradationr 3'refs.',,22~ figs. -4" tabs.- 7 f -
MAG'<Abbl&Y$ SOURCE-CODEi'#DE W W W W W M -# "" ' M B ** ~
Y CA' CORPORATE AUTHOR CODE:'021310000, 4832000 ' -
RN REPORT NUMBER: CONF 9104262 CN CONTRACT / GRANT NUMBER (S): Contract: AC05840R21400
" 7 hauc hs .
4 UD UPDATEaDATE: 9117 + - f- '-'
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3 og 9 Marked in Search: #3 TI TITLE:-Aging and Service Wear of Check Velves Used in Engineered Sofety-Feature Systems of Nucl eari Powe r -Pl an ts. *Vol ume 2. Aging Assessments ont Moni toring Method Evaluations. Topical rept.
AN ACCESSION NUMBER: NUREGCR470?V7 YAP.
AU PERSONAL AUTHORS: Haynes-H.D.
CS CORPORATE SOURCE: Performer: Oak Ridge National Lab., TN.
Funder: Nuclear Regulatory Commission, Washington, DC. Di v . of Engineering.
Funder: Department of Energy, Washington. DC.
REPORT DATE/ PAGINATION: Apr 91. 67p.
PY PUBLICATION YEAR: 1991 NT DESCRIPTIVE NOTE: Also available from Supt. of Does. See also 3 REG /CR-4302-V1. Sponsored by Nuclear Regulatory Commi s s i o n , Washington, 0 iv. of Engineering, and Department of Energy, Wa s h i r. g t o n , DC.
Cl COUNTRY OF INTELLECTUAL ORIGlN: UNITED-STATES LA LANGUAGE: ENGL!5H Ph NTIS PRICE CODES PC A04/MF A01 DE DESCPIPTOR5: Flutter-; Aging-teste-Mater,els; Weer-; rield-tests; Moni* ort- -
Acou tin-ennet , n U : r. a e s t roet've-tee -
ti r e s : r, ' c - r + : tr: m , c. ,
40 s ,
WESTINGHOUSE CLASS 3-DE DESCRIPTORS:
- Engineered-Safety-Systems;
- Chec k -val v e s ;
*Nucleer-Power-Plants.
D IDENTiflERS: Magn e ti c-f l u x- si gna t u r e-enel y si s .
['b
$ss SUBJECT CATEGORIES: Nucl e a r -sci enc e-a nd-t e c hnol ogy-Reac t o r -ma t e ri al s (77J);
Nuclear-science-and-technology-Reactor-engineering-and-nuclear power plants '[
(77H) 4?
CC SUBJECT CATEGORY CODES: 77J, 77H, 77 AB ABSTRACT: Check valves are used extensively in nuclear power pl e.n tYs a f e t'yff ;
systems and belance-of pl ent systems. The f a i l u r e s.. o f .. tp e se a_lj65,he.v,e; re sul t ed in significant maintenance efforts and ; on' oc c a si on , . Ev e r'es ul t e d i2((
v ;
n" water hemmer, overpressurization of low pressure. systems, and~ damage to flowuv system components. T he se failures have l e r.g e l y b'e e n attributed to severe ~g degradation of internal parts (e.g., hinge p i n s , . h i.nge arms, d i, s e s , . e rfd ' d i s c . ,
nut pins) resulting from instability, (flutter) o f c h e cl' v~a l v e normal plant operating conditions. In support of the-Nuclear Plant' d i s eAgi s u.n ngd ei"~gj17,f; Research Progrsm', Oak Ri dge. Na t i onal DLabora to ryy ho s?ca r ried ou t' a n .ev'alua ti opj(
of several d e v e l o pme n't e l and/o'r c omme r c i al .l y ' a v'a i.l abl e . c hic k v a l v e i tin ~g'n o s t iia, monitor,ing methods, in particular, those based on measurements of-acodstic ;jf6 emi s si on , s ul t ra soni c s, and magnetic flux. In each case, t he -e val u a t ip"' gha v e b e e n f f o c u'sle d ;oln ,* t h e ' c a p a b i l i t y . o f f e a 6 hamethegD5r.oyifd e{'di a gnoje tycd lorma usefulminidetermining' check valve.agingyandy'petv,icetwearjeffectss(de ati c hec k " val vef ai l u re s , and unde si r abl e ope ra ti ng m6 des. AJde'scription j wench, A
monitoring' method is provided in.the r ep or t',; i ncl u di ng e xampl e s "o f c t e'sta da t e{y acqui red under controlled laboratory conditions.'Intsome. cases,'fieldQfest'date acquired in. situ are also presented. The methods,are compared, and-sdggested areas in need of further development are identified.- ... n n .A'1 AG' 'AG ENCY7 SOURCE - CODE r NUREG 4 '* 4 i W"MF di " @ ' M'N' VMP #
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- T1 H T ITL EL: fWa t e i VR e a c t o'r S a f e t y ' I n f o rm'a'ti o n" M e'e tiYgb(18 th) . Vol u'me ' 3.FP r'e s s u?eN Vessel Integrity;-Piping and NDE; Aging and Components. - -nz AN ACCESSION NUMBER: NUREGCP0114V3XSP AU PERSONAL AUTHORS: Weiss-A.J. '
EI
~
CSaCORPORATE' SOURCE: Performer: Brookheven National ~ Lab., Upton, N Y . lo Funder: Nu cl e a r.; Re gu l a t o r y Commission. Wesnington, DC. Office of Nuclear 773 Regula~ tory Research. ' - '
Mr REPORT DATE/ PAGINATION: Apr 91. 588p. ....
PY: PUBLICATION YEAR: 1991 NT DESCRIPTIVE NOTE: Also available from Supt. of Docs. See also .
-04.
NUREG/CP-0114-V1 and NUREG/CP-0114-V2 and NUREG/CP-0097-V3. Proceedings hel d in Rockville, MD., October 22-24, 1990. Sponsored by Nuclear Regulatory C ommi s s i on , Washington, DC. Office of Nuclear Regulatory Research.
CI COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH PR NTIS PRICE CODES: PC A25/MF A04 DE DESCRIPTORS: Nuclear power plents; P r essur e vessel s; Pi pi ng-s y s t ems ;
Nonde s t ruc t i ve- t e sti ng; Age-; Reector-components.
DE DESCRIPTORS:
- Nuclear-reector-safety;
- Meetings, i
/ SUBJECT CATEGORIES: Nuclear-science and-technology-Reactor-engineering-and-l k scleer power plents (77H);
Energy-Selected studies-in nuclear-technolcgy (97Q)
CC SUBJECT CATEGORY r0 DES: 77H, 970, 77, 9' AE APSTFACT: Fartiel contents- H e a v y - 9. e c t , u n Steel T c k r <. l o g y P r e m r a rr, 41 Overview fetentiel Impect of E n h a r, c e d Frecture Tcuchre < [cte e r-Vt w L: ur' ~dh~r un 1 * ~ ' 5'r e' ' '*
t' += ' ' '- -
. WESTINGHOUSE CLASS 3 f irradietion-induced Sensitization in Austenitic Stainless Steel In-Core Components; Developments in Risk Eveluation of Aging; Degradation Modeling ' h 7 9pl i c a t i on to Aging and Maintenance Effectiveness Evaluation; Mechanical coperties of Cables Exposed t o Simul taneous Thermal and Radiation Agi n g ; e Recent Improvements in Check Velve Monitoring Methods.
AG AGENCY SOURCE CODE: NUREG CA CORPORATE AUTHOR CODE: 004545000 mo _ . . , . . , . . .
,,. . . .. .- _. ...- ~ ~ w . ~..
UD UPDATE DATE: 9116 . , . . . , .
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~2, Marked in earch: gr3 Tl TITLE: Check velves aging a s s e s t.m e n t . .v- ~ - %.m- - ,
AN ACCESSION NUMBER: 9X ..-e.,..~,~..W. . .4. M_ e AU, PERSONAL AUTHORS: Haynes2H. D E910 09 6 2. v,7, D.,1 ..S f:WP.i g.....nM.:b, Q " ' 7,.c.
l , :, , '? b . w..n... - T 7,
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. 3 CS CORPORATE SOURCl:: Performer: Dak Rid . M .J.S.~ .%
F u n d e r : D e p a 'r t m e n t .'o f f E pe n g rD'C g y%,yWeIs %' Q Mhj},nyCo,,g e ' N a t i o]n a l : . L a REPORT DATE/ PAGINATION: 1991. 35p. e yw .> t ,
en. 4 .sp, . .. M . V -
PY PUBI,1 CAT 10N YEAR: 1991 . . s y , ., 7 . : a- .g. , 4 NT. DESCRIPTIVE, NOTE: 1991 Nucl.ea rMPl a n tJ Agi n g.'Re se a rch ;(N P AR) eview- roup OS Sb'6#hTFetl
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.E Cl COUNTRY'0F INTELL ECTUAL OFpCIN.:OUN ITE D; STATES 4; . ' k 3.rff'N pfMW .
LA LANGUAGE: ENGL ISH " * " W'
;PR NTIS PRICE CODES: V 3 'O U ' m'R PC A03/MF.:A01 'YT g ~ g* # M y
~
P MC. E F '" Q i .X " * l Z $ C ; y/ .
n
.DE DESCRIPTORS:. Di a g n o s t i c,-;Te c hn,i q u.e s.;4F.a i,1 u r e s - ;1 M on i t o r i n g -';h C/.d. .
.. 4.1 Nuclear-Power-Plants'; Wear- Meetings- ' e t - g . . ~w M
-. c D E .' D E S C R I..P. T O RS .: N Val. i./6 s WAN; :G PMd.7aig .>. y.WM$o . DYi M - 0 1 D 'I D ENTI F I ERS :'JDB./220200,,;; ,e m-c e c to)n.c 4 a ;sys omp Re.gm , j. N;M.,,+d6
- n ph; m
x .. o:N..
.s o.'
W.w.WMM, M,,,
^
u AI 7
D ENTI F I ERS : 4 Che ek 6di ve'sW D ' 'a%, w.Mw, e n v.c< w p a C SUBJE'CT' CATEGORIES: . Nuclear;n,no-s,c i e ncepe n d ut e c h n o,l o g y-R e a c t o,rge n g i n e e r i n g - a n -4
.2.wnuc1,eecr. power p,1 ant-s4 3 77H)y W g M gf ifgh%Qg M c;te p 't. p , M AB' ABSTRACT: In support #ofA t h e N RC/N u,c1:e a rNP 'l a-.*
CC SUB" JECT CATEGORY CODES: 77H, 77f N X'. *. , M. . . ~ - , ~. ~ 4
.W~ . . .
n t" A gi n g +fR . . .
e s. -e a r c h "(N P4'All.) . ,
program, the Oak Ridge. National Laboratory *
of ' eeve ral c h e c k .v a l u e "d i a gn dsfi Mo'nYt'o'r' ins (tOtidRN L )'*h a s ic a YdNo r r i e dsou e #tra" #' n"a s s e s s
^
3;me sFi'd Ya"r~fGil based on measurements of a c ou s ti c demi ssi on ,~ u l t r a s oni c s , and magnetic' flux. The evaluations have focussed on the capabilities of each method to provide information useful in determining check valve aging ar'd service wear. y effects, check vel ve failures, and undesirable operating modes.'This papyr' describes the benefits-and limitations associated withreach method and includes recent
'loboratory and f i el d test d a t a , 'i n c l u d if q~ ' d it a ^o b t a i n e d ' f r om' t h sv e n M r's wh o O -
recen tl y participated in a comprehensive se ri e s of tests directed by a nuclear.
industry users group, in addition, ao part of the ORNL Advanced Diagnostic ..
Engineering Research and Devel opmen t :Cen tere ( ADEC) , two novel nonintrusive d monitoring methods were developed that provide several unique cepabilities.
These methods, based on external ac- en de megnetic monitoring are also described. None of the examine;d methods could, by themselves, monitor both the instanteneous position and motion of check velve internals and valve leakage; however, the combination of acoustic emi s si on monitoring with one of the other methods provides the means to determine vital check vel ve operational information.
AG AGENCY SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 021310000, 4832000 l REPORT NUM6ER: C O N F 910 314 21_V u o r a p h ~s
.A CONTRACT /GFiANT NUMBER (S)- Contreet: AC05840R21400 UD UFDATE DATE: 911r 42 E f 9 Mc< tee in see,c! . C
~
' ; r ;. e r a
, r. i. -
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- WESTINGHOUSE CLASS 3 AN ACCESSION NUMBER: DE91004392XSP AU PERSONAL AUTHORS: Haynes-H.D.
[DS CORPORATE SOURCE: Performer: Oak Ridge Netional Lab , TN.
under: Department of Energy, Washington, DC.
REPORT DATE/ PAGINATION: 1990. 37p.
PY PUBLICATION YEAR: 1990 NT DESCRIPTIVE NOTE: Water reactor sefety information meetino (18th).
Goithersbur,g,'HD.(USA), 22-24;0ct;199,0Gl '^
Sponsored by Department.of Energy,
~
Wa s hi ngt on s DC.* . f, M, . f.
.,i .(z2 C1 COUNTRf 0FiINTELLECTUAL~0RIGIN: UNITED-STA.TES N' LA LANGUAGE: ENGLISH -
PR NTIS PRICE _ CODES: PC A03/MF.A01 3., e g DE D E SCRI PT,0RS :f A c ou s t i c - Emi s s i on-T e s t,i n g ; , Ag i n g- ; .M,agn '*'
e t i c -T e s~ t* i "n g ;
Honi to ri ng-I Ul t ra s'oni c-Te s ti n g ; Mee ting s .. .
DE DESCRIPT0RSi
- N u c l e a r - P owe r .P 1"a'n t s'; # V I D ~1 D ENT i F 1.ERS fhEDB/2204 00:d ;".EDB/'220200@L M- A L al ve s .' .1 ID'IDENT!FIERSif*Nondeatructivlo-tks't % "$ I
SC SUBJECT; CATEGORIES: Nu cl ea r -sci e nce-a nd-te c hnol ogy-Re n e to r -engi n e e r i ng-a nd-nucleer,powejyplantsq(77H).;. 4.g g g g g . ;p , .
-_ .y .
peehapiee1.,e,ng1 gee g ,n N *;p w!CC n du eg.rj'egepp,ECOpYAf SUBJECy/ CAT 0D E S :t77Hg40f[g AB" ' A'B STR A CT :91'n support o7 ,t'h e "t4RCUN uc e a r;P.l a n t . Ag g4pQp; gr@ 'eAtr.ut c,th ,
e -t e 3 ti n g ; Re se a r c h(; g (NPAR p r og r am,30RNL!ha s'c e r r i e d *ou t-'a,n.yev e1Va ti ot3 'of;thr e e c hec k val ve moni toring; methods: " acoustic emission,; ultra'soni Minspection', and magnetic flux signature a n a l y s i s;.(N F,S A)'. ,T hi e ,wo r k~.ha s lf o c u sego_nyd e t e rmi n i ng the capabilities;of each; method to< provide diagnostic,informationxuseful in. determining check valve-ogin'gt?and%ser M e M iAr e > a n'a modes'.7 t f f s e t s'3('dYgr'
$d a gat *]$gn'o'l u n'de si r a bl e - o p e r a t i n g 'l h' a n sticEEngineering"Reeeci' hpveQm(dQ}
'~ Jo vel ope externa' orit .Ce,n,thgDEC) lac-Q n 'ad'di kwojn gOh i gegmo a n d -oc -ma gne tpygmonit o r i ng ) that provide several t1Tn7$2TaMNf n i[t o r i n g -rne t h o d s ? wj7 ret
; h'a30RN' M
s .i mpIpp' [ne3hsj 3 oge rg,t ,h e 4 t h ey rgm e tggigNyp,pggggagip e 4 me t h o d aj c o u yp.bygp themseives,-monitor the instantaneoustp6sition and motion of chec k val ve internalsiend valve l e a k a g e ; h owe ve r $t'h tiUcImb'i n a t'i on - o f acoustic emission
~
moni t o ri n g -wi t h one - of t h e other methods pr6vides-the.means to determine vi t al c h e c k% e l'v 6 4 pe"r a ti o n a l i n f o r m a tD rih l TIM $p eWd e s c r i b e s T t h e benefits 7dnd
~
T limitations a ssoci at ed wi th .ea ch me t hod -and .i ncludes - r e cen t laboratory.and field test data to illustrate the capabilities of these methods to detect simulated check velve d e g r a d a t i o n'. 3 refs. "22 figs., 4 tebs. (ERA citation 16:000456), o ~*G% Q M A, U' w r - - --
AG AGENCY' SOURCE CODE: DE w.w, dp ..
~
CA CORPORATE ~ AUTHOR CODE: 02131'0000 p4832000F > o
- RN REPORT NUMBER: CONF 901016511 CN CONTRACT / GRANT NUMBER (S): Contract: ,AC05840R21400 UD UPDATE DATE: 9107 - . - .
a.
N7 of 9 Merked in earch: #3 TI TITLE: Use of neurel networks in the operation of nuclear power pl ant s .
AN ACCESSION NUMBER: DE91002326XSP AU PERSONAL AUTHORS: Uhrig-R.E.
CS CORPORATE SOURCE: Performer: Oak Ridge National Lab., TN.
Funder: Depertment of Energy, Washington, DC.
REPORT DATE/ PAGINATION: 1990, 17p.
bY FJ U E:LICATION YEAR: 1990 t
k ./T DESCRIFTIVE NOTE: American Association of Artificial Intelligence cenference, D e y t o r; , OH (USA), 29-31 Oct 1990. S p o ri t o r e d by De pa r t me ri t of
. Energy, Washingten, M.
t; CDUNThi 0F INTELLECTUAL ORIGIN: UNITED-STAfE5 At - A V A I t A E l t iT' N CJ E Perrion- of t hi e documert e r -- i'l e g i t.1 3n micrnfiche
- n.'
43
. WESTINGHOUSE CLASS 3
, LA LANGUAGE: ENGLISH PR NT]S PRICE CODES: PC A03/MF A01 .
- DESCRIPTORS: Computerized-Control-Systems; Diagnostic-Techniques; uel-Cycle; Mechanical-Vibretione; Monitoring-; Operation-; Reactor-Safety, Values .
DE DESCRIPTORS:
- Nuclear-Power-Plants;
- Neural-Network 3.
ID IDENT!FIERS: EDB/220000-; -EDB /990200 , N
~~SC ' SU B J E CT _ C AT E GOR I E S : Nuc~l'Vrfscience-and-technology-Reactor-engineering-and-e
, nuclear power plants (77H) f;;,,. 7,.-
CC SUBJECT CATEGORY CODES: 77H, 77
;g)-{c; AB ABSTRACT: Application of neural networka t o .t h _e operation of. nuclear power plants in being investigatedeunder a US De.pertment of Energr eponsored program gc;a t'[t h e ' Uni v e r s i t y o f :,T e n n.e s se e . ..P r o j e c t s i nclude t h.e., f e a s i bi l i t y of using
' neural networks for the tot 1o' wing tasks: (a) d i e g n o s i~n'g~ specific'*abnormaf' condi tions, (b) detection?of d he change'of mode of operation, ( r- ) si gn al 9:r i1Wa v tTo n ', J ( d ) 'mo n il,t kr i kty,f[dh';eji['l v a l v mode e s . -1ing ( e of ) Lhe p1' ant t he rmod yn ami c s . . ( f ) . emul a.ti.on aofocore reload calculations. (g) analysi s of t empo r al sequences in NRC'.s . licensee event report, (h) monitoring of pl ant
. parameters, and (i) ,enal ysj spffpl e n t vi br a ti on s. Each of these projects and M1:t'syst,ussare ht oi s).a r t i cl e .l the :'obj e c't i vehof f e a c hc.of M he5*)Pyoject:sjsisito des'c rjibj0l{bof>neurEhneworkpagSr[efs.ipy and., perfor g ha .
through the use s. -
'AG" AGENCY SOURC E CODER"DEC@WW/ .
C A ~ CORPOR AT E AUTHOR ~. CODE:102.1310000, 4832000 RN. REPORT NUMDER: . CONF 9010,23511'uC Q , , ,. . . . /
CN, CONTRACT / GRANT NUMBER (S):2Contracia: AC05840R21400, FG0788ER12824 NU[ UPDATE
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.ANjACCESSION NUMBER:"NUREtCP,D147XS W ~ ,
CS SOURCE: P e rf o rme r~~* epa n d G Idaho, Idaho Falls.
' F D'n' CO R POR A T Ed e Ff N u h l e'a r "Re'g'u*1 aEoYyN8inNsfo%'I DC Wa s h i' rig t'o n ,I n c . ,7 'O f f i -
Reactor Regulation. - ' We* * ' -
Funder: American Society , of Mechanical Engineers, New York. Boaru of Nuclear Codes and Standards. _ ,.n.. .
-REPORT-DATE/ PAGINATION: O c t 90g4 62 p . - -
PY PUBLICATION YEAR: 19 9 0 w e ~ - ~
NT' DESCRIPTIVE NOTE: Al s o a v7We'b1'e 'f i om S u p t . of Docs. Sponsored by Nuclear Regulatory C ommi s si o n , Washington, DC. Office of Nuclear Reactor Regul ati on ,
and American Society of Mechanica1., Engineers, New York. Board of Nuclear Codes and Standards. +444*A w .+ - -
CI COUNTRY OF INTELL ECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH PR NTIS PRICE CODES: PC A20/MF A20 DE DESCRIPTORS: Inspection-; Vibration-; Measurement-; Chec k -val ve s ;
Relief-valves; Reliability .
DE DESCRIPTORS:
- Meetings;
- Nuclear power plants;
- Pumps;
- V a '. v e s .
ID IDENTIFIERS: Inservice-testing; Motor-operated-valves.
SC SUBJECT CATEGORIES: Nu cl ea r -sc i e nc e-a nd- t e c hnol ogy-Reac to r -engi n e e r i ng-a nd-nucleer power plants (77H);
.ergy-SeIected-studiet-in-nuelesr-technelogy (97Q)
,C SUEJECT CATEGORY CODES: 77H, 97Q, 77 97 AC ACSTRACT: The 1990 Symposium on Inservice Test,ng of Pumps and Velver, jointIy sponsored by the Bored on Nuclear Codes and Standards of the Amer 4 car l bociety of Mechenical E n g i r. e e r s and by the Nucl+ar Regulator, C ommi s s i on ,
p'o.1d+d e fcrun ?vr the di sc u s si on of current program! eno oethodt f..r
. '*e s
-:* r e+ .i;l*9r n r. w e . >
A. r t 4 : b- 5 or<ur y . erd 3r
WESTINGHOUSE CLASS 3 opportunity to discuss the need to improve i n te r vi c e testing in order to ensure the reliable performance of pumps and valves. The participation of industry r^s presentatives, regulators and consultants resulted in the di scu s si on of a koad spectrum of ideas and perspectives regarding the improvement of inservice
'~ t o s t i n g o f pumps and valves at nuclear power plants.
AG AGENCY SOURCE CODE: NUREG CA CORPORATE AUTHOR CODE: 046580000 RN REPORT NUMBER: EGG 2609 .
UD UPDATE DATE: 9102 , , ,; . f. ,,
. , . 9 of 9
.- Merked in Searc . 4 T1 TITLE: Prediction of. Check Velve Performance Degradation in Nuclear Power Plant Systems: Wear and Impact Tests. Final a tec n_d;~hn i c arept."Sep l ~
8 8-%p r 90.
AN ACCESSION NUMBER: NUREGCR5583XSP AU PERSONAL AUTHORS: Kalsi-M.S.; Horst-C.L.; Wang-J.K.; Sharma-V.
CS CORP. ORA 1E SOURCE: Fe r r o~rme r : )la l s i Engineering, Inc., Sugar Land, TX.
Funder: Nuclear Regul a t or y Commi s si on . Washington, DC. Div. of Engineering.
'R E PO,RTrD AT E/ P A G IN AT I ON : Aug 90. .
65p'.p,, 37g &
PY~ PUBLICATION-YEAR: 1990 ,
NT DESCRIPTIVE NOTE: Also available from Supt. of Docs. See also NUREG/CR-5159.
Sponsored by Nuclear Regulatory Commi s si on . Washington, DC. Di v . of Engineering.
C1 COUNTRY OF INTELLECTUAL ORIGIN: UNITED-STATES /
LA LANGUAGE: ENGLISH PR'NTis PRICE CODES:'PC.A04/MF A01' "E' 0E SCR fPTORS : Performance-; Degra'detion-; Wear-resistance; Impact-tedts; '
d iuf e5;j F a t i g u e. = M a t_ e r i a l s ; . A g e - ; Ma t hema t i c al -mo d el s ; Maintenance-;
spec tion .
2,J E;,D ES CRI ET08,$.:u N e u,c l .e a r p owe r p l a n,ty ;,
- C h e c k - v a l v e s . . .t SC SUBJECT CATEGORIES: Nu cl ea r -sci enc e-a nd-t ec hnol ogy-Reac t o r-engi nee r i ng-a nd-nuv1 ear power plants (77H) '
CC SUBJECT CATEGORY CODES: 77H, 77 AB ' ABSTRACT: Check valve f ail ures'in nuclear power plants have led to safety concerns as well as extensive damage and loss of plant availability in recent yocrs. Swing check valve internals may experience premature deterioration if the disc i s not firmly held open against its stop. At the present time no guidelines exist for the prediction of degradation trends and the determination of' suitable inspection intervals. The research is aimed at developing a reliable quantitative wear and fatigue prediction model for swing check' valves which can be used to improve the safety and reliability of their operation.
Additionally, the predictive techniques can be used to augment check valve preventive maintenance programs by providing the plant engineer with quantitative and conservative estimates of damage potential for checi valve internals.
AG AGENCY SOURCE CODE: NUREG CA CORPORATE AUTHOR CODE: 091370000 RN REPORT NUMBER: Kell 656 UD UPDATE DATE: 9023 ho 45
WESTINGHOUSE CLASS 3- G\l(/) \ - C bl. , DO C.
il erflatter 2_.01 NTIS 193"6 1904, 1985 (al-13) ho. Records Request 1: 649 CHECK 2: 1004 VALVE.
3: 27 CHECK VALVEe y 1 of~10 Marked in Seerch: #2 TI TITLE: Feilure Test.ing of Active Sclar Energy Components.
AN ACCE5SION NUMBER: DE84013024XSP AU PERSONAL AUTHORS: Farrington-R.E.
CS CORFORATE SOURCE: Performer: Solar Energy Research Inst., Golden, CO.
Funder: Department of Energy, Washington, DC.
REPORT-DATE/ PAGINATION: Jul 84 71p.
P) PUBLICATION YEAR: 1984 CI '; 0 U N T R Y OF INTELLECTUAL ORIGIN: UNITED-STATES LA LANGUAGE: ENGLISH in NTIS PRICE CODES- PC A04/MF A01 AV AVAILABILITY NOTE: Portions are illegible in microfiche products. Or) ,inal copy ava:lable until stock is exhausted.
DE DESCRIPTORS:
- Solar-Heating-Systems; Dra.in-Down-Systems; Failures-;
Free: 1ng-: Testing-; Thermal-Cycling; Valves .
DE DESCRIPTORS:
- Solar-Heating-Systems.
*D IDENTIFIERS: ERDA/140901 .
- SUE: JECT C AT E G0F:! E S : Me e he ni c al -i n du s t r i a l - c i vil -and-ma r i n e-en g i ne e r i n g- -
Ubcnciticr,ing heating-lighting and ventilating (13A);
E n- r g y-:en ve r s i on-non p r opul s i ve-Conv e r s i on- t ec hni que s (10A);
Energy-iolar energy (97N);
Energy-Heating and-cooling systems (97J); ,
Evilding-industry-technology-Architectural-design-and-environmental (890);
engineering I n du s t r a sl -an d me c he r. i c al engi nee r i ng-Qu a li t y c on t r ol-a nd reliability (94B)
CC SUBJECT CATEGORY (ODES: 13A, 10A, 97N, 97J. 89B, 94B, 10, 13, 89, 94, 97 AE AE'ETRACT: Component and system reliability of active solar energy systems continue to be a major concern of designers, manufacturers, installers, and c o r. m u me r s . Six test loops were constructed and the Solar Energy Research I r. s t i t u t e , in Golden, Colorado, to thermally cycle active solar energy system components. Drain valves, check valves t air vents, vacuum breakers, tempering v a l . e 5, end pol ybut yl ene pipe were included in the testing. The test methods and result: are discussed in t hi s report. Test results show poor reliability of s o n.,-
sf the components and limited performance from others. The results lead to a t.etter understanding of certain failures in the field and present designers with realistic expectations for these components. Recommendations are given to i n.p r o v e component reliability ano for further testing. (ERA citation 09:045765)
AG AGENCi SOURCE CODE: DE CA CORPORATE AUTHOR CODE: 056095000, 9506697 RN REPORT NUMBER: SERITR2532167 CN CONTRACT / GRANT NUMBER (S): Contract: ACO283CH10093 UD UPDATE DATE: GRAI 8502, p
f2 Marked in Search: *?
of 50 TI TITLE: EDS Coal Liquefaction Process Development: Phase V. Final Technical Progress Report, Volume 11. En gi nee ri ng Research and Development and Hybrid Boiler Program.
- AN ACCESSION NUMBER: DE85002064XSP 46
C V 9 4 - ( U L . t> v t WESTINGHOUSE CLASS 3 (4)d\ r,a .we m ree d 19erPlatter 2.01 _N 71 : ! ? 9( (u,; _ ; a . . g .e-53 9).s.
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is described in a companion guide.
I HPOllTANT_ COH H ANDS 1
sc (searchi marchen !or siriele words or ph ason from t. h o tillo, n bs t.r a c t . or tiee.e r i p to r . f ia ldc ; also comolnon j
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voe rr+ Lo r > tor maarchin>3 (e.M., m e t a l ( ) tin t.r ix )
't ( truncation ) l*ikes the place of a int.L"r ur icLLere in or at 1. h e end of a word te.s. s ruo n nu r Y retrieven measurenent, neanorinn, measurements, ele.)
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-SEARClliNG COMPENDEX step 1 Write down your topie in a sentence or two.
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step 3 Type un and sli the terms and phrases which describn your first concept. use OR between the terms. Press ENTER.
Repent for each concept. in your seareb.
example of firct concept: ss concrete or cement example of second concept: so fracture or failure step 4 Conibine the conceptu t.o narrow the search. Type-in the set numbers of your concepts and connect them with the word AND.
example: ss s3 und s6 The resulting set of papors will contain both concepts. In the example above, combin inre L. h e concepts results in a group of uapers that mention either concrete or cement and also mention either fracture or tailure.
I j SEARCil tilNTS l ,
Tc search for: example:
a word ::s robots a phrase ss neuralt) networks ss metal ( )ma t r i x( 1eumposi tei a word in t h e - L .i t i o '
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authors e au: Smith. D.K.
(then select currect entries from the l i s t. : e e:$ : s eS-eti )
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~
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- }imits set h 1.0 En F,l i s h latnjunge papors uk 51
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Portione (c) 1987, 1989 Dig 1tei Library Systemt, Inc
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n Copyright (c) 1991. DIALOG In f o rma ti o n Services, Inc. n m All rights reserved. No claim to original U.S. Gov't works. p h 6466e#G646#6# e##de#666u s6es &#e6es #6666+#EE6 6ebE6ethsbe##66##s+# 4f f sf ##s64 f s fi Commend Search Dialog User Interface es Audi o /Vi su al work, Copyright (c) 1986 Dielog Information Services, Inc.
Portions (c) 1987, 1989 Digital Library Systems, Inc COMPENDEX PLUS January - December 1987 set Items Description 75S CHECK () VALVE?
F1-Help F2-Seerch 51 668 CHECK S2 1,152 VALVE?
$3 39 CHECK () VALVE?
9-(^% Help F2-Search Fa-Formet F5-5crt
( 1
%J 52
WESTINGHOUSE CLASS 3
'7 of 38 Complete Record Tagged
. 02325305l -
AN- E1871010382Al TI- P l P l N G A N A L Y S I '. OF LARGE SCALE EXPERIMENT 5 WITH ADINA AN D D AP$Y. J AU- Muel1er, W. Cnristophj CS- Gessellscheit fuer Reektorsicherheit, Gerching, West Gerl 50- Computere end 5tructures v 26 n 1-2 1987, Nonlineer finite Elem Anel end A DIN A, Proc of tne Eth ADINA Conf, Cambridge, MA, UEA, Jun 10-12 1907 p 111-121l PY- 1987l CO- CMSTCJJ SN- 0045-79491 LA- ENGL15Hl DT- JA^(Journal Articlejl TC- A' ( Appli ce t i on s ) l AB- Large scele piping experiments have been carried out recently in Germany et the HDR test f a c i l i t y . T h e etm of these tests we: to investigete the fluid end structural d yn en>1 c behavior of a feedwater line and its check velve.
GR$ has carried out pre- and post-test calculations of these experiments using the fluid dynemic code DAPSY and the structurel enel y si s code ADINA.
Static and model enelysis reruite wi t h ADINA and both coupled and uncouplet anelysi: result o t' pressure trensients with ADINA and DAPSY ere presenteo end compered wi t h experimentel date.'The mein finding of the work presente:
in the peper is thet the highiy sophistleeted pipe e1ement in ADINA give:
edegaste retults et reasonable costs end is particularly ruitable to investigate special features such es the o v e l i :: e t i o n of the pipe or local stresses."(Author ebetract) 18 ref5.] -
DE-
- PIPING SYSTEM 5_* Computer Ai ded Anel y si r ^ MATHEMATIC AL TECHN1 QUES __ Finite Element Method' FLUID DYNAMICS Anal y si s'5TRUCTUR AL ANALYSIS _Dynemic Responte*
PRESSURE EFFECT5_ Transient: l ID- LARGE SCALE EXPERIMENTi'ADINA^DAPSY)
CC- 619 (Pipes, TenF: L Accessorie )'723 (Cemputer Software)"631 (Fluid F1-
! Hydrodynamice)"408 (Structurel Derign)ll O
l 53
WESTINGHOUSE CLASS 3- p 14 of ?8 Complete Record Tagged
.. 022970301 AN- E18706082060l T1- LADORATORY EVALUATIONS OF COBALT-FREE, NICKEL-C.ASED HARD-FACING ALLOYS FOR NUCLEAR APPLICAT!ONS.1 AU- Anon l S0- Electr Power Res Inst Rep EPRI NP 4993 Mer 1987 44pi PY- 1987l CO- ERNPD6l LA- ENGLISHl DT- R R' ( Re po r t Review)l TC- X^(Experimentel)!
AB- A number of international nucleer steem supply vendore rpecify cobalt-free hard-facing elloys to reduce r adi a ti on-fi eld bui l dup. "L abor e t or y tests have ~
identified several nickel-besed elloys having the weer r e si s t ence and other properties eccepteble for nuclear plant components."This report is e brief summery of work funded by Velen Inc. to eseess the potentiel of two nickel-bered alloys for use es hard facing in nucleer power plents.*These laboratory tests suggest thet the prepertiet are edequate for use in nucleer vel ve s.* Gene r all y , however, they are omewhat inferior to those of the cobalt-baseo alloy 5 typically r. sed for t hi s purpote.^The elley5 described in t hi s report heve performed sati sf act oril y in velse teste et e loop facility and are now widely used to hard-face gate, globe, and check valves in a number of plants d( si gne d in countries other then the United States.'(Edited author abstract)l nr.
- NICKEL AN D AL LOY S_*We a r
- N UC L E A R POWER PLANTS ^ STEAM GENERATORS *CORRO610N)
HARD-FACING ALLOYS l ,
u - 548 (Nickel & Alloys)^401 (Meterials Properties)'613 (Nuclear Power Plante.)*614 (Steam Power Plents)^539 (Metels Corrorion & Protection)ll l
54
WESTINGHOUSE CLASS 3 f
16 of 16 C o mp l e :. e Fecord Tegaed
.. 02^766711 AN- E I M E: 710 - 0 6 7 7 0 7 l TI- CAN WE DEVELOP A SAFE CHE V V A L V E ^. !
AU- Thorley, A. R. D.1 CS- City Univ, London, Eng);
CT- Papers Presented et the Internetienel :enference on Development i r. Vei.+r 6 Actuators for Fluid Centrol l CL- O< ford, Engli CD- 1965 Sep 10-1;l SP- E; H R A , Cranfield, Engi'Eritish Valve Manufacturers Assoc, Eng1' Inst of Mechanical Engineers, London, Engl!
50- Put1 by OHRA, Cranfield, Engl p .9:-5041 PY- 19E5l DN- 0-947711-06-6l LA- Englishi CN- 10193l DT- PA'(Conference Peper)l-AE- Non-return valves are intended to protect p unip s and encillary equipment tv preventing reverse flow.'Unfortunately, they can elso be the most lethe' end he;ardous p,ece of equipment fiitea to a p1pe system - due to ine phenomenon of check velve slam.'Tne dvnemic tehaviour of check valves t< s t teen poorly understood and nie a s u r e s teken to counterect valve tien1 have frequently been on a s onie w h a t orbitrary triel eno error basi - end not elways very successful.' Piping syst+ms and check valves most et risk are identified and a test fecility proposed whi c h it ie recommended should Le adop'ed as a stenderd."This could be used for development purposes but i mein use would be to provide data for check valve performance characteristics which engineers responsible for speci f yi ng and purchasing selvet should be entitled to demend from velve me nu f a c t u r e r s . '( Au t ho r uD st r ee t ) 6 reft. l DE-
- VALVES AND VALVE G E A R__
- D e s i g n ~ PIPING VSTEMS__Velves STPUCTURAL ANALYS1C_ Dynamic R e s p o n z e ' '~ E E DW A T E R P U M F s ' F L OWM E T E R 5 ' F L U l O DYNAMIC: l ID- CHECE VALVE' HON-RETURN VALVES ^ CHECK VALVE iLAM" DYNAMIC PERFOPMANCE CURvi REVERCE VELOCITY : LAM FREE VALVEi-l CC- 601 (Mechanical Design)'L19 (Pipes. Tanks & Ac c e s so ri e s)' 9 21 (Applie.
Physics)^61E (Compreeters Pumps)^942 (Mechanical L Miscellaneous Measuring Inetruments)"631 (Fluid Flow & Hydrodynamics)ll 4
O 55
1 ~
#4 WESTINGHOUSE CLASS 3 .
N
'['h l7 of-38 . Complete Record Tagged ,
\m-)-02276656l AN--EIM8710-0676321
-T1.- DESIGN-CONSIDERATION 5 FOR WAFER TYPE CHECh VALVES FOR NUCLEAR AND POWER-PLANT SERVICE.l
'AU- Hong, H.'Svobede, J. V.^81ech, A. E.1
_ CS-- C onco r di a Univ, Montreal, Cen)
(T- Papers Presented et t he. International Conference.on Developments in_Velves .
-6 Actuators for fluid Ccntrol.l CL- Oxford, Engli CD- 1985 Sep 10-12l
-SP- SHRA, Cranfield, E ri g l ' B r i t i s h Velve Manufacturers Assoc, Engl* Inst of Mechanicel Engineers, London, Engll Publ by CHRA, Crenfield, Eng! p 37-561 PV- 1985) f; N 947711-06-El LA- Englishl CN- 10193l DT- PA"(Conference Paper)l AB- The peper deels with the desi herecteristice of 'wefer type' check velves, in particuler velve piu.sure drop, velve dynamics and structurel i nt egri t y. 'It is shown that optimal d1 men si on f o f- the velve mechanism-resulting in e minimum pressure loss can be found.^The velve dynamics study performed led to tne development of e computer simul e t i on model , aiding in the selection of a desirable amount of velve demping end'best location of 7, the velve in the piping system."Both, enelytical end experimental work has
( been carried out to accomplish the ebove teskE.^The practical velve of1the.
% work presented is illustrated on a quantitative example of e. check velve.'
Both, pressure lose and structural integrity have been determined.*(Author ebetract) & refs.l DE--+ NUCLEAR POWER PLANTS _ Velves" PIPELINES _ Valves' MATHEMATICAL MODELS^ COMPUTER
$1MULATION^ VALVES AND VALVE GEAR _Eerthqueke Resistencel
.ID- WAFER TYPE CHECK VALVES' VALVE PRESSURE DROP ^ VALVE DYNAMICS ^ MOMENT COEFFICIENT Or ANNULAR PLATE" VALVE ORIFICE DIAMETER" VALVE STRUCTURAL INTEGRITY!
CC- 613 (Nuclear Fower Flents)'601 (Mechanical Design)*619 (Pipes, Tanke L
. Accessories)^921 (Applied Methematics)^723 l Computer Software)*484
( Sei smol ogy ) l l L),
56
. WESTINGHOUSE CLASS 3 .
21 of 29 Complete Record Tegged
-- 0 043425l AN- EIM8704-0275331 T1- NUMERICAL 5!MULATION OF SEL F ACTUATING V AL VE! AND ITE AFF L IC ATION. i
.AU- P u :: a l o w s k i , R."Neumann. U.l CS--Kraftwerk Union AG, Erlangen, West Gerl CT- First International Multiphere fl ui d Trenzients Symposium. (Precented at the Winter Annuel Meeting of the American Society of Mec hani c al E n g i r.e e r s . ' j CL- Anaheim, CA, USA l CD- 1986 Dec 7-12l SP- ASME, Fluid Transients Committee, New York, NY, USA ^A5ME, Multiphase Flow Committee, New York, NY, USA'ASME, Fluide Engineering Di v , New York, NY, USA {
$0- American Society of Mechanical Engineers, Fluide Engineering Division (Publicetion) F ED v 41. P u t.1 by A5ME, New York, NY, USA p 85-94j PY- 1986l CO- FED 5DLl LA- English!
CN- 09303l DT- PA^(Conference Paper)l AE- Self-actuating velves f u n c t i o ri e l l y c on t ri bu t e to eefety end plant uperet"ng availability of nuclear power plante end other procere facilitiet. 'A general feeture of the dynamical beheviour of these velve types is their dependence on the discharging fluid end flow rete end in many casee e ddi t i onell y on coupling parametert between the valve and ite system environment.'We report on developmente in numericel velve simulation, wh"
enable one to estimate velve performance under various different bounder conditions.'The numerical velve models presented are based on the comput ,
code TRAC-PFl and ere shown to be succesfully applicable to safety relief velves, demped check velvet and spring loeded velvee.^(Edited author ebetract) 11 refs.l DE-
- VALVES AND VALVE GEAR _*Methametical Model!^$AFETY VAlkE5_ Computer Simuletion!
!D- RELF-ACTUATING VALVES ^COMPUTEF CODE TRAC-Pfl'CHECh VALVES ^5 FRING LOADED VALVE 5]
CC- 619 (Pipe 3, Tanks & Acce::ories)'9:1 (Applied Methematics)^914 (Gefet Engineering)ll O
57
- )
WESTINGHOUSE CLASS 3 '!
1 1
24 of 35 C o n.r. l e t e - R e c o r d Tagged 022248271 ANi EIM6701-005477l JT 1 - VERIFICATION OF PIPING C AL CUL AT IONS UNDER F. L OW DOWN LOADING.EY-MEANS.OF I
-STRAIN _MEASUREMENTC. l
-AU- E:ei s sweenge r , F.l
($~ Univ Stuttgart, Stuttgart, . West Gerl l CT- Tran sac tion s of the 8th International Conference.on i. t r u c t u r e l Mechanics ir-Reactor Technology. (Vol, F1-F2, LWR Fressure Components.)l CL- Erussels, Eelg(
CL- 1985 Aug 19-231 50- Commission of the Europeen Communitie5, Brussels, C+1 9' Int
~
.A s soc f o r.
$tructural Mechenics in Reactor Technology l 4
50- Trentactions of the International Conference on Structural Mechanics'in Reactor Technology 8th v F1-F2. Publ by North-Holland, Ams t e r deni. Neth.p 5 - .
1021 FY- 1985J CO- TICTDVl SN- Ol67-563xl 6N- 0-444-06960-31
' LA- Englishi
. CN- 08781l
, DT- P A ' ( C o n t' e r e n c e Peper)l A E; - During tlowdown tests with a feedwater check valve et the HDR plent streing were measured et seversi crose-tections of a pipe."The strain measurements r
showed the oscillations of the pipe but elto cross section deformations-in L and near elbows.'To evoluete those deformations a highly optimized Finite-1 Element celculation of the blowdown test et. the pipe wet performed; the l theoretical stress- and strain-results without c r. o s s - s e c t i o n deformation were compared with values from the rne e s u r eme n t s , the differences showed the deformationt.~Further on in two elbows the ASME value5 of cross-section deformation were theoreti;elly celculeted enc thowed mostly a good j
egreement with the meeturements,"(Author ebetract) 6 refg.[
DE- +P!FING SYSTEM 5_*5 train" NUCLEAR REACTOR 5, LIGHT WATER Accident Frevention LTRE,1E5_Anelysie^ MATHEMATICAL _TECHN100E5_ Finite Element Me t hod ' PRE 5 50R E MEASUREMENT l ID- HER-POWER P L AN T " E L E:OW CROS$ SECTION5j
- CC- 619 (P4 pes, Tents & Accessorie5)~421 (Meteriale Properties)'621 (Nuclear
[ Reacters)^914 (Sa f e t y .Engi nee r i ng) ^931 _ (' A p p l i e d F hy rie s)l l l
l 1
1 I
I V
i l
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WESTINGHOUSE CLASS ?
?5 of 38 Complete Record Tegged
- v. 0222402El Af4- EIM8701-005476l TI- STRAIN MEASUREMENTS AT THE HDR-P!FE-1YSTEM UNDER LOCA-LOAD: EFFECTS ON ELCOWS AND DISPLACED WELDING 5.1 AU- Hunger, H.l CS- Kernforschungs:entrum Kerlsruhe GmbH, Karlsruhe, West Gerl CT- Trensections of the 8th International Conference on Structural Mechenics in Reactor Teehnology. (Vol. F1-F2. LWR Prerrure Components.)]
CL- Brussels, E: e l g t CD- 1985 Aug 19-23l SP- Commission of the Europeen Communities, Brussels, Belg^]nt Aseoc for Structurel Mechanics in Reactor Technology l 50- Trensections of the International Conference on Structural Mechanics in Reactor Technology 8th v F1-F2. Futi by North-Hollend, Amsterdam, Neth p 91-96l PY- 1985l Co- TICTDVl SN- 0167-563xl DN- 0-444-86960-?l LA- Englishl CN- 08781l DT- PA"(Conference Paper))
AB- T hi s paper chorectorizes Lome effects which have been detected during strain gauge measurements on a test piping with feed water check v el ve oscillating under blowdown-loed.*The oveli:etion of a pipe elbow subjected to in plane-bending effects the connected straight pipe; this is shown b) -
means of circumferential stresees.*Very high LOCA-loed produces plastic strain and changes the pipe dynamics."Artificiel di spl ac ed welds increese the local strein but no defects have occurred.^One exemple compare s t r e s t- e s from measurement and poet-celculation.*Moreover there are given some remerf5 on the optimization of the comparison of measurement and calculetion.^(Author abstract) 5 refs.l DE-
- PIPING SYSTEM 5_* Strain ^ NUCLEAR REACTOR $, LIGHT WATER _ Lost of Coolant Accident' WELD $" ACCIDENT FREVENTION"5 TRESSES}
ID- PLASTIFICATION EFFECTS ^ DISPLACED WELD $l CC- 619 (Pipee, Tenkt & Ac c e s so ri e s )' 4 21 (Materials P r ope r t i e s) ^ 621 (Nucleer Reactors)'914 (Sofety E n g i n e e r i n g ) 9 31 (Applied P hy si c s) ^530 (Welding &
Eonding)ll l
I l
O
! 59 1
WESTINGHOUSE CLASS 3 t( of : .
C ornpl e t e Record Tagged
- 0022492!I f AN* elm 0701-0054701 !
TI- CALCULAllON OF THE FLUlb INDUCED FORCES. ACTING ON t- FIPE OY MEAN1 OF THE ,
$URFACES INTEGRAL AND ITi AFPLICATION TO A tLOWDOr!N TEST I N T H r. HDp,; ;
AU- Meier, D.l t CS- V e r n f o r tc hungt z e n t r urn Karlsruhe GmbH, Verlsruhe ; West Gerl C1- Trentections of the 8th Internationel Conference.cn Structural Mechehior in- ,
F< c a c t o r Technology. (Vol F1-F2. LWR Pressure C otop o n e n t s . ) l CL- frutsels, E: e l g l
- t. D - 1960 Aug 19-231 SP C ornmi e s i on of tbe European Communitiet, Iruse+1s, felg^1nt Assoo for Structure 1 Mechanict in Reactor Technology l 10- Transactiont of the International Confer *nce en Structural Mechaniet in Reactor Technology Oth v T1-F2. Publ by North-Hollend, Arns t e r dam. Neth p _84 - . '
901 PY- 1480(
CO- TICTDVI SN- Ol67-5(?XI ON- 0-444-86960-2)
LA* Enolirht CN- 0078!1 DT- FA"(Conference Ieper)l I A L - - T h i r. c o n t r i t. u t i o n describes a methoo to calculate hydrodynamic forces ecting on pipet by applying the surface integral rr.e t h o d . " T h e s e f l u i d t 'o r c e '
wer+ calculated bered on n,* e s u r e d p r e t t u r e time hittories f_ rom a pipin_g r y t> t e rr, during blowdown with subsequent closing of 6 check-valve."A prediction of the structural retponse of the piping system wee _done_wi_t_h thete forcer and c ornp a r e d to meetured displacements.*(Author ebetract) 4 ref2 l DE-
- NUCLEAR REACTORi, L I GHT WAT ER_. Pi pi ng 5y:tems ~HYDEODYNAMICS , Fluid itrootore Interectien~ MATHEMATICAL TECHNIQUE 5_ Integral Equetions ACCIDENT PprVENTIOU"$ TRESSES Anelvei l 1D* ELOWOOWN TELTS'5URFACE INTEGRAL METHODi ..
CC--02)
;Nuclesr heectors)~619 ( f' i p e t , Tonit L Accenteries)^631 - ( F 1_ u i d _ - F l o w
& Hydrodynamics)~921 (Applied Methematic!)'9%1 (Applied Phytics)ll F
S
=- --
60
,e=
.. -- - .. - .~ . - _
_. - - . - - ~ _ -
i
- 1 WESTINGHOUSE CLASS 3 1
\
;' of 'c C on,p l e t e R e c e r ..t T ea ae d
. 02224Em il I A f1 - ElH0701-00b471l l TI- MODELLliJG OF COUILED S E L T - A C T U A T i rJ G SArETY, REll[r AflD DAMF[D CH[(r vt.t /[
SY!1 EMS WITH THE CODE; TRAC-Of1 AND ROLAST.)
AU- N e unie n n , U."Pu:eloweki, P . ' G r i rnm , l.l C5- Vreftwerk Union AG, Erlangen, West Gerl (T- Transactions of the 8th International i: o n f e r e n c e on Structurel Mechent: e in Reector Technology. (Vol, fl-F2. LWR treteure C omporm n t r . ) l CL- Erurselt, Belgl CD- 1980 Aug 19-0?l 5I- Comm1ition of the furopean C c rnn u n i t i e t , E,r u n t e 1 2 , E' e 1 o ' 1 n t A t-$ o c for Structural Mechenics in Reector Technology l 10- Transactione of the Internetionel conference on Structurel Mechanic; in Reactor T e c hnol o g y Oth v I1-F2. F u til by North-Hc' lend, Amrterdem, Netb p !9+
04l F(- 196b]
CO- 'i I C T D V l SN- Ol67-6(?Al EN- 0-444-909E0-11 LA- fnglithj C ff - 06701l DT- FA'(Cenference Ioper)l At- f4umericel velve models for timuletion of selfactueting refety velvet and damped check vel ve r are introduced for the computer programs TRAC-FF1 end ROLAST. At examplee of application post-test calculations and etability -
enely: T r. are gi v en . '( Au t ho r a b e. t r a c t ) 4 refs.1 DL- +5AFETY VALVE 5_* Computer Aided Anal y si s' M ATHfM ATIC AL TECHNIQUES _Num+rical Analyrit' NUCLEAR REACTORS, LIGHT WATER ^ EQUATIONS OF MOTIONj ID- COMPUTER FROGPAM TRAC-FFl=COMFUTER FROGRAM RO,ASTI CC- 619 (tipet. Tanks 6 Accettoriet)^914 (Safet) Engineering)^72? (Computer Ioftwsre)'621 (Nucleer Reactort)'631 (Fluid Flow & Hydrodynamict)'9?'
(Applied fhytict)ll O
61
WESTINGHOUSE CLASS 3 ge of ?? Complete Record Tagged O222??241 (KN-EIM6701-0042741 TI- COMPONENT REllA01LITY TESTING.l AU- T e r r i n g t o ri , Ro t,e r t 0,) l CS- Solar Energy Reecerch inet, Goiden CO, USA)
(T- ASES 1984, Pr oceeding t of the 1964 Annual Meeting American $oler (nergy Society inc - Technicel Papert, including Invited f*epers f r orn the 1903 Annuel Meeting.1 J CL+ Aneheim, CA, USA) l CD- 1984 Jun 5-71
- 5 P + A rne r i c a n scler Ene gy Soc, Loulder, CO, VAA^$oler Age Megazine, Sol e r vi si on i inc. Harrisville, NH, USA'US DOE, Weshington, DC, USA *$oler Energy Research '
Inst, Golden, CO, USA'$outhern Californie Solar Energy Soc, CA, USAl 1 50 Proccedings of the Annuel Meeting -
Arne r i c e n Section of the International-Soler Energy society 1964. Publ by American Solar Energy Soc, Boulder, CO, USA p !!6-1001 PY- 19841 CO- IMSlD$1 SN- 0146-406Cl LA- Eng)ithl j CtJ - 10 80 4 61 DT. PA'(fonferer.ce feper)!
AD- Component and system reliability of active soler energy systems continues to be a mejor concern of designers, manufacturers, instellers, and '
( 'contamere.'Six tert loops were constructed et the Soler Energy Research institute in Golden, Colorado, to therme11y cycle active colorfenergy L eystem component $.' Drain valves, check velves, air vents, vacuum breakert, tempering velvet, and polybutylene pipe were included in the testing.^ Test l resulte ehow poor reliability of s orn e of the componente end limited ;
performance from othere,^The resulte lead to e better underniending of j certain failures 1 ti the field and present de ri gne r s wi t h realistic expectationt for these components.'(Author abstreet) 3 refs [
E,0 - +SQLAR CNERGY_* Equipment ^ SOLAR RADIATION _ Collectors" PIPING SYSTEMS _Plastiet Applicatientl ID- COMPONENT REllAEltlTY^ TEMPERING VALVE #" DRAIN VALVES" AIR VENTS l_
CC- 657 (Space Physics)'913 (Production Plenning & Control)*619 (Pipee, T o rd s L Accessories)"731 (Automatic Contrel-Principles)ll s
62
. l WESTINGHOUSE CLASS 3 1
4 h ,
;9 of 3& Complete Record Tagged
... 022J2597l A fJ - elm 8701-004247l TI- PLANT A V A l t. A 0 ! L I T Y IMPROVEMENT EY EllMINATING DISC V![ RATION 5 IN LW!NG CHECK VALVES.l AU- C hi u , C h on g
- K e l s i_, M. S.l Ct- Southern C a lTf o r n i e Edieon Co, sen Clemente, CA, USA l CT- Joint ASME/IEEE Power Generation Conference.l CL- Fortland, OR, USA l CD- 1906 Oct 19-23l SP- AtME, New York, NY, USA *lEEE, New York, NY, USAj 50- American Society of Mechenicel Engineere (Peper) Publ by ASME, New Yort.
NY, USA 86-JPGC-NE-6, 7p]
FY- 19861 CO- ASMSA4l SN- 0402-1215l LA- Englishl CN- 000911 DT- PA^(Conference Peper){
AC- failure of several swing check velvet during flow in the normal direction p r ornp t e d en investigation of the root cause of the p r obl eni. 'Di s c vibratione resulting in repeated impacte egainst the disc stop cauted fracture of the tbreeded connection between the dice end the arm."A literature teoich end review of aveilable published date f r orn various velve manufacturert reveeled a surpricing lect of information regarding the mi n i rnum flow velocity necessary to hold the disc firmly in the open position."A theoreticol formule for determining the rni n i muro v e l o c i t y her, been develo which shows excellent agreement with actuel test resultf.^A proper application of t hi s formule een help identify potential check v el ve problems end irnp r o ve plant availabili t y by taking a timely corrective action '(Author ebttract) 13 reft.l DE-
- VALVES AND VALVE GEAR
- Vi b r a t i on s'N UC L E AR POWER PLANTS Auxiliary E qui p men t '
FLUID DYNAMICS
- FLOW OF F L U I DS_T u r bul e n t l ID- iWING CHECK VALVE 5' CHECK VALVE DI SC S ^ DI SC VIBRATIONS' MINIMUM FLOW VELOCITY-fLANT AVAILA0lL1TY'TURIULENCE FLUCTUATING FORCEl CC- C01 (Mechenical De si gn) ^ 619 (fipes. Tankt & Ac c e s s o r i e s) ' 613 (Nucleer iower Plente)^63) (Fluid flow & Hydrodynamics)ll O
63
.I WESTINGHOUSE CLASS'3 l 1
30 of st :enplete Record Tegged
-0221:3061 A tJ - (10706064744l TI- PREsiURE DROFS FOR WAFER CHE(M VALVEi.} l
/g U - Letham.-1.*Andereon, A.l _j CS- Univ of Newcastle upon Tyne, Newoestle upon Tyne, Eng1l j 50- Eur Water Sewage v 90 n 1079 Jan 1906 p 9-10, 10) -
FY- 1980{ .
CO- EWSEfYl LA- EllG L 1 S H )
DT- JA'(Journal A r t'i c l e ) l TC~ G'(General Review)!
AD- The 'wefer' rion-return v ee l v e has advantaget over the conventiondi swing-' .i check valve i ri terms of cort, spece r e q u i r e rne n t end ease of i n s t e l l e t i o r. . # i for exemple, typical overell weights for e 100mm velve are 0 Kg and 74 kg r e t, p e c t i v e l y . ' I t a c h i e v e t. these et the expense of hydreulic_ performance; t het is, for the same flow rete it they produce e greater pretsure drop.*
Since the various compendte of preteure drop date provide little design date for check v o l v e '., . the intention is to: d e s c r i t. e how wafer check valvet influence pipe flow, indicete the principal wafer valve featuret which influence the preteure drop for different producte, and compere the pressure drop performance of wefer end conventional twing-chect velves.^E ref l t DE- *WATEF PIPELINES
- Pressure Regulation" VALVE 5 Af1D VALVE GEAR _Ferformance >
FLOW OF W AT E R_,C o n t r o i 1
'h -WAFER VALVE ^ HYDRAULIC PERFORt4ANCE* LOCAL PRES $URE. DROP 1 f 440 (Weterworkt)*944 (fioitture, Pressure & Tempereture, & Rediation tieasuring Instruments)'601 (Mechenical Design)^631' ( Fl ui d Flow & '
Hydrodynemice}ll l
64
34 cf , ';rplett E teorj Iegged
. 02191 ?7l A tJ - Ele 7040}6113!
TI- HOW THE GERMAtiS ARE E E N E F I T !!J G FROM A RIGOROUS M PROACH TO QUALITf.l AU- Koch, E." Muser, W.^$cheut,, fi .1 CS- Kraftwert Union, Offenbech em Mein, West Gerl
$0- Nuclear Engineering International v 32 n 290 Jan 1967 p 44-45l FY- 1987l CO- NElNPFi SN- 0029-5$07l LA- ENGLISHj DT- JA"(Journal Article)l TC- A ' ( A p p l i c e t i o n t ) ^ M ( M a ri a g e rne n t Aepectt)l AD- Cince a modern 1.200MWe Germen PWR contains no lete than 17,000 velves, their ens i n t e n a n c e end repair can place e considerable burden on wtilitier."
Recent yeert have teen considerable progrett in i rnp r o v i n g valves, with consequent benefitt for overell p i ts n t performehce.^The following are some of the main measures teken recently in Germany to improve valve quality lets ute of arbettor-becca meteriel and wider use of grsphite-based meterial for seeling; subititution of esbettot-bered meteriel in stuffing box pectingt by graphite-teflon or t e f l o n - e. i l k ; wider use of forged, instead of welded, valve bodier; wider use of austenitic stainlett steels to avoid problemt eteociated with corrosion end wear; use of globe velves ,
instead of gete velves; further development of control valvet with respect to derign end functioning; end p r ovi si on of dethpot in main check velve .*
1 ref.l
- NUCLEAR REACTORS, PRESSUR12ED WATER _. Federal Republic of Germany ^ VALVES AND VALVE GEAR _Que1it.y Contrel^ ASBESTOS
- GRAPHITE ^ STAINLESS STEEL ^FLUORINL i CONTAINING POLYMfRSl ID- G L O E: E VALVES' GATE VALVES' TEFLON SlLKl CC- 621 (Nuclear Reectort)^601 (Mechanical Design)^913 (Production Flenning L Control)~41) ( Insul e t ing Met er i el t ) ^ 402 (Mineralogy E Petrology)^545 (Iron & Steel)ll O
65
WESTINGHOUSE CLASS 3
\
37 of sc C e rr.p l e t e F. e c o r d Tegged 02141179)
A tJ - EIM0012-069145l T!- C OMPON E tJT REL1A01L1TY A tJ D C otJ T ROL iyITEM T E S T 1 t1 G . ;
AU- Ferrington, Robert O.j C5- Solar Energy Reteerch Intt, Gollen, CO, USAj CT- F r o c e e d i n g s- of the Solar Luildingt Conference.l
( L - We t h i n g t o ri , DC, USAj CD- 1985 Mer 10-20l S F' - US DOE, Office of Soler Heet Technologies, We t hi n g t on , DC, V5Al 50- Publ by US DOE, Wethington, DC, USA p 115-1221 PY- 1905l LA- Englishi CN- 08824l DT - fA*(Conference Feperyl A0- The Leler Energy Reteerch Institute het been involved in tetting active c ornp o n e n t reliability and control eyttems.'Si> tett loopt were c o r. r t r u c t e d to t he rmell y cycle drein valves, chect velves, eir vents, vacuum breeters, tempering velvet, and polybutylene piping.'Results showing poor reliability of ome of the componentt and 1imited performance of otheri 1eed to a better understonding of certein failure? in the field end rretent designers with realietic e x p e c t a t i n n e- f on thete coroponentz.^The teven t-DHW control systemt tested included thermistort, switchet, RTDt, IC tentore, and controllers. Serious r eli abili t y problems included tentor degredstien nr failure from high temperaturet, end controllert thet did not meet specificatione. ^At much es 50% of collected energy can be lost because of sentor degradetion, and euxiliary energy requirements can increeze by 250%.*
(Author ebttract) e refS.j DC- *5OLAR EtJ ERGY_* C on t r o l
- 50L AR RADIATION C o l l e c t o r t. ' 2 '.:t: i RO L SYSTEMS Testing l 10- C OMPON ENT FELIA0lLIT) SENSOR T EMF ER ATURE REEF 0NSE CHARACTER!ZATION'50LAR ENERGY RESEARCH INSTITUTEI CC+ E6' (Spece Physice)'731 (Autometic C on t rol F rinciplet} } ]
66
.> ra
- ' * - * ' .h.,4 44 _
HESTZNGHOUSE CLhSS 3 O
e O
s-O
WESTINGHOUSE CLASS 3 abstract) 2 reis.l DE. e 5 T E AM G E N E F:A T OR i_,+ C o mp u t e r Aided An al y si r.' f L U l b DYN AMI C S Ma t hema t i c al Modei s 'NUC L E Ah POWER PLANT 5l ID- THERMAL-HYDRAULIC BEHAVIOR'RETRANl a
CC- 614 ($ team Power Plante)'723 (Computer Software)*C31 (fluid flow.&
H y d r o d yn ami c S) *9 21 (Applied Methemetic5)^613 (Nuc1 ear Power i1 en t t) J j _
e#++6+4e6+4&d6464ffe6e#664&BC n telect a File u 8+++6e++etef4&++ett+e&++++6&& a 1987 COMPENDEX -D: a e
a 1998 COMPENDEX -E: a a 1989 COMPENDEX F: a n 1990 CCMPENDEX G: u a 1991.COMPENDEX H: a.
u a n -c a a be++h+4&u&6+44te+4k+6+k4&Est#4$i PgUp Home *** End of Record **+ Next: Ctrl +PgUp 7
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COMPENDEX*PLUS January - December 1987
$et- ltems Description
$1 836 ISOLATION i S2 1,152 VALVE 7 53 7 ISOLATION () VALVE 7
?-
-Help F2-$earch F4-Format F5-Sort L
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67
_ . _ . . _ _ _ _ __ _ -- -. - - - - - - - - = - - -- -
WESTINGHOUSE CLASS 3 l
'\
ov-2 ef ~
AN- E18711114250l 02)"'329?l
. ; r: p l a t e EeJor3 T agged Ol !
TI- NEW REACTOR RECIRCULATION LOOF 5 FOR MUEHLEDERG fJUC L E AR FOWER iTATION.j l AU- Pauli, W.1 !
50- Sulter Technical Review v (9 n 2 1987 p 26-30l PY- 1907l CO- SZTRA0l 1 SN- 0039-49121 '
LA- ENGL15Hl DT- JA'(Journal Article)l TC- G'(General Review)l AB- The 320 MWe Muehleberg nuclear power station lies on the River Aare about 14 k rn west of Bern.'It is equipped with a boiling water reactor having e x t e r ri e l pipework and p urnp s for recirculating the reactor water,'The plant has tie e n in service since 19 7 2 . A s the austen1 tic steel pipework was showing si gn s of intergranular s t re s s-cor ro si on cracking, the owner and operator of the plant -
Et e r n i s c h e Kraftwerke AG (BfW) -
decided to renew the ntire pipeworf sy! tem.'After eight rn o n t h e of intensive planning and preparation, the pipework and isolatien valve housings were replaced durin an overhaul laeting 13 weeks.'(Edited author abstract)J DE- *NUCLEAd POWER PLANTS _ Pumps' FEE 0 WATER PUMP 5_Perfarmance' COOLING WATER _Fiping Systems' WATER PIPING SYSTEM 5!
ID- REACTOR WATER' VALVE HOUSING ^1NT ERGRANUL AR CRACK INGl CC- 613 (Nuclear Power Plants)"618 ( C ornp r e s s o r s & Fumps)'616 (Heat Exchangers)^619 (Pipes, Tanks & Accessories)l{
t l
9 68
WESTINGHOUSE CLASS 3 s.
- ? C;eplete F
- e :. r o Tagged
.- 0;.07105l
-a- Elt?O9092882) j T:- REDUCING PER50NfJEL EXPOSURE E; Y R E LUC I'JG C OE AL T LEVELS IN FRIMARY SYSTEMS.]
i2- Hunt. E. 1.l 4
Ci--Stone & Webster Engineering Corpj !
- ' - Nuci Plant J v 5 n 3 May-Jun 1967 r 24-05, f01 j F- 13E7l i
C0- NFJOE?I i La- ENGLl>H{ i D'- JA (Journal Artiole)1 j TC- A^(Applications)l i
ti- Cobalt-60 has been identified at the principal isotope responsible (or the out-of-core radiation c on t arni n e t i on problem pleguing the nuclear power industry.' Valve maintenance has been pinpointed er the source o f. 10 to 30 gtams of cobalt debris per year in p r e s s u r i :: e d wa t e r reactore (PWRt) snd 3 to 90 grams per year in b o i l i r. g water reactors (LWRs).*In.particular, rigorous and frequent valve teat lapping ( p o l i s h i r' g ') has been shown to remove significant amounts of cobelt-based hard-fscing materials (e. g, ,
stellite) from valve surfaces.'Methodt of limiting the introduction of l cobalt to the primary systems of light water nuclear reactors are being evaluated by the industry.^$tudiet show t hi s input of cobalt can be controlled by improved cleaning and repai r procedures."1 ref.l DE-
- NUCLEAR REACTOR $, LIGHT WATER ^ RADIATION PROTECTION ^CODALT AND ALLOYL' VALVES AND VALVE GEAR l
' 's
.-- STELLITE 6"$TELLITE 21" COBALT-60^ MAIN STEAM ISOLATION VALVES
- VALVE SEAT (
621 (Nuclear Reactors)*622 (Radioactive Materials)'914 (Safety Engineering)'549 (Nonferrous Metals & A11oys)-601 (Mechanical Design)ll s'
s I
4
)
k
.I 69
, r. :. f ' .:mplete F* .. s rj ' e , a e rt
...J- 02.3E375j AN- E I M 8 7 0 3 - 012: ' 7: 1 TI- OPERATING EXPERIEfKE OF MAIN ETEAM l'OLAT10h VALVE 1 (MS1V; AT FEiiENHE!M AND OUGEY.l AU- Dredemis, G.^Fourest. E.'Giroux, C.!
C5- CEA, Fontenay au,-Rotes, Frl CT- International Conference on Nuclear Power Plant Aging, Avail abili t y Factor and Reliability Analysi? - Conference Proceedings.l CL- len Diego, CA, USAl CD- 19EL Jul 0-12l
;P- ASM, Metals Park, OH, USA ^AWS, Miami, FL, USA' Atomic Energy Soc of Japan, Jpn^0ritish Nucleer Energy loc. London. Engl'Cenedian Nuclear Soc. Toronto Ont, Can'et all
'u- Publ by ASM, Metals Park, OH, U5A p 391-393}
PV- 1985l PN- 0-07170-253-3{
LA- English)
Ch- 09202}
DT- PA'(Conference Paper)}
AE- The paper presents the eacerience of Hopkinson MSIVe over about 40 reactor years of operation at Fessenheim and Eugey unit 5 (900 MWe PWR ) . T h e variou problema encountered including aging effects on auxiliary equipments and increases in closure time are discussed."The corrective actions undertaken t> y the utility and the safety assessment of these events performed by the French safety authorities are also described."This analysit proved th h anomelies related to the design of the valvet, as well as to their manufacture and installation, had been correctly dealt with.^Furthermore, it should have also revealed potential anomalies due to ageing of the e qui pmen t . ' ( Edi t ed author abstract){
DE- + NUCLEAR POWER PLANTS
- Valves
- NUCLEAR REACTOR $ Performance" POWER P L A N T S _, A c c i d e n t Prevention ~ NUCLEAR REAClORS, PRESSURIZED NATER_Agingi ID- COMPONENT AGING' FAST CLOSURE T!ME ANOMALY' LEAK $ FROM AIR CIRCUITl CC- 613 (Nuclear Tower Flant5)^601 (Mechanical Design)^621 (Nuclear Reectors)"421 (Meterials Properties)^913 (Production Planning & Control)
O 70
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WESTINGHOUSE CLASS 3 4
t wplete A e .:. o r d Tagges
<4
.a- 0223(.:13l AN- i!MB701-01691)[
T!- PEOBAEILISTIC A i 'i E S S M E t1 T 1 FOR 3(STEMi I N T E R A C T 10!15 AtlD THEIR EFFECT.l ;
Au- Coffman, F. D. Jr.) ;
CE- U5 Nuclear Regulatory C ommi s si o n , Washington, DC, USA l i Ci- International Conference on Nuclear Power Flant Aging, Availability Factor and Relistiility Anal y si s - Conference Froceedings.l
'L- San Diego, CA, USA) l
- D- 1995 Jul 8-12l l 15- A5M, Metels ParF, OH, USA'AWS, Miemi, FL, VIA Atomie Energy Soc of Japan, i 1pn' british Nuclear Energy Soc. London, Engl^ Canadian Nuclear Soc,-Toronto Ont, Can'et all 50- Publ by ASM, Metals Park, OH, USA p 69-72l fY- 1905l LN fj 717 0 - 2 5 3 - 3 l LA- Englishl
>: N - 03202l DT- FA~(Conference Fsper)l
)
AP E4perience at operating plants has led to questions whether the work of th.)
specialiets is sufficientiy well i .it e g r e t e d to minimi:e adverse snteractions emong a plant"s syst+ms."The Crystal River-3 event of Februari{
1960 (NUREG/CR-2515) exemplifies an adverse systems interaction.'The {
reactor power, turbine control valvo po si ti on , and ,f e e d w a t e r _ c o n t r o l s are J functionally coupled to the integrated control system, which depends upon the nonsefety grade power supply buses ^A single fa41ure in one-of the buser resulted in a stuck-open power-operated relief valve, a small loss-oq
\
coolant accidesii, and failure of one high pressure injection ~ flow indicato4 at midscale.'The Browne Ferry fire (t1UREG-0050) exemplifies a spatially 1 coupled systems interaction, which resulted i. n closure of the main. steam I isoletion valves end hindrance of the alternative supply of high pressure .
cooling water to remove decay heat.*3 reft.l DE- + NUCLEAR-REACTOR $_+ Safeguard S y s t ems ^NUC L E AR POWER P L AN T S_,P e r s o n n e l j iraining~HUtMN ENGINEERING ^PROBABit!TYl '
ID- CONTAINMEN' FAILURE PROBABillTY^NUREG-0050^ SINGLE FAILURE CRITER!ON)
.CC- 621 (, N u c l e a r Reactors)"613 (Nuclear Power Plants)*461 (Biotechnology)"
921 (Applied Mathematics)ll O
71 4
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53 Pgdn t)FT() VALVE' ;
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December 1987 Set I t ern e D e t e r i re t i o n 755 SWING () VALVE?
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December 1937 3-Set I t e rn s Description
- 755 STOP() VALVE 7 l
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WESTIliGHOUSE CZASS 3 c of i .anplete Re:ord Tagged DN- 02317::441 Elf 710lO7476) 1 WEAF MEASUREMENT OY $URFACE LAYER ACTIVATION.!
AU- A n o r. l 50- Electr Fower het I ri s t Coal Con bu s t 5yet Div Rep EPh! C5 516: May 1987 144 n{
PY- 1987l CO- EPRCD71 LA- ENGLISHl DT- RR'(Report Review)l TC- A ^( Apr li c s t i on e) 'G^ (Gener a l Review)^X^(Experimental)l .
AP- The use of surface laye r activation (SLA) -
a method employing radionuclide surface markers emitting wear g e mrn e reys - for moni t ori n g and mea su r i ng ruten4el lost in power plent c o m p o n e ri t s due to wear, erosion, or corrotion, it s, e s % r i b e d . ' T h e turbine s t op-val ve bypass valve (for solid particle erosion) and the boiler circulation pump bearing (for eb r a si on) , was ,
selected and, in laboratory testing, the radionuclides tuitable for '
activetion properties of the component ena t e r i a l s were determined."A rno n i t o r systeni to suit those properties and the c orop o n e n t geometries was developed.
Tbe study identified several radionuclides in the selected components having half -li ve s long enough to allow monitoring of valves and pumps for u r. to five years. *Moreover, in bench-scale timulations, the technique d e rno n t t r e t e d effective surfece rno n i t o r i n g from at far away at 30 in, and through et much es 10 in, of tteel.^!n one test, boron coating, which hed worn away by the second startup, did not lengthen the life of the valve.'
The accurecy of the monitor's predicted wear rates for bearing elementt i ndi c a t ed that the monitoring technique could p r o f i t a te l y be extended to other criticel rotating plant component 5.l '
+ WEAR OF MATERIALS _+ Measurements
- STEAM POWER PLANTS _ Corrosion" POWER P L ANT S_E qui pmen t ^ E ROs l ON_ Mon i t o r i ng ^ M A I NT EN AN C E ^ R AD I O ACT I V E MATERIAL 5_ Applications l 1D- RADIONUCLlDE MARKERS ^ DIAGNOSTIC M0!J 1 TORIN G' PRE DI CT! VE MA INT EN ANC E ^ IN-SERVICE INSPECTION ^ POWER PLANT A V A I L A 0 l l. ! T Y l CC- 421 (Materials Properties)'614 ( S t e a rn Power Plents)'559 (Metals C , r r o t i e r.
6 Protection)ll O
74
WESTIliGHOUSE CLASS 3
- r. of 6 C ornp l e t e h c t. r 3 Tagged J- 02186620l E10704041900l 5ERVICE FfiOPERT!EE OF THE MATEE!AL 'M VALVEi.I AU- Ivniteki, L. Ye.1 CS- All-Union Scientific fesear-h Inst of Autogenour Treatment f M-r ait, i ! ! c. t i
50- Thermel Engineering (English treneletion of 1 ploanergetite) . : n . Mer 1906 p 144-146l PY- 1986l CO- THENADl SN- 0040-60161 LA- ENGLISH{ ,
DT- JA'(Journal Article)! !
TC- X ^ ( E x p e r i rne n t a l ) ! I A E: - One of the rnost important requirements to be rnet by e .elve it to enture reliable ope r a ti on of the rhut-off or control e l eene n t . upon which depende t i ght sealing of a flow of roe d i um or precise meintenenc~ of desired control p e r e rn e t e r s .
- C h o i c e of rn e t e r i e l for these c l erne n t i must therefore be nie d e eareful1y and with al1owence for conditions of operation end the :s t r u c t u r a l features, service end technologicel propertier of the meteriale used, f: e f e d on experience of operation end the results of e x p e r i rr.e n t a l i n ve s t i ga ti oni it her been etteblished thet the bett combinetion of ter vics trorerties, required for the rna t e r i a l ! cf teeling turfacet, ie potrasted by special weer-resistent alloyt deposited o n t c. the perent metal of volv+ e l e rnen t s (clide, di t e , plug, seat, etc).'Dete on c herni c al composition and propertter of there meterials are g i v e r. . ' reft.l DE- + VALVES AND VALVE GEAR *Meterielt' MATERIALS Corrosion"EDOS!ONl
<A-) s VALVE SEALING MATERIAL 5'STOF VALVE MATERIALS l (d
E. 01 (Mechenicel De si gn)' 5 39 T h e r rn o d y n e rn i e 5 ) l l (Metelt Corrosion 6 F r o t e c t i o n ) ' (. 41 (Heat !,
A f b U
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WESTIllGHOUSE CLASS 3 O
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/b c 3f l (wplate F, cord regged .,
DN- 02f.410: 6l l l- E19609066493l l i!- WEAP ON METALS EXPOSED TO HIGH-VELOCIT/ I.TREAM 0F WET STEAM AND WATER.; I AU- Mikhailov. V. A.'Tomarov, G. V. Shelobesov. I. A.'Veril'chenko. E. G.'
Kislov, A. l.l 10- Soviet Energy Technology (English translation of Energomashinostroenie) n 12 1987 p 20-26l FY- 1987l CO- SETEDW1 SN- 0734-1024)
LA- Englithl D1- JA'(Journal Article){
TC- X^(Experimental){
AE;- Operating e<perience with heat power equipment, both in the USSR and elrewhere. confirmt a high incidence of severe weer on metal exposed to streams of water and wet steem."A characteristic pattern of wear on power equipment (wet steem turbinez. check valves and control valves, feedweter pumps) is crevice e r o si on . 'T he present article cites result 5 of a comparison of e wear process offecting structurel materials ewposed to feet water and wet steem.^9 refs.l DE- . METALS AND ALLOYS _* Wear' METALS T E S T I N G_E r o s i o n ' S T E A M_T h e rma l Effects' STEEL _ Surfaces!
JD- HIGH-VELOCITY STREAM ^ STRUCTURAL MATERIALS ^ EXPERIMENTAL PROCEDUREl CC- 531 (Metallurgy & Metallography)^421 (Meterials Properties)^641 (Heat &
Thermodynamics)*545 (!ron & Steel)ll O
O 78
.' WESTINGHOUSE CLASS 3 mb i 7 ci !? Completa 6ecord Tagged )
. p -DN- 0 2 s 17 9 N )-
( J- EIM6807-Oi!922l
,I- ! WING CHECK VALVE 0]$K i T A f: ! L I T Y UNDER TURE UL EfM E . t i AU- V a l t i,. M, S.'Horat, T.l CI- Kais1 Engineering Inc, Sugar Land TX, U$Al CT- Proceedings of tha 1988 Joint ASME-ANS Nuclear Pewer Conference.l CL- Myrtle Beach, SC. USA l j CD- 1909 Apr 17-201 .
j iP- ASME. Nuclear Engineering Div. New York. NY, U S A A N S , Power Div, La Gra'nge Part IL. USA l
!. 0 - Pub 1.by ASME, New York. NY. U$A p 23-28l F (- 190Bl LA- Engli shl CN- 11420l l DT- PA*-(Conference Paper)l )
A B - R n e_t cau?e 'investication into the f
~ _ ail _ure of taveral $ w i_ n o _ _ c h e c k v_alves ir l the feedwatir syslem at San Tenotre Nuclear Generating $tition in November 1995 resulted in the development of a generali:ed formula for mi ni mum ~ f l ow ;
velocity (V) required to fully open the disk against the backstop.*The presence of an upstream turbulence source can destabilire the disk from-iti equilibrium position against the stop even if actuel flow velocity exceeds V//m//i//n."This can cause flow-induced disk flutter _which eventually results in premature degradation and failure of the check valve internels.
This paper systematically addresses the effect of turbulence on di sk stability.*(Edited-author abstract) B refz.l DE-
- VALVES AND VALVE GEAR _+ Failure ^ FLOW OF FLUID $ Turbulent ^ DISKS Stability l
'D- SWING CHECK VALVE
- SAN ONOfRE* DISK FLUTTERI
\ 0- 601 (Mechanical Design)*619 (Pipes, Tanks & Ac c e s so r i a s)'631' (Fluid F l e,
& Hydrodynamics)^931 (Applied Physics)ll
[
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79
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, WESTINGHOUSE CIASS 3 I O of 17 Ceo.piete ;ecord Tagged Dh- 0261';95 1 4- EIMD507-0419211
' - EFFECT OF UPSTREAM ELEOW7 Off i W ! !J G CHECF VALVE FERFORMANCE.l 49- Horst, T.'Volsi, _M. i=.l CS- Velsi Engineering Inc. Sugar Land, TX, USA l (T- Proceedings of the 1988 ,1 o i n t ALME-ANS Nuclear Power Conference.]
CL- Myrtle Beach, SC, USAl CD- 1988 Apr 17-201 3F- ASME, Nuclear Engineering Div, fJ e w York, NY, USA'ANS, Power Div, La Grange Park, ll, USA l 10- Publ by ASME, New York, NY, USA p IS-21l FY- 1988l LA- Englishl CN- 11420l DT- PA"(Conference Paper)l AB- Premature degradation and failure of swing check valves can cause severe demage to the piping systems in nuclear power plants.*This p e r.e r _ p r e _s e n t s_
tha resolts of en experimental investication_ undertaken to systematicall_y explore end ouen tff y tte e (7 eg _p f u g re_am eIbows}n sw[ng]cleck v a,1 v e,
- t. c r fycA. This s t u7}yincluded varying the elbow proximity trom Dd to 2GT; all three orientations of the elbow (up, down and ho ri:ont al) ; and four different full opening angles to cover the range of angles used in different manufacturers' designs,^The results can serve as a useful gui de in evaluating a swing check valve installation and offer acceptable option; for modifications to eliminate premature degradation."(Edited author abstract) 5 refs.l
*E-
- VALVES AND VALVE GEAR _. Performance
- PIPE FITTINGS _ Applications ^ NUCLEAR POWER PLANTS _ Piping Systems l ID- ELBOWS" UPSTREAM F LOW DI STURB ANC ES AC C EL ER AT ED WE AR^ SN]NG CHECK VALVE!
CC- 601 (Mechanical De si g n )' 619 ( P i p e t. . Tank $ & Accessories)^613 (Nuclear Power Plants)ll O
80
. WESTIliGHOUSE CLASS 3 l-
; e, f 1- ;mplete b e e r. r d Tagge i n4- Q26139'.Jl
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i- E!MCs07-041920l
)- PUMP (HEfV VALVE FAltUPES IN EWP R E S ! C'U A L t'E A T_ A CMAV A L ev;trMt.,,{
T. .i . l AU- Herrmann, Ci- New York Power Authority, Lycoming, NY, USA l CT-' Proceedings of the 1980 loint ASME-ANS Nucleer Power Conference.l CL- Myrtle Deach, SC, USA l CD- 1909 Apr 17-20l SJ - ASME.-Nuclear Engineering Div. New York N(, USA"ANS, Power Div. La Grange-Park, IL, USA l 50- Pub 1 by ASME, New York, NY, USA p 9-13l PY- 1980l LA- Englishi CN- 11420f DT- PA*(Confarence Pr.per)l AB- Pump check valve failure mechanisms are often complex and represent a-unique challenge, since in many cases, the location of these check valves is critical to-proper system operation.^ Contributing ~ factors' identified at-the James A. Fit: Patrick Nuclear Power Plant included low flow operation of the System as well as e x ce s si ve flow induced turbulence and cavitation in the sy; tam upstream of the check val ve s . ^ A modi f i ca t i on to the system was made to eliminate, or reduce the contribution of the above factors to tt valve problems.^$everal non-standard epptoachee were taken during the course of modifying the fystem.^jn a ddi t i on , s y s t em reliability has bee, enhanced in a. key safety tystem.*(Edited author abstract) 9 refs.l DE-
- VALVES AND VALVE GEAR _* Failure ^ NUCLEAR REACTORS, BOILING WATER _ Piping.
, _ Systems
- HEAT TRANSFER _ Reliability" ECONOMICS l .
0- RESIDUAL HEAT
- CHECK V ALVE
- L OW F LOW OP ER AT ION ^ ANNU AL ! 2 ED COST S AVINGS l '
CC- 601 (Mechanical Design)*621 (Nuclear Reactors)*619 (Fipes, Tanks &
Accessories)^641 (Heat & Thermodynamics)^911 (Industrial Economics)ll l
l 1
r 81
. WESTINGHOUSE CLASS 3 l \
10 of 1- C omp l - t e E+. ri T3ag+i j DN- 02091000l N- EIM8806-v;,:%21 1- WATERH/iMMER F0PMULAT104 FOE fire NETWORVi WITH fHECk VALVE!.i AU- Ofown. T. D.l (5- Sendia Natl Lab, A l b u q u e r ci u e , NM, U$Al CT- Forum on Unstrady Flow - 1987 Presented at the Winter Annual Meetino of the American Society of Mechanical Engineers.l CL- Coston, MA, USA l CD- 1987 Dec 13-18l SP- A$ME, Fluids Engineering Die, New York, NY, USA'AiME, Pressure Vesselt &
Piping Div, fl e w Yor6, NY, USA l LO- American Society of Mechanical Engineers, Fluids Enginee ring Di vi sion (Publication) FE D v 6 's . Publ by ASME (PVP v 131), New York, NY, USA p 31-3 PY- 1987l CO- FEDcDLI LA- Englishl CN- 11162l DT- PA'(Conference Paper)l 40- Recently the power generation industry hat experienced waterbsmmer avant?.
which h a_v e been caused _by the pn Lrrmance of chech val ve s durinq hydrsulie
[rans1*nts, ~These waterhammer events can undermine ~the sole, dependable ~
operation of power generation plants.^]t is, therefore, necessary to understand the effects of check valves during a waterhammer transient.'In response to these events a waterhammer model was formulated whi c h has t he advantage of simpli ci t y and flexibility without numerous unnecessary options.*A basic objective of the formulation is to provide the capacity for making rimple changes to piping system paremeters and, thus, to a v the analyst to aesess de si gn or operational changes whi c h could t e us to reduce or avoid waterhammer effects,*A dynamic model for a simple swing check valve was developed in parallel with the waterhammer program for obtaining a realistic response to various system disturbances.l DE-
- WATER HAMMER POWER PLANTS _ Piping Systems ^ VALVES AND VALVE GEARI ID- CHECK VALVE 5' CHECK VALVE MODELl CC- 631 (Fluid Flow & Hydrodynamics)^619 (Pipes. Tenkt & Accessories)ll O
B2
.i WESTINGHOUSE CLASS 3
\
/-
11 a 17 :omplete A* cord Tagpa N!- 026 001 i 7- E15S060590fE!
l- HARD-FACING OF PAPTS OF r< 0 T A Fi Y CHECF VALVEi WITH POWDEP WIRE IN PROTECTIVE CASE?.l AU- Lopukhov, Yu, 1.*Eremeev, V, V.*Polnov, V. G.{
50- Chemical and Petroleum Engineering (E ngli sh translation of K h i m.i c h e s k o e i Neftyanoe Ma s hi n o s t r oeni e) v 23 n 5 - >6 M a y - J u n 1987 p 301-303l PV- 1987)
CO- CfTEAWl LN- 0009-2355)
LA- Eng),sbl DT- JA'(journal Article)l TC- A^(Applicatiens)"G^(Gtnerel Review)'X^(Experimental}l A E. - Witn the object of i nnp r o v i n g the auslity of the t'uilt-up metel'ord reducin the laboriousness of the process, work was done in selecting. the technology of mechanized hardfacing of the sealing surfaces of valves with powder w1re of 3. 4 mm diameter and with powder strip PL-AN150 of 20 multaplted by 4 mm section in flux AN-26,'and also with powder wire PP-AN133 of 2. 6 mm diameter in an atmosphere of carbon dioxide."It was established that with both methods of herd-facing the maximel tenzile stresses arise in the b u i l t - u p rn e t a l . ^ T h e tensile stresses in parts hard-faced with powder wire cre lower by a factor.cf 1. 7 than the stresses arisina.1n hard-facing with coated electrodes.^6 refs.}
DE- +vuVES AND VALVE G E A R_+ H a r d e n i n g ^ WI R E_Ma t e r i a l s ^ C A R E:0N DIOx!DE'
. ELDER;_ Applications {
ID- ROTARY CHECK VALVES *HARD-FACING ^ SEALING SURFACES ^ RADIAL RESIDUAL STRESSES ^
TRANSVERSE CRACKS' POWDER WlREl
- - 601 (Mechanical De si gn) ^ 53 5 (Rolling, Forging & Forming)^804 (Chemical Products)ii 83
i 1
WESTINGHOUSE CLASS 3 I
(w e i' 1: of l' >
_ rrp.1 - t e Aec?rd T a g ge 3 t4 g
?N- 02f?01041 N- EIMit0!-00905El I- CHECK VALVE E' E H A V 10VR U N D E F. TRIN31ENT FLOW C ON D l'10N ? ' A STATE-OF-THE nnT
~ " - - "~- ~~" ' ~' ~ ~ ~ ~ ~ ' " ~
'REVl_EW.I AU- 7hbriey, A. R. D.l C5- City Univ, Londen, Engil CT- Fluid Transients .a Fluid-Structure Interaction - 1987. Presented at the Winter Annual Meeting of the American Society of Mechanical Engineers.]
CL- Boston, MA, USA l CD- 1987 Dec 13-19l 3P- ASME, Fluids Engineering Dis, New York, NY, USA l
?O- American Society of Mechanical Engineers, Fluids En ginee ri ng Di vi si on (Publication) FED v 56. Publ by ASME, New York, NY, USA p 9;-99l PY- 1997l CO- FEDSDLj LA- E r. g l i s h {
CN- 109561 DT- PA'(Conference Paper)l AB- Recent edvances in the understandina of check valve behaviour are reviewed, it is evident that the basis now exists for providing reliable information on valve dynamics that is in a form that can be easily a s simi l a t ed and user by pipeline de si gn engineers.*The t. s e of non-dimensional valve performance curves is discussed and r e c omme n de d . 'Ma n u f a c t u r e r s are encouraged to provide t hi s data.' Design engineers are charged with the responsibility of using it and are provided with guidelines for so doing."(Author ab st rac t) 18 refs.l r, E -
- VALVES AND VALVE GEAR _* Performance ^ PIPELINE 5_ Transients' FLOW OF FLUIDS _ Pipes ^ MECHANICAL ENGINEERING Design Aids l ID- CHECK VALVE ~TRAN51ENT FLOW CONDITIONS ^ VALVE PERFORMANCE CURVES l CC- 601 (Mechanical De si gn )" 619 (Fipes, Tanks & Accessories)^631 (Fluid _Flov
& Hydrodynamics)^608 (Mechanical Engineering, General)^902 (Engineering Graphics & Stancards)ll 9
84
WESTINGHOUSE CLASS 3~ .
/\ .
1E ai 17 ,mplite F-cord T agge; DN- 0250931Jl EIB905049720L-
[( .)11-1 :- SELECTING CHECF VALVEL L
-AU- Ellis, John"Muelle, Waell
-CS-. Univ of 5trathelydej
!50- Process Engineering (London) v 67 n 11 Nov 1986 4p between p147 and 53l CD .PSEGAPl
$N- 0370-1859]
LA- English]
DT- JA*(Journal Article)l TC- G^(General Review)l AB- The authorc discuss the problems of using various data to best'advantagesi ~
~
the production of valve selection charts.^They also show how the characteristics of the piping system can in#luence'the s e v_e r i t y. o f - r e f l u x ,
(flow reversal) et a valve.'It is shown t ha t- i f t he numerical model is use together with closure test data for e particular va,1ve si e and data on.
phycical properties and di men si on e for a range of similar val ves, of different site, tnen a set of performance curves may be generated.*The authort show that the rate of change of. velocity with time (at~ the valve);
ie the primary variable used to present performance data.'A-pumping-statib layout is also discussed.]
DE- + VALVES AND VALVE GE A R_* S el e c t i on 'C H EM I C A L PLANTS _ Equipment ^
PlFEllHES_Valvee^ PUMPING PLANT 5_ Layout l ID- TILTING DISK. VALVE
- REFLUX VALVES ^ CHECK VALVES ^ REFLUX CON DI T ION ^ C LOSUR E-PERFORMANCE l CC- 601 (Mechanical Design)^800 (Chemical Apparatus & Plants)^619 (Pipes, Tank 3 & A c c e s s o r i e s ') ^ 4 4 6 (Waterworks)ll Os
-s 85-
WESTINGHOUSE CIASS 3 e
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53 7 ISOLATION () VALVE?
?DS F1-Help F2-Search F4-Format FS-Sort Set items Description 51 655 ISOLATION 02 977 VALVE?
53 7 ISOLATION () VALVE? __
?BEGIN COMDENDEX*PLUS January - December 1988 Set Items Description 75S ISOLATION () VALVE' F1-Help F2-Search
$1 655 ISOLATION S2 977 VALVE?
$3 7 ISOLATION () VALVE?
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2 of 7 Complete Record Teggea ' '
0260f310l AN- EI8607069156l TI- INTERNAL AN D ATMOiPHERIC LEALArE A!1EiiMEU' eND INTERGATE OV E fiF F Ei $UR i ? A T I ON OF ISOLATION VALVEi !
AU- Airey, D. R.' Lung, F, h. L 'M* cei'~, M. J. 5elter, i!
CE- CEGE, Southempton, Engli 50- Proceedings of the In s t i t u t i on :f Mechen cel Engineers. Part A: Fower end Frecess E ri g i n e e r i n g . 202 n ^1 10EF r JE-52!
ry- 1999l CO- PPENET]
SN- 0263-71381 LA- Englishl DT- J A' Journal Article))
TC- A '( E > p e r imen t al) (
AB- Ferearch, develppment, a n d .t._+ 5.t i n a. of iteinl+>s Yteel i sgl e t i on. ._ .- e l v e s for t rie tvreted water circuits of pressurized water r e.a c t o r s 4j ,rW R ,> 15 teinq carried cut at M a r c hw o oT Gj i ri e e r i n g . . _ .Leborator'ies (MfL).'The authors concentrete on i m p o r t e r, t generic faultt revealed by the test program end have produced theoretical modelI and experimental date in some of those erect. 'The specific topics co erad in this ceper are e dircussion of p r e t l e rn e end explenetions of intergete overpressure and gland leakage e rt 'ountered in high-pressure 9 1 be ena parellel slide gate volvei 'E ref!.}
DE- + V A ! '! E 5 AND VALVE GEAF_* Leek Detection' NUCLEAR REACTORS, PPESSUF12ED WATER _Velverl ID- 150LATION VALVES' INTERNAL LEAKAGE ~ATMO5PHERIC LEAKAGE'INTERGATE '
OVEEPRE55URIZATION!
t ,. 601 (Mechanical Design)~94? (Mechenical - Miscellaneous Mea su rin g Instruments)'621 (Nuclear Ree: tort)ll l
1 9!
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87
WESTINGHOUSE-CLASS 3 3
- [ 6 of 7 Compl'te e Recrgrd_ Tagged y ) 025404581
%d- EIMS802-0115911 TI- FEEDWATER E: L OWDOWN PIP]NG AtjD VALVE EROSION.]
U-:Orol. J o h n _^ F r e k e s , Roger l CS- Omahe Public Power Di s t . Omaha, NE,. USA l CT- Advances in Instrumentation. Proceedings of the ISAff6 Internationel Conference end Exhibit.]
_CL- Houston, TX, USAl CD- 1986 Oct 13-16l SP- ISA, Research Triangle Park, NC, USA l SO- Advances'in Instrumentation v 41 pt 3, Publ by ISA, Research Triengle Park, _ ,
NC, USA p 1445-1462l PY- 1986l CO- AVINBPl SN- 0065-2814!
BN--0-87664-951-7{
LA- Englishl '
CN- 10745l DT- PA'(Conference Paper)l AB- Pressure reduction in high temperature end pressure blowdown system induces; fleshing or two phase-flow downstream of the control velve.'The hi gh temperature blowdown water end the high flashing mixtureLvelocities_inducel the f o l l o w i r. g three problems: (1) velve, pipe, and blowdown tank target erosion; (2) control velve instebility; and (3) containment i s ol e tion volve seat leakeoe.*The purpose of t hi s paper is twofoTd: to describe '
g experiences with the three above problems; and to discuss the corrective
{/
g,, actions and practical approaches to the s ol u t i on of these problems.*(Author l
abstract)l DE-
- VALVES AND VALVE GEAR _* Erosion ^ PIPING SYSTEMS l -
ID- FEEDWATER BLOWDOWN ^ CONTROL' VALVE l CC- 601 (Mechanical Design)^619 (Pipes, Tanks & Accesseries)"641 (Heat &_
Thermodynamics)^731 (Automatic Control Principles)ll 4
c d
l 88
WESTINGHOUSE CLASS 3 7 of 7 Complete Record Tagged 02530590l AN- E10603026148{
T1- INVESTIGATION OF EFFECT OF PRESSURE CONTROL SYSTEM ON BWR LOCA FHENOMENA USING ROSA-111 TEST FACILITY.l AU- Kumemeru, Hi r o s hi ge ^ K oi:umi , Yasuo^Kukite, Yuteke*Tesake. Kenjij CS- JAER1, Tokat-mura, Jpnl 50- Journal of Nuclear Science and Technology v 24 n 10 Oct 19E7 p 044-858{
PY- 19871 CO- JNSTAXl SN- 0022-31311 LA- ENGLISHl DT- JA*(Journal Article){
TC- T^(Theoreticel)l AE- A pressure control system failure test series was conducted et the Rig of safety Assesement (ROSA)-ill test facility to evaluate the effect of_ the pressure control system on thermel-hydraulic phenomeno during a small break loss-of-coolent eccident (LOCA) of a boiling water reactor (BWR).*The break was assumed at the recirculation pump suction line."The pressure control
- ystem had ne effect for breake greater then 5%.^For breaks less then 5%,
if the pressure control system was inactive, the core wee uncovered temporerily because of the bubble collapse due to pressure rise by the closure of the main steem isoletion velve ( M 51 V ) 1_ end the fuel rod surface temperature ro h gh curing this- period. However, the peak cladding temperature (PCT), which occurred mainly during the later core uncovering by boil-off, was lower in e LOCA with pressure control system failure then .
in a corresponding LOCA with intact pressure control system ^(Edited eut abstract) 16 refs.j DE- . NUCLEAR REACTORS, BOILING WATER _+ Loss of Coolent Accident NUCLEAR REACTORS _ Pressure Control [
ID- BWR^LOCA' ROSA-3^ CORE _ SPRAY SYSTEM'$ MALL BREAK TEMPORARY DRYOUTl CC- 621 (Nuclear Reactors)^914 (5efety Engineering)ll O
89
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u efue6tF66666666666#66664#6EF446666usu6646tsvfv6##u46b46666##6##66666666666#uGV-Commend Search Dialog User interface as Audio / Visual work, Copyright-(c) 1986 Dialog Information s e r v i c e's , Inc.
Pertions-(c).1987, 1989 Digital Library Systems, Inc COMPENDEX*PLUS January - December 1988 Set items Description
?SS 5 WING () VALVE?
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h 64t6664+44666646&b6##6e+6666&&s4664666&suen tf #66466e64 64+4466644e66s64468+44
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Portions (c) 1987, 1959 Digital Library $ystems. Inc COMPENDEX*PLUS January - December 1998 L Set Items Description
?$$ STOF() VALVE?
F1-Help F2-Search S1 261 $ TOP S2 977 VALVE 7 53 5 STOP() VALVE 7
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! of 5 Complete Record Tagged '
- 026557621 AH- E i :. 312 ! ! 9 4 6 6 l Ti- D] AGNOSTIC MONITORING OF SOLID FARTICLE EROS 10N IN STEAM TURBINEi.l AU- Bellence, Charles P.1 CS- Dayton Power & Light Co, Aberdeen, OH, USAl 50- IEEE Transactions on Energy Conversion v 3 n 2 Jun 1988 p 249-253l PY- 1988l CO- ITCNE41 5N- 0885-8969l LA- Englishl DT- JA'(Journal Article)l AB- An in situ wear measurement system has been demonstrated for steam turbine applications."The diagnostic technique can measure the wear and e r osi on damage c.a u s e d by solid particle erosion (SPE) on a main steam stop valve bypass velve di sc (SVBV).^The t echni que consists of we a k I y activating t he areas on the disc subject to wear by placing the di sc in an ion accelerato beam.'The induced radionuclides emit specific gamma r e v e. in strengths safe ior personnel, but strong enough for detection.^The change in act i vit y can be accurately correlated to the amount of ercsion.^The retults of the fiel t e sting and associated economic evaluation indicate that the erosion monitoring system will allow Davton Power and Light to plan SVBV disc repiscement intervals based on actual measured erosion rates.^!9 refs.l DE- + STEAM TURBINES *Monitorinq^10N BEAMS ^X-RAY AND GAMMA RAY PRODUCTION ^ VALVE' AND V AL VE GEAR Wea g ID- DIAGNOSTIC MONITORING ^ SOLID PARTICLE EROSIONI
.- 617 (Turbines & Steam Engine 5)'601 (Mechanical Design)*932 (High E ty Nuclear & Plasma Physics)l]
O i
1 92 l
WESTINGHOUSE CLASS 3-
['
3,
- c. 3 r. wt A t a necora Tagged
.(p )~ - 025406161 V :.u- EIM;500-011749;
-TI- REAL TIME WEAP MEASUREMENT .Y5 TEM USING RADIGISOTOPE TECHN!QUE.l AU- licehansi, Firan'Blatchiey, Charles C.[
CS- Spire-Corp, Eedford, MA, USA l (T- I n s t r unie n t a t i on in the Aerospace Industry, Proceedings of the 32nd Internat1onal- instrumentation 5ymposium.l-CL- Seattic, WA. USA {
CD- 1966 May 5-81 3P- I$A, R e s e a t e r, Triangle Pa ri , NC, USAj 50- I ri s t r o me r: t e t i o n in the Aerospace Industry v 30. Publ by ISA (Advances in Test Measurement v 23), Research Triangle Park, NC, USA p. 457-4671 PY- 1986{
'0-
, IA51021 SN- 0096-72?81 EN- 0-67664-946-01 LA- Englishl
, CN- 107E51 E DT- PA'(;onferen - fsoer: 1 AB- An 3n-line diagnostic system using accelerator- induced radionuclides 1for nion t t o r i n g we a r , erosion or co r ro si on has been demon st r a t ed in a coal slurr< p i cci ng s v s t em, and two utility appli ca ti on s. ^The coal - sl ur r y -t e s t stand measurement 5 determined erosion rates for a variety of piping. shapes and si:*5. iolid particle e r o si on on a steam turbine stop valve bypass velve during system startups was measured at-one-utility,^The second
/ utility project mea su r ed bearing wear in three key components of a ' b o i .l e r
.g_ circulation pumo."These two crejects, which were conducted by the1EPRI establish the f ea sibili t y of using accel +rator induced radionuclides' to i remotely monitor small aino u n t s of wear'from key power plant components ovei
! p rol onged per iod s. 'In all of these techniques, the part to be monitored i s-exposed tc e con t roll ed high energy particle beam.'The induced radionuclides a r-e distributed in a reproducible depth near the surface of the material.'Ey detecting the penetrating gamma ra y s wni c h' l eave the operating 3ystem, i t- 's possible to pr eci sel y measure wear, erosion or corrosion because the decrease in activity is directly correlated with the loss of surface material '(Edited author' abstract) 10 refs.l' DE- + I SOTO P ES_+ Ra di o a c t i vi t y ' E L ECTR I C ' UT I L IT I E S'WE A R OF MATERIALS _Measurementsi, ID- EPR1^REAL T!ME WEAR MEASUREMENT'ON-L!NE DIAGNOITIC 3Y3 TEM ^ COAL SLURRY' FIFING SYSTEM ~ EROSION RATES" BOILER CIRCULATION PUMP l CC- 622 (Radioact1<e Materials)*803 (Chemical Agents 5-Basic Industrial Chemicals)"204 (Chemical Froducts)^706 (Electric Transmission &
Di s t r i bu t i on) ' 4 21 (Materials P r o p e r t i e :s ) l l
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'a Copyright (c) 1991, (Ei) Engineering inicrmation Inc. All ri ght s re ee r <e a, e i n1 :-
a Copyright -( c ) 1991, OlALOG Information Services. Inc. c u- All y ights reserved. No claim to original V,$. Gov *t worke. r l
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WESTINGHOUSE' CLASS 3-1 I
f .; File 5, C OMF E U D E :( + P L U 5 ( tm) t copyright (c) 1991, (Ei) Engineering i n f o r rne t i o n inc. AlI rights reserved.
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l Fortions (c) 1937, 1909 Digital Library Systems, Inc COMPENDEk+PLUS January -
December 1989 Set Items Description i
?SS CHECK () VALVE.
fi-Help F -search 51 494 CHECK
$2 675 VALVE 7
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WESTINGHOUSE CLASS 3 ;
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- 4 l'W 5i 2 of 15 "3mplete Record Taqqed
;- 02786302! .
AH- EIS9090371+55l '
TI- Check valve behavior under trensient flow conditiont: A state-of-the art review.l AU- Thorley, A. R. D.l CS- City Univ, London, Engll 50- Jcurnal of Fluids Engineering, Transactions of the A5ME v. 111 n 2 Jun 1989 p 178-1831 PY- 1989l CO- JFEGA4l SN- 0098-22021 LA- English}
DT- JA*(Journal Article)l TC- G^(General Re vi ew)'T * (Theo r e t i c al ) l AB- Recent advances in the understanding of check valve behavior are reviewed.
It is evident that the basis now exist for.providing reliable information on valve dynamics that is in a f o r n, that can be easily a s simi l a t ed and use-by pipeline de si gn engineer 5.^The us* of nondi men si on a l value performance curves is discusred and recommended.' Manufacturers are encouraged to provide these date.^ Design engineers are charged with the respon si bili t y Lot using it and are provided with guidelines for so doing.'(Author abstract) 18 Refs l DE- + FLOW OF FL Ul DS + Control ^ PUMPS Valves ^ FLUID DYNAMICS Transients
- WATER HAMMER _Controll ID- N ON- R E TURN VALVES ^ CHECK VALVE 3" FEED PUMPS l.
- - 631 (Fluid Flow & Hydrodynamics)^618 (Compressors & Pumps)^601 (Mechanical Design)^931 (Applied Physics)ll l
1 t
I 1
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96
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(' J- 027531471- i AN- El&9090911941 T]- Application _ guidelines-for check valves in nuclear power plants.l AU Anon l 50- ' Electric Power Research Institute (Report).EPRI NP.n'5479 ._ Jan 1988 372pl L
PY- 1988{
CO- ERNPD6l j r LA- English{
{
DT- RR'(Report Review)l '
TC- x ^ ( E x pe r imen t al ) l .
1 AB- Check valve failures in nuclear power plants can cause such= problems es water hammers, system overpressurization, and steem binding of pumps.* I Respondir3 to e report issued by the Institute of. Nuclear Power Operations on such failures, SOER $6-3, these guid'elines provide information ~o n c h~e c k .,
y' velve applications, limitations, and inspection techniques.-cOER 86-3 '
l- indicated-that misapplication and inadequate preventive maintenance are tb
) primary causes of check valve failure.^1n. addition, information gathered i-this project indicates that inadequate performance date from velve- ,
manufacturers contributes to the misappii;ation of check valves.^(Edited j I
auther abstract)l .
DE-
- NUCLEAR POWER PLANTS _* Valves ^ FLOW OF F L U I DS *M A INT EN ANC E 'INSP ECTION l ID- CHECK VALVES
- POWER PLANT AVAILABILITYI l CC- 613- (Nuclear Power Plants)^619 (Pipes. Tanks !. Accessories)'601 (Mechanical Design)"631 (Fluid Flow $ Hydrodynamics)^913 (Production Plenning & Control)ll
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,I 5 .o f 15 Complete Record Tagged i- 0:763104]
Au- El&9070675121
-T I - Innovetions in n o n - t r. t r u s i v e testing and trending of mo t or operated valves and check valves.l AU- Cherbonneau, S. .R."Huskys D. R.l CS- Movets Inc. Marietter, GA, USAf CT- Preprint - Ame ri c a n Institute of C hemi c al- Engi nee r s l CL- New Orleens, LA, USA l CD- 1988 Mar 6-10(
50- American Institute of Chemical Engineers, National Meeting. Fubi b AIChE.
New York, NY, USA. 37G 17pl FY- 1988l CO- ACENC9l tA- Englishl CN- 12138l DT- PA"(Conference Peper){
TC- A*(Applications)l AB- Two significent p r o b l e rn areas recently noted in nuclear power plants are the inobility of rno t o r operated velves to perform es intended and prematur.
failure! of : heck valves in service. The purpote of this report is to provide e status of testing and trending techniques which can diagnose developing dagradations in these components.'Eecause of the great difference in technique an testing motor opereted velves end check volves, this report will be divided int two mejor sections.'Section I will describe advences made in the testing of motor operated valves."Section 11 will describe innc/ations in predictive meintenance techniques for ch<
velves.'(Edited author abstract) 4 Refr.)
DE- + VALVE 9 AND VALVE GEAR *Temting' MAINTENANCE ^ NUCLEAR POWER PLANTS Auxiliary Equipmenti ID- MOTOR OPERATED VALVE"' CHECK J AL V Ei 'MOV AT5 DIAGNOSTICS TEST SYSTEMi" MOTOR LOAD 5 Y c,T E M 5AN ONO RE UNIT ,
^ C H E C K M A ,. E TEST EQUIPMENT l
.'- 601 ( M e c h a n i <. a ) Det , , i. ( F i ra e s , Tanks e A c c e s s o r i e s ) ~ 910 (Productior P l a n n i ri g ^ ' :, n t r o l , :'a sai-t. E r g i n e e r i n g ) "' 613 (Nuclear Fower Plants)lt O
98
~
.HESTINGHOUSE CLASS 3 ,
_64 f .15 Complete Record Taggea ;
i- 027629391-AN- E!0907061579l TI- Tran si ent s induced by large ch+ck valvet.[
AU 1Hau, bheng T.^Ramey, Michael P.l CS- Bechtel Civil Inc. San Francisco, CA, USAJ CT- Preprint -
American Society of Mechanical Engineers Presented at the:Winte' Annual Meeting]
CL--Chicago, IL, USA l CD- 1988 Nov 27-Dec 2l '
50- American Society of Mechanical Enginee r s (Paper). Publ by ASME, _New" York, fl Y , USA. WA/ Fell 6pl fY- 1988l CO- ASMSAal IN- 0402-1215l LA- Englishl .
! CN- 12132[
L DT- PA^(Conference Paper)l '
l' TC- X'(Experimental)l AB- The Limerick Generating Station has 60-inch diameter double-door type spring-loaded check valves at the pump discharge of the man c i r c u l a t i,n g water system.^For the design enal ysi s, it was assumed that. t he val ve s woul-close at the time of flow reversal.'It was recognized that this assumed '
closure behavior was non-conservative 'To ensure the system's safety, a field test was performed.'The resui ts indicated that the valves closed fully about 1.5 seconds after the system flow had reversed ^!n this paper, the dynamic behavior of the check valves is compared with published date.^
Transient characteristics of the system associated with the slamming of th' valves are also presented."(Author abstract) 4 Refs.(
DE- + FLOW OF FLUIDS,+ Transients
- VALVE 3 AND VALVE G E A R ' C OM P U T E F< SIMULATION l ID- CHECK VALVES l CC- 631 (Fluid Flow E Hydrodynamic 5)"601 (Mechanical Design)^723 (Computer l software)((
i 9?
WESTIliGHOUSE CLASS 3 E cf 15 Complet+ Fecor1 Tagged i- 027457341 Au- E!E.306052967l TI- Valves: Keeping the critical 14nF healthy,(
AU- Rittenhouse. R. C.l CS- Power Engineering, Tulse, OK, USAl so- Power Engineering (Barrington, I l l i n o i t. ) v 93 n 1 Jan 1989--p 20-25l PY- 1989l CO- POENA]l SN- 0032-59611 LA- Englishi DT--JA'(Journal Article)1 TC- G^(General Review)l AP- This paper deals with the probl*m of ensuring proper operation of valves a nuclear power plantr.'The authcr di s cu s se s a Nuclear Regulatory Commission.
bulletin on failures of motor operated check valves,_the use of valve diagnostics systems, the use of resistance temperature detector bypass tystems, valve improvement through project management, a new approach to '
valve packing, live loading of valves, c o b a l t - t> a s e d alloys as hard-facing materials for valves, valve leak detection techniques, valve reconditionin:
and valve r e ti v i l d i n g . ^ 4 Refs.1 DE- + NUCLEAR POWER PLANTS + Valves' VALVE $ AND VALVE GEAR Reliability l 1D- NUCLEAR POWER P L A.N T SAFETY' VALVE DIAGNOSTICS ^ VALVE RECONDITIONING l l
CC- 613 (Nuclee- Power Plants)"C01 (Mechanical Design)'619 (Pipes, Tanks &
Accessories)'421 (Materials Properties)ll 9
9 100
WESTINGl!OUSE CLASS 3
[
, 3 :. t' 16 (6mplete Fe:ced Tegged
( ). i --- 0 2 7 41 ': 0 4 l U. TI- Case of water hammer due t e- check volve ilam.l AU- Wilkinson, D. H,'Curtis, E. M.' Peke,-M.
C,l CS- CEGB, Leatherhead, Eng1]
CT- First. international Symposium on Power Plant T ran si en t s -
1987 Presented a; the Winter Annual Meeting of the American Society of Mechanical Engineers lI CL- Chicago, IL, U$Al )
CD- 1986 Nov 27-Dec 21 iP- A$ME, Flui d s Engineering Div, Fluid Trensients Committee, New-York, NY , - U? l 50- Avne r i c a n Society of Meenanical Engineers, Fluids Engineering Di s i r i on 1 (Publicat3on) FED v 67 Publ by ASME, New York, NY, USA. p 75-78]
PY- 1988{
CO- FEDSDLl LA- Engli e hl
-C N - 12047l l DT- PA"(Conference Paper)l AB- This paper describes an investigation into a water hammer problem on a cooling system caused by check valve slam occurring on the pump di sc ha r ge check valves both during automatic pump changeover or by'a pump trip when-two pumps were operating,~After the problem had been observed during'the c ommi s si oni ng o f the system measurements were taken to determine the. peak -
pressures. ^These pressures exceeded the de si gn pressure and it was decided
-to fit stronger closure springs to the check valves and t hi s was success (u in reducing the water hammer to en acceptable level,"2 Refs,l DE-
- WATER HAMMER ^ VALVES AND VALVE G E A R_Fl u i d Dynamics ^ FLOW OF
_(~Vt FLUIDS _ Transients' PIPING SYSTEMS _ Surges l fD- CHECK VALVES' VALVE SLAMMING ^ COOLING SYSTEMS l CC- 631 (Fluid Flow & Hydrodynamics)^601 (Mechanical Design)'613 (Pipeg, Tanks & Accessories)(J G(_./ .
101
WESTINGHOUSE CLASS 3- l 10 3f 15 Complate Pecord Tagged >.
!- 0:74130!!
TI- Frevention of water hommer problemi t. , limine+ing check <siv+ degrad .cn AU- kalsi. M _. 5 .J CS- kalsi Engineering Inc, sugar Land, TX, USA l CT- First International 5ymposium on Power Plant Transients -
1987 Presented a-the Winter Annual Mee ting of the American Society of Mechanical Engineers l CL- Chicago, IL, USA l CD- 1-388 Nov 27-Dec 2l SP- A5ME, Fluids Engineering Div. Fluid Transients Committee, New York, NY, U 5 r-20- American Society of Mechanical Engineers, Fluids Engineering Di vi s i on (Publication) FED v 67. Publ by ASME, New York, NY, USA. p 63-64l fY 1988l CO- FEDSDLl LA- E r. g l i s h i CN- 12047l DT- PA^(Conference Paper)l AE- Degradation of check valve inte rnal s can lead to conditions which cause water hammer in power plant piping systems.~The valve manufacturer 5, architect engineers, and the users have known for years that, in order to avoid premature degradation of check valve internals, two important conditions must be met." Data from several power plants also show that, in spite of violating one or both of the conditions, many valves still give years of trouble-free performance, whereas other valves degrade relatively quickly and cause problems.'Untortunately, no technicel information has been available in the past to predict which of the valves installed or operated under sub-optimum conditions will or will not degrade suffic' 1-to cause performance p r obl ems . "Thi s paper summari es the results of s .
recently completed research that addressed the above issue.^4 Refs.l DE- + WATER HAMMER ^ VALVES AND VALVE GEAR Degradation ^ WEAR OF MATERIALS l l
ID- CHECK VALVES' FLOW DISTURBANCES {
CC- 631 (Fluid Flow & H y d r od yn ami c s )"601 (Mechanical Design)^619 (Pipea, Tanks & Accessories)^421 (Matericis Propertie5)ll l
l 9
i 102
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f14_ or - ; f Complete R + c o r d '. T e g g e d
; - - 0 2 7 1 2 3 9 1 1--
Ana E!!i>0302 M50j
; TI- Using ultrasonias_to avoid check-velve di sa t sembl v. !
AU- Ciesielski, D. M,[
CS- MOVTS Inc, Kennesaw, GA, U$A)
, .SO- Nuclear Engineering Internatienel v 33 n 410'Sep 1980 p 42, 44-45]
i- FY- 1988l ,
CO- N E I N E. F j
, SN- 0029-5507l LA- Englishi DT- JA'(Journal Article)l TC- A'(Applications)^G"(Generel Reviev){
l AB- While check velve failures have become a significant. concern in the nuclea, industry, the actuel percentage of valves that have failed 'other s 't han see leekage) has been small.^Using a diagnostic system based on ultreronics, i~
l is.possible to test valves for in st abili t y, thereby avoiding extensive
,. d e si on review efforts and unnecessery dismantling.'The procedure is l reviewed in this a r t i cl e. ' Cha ra c t e ri s t i c s of the CHECKMATE system, which l was developed by MOVATS Incorporated to provide positive ider.tification of-l the smell number of check valves that are octually unstable,-are presented' l (Edited author abstract)l
! DE- ' VALVES AND VALVE GEAR _* Nondestructive Examination' NONDESTRUCTIVE' EXAMINATION _Ultrasoni: Applications!
ID- CHECK-VALVES' DIAGNOSTIC TESTS" CHECKMATE SYSTEM
- VALVE INSTABILITY l CC- 601 (Mechanical Design)'619 (Pipes, Tankt & Accessories)*421 -(Me t > riels Properties)'422 (Ma t e ri al s Testing)'753 (Sound Technology & Ul t r a soni'e s )
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, File 9, COMPENDEX*PLUS(tm) e U L n Copyright (c) 1991 (Ei) Engineering Information Inc. All rights reserved. a n v u Copyright (c) 1991, DIALOG Information services, Inc. a n All rights reserved. No claim to original U.S. Gov't works. =
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Fortione (c) 1987, 1989 Digital Library Systems, Inc COMPENDEX PLUS January -
December 1989 Set items Description
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1 of 2 Complete Record Tagged 02819083[
A.- EIM8911-039081l TI- Velve testing and development in the laboratories of the tWu group .
- Siemens AG.l AU- Simon, U.^Dernbach, D.!
CS- Siemens AG, Erlengen, West Gerl CT- Selected Papers'from the 13th MPA Seminer From the serie Safety and Reliability of Pressure Components!
CL- Stuttgart, West Gerl CD- 1987 Oct 8-9) 50- Nuclear Engineering and De si gn v 112 Mar 1989. p 229-2411 PY- 1989l CO- NEDEAUl SN- 0029-54931 LA- Englishi CN- 12245l DT- JA*(Journal Article){
TC- X^(Experimental)l
" i AB- In nuclear power plants, valves meke up the largest number of active ex components.'Velve failures contribute to safety-related events and to nuclear power plant downtime.'KWU together with plant operators end velv+
manufacturers have therefore made increasing efforts to improse velve performence, pa r t i vul a rl y through e x p e r i rn e n t a l qualification et velve teet facilities.'Newiy-developed velves are qualified by type tests.
Hypothetical accidents such as ATWS and main steem pipe breaks have been modeled et full-scale test facilities, and the as specified performence -
safety velves and mai n steem isolation valves has been demonstrated experimentally."In-service testing end maintenance using a valve service system developed by KWU, whi c h is conducted in close cooperation with the power plant operators and the velve manufacturers during plant operation end sc he dul ed ou t age s further improve velve reliability and safety over the entire service life of the plant,'(Author abstract) 11 Refs,l DE- + VALVES AND VALVE GEAF +Testinq^ NUCLEAR POWER PLANTS Velvest ID- TEST F ACILITI E5'S AF ETY RELATED VALVES)
CC- E.19 (Pipes, Tanks & A c c e s s o r i e 5) 601 (Mechenical Design)'613 (Nuclear Power Plents)ll O
105
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v n Copyrignt (c) 1991 DIALOG Information services, Inc, e n All rights reserved. No c l a i rn to original U.$. Gov't works. a h Fe6 46&f # # 66ss +6se& #6tf e e&664 ts&66+& 6+66e d bef t #6666etse64E4 4# &&&&4 򢰪 h.
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WESTI!!GHOUSE CLASS 3 l 10 of 02 Complete R e c :.r d T e g cm d 02916040l A iv - E I M 9 00 6 - 0 2 ; 01 '; l TI- Feedwater erstem wetarhemmer e n -s l v 4
- AU* Vim. H. T.l C$- General Electric Co. Een J:t . IA, UiAl CT- Trentient T h e r ro e l - H y d r e v l i c t i n Vettel and floin; i.yetem! - F r e t e r. 9 e d et the 1999 A$ME F' r e t s u r a Vessel! end Firinq C :. n f e r e n c + 1 CL- Honolulu, Hl. USA!
CD- lii?9 Jul .:-;'l RF- ASME, New York. !J y , USA 1sME, To6yo, usa!
50- American Societs u. Mecheni;el Eneineers, Pretture Vercelt end Firing Division ( F u t.11 c a t i o n ) FVf .- 156 !929. p 11-10!
PY- 19 f:9 l ro- AMFPDEl SN- 0277-027) )
LA- Engliehl CN- 12635l DT- J A' ( Jou rnal Articie)I 10- T ~ ( T h e o r e t i c a l ~e l A (' - A h y d r o d y n e rni c eneIv31! Of the ietdweter !yttem w e t e r h e rnm e r e/ent1 whi c h occurred at c Er iling Wet <r Reector ( E:WR) plant wet p e r f e r rne d u : i ri g a w a t e r h e mro e r anelytii computer program. The program is formulated LSted on the en e t h c. d of cher6cterietTc! and include! e d y n e rr. i c model for e timple chech velve which providet e c e p e t. i l i t y of ttudying a wa t e r h e rom e r caused ty check velves.'The enelyset involved studying a h y d r o d y n e tni c interection of
^
pumpe end c hec k v e t v e t- in the feedwater t y ? t e rn during a hydraulic trenti initteted t. y the opening of e p urno ditene;gt velve 'Cy enelvticellv Eimuleting the cpaeting conditions which resulted in waterhemmer, the root cause of the w a t e r h e rnm e r wee determined."Aleo, corrective meerures to esoid recurrence of these events were identified 'The enel y si! presented in t hi i paper demonstretet usefulnet: ef a computer method for the ttudy of check ve1ve-eeused w e t e r h e rnm e r p r o ts i e rn t in e I1 quid-fii1ed complex piping 5y5 tem in nuclear power plant (Auther etatrect) 1 Ref.I DE-
- WATER HAMMER *Analysi! IEEDWATEF PUMP, Hydrodynamiet NUCLEAR REACTORi Trentient! ~FlP!NG .L i i i E M i C oropu t e r Aided Anal y ri t ]
!D- CHECE VALVE RESPONSE'Di$ CHARGE FFESSURE FEEDWATER F UMF f " H Y DR AUL I C TRANS1ENT5l CC- 631 (Fluid Flow & H y d r o d y n a mi c t ) ' 61 t- (Compressort & Fampt) 621 (Nucleer Reactort)'E19 (Fisset, Tenk i Ac:esceriet) '2. ( i. o n,:. u t e r ioftware)lj O
111
p WESTINGHOUSE CLASS _3 13 of 22 Complete Record Togged
) b289Ca?Bl
- E '. 9 0 05 0 5 ) L 01 1 TI- Dynernic world of velve testing.l A 1.i - Rittenhouse. R. C.I to- Power E ngi n e e r i n g (6ertington, Illineit) v 94 n 1 Jen 1990 p 18-2){
PY- 19901 {
CO- POENAll i SN- 0032-5961{
LA- E ngli s h ]
DT- J A' ( Jo u r rie l Artiole)l j
TC- X'(Experimentel)I
]
A0- All eyes in the world of nuclear p c+ + r plant valves ere, o r' should-be, l focuted on changes i ts testing and testing r e qu i r erne n t s .
- A renewed hi gh ]
1 evil of releted eativity, much of it t,e h i n d the scenes, is r e p o r_t e d _ i n : the halls of the Nuclear Regulatorg Commirsion (lGC) and the Anie r i c an . Gooi e t y l of Mechanical Engineers (ASME). Actions relating to val ves: in_ f os sil pcw r :
plants also_ere evident." Regional worksheps already have reduced confution over t es ting st enderds and rulee through increased dialog between the NRC, ASME end the power ganeration industry.*However, one of the nio s t - p r odu c t i ve mejor events in this regard was the ASME/NRC Symposium on loservice Testing of P urno s 6 Velves, held August 1-3, 1989, in Wa s hi n g t on , D. C . "T hi s forum considered, among other things, stroke t i rni n g of tefety-related power-operated velves, the detection of pump and valve degradation, a l t e r n a t i v'e nonintrustve techniques for velve inspection, t_ h e d e v a l e. n tn e n t of e_ check velve t e s t _rrie__t_ h o_d o l o g y , valve designs for foss1'I_ plants ure'd ior load
'c~iTling duty, velv M 14ebility improvement through live loading, and-replacements for esbestos e s- e velve materiel
_ V-
^6 Refs.[
+ ELECTRIC F0WER PLANTS
- Valves ^ VALVES AND VALVE GEAR Testing-INSPECT!ON_Standerdsl- ..
1D- POWER PLANT VALVE TESTING # IN-5ERVIC C TEST!NG'V ALVE TESTING ST ANDARDS*
NONINTRU51VE TESTING TECHN]QUE!{
CC- 61) (Nuclear Fower Plants)"614 (Steem Power Plants)'619 (Pipes. Tanks &
Accerseries)"913 (Production Flanning & Control)~902 ( E n g i n e e r i_ n g Graphics & Standerds)ll t t
(
-112 .;
w we- w m a-- ,yw4-, ---w4y-wwew~ w
WESTIllGHOUSE C& ASS 3 14 of 22 C ernp l e t e Record Tagged D;i76 57i A iv - EIMs0D3-011799i T 1 - Wa t e r - h amme r prediction in cheet velse eauirped c i p e l i r.
- uitng l u ro p e d -
p a f eine t e f fnethod.l AU- Coverroni, E. isobode. J. V.1 C5- Concordie Univ. M o r, t r e a l , Que, C a r. ]
CT- 5tructural Vibration end Ac ou st i c s Frerented at the 19 M ASME De t i an T*chnical Conferencer - 12th biennial C o r. f e r e n c e on M e c h e n i c t; l Vibretiot, and Notte{
CL- M o ri t r e e l . Que, e r, {
CD- 1989 Sep 17-211 '
iP- A5ME, Design Engineering Div, New York, NY. USA!
50- Arne r i c a n io.iety of Mechenical Eneineers, De s i gn Engineering Division
( P u b l i c e t t e r. ) DE v lk-: . Publ b, A rne r ' c e n 50c of Mechenical Engineers (A!ME), New Yeti , NY, USA. p 9-151 PY- 19091 CO- AMEDEHl ,
tA- Englishl CN- 12730j DT- f A ' ( C o n f e r
- r. c e reperil TC- i (Theor*ticalj!
A E. - T hi s paper deel: with the model of velve equipped pipelinet tuitable for predletion of weter-hemmer p h e r. o rn e n e . ' T h e pipe 1ine nie d e l io bemed on the l u rnp e d - p e r a m e t e r methced rather then on the traditional method of cherecteristics, which providet the model with a festibility and user-f riendline s t. The model it suitable for both compressible and i n c ornp r e t t i b l e fluid.'The p e ri e r elto shows the approsch te incorporeting velving element! into the piping t y t t e rri model.' Finally, a case study of a vertical pipeline equipped with a flow-reversel treventing check valve is presented.'(Author ebitrect) E Refs.1 DE-
- f I F E' l l N E S +Velves' VALVE $ AND VALVE GEAR Hydrodynamics" FLOW OF F L U I D S_C ornp r e s e i o l e "M A T H EM A T 1 C A L MODELS" WATER HAMMER l lb- WATER HAMMER F RE DI C T ION'US ER-FRI ENDL IN E S 'L UMP ED F AR AMET ER METHOD' FLOW E E V E F, 5 A L ~ C H E C F VALVE INCOMfRESSIELE FLUID l CC- E19 (Fipes, Tenke 2. Accettoriet)"6D1 (Mechenical De ti gn)' 631
& Hydrodynamics)'931 (Fluid Flow (Applied Phytier)ll 0
113
WESTIllG110USE CI. ASS 3 i
s . 10 of 22 C c tr.p l e t e Record Teoged (i20709491 EIMiz00?-011491l T1- On the p e r i o r rne n c e of t. e 1 ) cbecf se1v*! j AU- He r nen de t -Gel ete , Jose L . ' I' v e n d i e . Eduardo!
CL- In t de investigaciones E l a - t r i c a r, . Me<1co citv. Mex CT- Geyser - Three Deceder of Ac hi e v erne n t : A Window on the futurel CL- Santo Rose, CA, ULAl CD- 1909 Oct 1 41 50- T r a n r e c t i c.n t - Ge o t he r nie l Petource? :c uncil + 1 '. . Fut1 ty Ge o t he r n,e 1 herourcer Council, Davie, CA, usa o E?r-!;01 s
FY- 1909l CO- TGRCD7l
$N- 0191-0933l LA- Engliehl C lJ - 127011 DT- fA-(Conference Feper){
AD- Dell check velves are used to stop water f r orn entering the s t e e rn pipeworkt tyrtem of g e e t h e r rn a l i n t i c l 10 t i on s . 'lic we v e r , f r o rn the very be gi nni no of fheir ute, it has been frequentiy found that they do not consistently cperate et it wet expected. A deteription it given of tettt performed on trentparent ru o d e l t using air water mi,turer to f i rnu l a t e s t e e rn w a t e r flows, it it shown that the original design of bell check val ve s i; based on e r, eversimplified conception of the way ga e -li qui d mi r t u r e s behove end the varioue a l ernen t e added to i rnp r o v e itt operation cannot rn e k e the eouipment function any better.'The authcre suggest inst ead en c l e r rn t y t t e rn , with the pottible eddition of a u t orn e t i c interception velvet instelled in the s t e arn maint. '(Edited author obstract) 4 Refs,l
-
- GEOTHERMAL WELLS _+Velves'VALVEi AND VALVE GEAR _Performancel ID- LA.LL CHECK VALVES'OPHERICAL V A L V E ' V A L V E O P E * /4 T I OlJ ANALYSl$j CC- 461 ( Ge nl o g y & Geophytict)^615 (Thermeelectric & Other Power Generatore)'
- 04) (Heat i T he r mo d y n erni c s 1 ' 601 (Mechanical DetignJll 114
- . _ . _ -. _- - - -. . - - - - - . - - ~ - - - - - - - - - - -- - --
WESTINGHOUSE CIASS 3
- i 19 of 22 ( o rnp l e t e Recced Tegged 0 2 6 ' 2 0 .1 1 l ,
An- E!9002020:401 !
TI- Invertigation of earthquake resistance of pipe fittsngs.)
/t U - korolev, $. F . ' Z h e rn o v , E. A . ' U t F t r. , A. G.l
$0- C h eroi c a l and Fetroleum Engineering ( Engli s h translation of Khimichestoe i Neftyence Mashinottroenie) v 24 r. 2-4 Nov 1668 r. 119-121l CO- CPTEAWl LN- 0009-230Dj LA- Englicht E)1 - JA*(Journal Article 1l T C - A ' ( E x p e r i rn e n t a l ) l
/s t; - T h e I.I.Lepee design organization L e n p r o rr a rrr.a t u r a has developed e procedure for t e s t i n g p i re e fittings for e a r t hqua k e- r e si s t anc e . "I t layt down the scope, composition, and order of the tests to tr e conducted with a view to c o n f i r tni n g the e tr i lity te maintain their s t r e r,9 t h , air / water tightnett, and fitness fer cperation unoer reismic loads, as well as to determine-the-n att.re l frequencies a n d ma x i rnurn accelerations under the same conditions.
Slide valves with pneumatic, hydraulic, and electric dri ves; bellows-type valve 5 with oneumatie a ri d electric drivee; t. e l l o w s - t y p e valves with electric drives; flat check valves; regulating valve; a 'i d safety valves were tetted.'The resulte show that the dynamic coefficient may ettain significant values (k//d equals 20-34) for some-typet of pipe fittings with large rnarret (more then 300 Lg) and nominal inside diameters (exceeding 200-rnm ) . particularly valves with electric, pneumatic, and hydraulic drives.'l Ref.]
*FIPE F1TTlhG$_* Earthquake Re si stance'V AL VES AND VALVE GEAR,_ Testing l 4
DYNAMIC COEFFIClENTS'RE50 NANCE FREOVENCIE5]
CC- 619 ( P i r. e s , Tanks & Accessories)"605 (Small Tools & Haraware)*484 (Seiemology){l l
[
i I
1 l
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115
= . _ .__ _ _ . _ -_ _ a
WESTING!!OUSE' CLASS 3 p ,
20 of'22 Complete Reccrd Tagged 029470061 EIM9001-001508l T !- Anal ysi s , testing, and optimization of check velvet.l AU- Weisebeupl. H. Echauk1, N.'Breddy, R,l CS- tiemens UD KWU, Karlstein, West Ger[
CT- Pipeline Dynamice and Velves -
1969 Presented et the 1989 ASME Pressure Vessels and Piping Confereneel CL- Honolulu, H], U$Al CE>- 1969 Jul 23-271
'5P- J5ML, Tokyo, Jpnl
$O- American Society of Mechanical Engineers. Fressure Vessels and Piping Division (Public a ti c n) PVP v 180. Publ by Arne r i c a n 50c.of Mechanical ,
Engineers (ASME), New York, NY, USA, p 119-123l '
PY- 1999) ,
CO- AMPPD0l SN- 0277-027xl LA- Englisht .
CN- 12635l DT- PA'(Cenference Paper)l TC- G (General Re vi e w)' X * ( E x pe r in>en t a l ) {
AE- C he c k valve performance het become a mejor concern in the operation of noclent power plentt,^ Computer progroms especielly developed to enely:e tb
~
dynamic behcvior and interaction between valve end system ellow optimi etion of the eritical velve partc.'The methods.used are qualified based on ' t e st r during plent startup, laboratory tests on speciel designs.tc F verify certain p a r erne t e r s , and integrel t e s t e ,
- Di sc stability during both operation and portial lood can be achieved by maintaining a sufficient belance between disc openino end closing forcee.^Leektightness after
__ closing can be achieved by appl ying a tufficient closing __ force.l DE- .VALVfE AND VALVE GEAR,,,+0ptimi:etion^P! PING SYSTEMS Pressure Reoulation' ,
NUCLEAR POWER PLANTS.,, Pressure Vessels l _
lD--CHECK VALVE P E R F ORM AN C E ^' P R E S SUR E SURGE LOAD ^ DISC STABILITY'LEAKTIGHTNFSSI CC- 619 (Fines. Tanks & Accessories)^944 (Moisture, Pressure & Temperature, &
Radiation Measuring instrumentsl'61? (Nuclear Power Plante)ll ,
h
'L
+
L t
116_ e
. _. . _ . __ _ _ _ . _ __ _ _. . _ .- ~
WESTIllGHOUSE CLASS 3 11 of 20 C ompl e t e Record Tagged 00i4034Et AN- EIM9001-000340!
T1- Lipeline Dynamict end Velves - 1909.I AU- Aggerwel, M. L. (Ed. )'E:ekoye, L. I. (Ec. ) !aleem, M. A. (Ed. )
C5- Onterio Hydro, Toronto, On', C e r; !
CT- Pipeline Dynen ic s and Velves - 1989 Fres*nted et th- 1989 ASME Pretrure Vetsele end Pipi ng C onf erence )
CL- Honolulu, H1, USA l CD- '909 Jul 2S-27{
SP- J5ME, Tokyo, Joni 50- American Society of Mechenical Engi r ee r s , Pretture Vessels and Piping Divition (f ubli c a t i on) PVP v 100 190". Fubl by American Soc of Mec hani c el E n gi r:e e r t (A5ME), fl e w York, NY, U '.- A . 123pl FY- 19091 CO- AMFPDS1 54- 0277-02771 LA--Englisbl CH- 126?5l DT- CP'(Conferense Proceedings)l TC- G'(Generel Review)'T'(Theoretical)"X (Esperimentel)\
A E: - T h i t conference proceedings conteint 18 papert 'The mein topics d '. s c u s s e d are: dynamic performance of pumps in a two obese system; v i b r e t i o r. enelvsis of p, ping subjacted tc loading; pipe vibration end clearance check 5 during CANDU NPP commiseioning; dynamic !trese end vibretion ve1ocity, i1ew stabil,ty in piping s y st ems ; vibration acceptance criterie of circular cyIIndericeI she111; on-1ine pipe fIaw monitoring; mispositioned intermediate supports and stability of continuous pipe; vibretion/meerurement of hydrogen quench lines; residual stresses in nuclear reactor pressure tubes; ped-reinforc-d nor-les in pressure vessel heeds; steedy-stete hydraulic profiles in di sc ha r ge piping; safety / relief velves; checi volves; spring loaded safety relief velvet subjected to back pressure.]
DE- 'P!PELINES
- Vibrations' NUCLEAR POWEP FLANTS Piping S y st ems
- SAFETY VALVE 5' PIPING SYSTEMS Pretsure Reauletion^fRE55URE VES EL5'FLO.4 QF FEUIDS Pipet' iD- P R E O P E Fi A T I O N A L FEEDER PIPE VIERATION^M15P051TIONED INTERMEDIATE SUFFORT' FLAW LT AP!L ITY'P AD REINFORC ED NOZ2 L E S'CHECL V A L V E 5 '- E l R E V l CC- 619 (F1 pes, Tenks & Accessoriet)'931 (Applied Physics)'613 (Nuclear Fower Plante)'914 (5efety Engineering)'944 (Moisture, Pressure &
Temperature, & Redietien Meesuring Instruments)'631 (Fluid Flow a Hydrodynemics)}}
9
-117
_.__._._m._._._ . _ . _ _ _ . . . . . _ _ . _ . . -
WESTINGHOUSE CLASS 3 - ,
t r
20 of 22 Ccmplete Pecord-Tagged 02641;221 E 1 ?> 0010 0418 3 l ,
TI- B ac k f l ow protection for water supply to fire eprir.iler t',rtems,}
AU- Higgins, Patrick ?.^fellence, Julius A.[
CS- P.J. Higgins C. Associetet Incl 50- F l unibi n g E n gi ne e r v 17 n 6 Jul-Aug 1989 p 40-42, 4f-47l
- PY- 19B9]
Co- VL ENEa t SN- 0192-17111 ;
LA- Englithl DT- J A '- ( J o u r n a l Article))
.TC- A'(Applicotion!)l AB- In the absence of antifree:e or other hazardous chemicals in 3 sprinkler s y s t e rn , e double check velve arsembly it en appropriate means of bec k f l ow rrevention from the 5tandpointt of reliability and l e r 5. pressure 1oss, Water conteined within e-fire sprinkler system constructed cf black steel pipe is now classified or nonpotable.'The question erises, What -l e ve l o f-backflow protection ie necessory between the fire sprinkler aystem and the potable water supply? At the pretent time, sprinkler systems are t ypi call y l
isoleted from the p o t e ta l e weter supply by e single check valve.'However, e '
single check volve has never been r e c o g rii t e d by any ttandard as being an ecceptable backflow preventer.{
DE-
- FIRE FIGHTING EQUIPMENT _+$prinkler 3vstems VALVE 9 AND VALVE GEAR'PlPE, CAST !RONl ID DOUBLE CHECK VALVE A$5EMBLY"FOTAE'LE WATER' BACKFLOW FREVENTERl 914 (Mechanical Design)"619 _(Pi pe s , Tank: &
(Safety Engineering)"E01 Accessories)^545 (Iron & Steel){l l
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l, c .' o p y r i g h t (c) 1991, D I A L QC, I n f o r tn e t i o n Servio*s, Inc. !
j- a All rights reserved. No claim te original _U.$. Gov't workt. i
! e4+4ea6&ee+&ae444++644#44eeeete466t#E&seeveh&6+46st#f4&ese##ehet64664see+#ffs 1 i j Commend b e e r r: h ;
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TI- Etratificat1cn itguet and asperience in o r.
- r a t i n g p o w e r plants.I AU- Itrauch, F, L.~Rearty, Lt . H. Faluremy, t. .l
'" ! - fJ uc l e a r and Advanced Technology Div, P i t t s ti u r g h , PA, USA (
Cl- High P r e r t.u r e Te c hnol og y , fracture Mechanict, and Seevice Esperience in '
Dperating Power P l s r. t 5 - Prerented at the 1990 Fressure Vessels and Piping Conference l CL- Nashville, TN, USAj CD- 1990 Jun 17-21{
'i P - ASME Fressure Vessels 6 Piping Div. New York, NY, USAl 50- American bociety of Mechanical Engineere. Pressure Ve s sel s and Piping Divition (Publication) PVF v 192. Publ by American S ci c of Mechanical Engineer! ( A S M E 'i . New York, NY, U$A. p 05-91l PV- 1990l CO- AMf f Db l 1N- 0277-027:.[
LA- Englishl lN- 1357!(
DT- f A' (C onf e rence f'eper)l TC- T^(Theoretical)[
AC- Th1a paper pr o vi de s e background of recent pipe cracks which have occurred in commercial nuclear power plants and have led to the itsuence of NRC Oulletin 68-08.'Specifically, these cracks occurred in unisolable sections of piping and were attributed to fatigue resulting from thermal stretification and cycling, which in turn resulted from valve leakage Utility response to the bulletin is summari:ed, and details of an evaluation which addresses the issue are provided.^(Author aLstract) 15 Reff.l DE-
- NUCLEAR POWER PLANT 5_eTnermal Effects"PIPlNG 5VSTEMS_ Cracks ^ VALVES AND VALVE GEAR teak Detection ^ NUCLEAR REACTORS. LIGHT WATER Transi+nts# FRACTURf-MECHANIC 5_Analytisj
!D- STRATIFICATION IS?UES^NRC BULLETIN 88-08^EEAKING ISOLATIOfJ VALVEsl CC- 61.; (Nuclear Power P l a n t s ) " 619 (Pipes. Tanks E. Accessories)^621 (Nuclear R e a c t c. r s ) l l O
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@ AN+ 'EIM9001-QOjr,Qf,l TI- Testing of safety-related valv+e cf 8WR ord EWR power plants.1
. AU- S i rno n , U . '- R a u f f en e n n , N . " sc ha f e r , H.{
CS- Siemens'AG, Verlstein, West Gerl CT4 ripeline D y n erni e s a n d Valvec -
1985 Presented at the 1989 ASME Presture Vessels and P i p i ti g C o n f ' r e n c e l
- _CL- Honolulu, Hl. U3Al
- /.D- 1989 Jul 23-27{
sP- J5ME, Tokyo, Jpol 50- American 50ctely of Mechanical. Engineers. Pressure Vessels and F;iping-Di vi si on (Publication) PVP v 180. Publ by American Soc ~of Mec hani c al-.
Enginee r s (ASME), New Vork, NY. USA. p 37-92-j PY 1989l (0- AMPPD5l 'j SN- 0277-027Xl ;
LA- Englishi [
CN- 12635l ;
DT- PA"(Conference raper)) ,
TC- T.^(Th+eretical)^X"(Erperimental)l ,
AB- New valve de si gn s for Siemens-KWU nuclear power plants are qualified at valve test stands.* Typical velve tett results include.the.qua,lification of ,
gate valves in steam and in cold and hot water; steam safety velves of-BWE' and FWR primary end secondary' ride; in s t e a rt , water, and two phase' flow; i main steam isolation volver, both gate and globe types, under' pipe break conditione.'To maintain-.the high quality ef velve design, in; situ-diagnostic-testing is performed in the p'wer plants during outages ~end, to ;
- e. lesser-extent, during operation.*(Edited author abstrect) 3 ' Re f s . l-DE- +' SAFETY VALVES _* Testing
- PRESSURE VESSELS _ Safety ValvesrPOWER P_ L AN T S Prersure Vessels" VALVES AND V ALVE _ GE AR Reli abili t y l ID - IN SITU DIAGNOSTIC TESTING" GATE VALVE 5^ MAIN STEAM ISOLATION"VALVESI CC- 619 (Pipes. Tank s L Accessories)"914 (Safety Engineering)^614 (Steam-Power P1 ant 5)l{
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- 0 n Copyright (c) 1991. DIALOG Information Services, Inc.
n All rights reserved. fJo claim to original U.S. Gov't_ works.
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a- 03.40407l AN- EIM9111-057621l T!- Potential application of neural networks to nuclear power plantr.l AU- Uhrig, Robert E.l C :. - Univ of Tennessee, Knoxville, TN, USA l l ET- Proceedings of the 53rd Annual Meeting of the American Power Conference ( l CL- Chicago. IL, USAl CD- 1991 dpr 29-May !! l
;P- Illinois Inst of Technology l ,
i, 0 - Proceedings of tha American Power Conference /r. pt 2. Publ t. y Illinois '
inst of Technology, Chicago, IL, USA. p 946-951l PY- 1991l C0- PAFWA2l CN- 0097-2120l LA- Englishl ;
(N- 14976l DT- PA'(Conference Paper)j TC- A'(Applicetionz)'G'(General Review)l AE- Application of neural networks to the operation of nuclear power plant is '
being investigated under a U.S." Department of Energy sponsored program at the University of Tennessee. [1] Projet.ts include the feasibility of using neural network: for the following tasks: (a) d i a g t.o s i n g specific abnormal
- conditions, fb) detection of the change of rno d e of operation. (c) signal validation, (d) monitoring of check valves, (e) plant wide moni t or i ng u sin.
autcessociative neural networks, (f ) modeling of the plant thermodynamie ,
(g) emulation of core reload calculations, (h) monitoring of plant parameters, and (i) analysis of plant vibrations.^Each of these projem and its status are described briefly in this article.^The objective of each I
of these projects is to enhance the safety and performance of nuclear plants through the use of neural networks. (Author abstract) 9 Refs.l DE- . NEURAL NETWORKS _* Applications' NUCLEAR POWER PLANTS l ID- L 1 AGNOiT!C $ " MONITORING l
.J- '2? (Cemputer S o f t wa r e ) 613 (Nuclear Power Plants)ll l
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\ .AN+ E1M9103-u!1006l i T!+ Fission product transport in the reactor coolant svStem for a spectrum of ,
interfacing system LOCA scenarios.]
AU- Warman, Edward P.'Metcalf, James'Hestian, Robert Jr.*Donanue, Michaell CS- Stone f. Webstei [ngineering Corp, Boston, Ma, U$Al CT- P r oc ee di ng s of the International Centre for Heat andl Mass Trensferj ,
(L- Dubrovnik, Yugosil-CD* 1989 May 22-201 .;
SP- UNESCO'Carleton Univ, Ot t awa"Do r i s Kidric Inst of Nuclear i:iencez, i Delgradel 50- Fission Product Transport Processes in Reactor Accidents Proceedings of th-International Centre for Heat and Maes Transfet, Pubt b y Hemi sphe r e Pub 1 i Corp, New York, NY, USA, p 329-338l FV- 1990l CO- PCHTD41 SN- 0272-800Xl tA- English)
-CN- 13959j DT- PA-(Conference Paper)l TC- G*(General R e v i'e w ) l
-AB- One of the most important potential s. e v e r e accident sequences for any "
pressuri:ed water reactor (PWR) is a loss of coolant accident-(LOCA),.or:V '
sequence, in one of the interfacing systems."An ini ti all y described in-the i Reactor Safety $tudy (WASH-1400), interfacing system LOCAs involved.the-failure of check valve 5 in emergency core cooling systems-(ECC$), but coul6t also. involve the reridual heat removal (RHR) systeme *The check valves protect the low pressure portions of these systems from the high pressures of the reactor coolant system (RCS) to which they are connected to provide cold leg injection."This paper addresses the retention and transport of ,
fission products (specifico11y, Cs!) in t h e__ R C G in V-sequence scenarios ^1*
summarires some of the major differences between models.r}}