ML20024A685
| ML20024A685 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/15/1983 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML20024A680 | List: |
| References | |
| REF-SSINS-6820 IEB-79-01B, IEB-79-1B, NUDOCS 8306220055 | |
| Download: ML20024A685 (507) | |
Text
{{#Wiki_filter:. TABLE OF CONTENTS-O SECTION 1 EQUIPMENT QUALIFICATION REPORT REVIEW RECORDS SECTION 1.1- KERITE CO. CONTROL CABLE, FR INSULATION SECTION i.2 KERITE CO. 1KV POWER CABLE,. SPLICE AND TERMINATION #39-69 ' SECTION 1.3 KERITE CO. 1KV POWER CABLE, HTK INSULATION , i SECTION 1.4 KERITE CO. 5KV POWER CABLE, HTK INSULATION
. SECTION 1.5 CONTINENTAL WIRE & CABLE CO. INSTRUMENT AND THERMOCOUPLE EXTENSION CABLE SECTION 1.6 ROCKBESTOS CO. CONTROL AND T/C EXTENSION CABLE SECTION 1.7 BIW CO. CONTROL AND INSTRUMENT CABLE SECTION 1.8 GOULD CO. MOTOR STARTERS SECTION 1.9 WESTINGHOUSE CORP. FAN MOTORS TYPE LLA SECTION 1.10 VALVE MOTORS OPERATORS, LIMITORQUE CORP. REPORT NO. F-C3271 SECTION 1.11 VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. B0003 SECTION 1.12 VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. 600456 SECTION 1.13 VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. F-C2232
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SECTION 2 MATERIAL AGING ANALYSES
~
TABLE l COULD MOTOR DIVISION - FAN MOTORS
~ TABLE 2 WESTINGHOUSE CORPORATION - PUMP MOTORS
~ ' ~
FABLE 3 ELECTRIC MACHINERY CU. PUMP MOTOR 5' TABLE 4 GENERAL ELECTRIC CO. - PUMP MOTORS TABLE 5 ALLEN-BRADLEY CO. - LOCAL MOTOR STARTERS AND CONTACTORS TABLE 6 ALLEN-BRADLEY CO. - MOTOR CONTROL CENTERS TABLE 7 MULTI-AMP CORP - STATES TERMINAL BLOCKS TABLE 8 KERITE CO. TERMINATION TYPES T-1NS-HT AND T-5NS-HT-B&W COMPANY, EVALUATION OF AGING OF CLASS 1E INCONTAINMENT < CONTROLS AND INSTRUMENTATION FOR B&W-177FA SCOPE OF SUPPLY DOCUMENT NO. 77-1127001-00. O Geert/Comonmeou 8306220055 830615 PDR ADOCK 05000302 , ; p PDR 1 j
TABLE OF CONTENTS (CONT'D) SECTION 3 SUPPORTING DOCUMENTATION , i SECTION 3.1 GOULD INC. ELECTRIC MOTOR DIVISION, LETTER DATED OCTOBER 8, 1980 SECTION 3.2 ELECTRIC MACHINERY COMPANY, LETTER DATED SEPTEMBER 15, 1980 SECTION 3.3 GENERAL ELECTRIC COMPANY, LETTER DATED SEPTEMBER 10, 1980 SECTION 3.4 ALLEN-BRADLEY CO. BULLETIN 798, CONTROL CENTER SERIAL NO. 967929 NON-METALIC COMPONENT LIST SECTION 3.5 MULTI-AMP CORPORATION, STATES DIVISION, LETTER DATED i SEPTEMBER 17, 1980 SECTION 3.6 EXCERPTED SHEETS FROM THE " ENGINEERING COMPENDIUM ON RADIATION SHIELDING," VOLUME 2 SHIELDING MATERIALS, SHEETS NO. 309-317 SECTION 3.7 IEEE TRANSACTIONS ON ELECTRICAL INSULATION, VOLUME El-8,
- NUMBER 2, JUNE 1973 (m) '%' SECTION 3.8 UNDERSTANDING ELECTRICAL INSULATION LIFE, BY JEROME M.
FRANK, SORGEL ELECTRIC CORPORATION SECTION 3.9 EVALUATION OF AC MOTOR INSULATION SYSTEMS BY IEEE-275, WESTINGHONSEELECTRICCORPORATION SECTION 3.10 AN ARTICLE ENTITLED "A NEW TEMPERATURE INDEX: WHO NEEDS IT," MODERN PLASTICS, SEPTEMBER 1970 SECTION 4 CHEMICAL SPRAY EVALUATION AND ANALYSIS SECTION 5 LOCAL CONTROL STATIONS FAILURE ANALYSIS CRITERIA 13
\_/
Gdbers / Commonwealth ii
-- - p. _
N O SECTION 1 il EQUIPMENT QUALIFICATION REPORT REVIEW RECORDS M k O O Gdhert/Commonsseith
.-- --.. ~. . - _ . - - - . .- .. .. - . . _ - _ - _ .
1, 1 f 8 a d i SECTION 1.1 I r " F
- KERITE CO. CONTROL CABLE, FR INSULATION 4
A 6 t P I i i ( l b. f f. i Gdhert /Commanuseth , 3 f i- - - . . - . - , _ . , _ . . _ . . _ . . . _ . . - . . , . . _ _ . . - . , - , - _ . _ _ , , _ . , . . _ , , . , , , , , _ . ,__,.,_..,.._,_...,_..,_..__.,.._,.,-...-___v.
j.h 4.
; CRYSTAL RIVER UNIT 3 GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No.
Originator D.M. A4 C.tN 71RF Date 1hs,)12 Revteuer l$. IE. EJ2Ed3CN-Date 4 h } ?3 i i YES NO 4.1 Testing to'LOCA conditions inside containment adequate? / 4.2 Equipment qualified to service conditions outside M/A containment? 5.,1 Qualification method identified? 5.2 Each test requirement addressed? 5.3 .Is qualification method other than testing adequate? M/A 6.0 Margin requirements add'ressed? / 7.0 Aging requirements addressed or replacement schedule / established? 8.0 Documentation adequacy addressed? y y p 4 >^u' 4 W Supervisory Reviewer Date "b
- .- - - _ . _ . _ . _ _ . , , _ _ _ _ , .- . . _ . . . . . , _ ~ _ . _ _ . _ . , _ _ , _ _ _ . _ _ _ - _ . . . . _ . . ~ . _ _ . _ . , , _ , _ _ _ - . . - . _ , . . . . _ _ , . . . . ,
FLORIDA POWER CORP. CRYSTAL RIVER UNIT 3' REVIEW RECORD 01B Equipment Description Kserrr contrea1. canos (h r# msuz m , f M'/** % c u d Spec. No. Reviewer (name and date) D.K.. M CLv sea. 1//g/PL l Review Summary: 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment (1) vo Did the equipment temperature and pressure profile completely envelope the accident profile? Yrs- Ree.c p-c 4 olo- t s1 tsecer 5.3 o If "NO", see
-(2) do Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure? Yes. r -c.mo.: sect 5.2 4 AM. E (3) So Is~the equipment submerged during a DBE? Na o If "YES", is it qualified?
O c4) w 2 19 c t c a ce ci -ic 1 7 ce aitie . < ita vect to PPM of boron and spray pH) which are equivalent to or greater than l those expected for a DBE? m - F.C. 4oln-l ,ssc r s.2 j s. 4, + 3 l 4.2 ., Service conditions outside of containment y/,, l (1) o Is equipment identified as being necessary to mitigate a HELB7 i l o If "YES" is it qualified to Service Conditions (temp., press., humidity)? f '(2) o Is equipment identified as being necessary to mitigate a LOCA? l l o - If "YES" is equipment in an area where fluids are recirculated from l' inside containment to accomplish long-term core cooling following a LOCA? l. o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radiation? t- , -(3) o If equipment is not served by redundant HVAC systems p wcred from onsite emergency sources, is it qualified to environments resulting from loss of HVAC? O . e
I REVIEW RECORD 01B h '5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
- a. Test, rws. rtst P tn Es_st-3 2.3 'll P an A. 4. 3
- b. Analysis,
- c. Both test and analysis,
' d. (Other),
'5.2 Qualification by Test o Operability monitored during test? Yrs FC 4oa.o-l s ac r -4,5. f l . 5. 2, ev ~
4.2. 4.3 s . V . Twt c a 4 arc r r. o Test results demonstrate operkbility? Ws- srcy 6.3. 4.4 rAmt z 3 & l ster ~1. or sc. c ou- l o Test chamber environment envelopes service conditions? ws Fc 4o2o-1, sten r.: . S.3 M A PP. B. o Is equipinent qualified to operate as required for the time necessary to perform its safety function? Ws - sct. samtre, rat. -wrri
- o Test specimen same as equipment being specified? vrs_ sc.s.oao- Sec r 2.
t rea ren. i_rr rcac or + turn men N,H. Oost r. m.t ourR
-o Test sequence as specffied? ws_ s:c 4.ao.1 3e er 3. ( s.
'o Was . the same sample tested to service conditions? ws. giu...m., s ange n-_
ca um en e u s . F e. soso.1 Ftc.1. Stc.T 3 4 Sat., G. o~ Test Failure Criteria established? Ws FC +oac-f sact .i o Test Equipment accuracy requirements' addressed?N.y proverov - <tmu n.c snap ts maan ou c a.s. pusormauet ne reoute (<nr wituim e cairrara Amod o Equipment mounting and electrical or mechanical seals represent speci-- fied installation? m -r T> ce.fiu tor 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? No cre A o If "Yes", does the calculation satisfy postulated service conditions.
- 2. Is equipment qualified by analysis for effects of chemicals on the 4
enclosure, gaskets, and seals? N/A o If "YES", does the analysis satisff postulated service conditions. e . O 4
, , - - , r.. , , - - . , - - - -,v,,y.-, ,n-c,-,-,,w.,,me,_,. ,-,,,-,y-e. , awe--,e.,-m,,-,-,,,.m.,,.n _c--s.- . .-_____ -
4 REVIEW AECORD 01B 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? % s o -Were the guidelines of Section 5.2 above satisfied? ws o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +150 F _ o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10% o Volt: 110% of rated
- o Freq.
- 15% of rated o Time: +10% of time required following a DBE o Environmental Transients: Initial and dwell at peak temperature applied
'twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING o Was aging considered in equipment qualification? w . FC4ou-f
- stor L,2.3. 4.t l' .
o' If "NO",' have materials susceptible to degradation from thermal or radi~ation aging been included in aging list? - o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? - 8.0 DOCUMENTATION o Data is pertinent and auditable? ws: Ruoa r FC,4o2o-l manca . igns Documentation supports qualification method? ws i o l l O
ATTACHMENT 1 g POWER DIVISION - RE ADING PAGE I OF
/
DESIGN VERIFICATION RECORD A. PROJECT FILIN
, 4WA L P D Grc UWW 3 i CDDE SU BJ ECT: Pc5T Accr M ur 'c u t' D u o C 7aA /t/> fct:
(Qrmes W O' M ' TC/' CG A cEnrrE 6CO V 7c w& v Couvece C4 swr SECTsON N AME AND NUMBER S. s, n oacar- M E. os&c ORIGIN ATOR PROJECT ENGINCER THIS CALCUL ATION CONTAINS ASSUMPTlONS REOUIRING L ATER CONFIRM ATION-NO r/ YES P AGE (S) A COMPUTER PROGRAM WAS: USED (CERTIFIED P .R COMPUTER APPLICATIONS MANUALI NOT USED USED (NOT CERTIFIED BUT VERIFIED PER CAM) COMPUTER CODE: REVISION. VERIFICATION PACK AGE (IDENTIFY EACH ITEM OR GROUP OF ITEMS): DOCUMENTS TO BE VERIFIED g3y 8)(62/d??L - [&W/G" $c W dif4ff 7c1/7- AV/rA'W 77/'[ ggy , h (2) 28*##VI'dD- ,REV. (3) ,REV l h (4) ,REV (S) , R E V. (6) , R E Y. SUPPORTING DOCUMENTS g,, 7/Tt;P 7C /Mr* ff J//McA!/th 'htt/He2C , g e y. ggy INE IW 8 YAI M WYW/W ,REV. (3) ,REV (4) ,REV (S) , R E V. l (6) , R E V.
- "4N$ Y Y - /J/53 ORIGIN ATOR S SIGN ATU RE { 'OATE B. NO VERIFICATION REQUIRED PER DCP 2.05, PARAGRAPH 2.2:
PREVIOUSLY VERIFIED DESIGN: FILING CODE: DATE OF VERIFICATION VERIFICATION REQUIRED (CHECK METHOD (S)): g DESIGN REVIEW ALTERN ATE CALCUL ATION OUALIFICATION TESTING IDENTIFICATION OF VERIFIER /VCL. iu 4. TELA 5.R. h
-- ._ 0 TRO7ECT ENGIN EER $ SIGN ATU R E # O AT E G Al 468 R E V. 52 -82
PAGE 2 GF c C. CONCURRENCE WITH SELECTION OF VERIFIER (S):
~
SECTION M AN AGER'S SIGN ATURE ___ V-/f-f 3 DATE l > D. EXTENT OF YERIFICATION: Ov% %AOtW ed As s i+ tit / 0 0 .191 8 c/ TAJ g u o u RESULTS OF VERIFICATION: Ya% d asM m L 00 o Rc85 A&t 40$0/r sGhlr~iu Na w OAn W i y l 4 I l l l ATTESTATION: THl$ DE51GN VERIFICATION WAS PERFORMED IN ACCORDANCE WITH DCP 2.05. h%~ '/
'OATE S
VERIFIErt'$ SIGN ATURE [ E. PROJECT ENGINEER REVIEW AND APPROVAL: PROJECT ENGINEER'S SIGN ATURg TE l l
1
, KERITE 600V CONTROL CABLE, POST-ACCIDENT TIME DEMONSTRATED k
PURPOSE: The purpose of this calculation is to determine the post-accident time period for'which the Kerite 600V power and control cable is qualified. This time period will then be compared to the post-accident time period required. METHOD The general approach will be to calculate the post-accident time period with i the temperature of the actual post-accident environment. This calculation will transform a given time and temperature to a longer time period at a lower temperature. The slope of Arrhenius plot in attachment will be used as a base. This method uses the Arrhenius data for a purpose other than its original intention and may not have a completely sound basis; however, it is the best approach for using the available information. f3 i
\- UNITS t - time in seconds, hours, months T - Temperature in' C, K, F t
REFERENCES
'l. KERITE CO. - ARRHENIUS PLOT FOR HT KERITE INSULATION 2.- KERITE CO. - ARRHENIUS PLOT FOR FR INSULATION AND FR JACKET
. MATERIALS
- 3. POST-ACCIDENT OPERATING TIME REQUIRED, FROM SYSTEM COMPONENT
, EVALUATION WORKSHEET.(6 MONTHS). l O Geert/Commomseeth l
4 REFERENCES (CONT'D)
- 4. POST-ACCIDENT TEMPERATURE 150 F, FROM FIGURE 4-6 0F QUALIFICATION
SUMMARY
FOR FLORIDA POWER CORP., VOLUME 2. (79-01B)
- 5. FRANKLIN INSTITUTE RESEARCH LAB. FINAL REPORT NO. F-C4020-1.
t
- 6. KERITE ENGINEERING MEMORANDUM f's 178A (5/1/79) & 178B (12/1/77)
ASSUMPTIONS
- 1. The basic assumption is that Arrhenius line given for pre-accident thermal aging can be applied to a post-accident time / temperature combination. It is assumed that the slope of the given line can be J
used anywhere on the log t versus 1/T plot. The slope will be calculated. h f-~g 2. Qualification smnmary, volume 2 (ref. 4) shows temperature 150 F after 10 seconds. It is assumed that the Post-LOCA temperature remains constant at 150 F for the duration of the operability time of 6 months. This assumption adds a certain conservatism to the calculation since some decay of'the temperature below 150 F is , expected. I CALCULATION Arrhenius theory of thermal life states that the log of time is directly proportional to the increase of the absolut'e temperature. Therefore, the slope will be calculated using two points on the given plot on page 7 (ref. #2). l 37, ,_ A log t t = time in hours . A1 . o y T = temperature in K rO ,~ Geert/Commoneenth i
CALCULATION (CONT'D) Point 1 t g = 16000 T1 = 95 C = 368 K Point 2 t 2 = 100 T2 = 168 C = 461 K Since 16000 hours in circulating air oven is equivalent to 40 years'of service we can write. t 1 = 40 years = 350400 hours Tt = 95 C = 368 K 350400 X 100 hours = 2190 hours T2 = 168 C = 441 K t2= 16000 H 350600 tg _ log 2190 2.2 .
-Slope = loa -
= = 4890.87 1 -1 1 - 1 4.5 X 10-4 T-1 T2 368 441 The test report F-C4020-1 states that tested cables maintained their rated electric loads for up to 58 days of the simulated LOCA exposure. After 6 days the temperature remained constant at 212 F until cable samples could not hold their electric loads and were removed from the loading circuits.
I The objective is to compute the time period at the post-accident ambient temperature of'150 F that is equivalent to test time period of 54 days of
- 212 F. Using the assumption and the computed slope of Arrhenius plot, the t
[ following equation can be utilized to compute the time / temperature 1 l- equivalence. 1 A log t = m X A 7 m = slope
) T = temperature in K log = m X (T
, t = time in hours Geert/Commonussith
CALCULATION (CONT'D)
- ti = time unknown t2 = test time 54 days = 1296 hours T1 = Post-LOCA ambient temperature 150 F = 65.56 C = 338.56 K T2 = Post-LOCA test temperature 212 F = 100 C = 373 K m = 4890, 87 t 1 1 log -t = 4890.87 X (338.56 - 373 tt , g,33 log 1296 tt'= 1296 (101 33) tt = 27708 hours = 1154.5 days CONCLUSION s_- The critical post-accident operability time demonstrated is 1159.5 days at ambient temperatures of.150 F. Comparing the result with 180 days of required equality time a substantial margin exists. Therefore, the equipment is sufficiently qualified for post-accident operability time.
The. calculation was prepared for Kerite cable with FR insulating material. HT materials are considered qualified as well since the test results and i parameter are more favorable, as shown on previous pages (ref. #6). Pressure i affects were not considered because after the accident the pressure
' approaches the atmosphere.
8 (:) Geert/Commanussith -
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. . ARRHENIUS PLOTS FOR KERITE (,@M FRINSULATION AND FR JACKET MATERIALS ISSUED g .m pU _A - 40 Yea.r .End of Lif.e Surface. .T. e.mperature fo_r. ..K..er. ite - - .
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_EM 178-B Attachment 1 Y . ARRHENIUS PLOT FOR HT KERITE INSULATION ' ii "A-40 Year "End-of-Life" Surface Temperature for Kerite
'.BTJustified HTK Surface Temperature (1200 .--J.--- -'
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- SECTION 1.2 4
1 1 , I h i KERITE CO. IKV POWER CABLE, 4 , ' SPLICE AND TERMINATION f39-69 , [ 1 ! I I I t O
13. CRYSTAL RIVER UNIT 3 GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. OriginatorM./(, /4'2NCRE Date
]h&//1 Revteuer B.t?. exEAukW Date 9/ y/f3 YES NO 4.1 Testing to LOCA conditions inside containment adequate? /
4.2 Equipment qualified to service conditions outside A containment? . 5 . ,1 Qualification method identified? 5.2 Each test requirement addressed? 5.3 Is qualification method other than testing adequate? M/A 6.0 Margin requirements addressed? [ 7.0 Aging requirements addressed or replacement schedule / l established? 8.0 Documentation adequacy addressed? COMMENTS: Supervisory Reviewer Date ui-o
~ % FLORIDA POWER CORP.
CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B
. Equipment Description Kre t-rE I LV ben. CA w r Svu eL 4 Tame'* o b 9-69 Spec. No. Reviewer (name and date) ~'D. K. M 'INTHtE. ~7- 14-62 Review Summary:
4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment (1) o Did the equipment temperature and pressure profile completely envelope the ' accident profile? Ya<;- Fat REPen r F c +020-2 Fic,14 St.cT 4 3 ; o If "NO", see (2) o Has equipment been tested for normal radiation over the equipment life, plus the-DBE exposure? W 5 FC. 402 o -1 suc-r 6..t 4 ADO. 6 (3) o Is the equipment submerged during a DBE? wLa o If "YES", is it qualified? (4) o Has equipment been tested to citemical spray conditions, (with respect to PPM of boron and spray pH) which are equivalent to or greater.than those expected for a DBE? M s F-C - 4020 -l ,S ac r K a_ t L 3 4.2 Service Conditions Outside of Containment (1) o Is equipment identified as being necessary to mitigate a HELB? l o If "YES" is it qualified to Service Conditions (temp., press., l humidity)? (2) o Is equipment identified as being necessary to mitigate a LOCA? o If "YES is equipment in an area where fluids are recirculated from l l inside containment to accomplish long-tem core cooling following
- a LOCA?
I o If it is required to mitigate a LOCA, is equipment qualified to 1007, humidity, the required temperature and pressure, and expected radiation? (3) o If equipment is not served by redundant HVAC systems posered from i onsite emergency sources, is it qualified to environments resulting from loss of HVAC? l-l_-_, --m _ _ _ _ _ - . _ _ . . _ _ _ _ _ _ . . . _ _ _ , _ . _ _ . _ _ _ , _ _ . _ , , _ _ _ _ _ __ _ , . _ _ _ , __ _ _ _ _ _ _,
REVIEW RECORD 01B 5.0 QUALIFICATION METHODS-5.1 How was equipment qualified and where was its method justified? a . :- Test, ' rype vesi Tosymso w rere_323 1: RAu 4.3
- b. Analysis,
- c. Both test and analysis,
. d. (Other),
5.2 Qualification by Test . o Operability monitored during test? %.s FC, 40 Ao 2 ,sse.y 4.5. s.i F.A
- s. 4_ c .2. c . 4 . -nn ts. ~4 1 .<;tc.T 1 o Test 'r esults ' demonstrate operability?ws . i: c. 4o2o-1 srcT 4.3 6.c.
-rAmm. 3 4 5 ner '7 o Test chamber environment envelopes service conditions? Ygs F C - Aolo - R
=, ac.r 5, A A App B o Is equipment qualified to operate as required for the time necessary to perform its safety function? Yes Srr 5079 SHT 1 o Test specimen same as equipment being specified? ws - <ma e ra_- = u-a s 4 -as-ra ( w. a nosa. v. neonced & Tamiammo N r rmo n s_ m. cA / A ms;p).
o -Test sequence as specified? Ws . F e. *oao .1 s uc-r 3.o a 5.o o Was the same sample tested to service conditions? m . smc., um e.t co unmoo s F t4eno-a, fig 1 4 Srn 3.ts, o Test Failure Criteria established? w r. FC 4oJo- a st.cr 1 Test Equipment accuracy requirements addressed? N.T Psam eter. hu ssAT,ou
~
o is m A+ ou c.nass penirttuncor e op tessusui (ot %ta r. -acto 4 Awv$ o Equipment mounting and electrical or mechanical seals represent speci-find installation? N/A e 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? w. ( te o' If "Yes", does the calculation satisfy postulated service condit16ns.
- 2. Is equipment qualified by analysis for effects of chemicals on the
- enclosure, gaskets, and seals? w /a o If "YES", does the analysis satisfy postulated service conditions.
9
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7+ , i 1 j ' REVIEW RECORD 01B , i e
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- 6. 0, , MARGINS
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.' o . Were the guidelines in Sections 4.0 satisfied? Ms '
,o Were the guidelines of Sec. tion 5.2 above satisfied? w s r
o If "YES", no further margin information is needed. . y o If "NO", docuent tid,folloUing margins: i o Temp: +15 F' ' ' _ o Press.: +10% gauge, but not more than 10 lb F/in' i '; o Rad: +10% o Volt: +10% of rated - U -o Freq.: + _5% of rated _
+10% of time required following a DBE
.J. o Time:
- ~' o Environmental Transients
- Initial and dwell at peak temperature applied
\. twice E \ , o Vibration: +10% of response spectrum at mounting point 7.0 ,
AGING 4
- o. Was aging..cansidered in equipment qualificationi n g - ,,.a eter (tN3.4s~A
) -
o If "NO",_have' materials susceptible to degradation _from thermal or radiation aging been included in aging list? - / o Have maintenance and replacement schedules been established for equip-p'k mecc not meeting life' time aging qualification? --
- . . .1
"'~ y, , 8.0 DOCUMENTATION ~ j g. y / o Data is portinent and auditable? ws. Am. a.aporer Pc +oao-a wrt.n 3/m5 -' o Documentation supports qualification method? Yes { I l
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KERITE - 1 KV POWER CABLE SPLICE REQUIREMENT Para. 5.2 "Is equipment qustified to operate as required for the time necessary to perform its safety function" (6 months). . CONDITIONS The cabis splice in subject performed adequately for the 100 day planned duration of the test. At the time the test was performed, the 100 day period was thought to be adequate to meet or exceed the requirements for typical plants. ANALYSIS The splice in subject passed the 100 day planned duration of the test. There is no reason to believe it would not have passed after 180 days also. The test conditions are materially more severe than the CR-3 accident environment and it is reasonable to assume this would have aided the test sample in meeting extended performance periods. - The 100 day qualification time is therefore' considered adequate. I l
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, , the kerite company
.s April 22, 1982 GIIbert/ Commonwealth RECEIVED P.O. Box 1498 Reading, PA 19603 APR 2 81982 ATTENTION: MR. M.E. OBER M.E.OBER PROJECT ELECTRICAL ENGINEER gg, . g g Gentlemen:
SUBJECT:
CRYSTAL RIVER UNIT #3 FLORIDA POWER CORPORATION RE: TELECON H. OBER/R. FLEMING, 10/6/81 LETTER SEPTEMBER 11, 1981, M. OBER LETTER MARCH 1, 1982, T. GARBINI TELECON T. GARBINI/R. FLEMING, 3/29/82 & 4/1/82 We are providing the following reports and Information to update yot.r qualification documentation file. Cable or Termination Report l IkV Control Cable F-C4020-1 1 IkV Power Cable F-C4020-2 F-C4020-2 (materials tested in splice 38-69, 39-69 Terminal same as 39-69) 33-74 (Special Terminal) I-R975-01 (materials tested in spilce S-5NS-NUC, same as 33-74) Kerite Tape Type Terminals are quallfled by comparison with qualified splices using simliar designs and Identical materials. The 39-69 terminal
. corresponds to Spilce 38-69 covered in FIRL Report F-C4020-2, while Terminal 33-74 corresponds to Spilce S-5NS-NUC coverd by Isomedix Report I-R975-01.
Note--the copy of print 33-74 (Special) returned to Kerite with your letter
. has Bishop Bi-Seal 3 tape included in instruction 2 as an approved equivalent to Bishop W962, this note was not added by Kerite and certainly Bi-Seal 3 is not an approved equivalent to W962. A copy of print 33-74 (Special) is attached.
The following is a IIsting of Kerite Kit' materials and corresponding manufacturer designations: O
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Gilbert / Commonwealth April 22, 1982 O Karite Kit Manufacturer Designation Bishop Bi-Seal 3 Bishop BI-Seal 3 (see section 1 for comments on this tape) Bishop W962 Bishop W962 , j Kerite Friction Tape Karite Friction Tape ' l i Glass Electrical Tape Permacel P212 Glass Electrical Tape (not Scotch 27) Silicone Rubber Tape Scotch 70 Sill' cone Tape l The Bishop BI-Seal 3 tape has been subjected to radiation and maintains l Its physical properties up to 0.1 megarads of exposure. Similar information i on Scotch 33+ is no longer needed per Tom Garbini. [ The purpose of both terminals is to provide a lug seal to prevent the cable from breathing during normal thermal cycling allowing moisture to ! collect in the conductor strands. The Bishop W962 tape will maintain its Integrity during 40 years of normal service (both thermal and radiation aging) and a LOCA accident. The Bishop BI-Seal 3, as stated in earlier conversations, starts to revert at radiation levels above 1 megarad (0.1 includes safety factor.) Therefore, its performance cannot be guaranteed ( at levels above this, but our Judgement is that it will still adequately seal the end of the cable. The reports provided are CONFIDENTI AL, and as such, should not be copied or dupilcated without permission from The Kerite Company. Please acknowledge receipt of this package by signing the Duplicate Copy of this letter and returning it to the undersigned. Received By . . . - l Title AdPf' . u Date: ZWW 1 . ! Yours truly, THE KERITE COMPANY From the office of: E.N. Sleight Vice President - Eastern Region G u;/) s, Signee: J[l.aQl.u. N. H. Dube n Administrative Sales Assistant NHD:ss Enclosures pl.' '9#j
. - - - ~ .
f I O t b SECTION 1.3 [ KERITE CO. IKy POWER CABLE, HTK INSULATION I s } } l O , i Gdtert/Conmenneen
. j, g^s CRYSTAL RIVER UNIT 3 Q
GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. Originator D.N. 41'TN8/L6 Date ,f t s/tz. Reviewer [> /(. EAGUC& Date 4/ 6 /13. I i YES M 4.1 Testing to LOCA conditions inside containment adequate? [ 4.2 Equipment qualified to service conditions outside YA containment? 5 . ,1 Qualification method identified? O 5.2 Each test re2uirement addressed 2 5.3 Is qualification method other than testing adequate? 6.0 Margin requirements addressed? 7.0 Aging requirements addressed or replacement schedule established? 8.0 Documentation adequacy addressed? COMMENTS:
" SVkro 2 0 -
Supervisory Reviewer Date
\
GdbertICommonwea th
FLORIDA POWER CORP. p V CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B Equipment Description kEftpTE /kV Rn44 cagy [%y yrw musuu s,sm orund Spee. No. . Reviewer (name and date) 3 E #8JArrrRE 7-/K-s2 Review Summary: 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment . (1) o Did the equipment temperature and pressure profile completely envelope the accident profile? Yts - str REPoer rc-doto-2. Fl(. IJ Sect 5,3 o If "NO", see (2) o Has equipment been tested for normal radiation over the equipment 4 life, plus the DBE exposure? )EE - FC4010 2 AM. 8, SEtr S. 42,S.3,7d TABLE I Is the equipment submerged during a DBE? MO (3) o i o If "YES", is it qualified? ( (4) o Has equipment been tested to chemical spray conditions, (with respect to PPM of boren and spray pH) which are equivalent to or greater than those expected for a DBE? YIts -FC de20-2. ser s. 9.3,s.3, s.4 l 4.2 Service Conditions outside of Containment (1) o Is equipment identified as being necessary to mitigate a HELB?
. o If "YES" is it qualified to Service Conditions (temp., press.,
humidity)? (2) o Is equipment identified as being necessary to mitigate a LOCA? l o If "YES" is equipment in an area where fluids are recirculated from l inside containment to accomplish long-term core cooling following i a LOCA? j o If it is required to mitigate a LOCA, is equipment qualified to l 100% humidity, the required temperature and pressure, and expected i radiation? (3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC7 O
= .
REVIEW RECORD 01B O- , l 5.0 QUALIFICATION METHODS l
" 5.1 How was equipment qualified and where was its method justified? l
- a. Test, rypt ysw :rmspie Pga f rar ,3 n .t4 W -ga. +,3 l
- b. Analysis, i I
i c. Both test and analysis,
- d. (Other),
f 5.2 Qualification by Test l l l l o Operability monitored during test? Ygs- Fe. 4oao-a ' scc-- 4.0 E.I. K.:L 4,4 c . A. 6. 3. c.4 -ra m tr_ S d str.T 7 ! o Test results demonstrate operability? vts- FC 4oao- A s ec.T 6.3,6.4 ! -r. at,_ a 4 sEcir 7 o Test chamber environment envelopes service conditions? vrs- FC 40:o- 0. s ster s'.1 4 ape G i o Is equipment qualified to operate as required for the time necessary to perform its safety function? m- sEs. sove. sutt, .1 o Test specimen same as equipment being specified? Yss. SEE. F C 4 o-l1o-1 O o
- 2-Test sequence as specified? vcs- Fe,4oso s s.c,T 3.e 45.o o Was the same sample tested to service conditions? vas-seernrd se Mes_ l capacei as FC403o- A fig 1. 5 E.c,T 346 o Test Failure Criteria established? ves- p e_ *a.no-1 <ne 1 o Test Equipment accuracy requirements addressed? N.T - Permant-h eie Afgu
.is aAsso ou Mton Pensioni.uuie r_ o, tecimmer C we smtoo s camie A Anow).
o Equipment mounting and electrical or mechanical seals represent speci-fied installation? N,/ A . 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? No e rse o If "Yes", does the calculation satisfy postulated service conditions.
- 2. Is equipment qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? u/A o .If "YES", does the analysis satisif postulated service conditions.
O
REVIEW RECORD 01B
. 6.0 MARGINS' l
o Were the guidelines in Sections 4.0 satisfied? M s o Were the guidelines of Section 5.2 above satisfied? as o If "YES", no further margin information is needed. .. o If "NO", document the following margins: l o Temp: +15 F _ l o Press.: +10% gauge,_ but not more than 10 lb F/in' l o Rad: +10% o Volt: 110% of rated o Freq.: 15% of rated !' o Time: +10% of time required following a DBE o Environmental Transients: Initial and dwell at peak temperature applied twice o Vibration: +10% of response spectrum at mounting point 7.0 -AGING o Was aging considered in equipment qualification? Ylrs- Fc.4oao- A
- S Scr .1 2. 3. 4 O A If "NO", have' materials susceptible to degradation from thermal or . o radiation aging been included in aging list? -
o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? - #A l 8.0 DOCUMENTATION o Data is pertinent and auditable? yss c c 4 eao-a "Dxts b M Nte.H A 75 o Documentation supports qualification method? w t i i I ( O .
p XERITE POWER CABLE d REQUIREMENTS Para. 5.2 "Is equipment qualified to operate as required for the time necessary to perform its safety function." (6 mos.). CONDITIONS All power cables in the test performed adequately for the 100 day duration of the test'. At the time the test was performed, the 100 day period was thought to be adequate to meet or exceed requirements for typical plants. ANALYSIS All samples passed the 100 day planned duration of the test. There is no reason to believe they would not have passed after 180 days also. CE) The test conditions are materially more severe than the CR-3 accident environment and it is reasonable to assume this would have aided the test samples in meeting extended performance periods. The 100 day qualification time is therefore considered adequate. l l G C) - ddbert/Commesseeth
?
( ! SBCTION 1.4 KERITE CO. SKV POWER CABLE, HTK INSULATION a f I 4 i ', f 4 L f 4 i 1 I I r 1 i l I I l l 1 4 t i + t !=, Geert /r-% i
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s CRYSTAL RIVER UNIT 3 l s 1 l GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. Originator 6. f. 6'040v7' Date r1/2a/yt Reviewer E. d. EM9? sow Date aff, Jn YES NO ! 4.1 Testing to LOCA conditions inside containment adequate? 4.2 Equipment qualified to service conditions outside N!4 containment?
/
5 .,1 Qualification method identified? O 5.2 Each test requirement addressed?
/
5.3 Is qualification method other than testing adequate? N/4 - 6.0 Margin requirements addressed? 7.0 Aging requirements addressed or replacement schedule established? [ ' l 8.0 Documentation adequacy addressed? COMMENTS: ,
& Mce A M s l
1 l Supervisory Reviewer ; Date O i
' Gdbert /ConnonweatLh
l FLORIDA POWER CORP.
^
CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B Equipment Description KeeirE Edb/ POWit ddNE /HrK p/. ruler 7&/ A/S CE F2 .MdEGT) Spec. No. Reviewer (name and date) 3 I ###00'7' /f/tO/Bf-Review Summary:- , 4.0 SERVICE CONDITIONS 4.1 IDCA conditions Inside containment' , (1) o Did the equipment temperature and pressure profile completely envelope the accident profile? FG I-R 975 -O/ N13 o If "NO", see (2) o Has equipment been tes_ted for normal radiation over the equipment life, plus-the DBE exposure? itE T-E 975'-O/ F# ## r / , 4 n'42/p/x 4. (3) o Is the equipment submerged during a DBE? 80 o If "YES", is it qualified? (4) o Has equipment been tested to chemical spray conditions, (with respect to PPM of boron and spray pH) which are equivalent to or greater than those expected for a DBE7 7-R 9/F-#/ F#E# 6't. 4.2 Service Conditions outside of Containment g (1) o Is equipment identified as being necessary to mitigate a HELB7 + o If "TES" is it qualified to Service Conditions (temp., press., humidity)? (2) o Is equipment identified as being necessary to mitigate a LOCA? o If "YES" is equipment in an area where fluids are recirculated from inside containment to accomplish long-term core cooling following a LOCA? - o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radiation? . (3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC7 0
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REVIEW RECORD 01B i 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified? '
'a. Teat, ' 7YA?" 73?37~ A Afdeta h &f kVTN' /EE~f 323 /M'b /c~fl~ 3 6*3
- b. Analysis,
- c. Both test and analysis, Zmt to 2Edbew serota ArrntMMK47
- d. (Other),
5.2 Qualification by Test o- Operability monitored during test? /'C I-E f/f-v/, M/7tX / 8 o ' Test results demonstrate operability? Ver I-E *//r W Arac 4E 6, i A*D kV pg. /c. o Test chamber environment envelopes service conditions? t'rs 1-2 975* C/ , r/4. 3 o Is. equipment qualified to operate as required for the time necessary to perform its safety function? EErsa re #rr h a c W ci11 42 '*' O - r = ei a i> == d 1== Z-2 97S~-0/, AdNMr 2 pg. 3 o Test sequence as specified? rFI I-E 975'-O/ /er72eE 5#/4" o Was the same sample tested to service conditions? WW/ reap 704' arMWrED tv) /Arff MarotNAWE . Mar 4* JkA rssr grpe.wgg, _ o Test Failure Criteria established? Nt##4r M7 FEN /4'ED rr S/-/cr rasr l o Test Equipment accuracy requirements addressed? tscr I-E f/5-c/
#AszW4 8.3' o Equipment mounting and electrical or mechanical seals represent speci-fied installation? 4//
/
i I 5.3 Qualification by combination of Methods l 1. Is the equipment qualified for radiatifon by calculation? 4/0 o If "Yes", does the calculation satisfy postulated service conditions. l .
- 2. Is equipment qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? #O o If "YES", does the analysis satisfy postulated service conditions.
5 0 .
l i l REVIEW RECORD 01B 1 O I l 4 6.0 MARGINS o were the guidelines in Sections 4.0 satisfied? I'< r o Were the guidelines of Section 5.2 above satisfied? Mar o If "TES", no further margin information is needed.
; o If "NO", document the following margins:
i o Temp: +150 F _ o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10% o Volt: 110% of rated - o Freq.: 15% of rated o Time: fl0% of time required following a DBE Environmental Transients: Initial and dwell at peak temperature applied 1 o twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING o Was aging considered in equipment qualification? NJ O have materials susceptible to degradation
'-* " "- " " " " " " " ' from thermal or o' If "NO", "
radiation aging been included in aging list? o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? - _. 8.0 DOCUMENTATION o Data is pertinent and auditable? MJ J-E f7f -f/ Er#R /fM-o Documentation supports qualification method? re3: l 6 1. !O \ l l
ATTACHMENT TO QUALIFICATION REVIEW RECORD
.O 01B FOR SKV KERITE POWER CABLES SECTION 5.2
< ITEM: IF EQUIPMENT QUALIFIED TO OPERATE AS REQUIRED FOR THE TIME NECESSARY TO PERFORM ITS SAFETY FUNCTION? DISCUSSION SKV cables are required to renala eparational for 6 months (180 days) i
~following the DBE. The qualification test report demonstrates that' cable test samples were exposed to Post-LOCA temperature of 203 1 3 F for 100 days. The figure 4.6 of " Environmental Qualification of class 1E Equipment Qualification Summary" shows that Post-LOCA temperature decreases to 150 F 1
after 2.8 hours and remains constant for the rest of required operating time. Considering the satisfactory performance of test samples during the 100 days test, it is reasonable to assume that cables would withstand lower temperatures for a longer period of required operating time. The pressure after 2.8 hours from the accident decreases to 5 psig and is expected to approach the value of atmospheric pressure. Because of the small value, the pressure is considered nonsignificant and thus not included in evaluation of degrading factors. i J .
- Geert/Conunemmene , . . _ _ . - - - . . . _ - - - - - ,= .._ - ,-._.-_ _ .. _ _ - ,- _ _ .. _ __ _ _ _ _ -, . , . . . . . . _ _ . . . . - - - -
- - - - . . - _ - = .. _ ., . -.
s i t i i SECTION 1.5 l' CONTINENTAL WIRE & CABLE CO. I i INSTRUMENT AND THEMOCOUPLE EXTENSION CABLE O l t i a O Geert/Commoneenth
/. 6 CRYSTAL RIVER UNIT 3 GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No.
Originator 8. 5, / rom,vr Date tht/t a-Reviewer k tr. EMEtt30/V Date y/r)23 YES N0 4.1 Testing to LOCA conditions inside containment adequate? / 4.2 Equipment qualified to service conditions outside N/A containment? 5 . ,1 Qualification method identified? O 5.2 Each test requirement addressed?
/
5.3 Is qualification method other than testing adequate? M/A f 6.0 Margin requirements addressed? ! 7.0 Agin3 requirements addressed or replacement schedule / established?
~
8.0 Documentation adequacy addressed? COMMENTS: h % a& %. Supervisory Reviewer Date O . t GJtet /CommonwWth
I PLORIDA POWER CORP. O c='Srit x1vi uxtr 3 REVIEW RECORD 01B 4 MsiEUMe2'T /WD Tre*RNdtoe/Ptf eyrE1!t/CA/ ddetE Equipment Description dtW!!4' fab ~ML WAef s' CJB/f cc. Spec. No. Reviewer (name and date) 7 1- ###fv7 8/J//44-Review Sununary: 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment' 1 (1) o Did the equipment temperature and pressure profile completely er.velope_the accident profile? FS r< ff5f," .ttr, ye, Is7rtr /AA&2A o If "NO", see f>MrD /c/7.) (2) o Has equipment been tested for nornal radiation over the equipment life, plus the DBE exposure? MJ FT f93f teF.3 TW/E / o Is the equipment submerged during a DBE? M# (3) o If "YES", is it qualified? l (4) o Has equipment been tested to chemical spray conditions, (with respect to PPM of boron and spray pH) which are equivalent to or greater than those expected for a DBE? AAG 7FfAt'M FM/B**W PM*'MO /d saW B42t$ 4.2 Service Conditions outside of Containment - (1) o Is equipment identified as being necessary to mitigate a HELB7 o If "YES" is it qualified to Service Conditions (temp., press., humidity)? j (2) o Is equipment identified as being necessary to mitigate a LOCA? l o If "YES" is equipment in an area where fluids are recirculated from l f . inside containment to accomplish long-term core cooling following a LOCA? o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radiation? (3) o If equipment is not served by redundant HVAC systems powered from onsite e:nergency sources, is it qualified to environments. resulting - from loss of HVAC7 O
l REVIEW RECORD 01B I
- 5.0 QUALIFICATION METHODS l
5.1 How was equipment qualified and where was its method justified?
- a. Test, 2Gr? v er* A 562955 '9ho 4' daw 2/N/M J/N O ///?te
- b. Analysis, l c. Both test and analysis, HI - Err. & E47t'er e/r. /'///B l d. (Other),
5.2 Qualification by Test o Operability monitored during test? F45 F-d 2f3//A'/N) .4e. 3 6 / 5c ' YA8 W / , Rfktr Ab. 7fff o*Afic~ /f o Test results denenstrate operability? VtX Ac EfJr /h/*/ /s2' rte 30 Ae/NW y/ 742W / o Test chamber environment envelopes service conditions? WS fd193f .feiret/s 382 3c /so/pe) i o Is equipment qualified to operate as required for the ' time necessary i to perform its safety function? FrJ Arpae 77 r#7 M*pNeSF tr /ce 74F/=V-Test specimen same as equipment being specified? M r d4536~ /Ax2W<N O o
.htr' t , EJP. 79t/f ferz .B _ MMUNes! Dr 79/1 MEW.
o Test sequence as specified? M Ed. A. 79/18 .Cei!Y: A fC, Pe zy.sr .tdek,t o Was the same sample tested to service conditions? rer r-etF5s-
.Aetiroff 3E / 3C
'o
'~
7 l Test Failure Criteria established? 40. E4r. A'W4We# 472 /#/7/#4 o Tes't Equipment accuracy requirements addressed? 4/0 dr ?manu/e2V G M & t n t?d M t/ dzrdatt.r4o cA/ aw tvera parAr.ex4ccE. l al or mechanical seals represent speci-o
- Equipment mounting and electrij/#
i fled installation? 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? //0 o If "Yes", does the calculation sat.sfy i postulated service conditions.
- 2. Is equipment qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? #/8 o If "YES", does the analysis satisfy postulated service conditions.
O
RE7IEW RECORD 01B O 6.0 MARGINS were the guidelines in Sections 4.0 satisfied? M'3
, o o Were the guidelines of Section 5.2 above satisfied? pie - u',w .Ae suspuir ,
M rh u/Rf retre2/A OrMauMMaf" o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +15 F _ o Press.: +10% gauge, but not more than 10 lb F/in' o< Rad: +10% o Volt: 110% of rated - o Freq.: 15% of rated o Time: f10% of time required following a DBE i o Environmental Transients: Initial and dwell at peak temperature applied twice o Vibration: +10% of response spectrum at mounting point l 7.0 AGING o Was aging considered in equipment qualification?/ t'd M A 7F'/8 Jerred C/ ret /r [ Anta'A // d Jeff awet . o If "NO",_ have materials susceptible to degradation from thermal or radiation aging been included in aging list? 4//# o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? #7# - 8.0 DOCUMENTATION r3 o Data is pertinent and auditable? M h 79//8, f*C 293r , nur@t/M /'/ya) o
~
Documentation supports qualification method? re3 l I i Herf: rarr pareer iM. 79n8 cc/d21 7Esr .fANMa sttr# / /#ts<4riod or .//ww Roact W/ry Gins zesD . dows /Ak' . ir e sta a 's Tfffg s%sdC sf#D /94/ A'W//4 Toe Wf MAfd7/Cd JF" "Mr Aftetrz'/03 l 7 tor . l
# MW f~dfY35" ACD /75 / ADMZW//N des'f72 *rgtg pp Y C$* f/Q /4,fM/$7/CY AWE, /////425 && ffMr. s,kCeg4?
lO *"" " '"""'" '" " " " " " * " " ' " ' ' a . ,"1,> ,. - n - an . I
ATTACHMENT 1 D ANACONDA ~ CONTINENTAL WIRE & CABLE CO. INSTRUMENT AND THEMOC9UPLE EXTENSION CABLES REQUIREMENT 5.2 TEST SPECIMEN SAME AS EQUIPMENT SPECIFIED? TEST SEQUENCE AS SPECIFIED? DISCUSSION To identify type and insulation materials of instrument and thermocouple cables, the review of FPC purchase order no. PR3-2178 was conducted along with referenced bills of materials and their cable descriptions. i As a result of this review it can be summarized that all cables have
% silicone rubber insulation type CC-2193. The outer jackets are either glass ~ '
braid or silicone rubber type CC-2193. Available qualification test reports Anaconda Co. no. 79118 and Franklin Institute no. F-C2935 and its addendum dated November 1970, provide qualification test data for previously mentioned materials on comparable test samples to specified cables. Individual test' reports alone provide only partial qualification data. For this reason, the canbination of both reports and their test results was used for evaluation of cable performance in class lE j application. This approach can be justified, because of the same insulation
- material of tested samples and specified cables.
l^ ( It is reasonable to expect satisfactory performance of cables as concluded L in referenced test reports and consider Anaconda Co. cables, purchased for FPC purchase order no. PR3-2278, qualified. ( l ATTACHMENT 2 t O Geert/r-l n - - - - - ,- . , - , --
- , . , - - - - , - , - - , , , . . , . . . , , - - - - - , , , . . , , ---n , - - - - . . . - . - . - -
5 POCER DIVl518N - READING 7 7 DESIGN VERIFICATION RECORD PAGE I OF h g, '
'C RYTML /t2vR vN.7 r J O E O(* kOkt*0b M l Fcrc l Q Eamcanessua3ECT, Foxr ACc.zoenr 92Mt b EM ON 17t?6 MD
} CouTIAJEN7A L ZNST. +7ngghecourg Ex;(mgew uu; ' O UW'NA SECTION NAME AND NUMBER ELECTC1 CAL lC42l
- 3. 5. KoHoVT ph6. os&
ORIGIN ATOR PROJECT ENGINEER THl5 CALCULATION CONTAINS ASSUMPTiCN5 REOUIReNG L ATER CONFIRM ATION NO YES P AG E(5) A COMPUTER PROGRAM WAS: USED (CERTIFIED F ER COMPUTER APPLICATIONS MANUAL) NOT USED USED (NOT CERTIFIED BUT VERIFIED PER CAM) COMPUTER CODE: REVISION. VERIFICATION PACK AGE (IDENTIFY EACH ITEM OR GROUP OF ITEMS): DOCUMENTS TO BE VERIFIED o} MidMdf4%l -- 7Ct7" /MNor2V TME' 28/ptkM , ggy 0 (2) ,REV. (3) . R E V. _ g (4) ,REV. { (5) , R E V. (6) , REY. SUPPORTING DOCUMENTS 9, 7s ig x y; ?ccing2ksa Jtt'shtrahYr/d d' BEE- , R e v. ntir hiatw' dN7' " , 7W V fr C. .REV-(3) .REV-(4) .REV. (5) , R E V. (6) , R E V. Wbl 'l M ORIGIN ATOR*$ $1GN ATURE [[DATE B. NO VERIFICATION REQUIRED PER DCP 2.05, PARAGRAPH 2.2: PREVIOUSLY VERIFIED DESIGN: FILING CODE: DATE OF VERIFICATION. VERIFICATION REQUIRED (CHECK METHOD (S)): DESIGN REVIEW V ALTERN ATE CALCUL ATION OUALIFICATION TESTING IDENTIFIC ATION OF VERIFIER /'/:~ ~; /-11, i um. b. . -- l 0 IROJ ECT ENGIN EER $ $1GN ATU R E [ D AT'E G Al 468 R EV. 6-82
l
- PAGE 2 OF 6 C. CONCURRENCE WITH SELECTION OF VERIFIER (S): !
W l l V-/r 4 3 l SECTION M AN AGER'S SIGN ATURE DATE D. EXTENT OF VERIFICATION: Y annUn W & d ' y / n, v& 0 Lt1 A ev' 'ALs GLeA*0% ' G' RESULTS OF VERIFICATION: Y8e its ^A x w n [ w & MDNO > W $Nh ' ofA2 - Mn a
',w- L ~% , '
y i l I l l l ATTESTATION: TH15 DESIGN VERIFICATION WAS PERFORMED IN ACCORDANCE WITH DCP 2.05. B. 17. 1 m~ VERIFIER *$ SIGN ATURE d'i/n [ OATE M I E. PROJECT ENGINEER REVIEW AND APPROVAL: l & ' TROJECT ENGINEER'S SIGN ATURE DATE l
ANACONDA - CONTINENTAL WIRE AND CABLE CO. INSTRUMENTATION AND THERMOCOUPLE EXTENSION CABLE POST ACCIDENT TIME DEMONSTRATED. PURPOSE The purpose of this calculation is to compute a post-accident time period , l for which the cables are qualified. Computed time period will be compared l to the post-accident operability time required. UNITS t - time in seconds, hours, months , T - temperature in #C, F, K METHOD The approach will be to calculate from the latter most portion of the LOCA time / temperature profile an equivalent time / temperature combination with the temperature being of the actual post-accident environment. The transfo mation of a given time and temperature to a longer time period at ambient temperature will be based on the slope of the Arrhenius plot provided by the manufacturer. This method makes use of the Arrhenius data for a purpose other than its original intention and may not have a , completely sound basis; however, it is the best approach using the information available. O Geert/Commennesith l
l l
, DESICN INPUT !
- 1. Anaconda Co. qualification report no. 79118 LOCA test profile.
- 2. Arrhenius data from Anaconda Co. qualification report no. 79118.
- 3. Environmental post-accident conditions from FPC Safety Evaluation Response figure 4-6.
- 4. Required post-accident operating time - 6 months FPC Safety Evaluation Response, sh. 2-124.
ASSUMPTIONS
- 1. A basic assumption is that the Arrhenius line for the pre-accident thermal aging can be applied at a post-accident time / temperature combination. It is assumed that the slope of the line can be used
- anywhere on the log t vs. 1/T plot. The calculation of a slope will be included.
l i 2. ' Reference 3 of the design input presents the post-accident - 5 temperature of 150 F up to 10 seconds. It is assumed that the Post-LOCA temperature remains constant after that time for.the duration of the operating time of 6 months. This is a conservative assumption since some decay of th'e temperature below 150 F is expected.
- 3. The post-accident environmental pressure is assumed to decay close to atmospheric and is not consideied in its calculation.
O Geert/Commanusean l
.. - . - - - ~ . . . _ . _ . . . _ _ _ . _ _- . _ . . _ _ . . . _ _ , _ . . _ _ _ . _ _ _ _ _ . . . . _ . . . . _ . . . _ . . , _ . _ . _ . -
CALCULATION: SCOPE OF THE ARRHENIUS PLOT
; The Arrhenius theory of thermal life states that the logarithm of time is directly proportional to the inverse of the ab::olute temperature.
Therefore,~the slope can be calculated using two points on the given line. Point I t g = 10,000 hours Ty = 138 C = 411 K Point 2 t 2 = 168 hours T2 = 175 C = 448 K
.gg,p, , &a1 loa t t = time in hours
. o y T = temperature in K 10000
,, loa 168 1 1 411 448 m=
* ' = 8833.2 2.01 x 10-4 I
POST-LOCA ENVIRONMENT The Anaconda Co. test temperature profile envelopes the actual LOCA temperature with a sufficient margin up to 4 days after which the temperature is decreased to 180 F and remains constant for 12 days. The objective now is to compute a time period at the post-accident ambient temperature of 150 F. l Using assumption 1 and the slope derived from the Arrhenius plot, the
.following is a computation of time / temperature equivalency.
m = slope Alogt=mxAh t = time in hours T = temperature in K O I Geert/Commennesith t
] . t -.
.f-
'i
-.e ,
, . ,s" x ,,
& POST-LOCA ENVIRONMENT (CONT'D)'
} ;I ,
I .# 'tt = time to be computed
~ .* ,
.- t2 "* test time 12 days T1 m, Post-LOCA ambient temperature 150 F = 65.6 C = 3'38.6 K T2 test temperature 180 F = 82.2 C = 355.2 K /
= a x'A 1 log C.2 ,,.,-T
- j. . -
log t / l I 288g 1 = 8833.2 x/(338.6 - 355.2) , t
~~
108 El =.1.219 / 288 r
- r' 1
,r '
t 1 = 288 (10 *219) g t 1 = 4768.6 hours = 198.7 days ll . ./ CONCLUSION: j- ( ,
; /=
=
1- 3' < . The criti~ cal post-accident operability time demonstrated is 198.7 days at
; the post-accident ambient temperature. of 150 F. This result exceeds
. required time of 6 months (180 days) with margin of 18.7 days, over 6%.
~
# $ Therefore, the Anaconda instrumentation-and thermocouple extension-cable is-
- . q sufficiently[qualifiedforpost-accidentoperability.
/
! ~ ,
, t ,
b
'~
l',',pr #
,f' Y r i
'+
g ., r, 4
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< r AI
- [ .
< , ? , a y . J- u ,_
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- 1 5 * ^ ' '
. A y ; q
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4.5 e. i i e 1 i SECTION 1.6 l: 1 I l ROCKBESTOS CO. CONTROL AND T/C EXTENSION CABLE i 1 I i 4 R F I E, t. I 1 b I l L l' i 2 4 1 ? L Gdtert/Commonuesth t i 1 w,+r.,,--,,,-w-,- -e-..,-w.--,s,-.,-.w.m,- w- ,,c. ,_.--vy.-.. , , ,+.,..m_wm.m_.
----_,.-,--,---,,----..---,.e.---- . - , . m-n-- + - - -- - . - . - ,
I,7 CRYSTAL RIVER UNIT 3 pm V GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. Originator O. K. J1c.tNTZrtG Date 124/fL Reviewer 4/p/f? [ [ IA g Date ev YES p'O 4.1 Testing to LOCA conditions inside containment adequate? / 4.2 Equipment qualified to service conditions outside / containment? 5.,1 . Qualification method identified? 5.2 Each test requirement addressed?
/'N V 5.3 Is qualification method other than testing adequate?
.6.0 Margin requirements addressed?
[ j 7.0' Aging requirement,s addressed or replacement schedule established?
/
8.0 Documentation adequacy addressed? COMMENTS: *. a Supervisory Reviewer Date MNh T- ?
FLORIDA POWER CORP. CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B , Equipment Description d ear,let i ~77c fwrsussed batr (Rect:nesss) Spec. No. J/M (4:-554 Reviewer (name and date) JD .')(, 7 # ' d 7/16/P5 Review Summary: 4.0 SERVICE CONDITIONS 4.1 IACA Conditions Inside Containment
/(1) o Did the equipment temperature and pressure profile completely envelope the accident profile? Ws- Tas Rga 1 A "7 o If "NO", see V
v(2) o Has equipment been tested for normal radiation over the equipment i life, plus the DBE exposure? Vss. ,Sta Zse 2 P. P 0
/(3) o Is the equipment submerged during a DBE? N.
o If "YES", is it qualified? ' h / (4) o Has equipment been tested to chemical spray conditions, (with respect to PPM of boron and spray pH) which_are equivalent to or greater than l those expected for a DBE? W e %s / tsp. 1 A "/
- v i 4.2 Service Conditions outside of Containment (1) o Is equipment identified as being necessary to mitigate a HELB?
-- %s.s /
! o If "YES" is it qualified to Service Conditions (temp., press., l humidity)? VE5 ? Std Rep J R7 - I cr . (2) o Is equipment identified as being necessary to mitigate a LOCA? ' Yes o If "YES 1's equipment in an area where fluids are recirculated from inside containment to accomplish long-term core cooling following a LOCA? VCs o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radistion? Vcs: Sss. REF 1 Phv
~14 Y (3) .o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC? V(5 - Su ' Notr ]
lO L - . . _ _ _ _ _ _ ____
i L REVIEW RECORD 01B 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
- a. Test. 1 van rest ro. res,rn ina
_ rut m.m
- b. Analysis,
- c. Both test and analysis,
- d. (Other),
5.2 Qualification by Test
'o Operability monitored during test? Ws.Rtc 1. Ps 2hr e
"o Test results demonstrate operability? Ws . Ras .LTA 4. (c.we: usi.4 7 '
Vo Test chamber environment envelopes service conditions? Vas Res 1 - %s *1 ( taa mmh do Is equipment qualified to operate as required for the time necessary to perform its safety function? Ws. .ssr Juppt.resa at 'A 1 # Rt; R bo Test specimen same as equipment being specified? Yss- szs "#rs 1 R,1 e1857 nAnrut -nese e >psse O) C'
/o Test sequence as specified? Pz,-Rsa 1, Air J. NA Ib vo Was the same sample tested to service c'ondftlons? vis . Ess 1 rwa w,,,,,vr do -Test Failure Criteria established? %s,. S EE Mevt 2 vo Test Equipment ac' curacy requirements addressed? S44 L aac a n ur4 <.,
$H12f 2
#o Equipment mounting and electrical or mechanical seals represent speci-fled installation? N.* Frerwr #
- l. 5.3 Qualification by Combination of Methods
-1. Is the equipment qualified for radiation by calculation? Ato C-r.s-r) o If "Yes", does the calculation satisfy postulated service conditions.
l
- 2. Is equipment qualified by analysis for effects of chemicals on the i
enclosure, gaskets, and seals? A t'trs-r) o If "YES", does the analysis satisfy postulated service conditions. 4 0
..,-._.,,---<my.,... ,,m,_pp_ , _ _ _ , , . . . . _ ..,y, ....,_,,..,,.,y,_,....,__,mm,.q.
i REVIEW RECORD 01B J. 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? Ws o ' Were the guidelines of Section 5.2 above satisfied? Ws o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +150 F _ o Press.: +10% gauge, but not more than 10 lb F/in' . o Rad: +10% o Volt: 110% of rated o Freq.: 15% of rated o Time: +10% of time required following a DBE , o Environmental Transients: Initial and dwell at peak temperature appliu. twice o Vibration: +10% of response spectrum at mounting point j-7.0 AGING o Was aging considered in equipment qualification? Ws- E s.p 1.1% 'V t (NArb2)J l P e A . Pn A TIT * $9s ( l -o If"'Nd",. have'matatials susceptible to degradation from thermal or j radiation aging been included in aging list? - ! o Have maintenance and replacement schedules been - established for equip-ment not meeting lifetime aging qualification? l 8.0 DOCUMENTATION o Data is pertinent and auditable? Ws-Rap 1, h "I o Documentation supports qualification method?. Ms- Pro 1 THechHodT O
REVIEW RECORD 018 REFERENCES
- 1. Rockbestos Report " Qualification of Firewall SR Class lE Electric Cables" dated March 2, 1978.
- 2. Rockbestos Company to Gilbert / Commonwealth letter dated October 9, 1980. -
NOTES
- 1. Page 4 of Ref. I states that the cables will function for at least 40 years at a continuous operating temperature of 125 C. For the effects of loss of HVAC in the Auxiliary Building see the last paragraph of Section I.1.3 of the IE Bulletin No. 79-01B Qualification Summary. Effects of loss of HVAC in the Intermediate Building is presently being determined; however, since the loss of HVAC is considered to be of short duration, and since the cable is qualified for continuous operation at 125 C the cable is considered qualified to the environment resulting from loss of HVAC.
l-
- 2. The failure criteria is the ability of the cable to withstand the l voltage withstand test of 60v/ mil for 5 minutes. Although not specifically labeled " Failure Criteria" in the test report, it is l
such; it is in paragraph II on page 2. l L l-I i O Geert/Connensesith l l t
. CONTROL AND INSTRUMENT CABLE REQUIREMENT Operating time after accident condition to be 6 months.
CONDITIONS Qualification test duration - 30 days. ANALYSIS All cables in the test performed adequately for the 30 day duration of the test. At the time the test was performed the 30 day period was though to be adequate to demonstrate the cables capabilities. Since the sampi,es passed the 30 day duration of the test, there is no reason to believe they would not have survived further into the relatively low
)
l stress long term transient conditions to meet the 180 day requirement. Also, the test conditions are materially more severe than the CR-3 accident environment and it is reasonable to assume this would have aided the test samples in meeting extended performance periods, i i l The 30 day qualification is therefore considered adequate. l I l l i l i Geert/CommoneesRh
O REQUIREMENT ().. Test equipment accuracy addressed. CONDITION Equipment accuracy not addressed. ANALYSIS Although the test equipment accuracy was not addressed, the test conditions exhibit significant margin over the accident requirements; also, the sample condition is determined by relatively gross measurements that are not materially-affected by equipment accuracy. Therefore,.the omission of accuracy data does not void the qualification program. O. a l 9 i I l I t Geert/Commoneese
i i . SECTION 1.7 BIW CO. CONTROL AND INSTRUMENT CABLE 5 I 1 I a 8
,e
- r at-1 l
5 4 d i f l Gdtert /Commenneeth i i
, ,. -- - ,,--,-----,..-,.---rw-..-,.,....m......-.--.... - . . - - . . - . . . - . ~ , _ _ - - - - - - - - ,
,]h< k -
,,g CRYSTAL RIVER UNIT 3 O
GUIDELINES FOR TECHNICAL' REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BUI1ETIN' 79-OlB Spec. No. . Originator m v. d a gewf Date 2 1 <. -s x Reviewer $W7K/f$ Date 1 - s. -1 x
~
YES NO, 4.1 Testing to LOCA conditiors inside' containment adequate? / 4.2 Equipment qualified to service conditions outside / containment?
- 5. ,1 Qualification method identified? /
5.2 'Each test requirement addressed? 7 _O' 53 . Is qualification method other than testing adequate? g/4 , 6.0 Margin requirements addressed? / 7.0 Aging requirements addressed or replacement schedule , established? 8.0 Documentation-adequacy addressed? [- COMMENTS:
. Supervisory Reviewer Date O .
GdbertICommonwealth
i FLORIDA POWER CORP. p CRYSTAL RIVER UNIT 3 V REVIEW RECORD 01B (EW YLENE PRoPYt.ENE Ru& Gest INivan; ton t 3Q57A4 b 7 TACRE Equipment Description CMMtos, bb lut"mammuT CARLE. EY 81W Spec. No. Reviewer (name and date)TN, GAmh31 2. /G[B2., Review Summary: r l 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment
~
(1) o Did the equipment temperature and pressure profile completely enyelope the accident profile? yen, RawA Aq=r .UT" Mr. tE o If "NO", see l (2) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure?NE( ugle A gac,3Z'. Fic. A l (3) o Is the equipment submerged during a DBE7 NO o If "YES", is it qualified? l h (4) o Has equipment been tested to cilemical spray conditions, (with respect to PPM of boron and spray pH) which are equivalent to or greater than those expa.cted for a DBE? VES , REM A , SKt , k*u . p 4.2 hrvice Conditions outside of Containment (1) o Isequipmentidentifiedasbeingnecessaryto$titigateaHELB7 NES ' o If "YES" is it qualified to Service Conditions (temp., press., j humidity)?Nat.E ms.A.Ce c. W . m G_E*. l ! (2) o Is equipment identified as being necessary to mitigate a LOCA? l NES o If "YES" is equipment in an area where fluids are recirculated from inside containment to accomplish lorg-term core cooling following l a LOCA? VER o If it is required to mitiga,te a LOCA, is equipment qualified to 100% ' humidity, the required temperature and pressure, and expected radiation? NE< ;1ltr_w. A. Same W hq.T (3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting
- from loss of HVAC? Sc:_F thws: 1
REVIEW RECORD 01B O. . 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
@ Test, %pa "T"msT. _%crtwish P== tstw Gutnri t um.EEC. 5.1.
- b. Analysis,
- c. Both test and analysis,
- d. (Other),
5.2 Qualification by Test o Operability monitored during test? Vaq EarFN Sue irr Cid.E ; o Test results demonstrate operability?%/trc .1 pen A , scrr .9rr,wir.X
. o Test chamber environment envelopes service conditions? hs REir L' cm.M i F)d E o Is equipment qualified to operate as required for the time necessary to perform its safety function?SEE.SuPPI ammTAt_. 7%ce. 3 "
o Test specimen same as equipment being specified? NEs , itirN K. stc.fN Fin.I. l o Test sequence as specified? NER. tRW, A.ERC .W j o Was the same sample tested to survice conditions? \tsK. DwrA.5Et3Ili ' ' ' G\C. W . o Test Failure Criteria established? Ces Lom EmEList Paan_ l .
- o Test Equipment accuracy requirements addressed? SEE SVPPtzmuhl _
PArin 2_ o Equipment mounting and electrical or mechanical seals represent speci-fied installation? k)/A 5.3 Qualification by Combination of Methods ! 1. Is the equipment qualified for radiation by calculation? MO o If "Yes", does the calculation satisfy postulated service conditions.
- 2. Is equipment. qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? M O l
o If "YES", does the analysis satisfy postulated service conditions. l l O i
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REVIEW RECORD 01B 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? V K R o Were the guidelines of Section 5.2 above satisfied? WC o If "YES", no further margin information is needed.
, o If "NO", document the following margins:
o Temp: +150 F _ Press.: +10% gauge, but not more than 10 lb F/in' o o Rad: +10% o Volt: +10% of rated o 'Freq.: 55%ofrated { o Time: t10% of time required following a DBE o Environmental Transients: Initial and dwell at peak temperature applied twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING ' l i o Was aging considered in equipment qualification? MER , Rwgr A,, Sg.c T7, o If "NO", have materials susceptible to degradation from thermal.or radiation aging been included in aging list? o Have maintenance and replacement schedules been established for equip-ment not meeting lifetir.m aging qualification? T4 / A , 8.0 DOCUMENTATION ! o Data is pertinent and auditable? Vs 4 o Documentation supports qualification method? NW A I e O :
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CONTROL AND INSTRUMENT CABLE RECORD REVIEW 79-01B
, NOTE Ref. A, Sec. IV, Page 5, states that the cables will function for at least 40 years at a continuous operating temperature of 90 C. For the effects of loss of HVAC in the auxiliary building, see the last paragraph of Section I.1.3 of the IE Bulletin-No. 79-01B qualification Summary. Effects of loss of HVAC in the Intermediate Buiiding is presently being detennined; however, since the loss of HVAC is considered to be short duration, and since the cable is qualified for continuous operation at 90 C, the cable is considered qualified to the environment resulting from loss of HVAC.
REFERENCE O BIW Bostrad Cables, Report No. B910, dated May, 1975. i e b I I l O Geert/Commommesoth i l .,- _. . , - - . _ - - . _ _ , . . _ ._ - , . . . _ , . . , . _ _ , _ _ . . _ _ _ _ _ , . . , , _ . _ , . _ _ . _ . . __ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
p 5.2 FAILURE CRITERIA V DEFICIENCY Failure criteria not established for the test. ANALYSIS The function of control and instrument cable is to transmit electrical signals from one location to another. Based on this functional requirement the failure criteria can be postulated as follows:
~
Throughout the test rated voltage shall be applied between conductors; and between conductors and shield. Failure of conductors by continuity testing, or failure of insulation by meggar testing shall be considered as failure of the specimen under test. CONCLUSION w BIW Report No. 8910 indicates throughout the test 600 volts was applied between conductors, and 345 volts applied between conductors and shield. Also, a 1 amp / conductor was applied throughout the test. The report documents the performance and results of the testing, therefore, the omission of established failure criteria prior to testing is acceptable. O Gdtert/Commonweeth
5.2 TEST EQUIPMENT ACCURACY D V DEFICIENCY Test equipment accuracy is not documented. ANALYSIS BIW Report No. B910 indicates the LOCA simulation test was performed in an autoclave chamber. The report made no mention as to how test data was measured. CONCLUSION The test parameters documented in BIW Report No. 8910 envelope the required environmental parameter with sufficient conservatism that omission of test equipment accuracy is acceptable. O d O 4 e i l i l l l (O Gibert / Commonwealth
5.2 OPERATINC TIME O
, DEFICIENCY Qualified test operating time is less than the specified time.
ANALYSIS BIW Report No. B910 indicates.the cable successfully withstood heat aging and gamma radiation doses followed by IEEE 323-1974 LOCA environmental conditions for a duration of 100 days,'and then met all the requirements of the IEEE 383-1974 Post-LOCA simulation test. CONCLUSION The duration of the qualification test extends well beyond the extremes of the harsh environment encountered during a LOCA. Although the cable is required to operate for 180 days af ter a DBE, the qualification test has
- demonstrated considerable conservatism in environmental extremes vs.
duration time and specification time is acceptable. l l l i ( t l i
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Geert/Commanuseth
l I f t-7 e, f. I .. I
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f 4 P i I- SECTION 1.8 4 i i i i s' GOULD CO. MOTOR STARIERS l r 4 I i I I l l Gdhert/Commoneesith i~ v WP--NN--wm,9-m.--,-4_.,_g9,, ,,y. , _ , ,
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e Erh CRYSTAL RIVER UNIT 3 \ GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. PR AL. 72 ')- Y/ coq Originator T M 6arla/9/ Date 1/8/RL Reviewer k'hv2<w Date g/p/F3 YES M 4.1 Testing to LOCA conditions inside containment adequate? N[A 4.2 Equipment qualified to service conditions outside & containment? 5.1 Qualification method identified? X 5.2 Each test requirement addressed? 5.3 Is qualification method other than testing adequate? 6.0 Margin requirements addressed? 7.0 Aging requirements addressed or replacement schedule X established? 8.0 Documentation adequacy addressed? COMMENTS: l 6 Supervisory Reviewer Date i Gdbert/C_ ? l l
FLORIDA PO L CORP, f i CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B GOJLD ST 'tE 1. Equipment Description Me Tom S%mvero MO-23/2.4 ; M U -2.E /7_ c, Spec. No. ffF NdTE 3 Reviewer (name and date) "T" N/.GAsisme L lE l %7_ Review Summary: 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment N/A (1) o Did the equipment temperature and pressure profile completely envelope the accident profile? o If "NO", see (2) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure? (3) o Is the equipment submerged during a DBE? o If "YES", is it qualified? Q (4) o Has equipment been tested to chemical spray conditions, (with respect V to PPM of boron and spray pH) which are equivalent to or greater than those expected for a DBE? 4.2 Service Conditions outside of Containment (1) #o Is equipment identified as being necessary to mitigate a HELB? - MO
- o If "YES" is it qualified to Service Conditions (temp., press.,
l humidity)? (2) /o Is equipment identified as being necessary to mitigate a LOCA? M% lo If "YlS" is equipment in an area where fluids are recirculated from inside containment to accomplish long-term core cooling following l a LOCA? \/ES i ,o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radiation? Nt& . SEE A/076 l/ ? / (3) #o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting i from loss of HVAC? EEE b;: I l l (3/
- e
REVIEW RECORD 01B v 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
- a. Test,
- b. Analysis,
/@ Both test and analysis. Jor/Mo/ mar DOP Gvih //wat Ce
" ' ~' c r/an F. /.
- d. (Other),
5.2 Qualification by Test , v6 Operability monitored during test? W;g 12:=_1. A .. SEc. 5.3. 2 l'pActo 48)
,o Test results demonstrate operability? Nes Retr A .; .5'EC. 9,3,t,4 7o Test chamber environment envelopes service conditions? W_s, ra p A A-r w e = w li! ,
o Is equipment qualified to operate as required for the time necessary to perform its safety function? GEE 10sE 2
#o Test specimen same as equipment being specified? WA Dgrc L ,
b" Asa Twet:ncAvtu) A-X DAcIE. 'UT 4 TECT/ok i . d'
/o Test sequence as specified? Myk. Mets A.SEC,R 3 7 Aun S.3.1.
/o Was the same sample tested to serfrice conditions? h% pp.p. h.
Auc . G.%. l . Vo Test Failure Criteria established? Smu d;;oopt Emmh PAqu ) vo Test Equipment accuracy requirements addressed? SwF CuestsmewfAt Na2 yo Equipment counting and electrical or mechanical seals represent speci-fied installation? gEt 5000, emaArfat 9het. E 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? Me.9 spa .5GC.E.t.Z(5.3.3:
o If "Yes", does the calculation satisfy postulated service conditions.
- 2. Is equipment qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? K1/A -
o If "YES", does the analysis satisfy postulated service conditions.
6 REVIEW RECORD 01B (')J R 6.0 MARGINS o WeretheguidelinesinSections4.0 satisfied?M/4 o Were the guidelines of Section 5.2 above satisfied? W m n ew_ cry As IWtteA7W_h Oc hm amawTaL PAN l Tano "A . o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +150F _ o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10%
- o. Volt: 110% of rated o Freq.: 15% of rated o Time: +10% of time required following a DBE o Environmental Transients: . Initial and dwell at peak temperature applied twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING o Was aging considered in equipment qualification? Wi , Dt:.F. k . ,
Swr- E _ "N . p/ L o If "NO", have materials susceptible to degradation from thermal or radiation aging been included in aging list? o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? neem Eps.k~'<se.G,K Aw o 2,0. 8.0 DOCUMENTATION , o- Data is pertinent and auditable? Ng.s l o Documentation supports qualification method? Stet l l i l
MOTOR STARTERS REVIEW RECORD 018 NOTES l '. Reference the last paragraph of Section I.1.3 of the IE Bulletin 79-01B Qualification Summary.
- 2. As a result of the specified ambient conditions and aging qualifications, operating time is not considered to be a constraint.
- 3. Purchase Requisition No. 723-9100Q.
- 4. Temperature, pressure, and humidity remain at ambient conditions throughout a DBE. See Ref. A, Sec. 3.0 for radiat. ion.
l c p gj REFERENCE l s l Ref. A.': l Could Qualification Sununary Report for Class lE Equipment CC-323, 74-49, Rev. 1, dated January 17, 1980. g O Geert/Commonuesth i l
p GOULD CO. MOTOR STARTERS V 5.2 FAILURE CRITERIA DEFICIENCY Failure criteria not established for the test. ANALYSIS The function of a motor starter is to provide power, protection, and control for valve motor operators. Based on these functional requirements the failure criteria can be postulated as follows: The motor starter shall be activated under load conditions, and shall energize the valve motor which will cycle the valve to its open and closed position intermittently throughout and subsequent to the qualification testing. Any material degradation, or failure of any electrical or mechanical functions shall be considered as failure of the specimen under test. CONCLUSION - Could' Report CC-323.74-49, Rev. 1, indicates throughout the test, the j devices progress was checked by base line functional tests in order to-determine failure causes. These checks consisted of a visual check for structural anomalies and electrical check for proper operation and contact continuity. This test report documents the performance and results of this l testing. Therefore, the omission of established failure criteria prior to t testtng ts acceptable. l-r~ w l i l Geert/Comnunweeth
5.2 TEST EQUIPMENT ACCURACY U DEFICIENCY Test equipment accuracy is not documented. ANALYSIS The purpose of this qualification is to certify the equipment will meet or , exceed DBE harsh environmental conditions. The motor starters are located in the auxiliary building. During a DBE a harsh environment (temperature, pressure, humidity) in the auxiliary building is precluded. The radiation exposures in the auxiliary building during and after a DBE reach levels which will create a harsh environment. CONCLUSION
- Since the environment (temperature, pressure, humidity) in the auxiliary l
building during a DBE, remains ambient, the test equipment accuracy used to test temperature, pressure, and humidity is negligible. Could report CC-323-74-49, Rev. 1, indicates radiation levels encountered by the qualification exceed time.specified in the auxiliary building during a DBE. Therefore, the omission of thest equipment accuracy is acceptable. t I l O Gdbert/Commoneesith I
1 l l _5.2 EQUIPMENT MOUNTING AND ELECTRICAL OR MECHANICAL SEALS
.0 DEFICIENCY Equipment mounting and electrical or mechanical seals not addressed in test report. .
ANALYSIS The motor starters are wall mounted in the auxiliary building. Could Report CC-323.74-49, Rev. 1, makes no reference as to how the motor starters I were mounted or sealed during the test. i CONCLUSION - Temperature, pressure, and humidityJeemain ambient in the auxiliary building throughout a DBE. The only environmental parameter that will change l throughout a DBE is radiation levels. Based on the actual environmental l l parameters the motor starters are subject to, the omission of mounting and j sealing from the test report will have no impact on the motor starter i qualifications. I i i i g. e i i Geert/Commoneesth
'h
. - . .- . - .. - . - - ~ -- , . . . _ . . _ - .. . . .--
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SECTION 1.9 1 t l l .j . WESTINGHOUSE CORP. FAN MOTORS. TYPE LLA 9 0 f* .I f , i i i r 1 t-t a + G a
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'~[ ~ GUIDELINES FORT TECHNICAL REVIEW OF T'IE , j ,
' . j';/ DISCUSSIONS F COMPLIANCE WITH IE BULLETIN?79-01B
* ^ *
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Spec. No.- '
.u Originator 8.S./(CVkid7,
' Date 3/3/11 Reviewer 8.ff. 6MAMV Date y/fJ12 , YES NO
~
/
4.1 Testing to LOCA conditions inside cdntainment adequate?
/ 4 4.2 LEquipment qualified to service conditions outside i g/4
. containment? _
l 5.1 Qualification method identified?
',t, -
5.2 Each test [ requirement addressed? T
? 5.3 Is qualification method other than testing adequate? M 6.07 Margin requirements . addressed?
<l
/
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[[~.,g,'7.0!A'singrequirementsaddressedor'replacementschedule /
~
established?. $ s 'I , , *
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8.0 Documentation adequacy addressed?' l4 . , C I.< ,
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1 COMMENTS: , Y Nfnf Y Y'
! t-Supervisory Reviewer Date O
PLORIDA POWER CORP. c= =tv== == > O AEVIEW RECORD 013 W13/WGMkWF dneP. 7*y'Pr u/7 f4A! Mer0Er i Equipment Description N- N ##-/# /8 t' /C Spec. No. Reviewer-(name and date) 3 / D*M MT[82-Review Summary: I 4.0 SERVICE CONDITIONS 4.1 IACA Conditions Inside Containment' , b ' (1) o Did the equipment temperature and pressure profile completely envelope the accident profile? df e't#' 7/tf .AIPr f4 ! o 'If "NO", see (2) o Has equipment been tested for normal radiation over the equipment P6r et'## 73ys 4 4447 7 pry Aef;y life, plus the DBE exposure? (3) o Is the equipment submerged during a DBE7 d o If "YES", is it qualified? l O c4) o - e,ui-oeen tested to cwca1 sPrax conditions. <wi=h res,ect to PPM of boron and spray pH) which are equivalent to or greater than l those expected for a DBE7 MT *tGP 78 4 ./#/: # 4/ Nm'ME 4.2 Service Conditions outside of Containment A/A I I (1) o Is equipment identified as being necessary to mitigate a EELB7 i' If "YES" is it qualified to Service Conditions (temp., press., o humidity)? l (2) o Is equipment identified as being necessary to mitigate a LOCA? l o If "YES" is equipment in an area where fluids are recirculated from inside containment to accomplish long-term core cooling following a LOCA? o If it is required to mitigate a LOCA, is equipment qualified to '
. 100% humidity, the required temperature and pressure, and expected
- radiation? _
(3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC? O . t v ,-,+-y--- p i,,~ ..ep_ m,--,,-yn,--.y,
REVIEW RECORD 01B pJ l 5.0 - QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified? i a. Test, Wr4P 78tf i 4tW- 73M-L
- b. Analysis,
- c. Both test and analysis, d,. (Other),
5.2 Qualification by Test o Operability monitored during test? /Er 4,M 7 Bey fees # < *T4 tin f Met <Mr 9 o Test results demonstrate operability? rcr We# Mrf .frer, c i I o Test chamber environment envelopes service conditions? F,T 4'4P 19tk Jerz 7 o 'Is equipment qualified to operate as required for the time necessary
- to perform its safety function? &n r, sprekwear Ar*wer raw a i> == 6 *== *** 42 '
- ~ ' " ~ < < > :
O - ' = ci t'er ac# 7J! sty . agers / E AsarAw' 3 o Test sequence as specified? o Was the same sample tested to service conditions? MT ar# 7 sty fernet/ C, M8t4~S*. _ o Test Failure Criteria established? fve eeroX towtw'ezr fu',necese// e ~ o Test Equipment accuracy requirements addressed? Ha 'se # 7#E9 mat 3/Mc 2 I o Equipment mounting and electrical or mechanical seals represent speci- i l fied installation? MS *t47 7Bty M /s g' # 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiasion by calculation? 80 o If "Yes", does the calculation satisfy postulated service conditions.
- 2. Is equipment qualified by analysis for pffects of chemicals on the enclosure, gaskets, and seals? #v j
! o If "TES", does the analysis satisfy postulated service conditions. A' MrFEt TD 4k'dP 73V3-4 rasic /, l 0 - l r l l
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l REVIEW RECORD 01B
+
lO 4 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? fd o Were the guidelines of Section 5.2 above satisfied? r2r ..sswr tw
?>ntr - Ate'sAes/r' ulrestRNt/>' ME fdtutautWf Jea mwea7' o If "TES", no further margin information is needed.
- ' ' o If "NO", doctament the following margins:
o Temp: +15'F _ o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10% o Volt: 110% of rated - o Freq.: 15% of rated - o Time: fl0% of time required following a DBE P4F. 5 /h74t#Nc2P - o Environmental Transients: Initial and dwell at peak temperature applied twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING , 1 o Was aging considered in equipment qualification? MT i O o If "NO" have materials susceptible to degradation frem thermal or j radiation aging been included in aging list?__ o -Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? ## 8.0 DOCUMENTATION 1-I o Data is pertinent and auditable? M Bry 4eV# 7&.?-I., wer fcd o Documentation supports qualification method? r'es a
- O -
.-----*_.--...-,-m-- , , . -.-,-,.--,-,e -..~,.,--.,,4-,--..,,--.y..---,,,,,,e-.w--py, - - - . - - - - - - - ,-.,-------,w-mm,.s.--c-r- - - - . .-, -,
ATTACHMENT O WESTINCHOUSE FAN MOTORS REQUIREMENT Paragraph 5.2 - Is equipment qualified to operate as required for the time necessary to perform its safety function. DISCUSSION i No test data are presented in the qualification reports to support the motor 1 operability for required six months following the accident. Considering several days of testing under more severe conditions than the CR-3 accident environment, it would be reasonable to assume that subject motors would i satisfactorily perform during the required six months post-accident time j span, when temperature and pressure would approach the pre-accident values. Another supporting feature is a presence of heat exchangers on installed motors. Test results qualifying motors without the exchanger are still adequate for CR-3 accident environment. Therefore, the post-accident , operability of motors with the heat exchangers can be expected to meet the extended performance period. ll I l l l i i-l i Gdbyt/Commeauseth
i. 9 f l l i SECTION 1.10 3 f k k 4 VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. F-C3271 i ,
+
a 1 I i e t l i !e i i l-1 l f Gdhert/Commanuseith 1 r 1 w---,ym - < , - , . - > . - ,, , a --,- .g.. ,,, , m,,a,n , , , , , , , . _, n._ _, _ . , _ _ . _ _ _._,. , _, _,n, - - , , , , . ---,-___.__,-.w _ ,,-
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r CRYSTAL RIVER UNIT 3
\
GUIDELINES FOR TECllNICAL REVIE'J OF Tile DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. Ipo Mok I Originator O A, [[md Date 1// 2./62 Reviewer , , Date 4l?g/82. \T YES NO 4.1 Testing to J0CA conditions inside containment adequate? Nfk 4.2 Equipment qualified to service conditions outside K, containment? 5.1 Qualification method identified? X 5.2 Each test requirement addressed? X 5.3 Is qualification method other than testing adequate? A 6.0 Margin requirements addressed? X 7.0 Aging requirements addressed or replacement schedule K j established? 8.0 Documentation adequacy addressed? X COMMENTS: flo T E .t.: Egaiponat ;FJPPl led' by 8 + W. , VAwE lAoTom oPER.Ricas , TK,. No s WV-6,6 y F, M , ! MOV-58d.73, 2 - Re.vm.w ye,acogo cog %ps, %g.%e.s wwm stw;u> NE\hED, - 4212 @ M'/783 Supervisory Reviewer 'd Date O Geert/C; J?
FLORIDA POWER CORP. CRYSTAL RIVER UNIT 3 REVIEW RECORD 01B Equipment Description k/olvo. Moh, doend+rt; Toy Ahr. DW-{ ( 3 Y,39 MCV-% 77 Spec. No. See No[e I Reviewer (name and date) E, A, FA cua/s 2.//Z//2 Review Sumary: 4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment y . (1) o Did the equipment temperature and pressure profile completely envelope the accident profile? o If "NO", see ). - (2) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure?
- . (3) 'o Is the equipment submerged during a DBE7
- o If "YES", is it qualified?
f (4) o Has equipment been tested to chemical spray conditions, (with respect to PPM of boron and spray pH) which are equivalent to or greater than those expected for a DBE? l l 4.2 Service conditions outside of Containment I (1) /o 'Is equipment identified as being necessary to mitigate a HELB7 Yes vo If "YES" is it qualified to Service Conditions (temp., press., humidity)? Yes,. L
- Note 2 (2) M Is equipment identified as being necessary to mitigate a LOCA?
Yes
/o If "YES" is equipment in an area where fluids are recirculated from inside containment to accomplish long-term core cooling following a LOCA? Yes
,e o If it is required to mitigate a LOCA, is equipment qualified to the required temperature and pressure, and expected 100% humidity,7es radiation? Soa Nefo 3 j
(3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC7 TM. fae. Mete 6t-O l r
- REVIEW RECORD 01B 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
's. Test, Type fes/ ': ~ sushrin/ p er~ Dc2 Guiclelih+c . Section 5.1 '
Analysis, b. l c. Both test and analysis, i d. (Other), { 5.2 Qualification by Test f vo Operability monitored during test? Us
' fel. fecert F-cu7/ . Sechica 2,2-l vo Test results dem' o nstrate operability? %e 1 for. Procrt 5-C4271. Secficns 3. 2. , 4,2 an,/ 7L.f,fr 1 Test chambdr environment envelopes service conditions? Soo Nato F
~
! to
-o for the time necessary Is to equipment qualified perform its safety to operate asFeo function? required,d, Ne 6 p yd Test specimen same as equipment being specified? Ver G 4 Rec. Ro m t f- c 3171. rac +ta m 1,o Test sequence as specified? 'See A/ofe 7 vo Was the same sample tested'to service conditions? h
$CC S>Owf F-C M 71 % fich '2. . O vo Test Failure Criteria establish'ed? Sa_a Loo /mwn /a / m , ,, 1
/o Test Equipment accuracy requirements address'li? e San Lon/~~oaM onn o_ 2 fo Equipment mounting an'd' electrical dr dechanical seals represent speci-fled installation? feo A/o/e 9 5.3 Qualification by Combination of Methods
- 1. Is the equipment qualified for radiation by calculation? A/n o If "Yes", does the calculation satisfy postulated service conditions.
l l - l 2. Is equipment qualified by analysis for effepts of chemicals on the enclosure, gaskets, and seals? N/A j o If "YES", does the analysis' satisfy postulated service conditions. l l v
REVIEW RECORD 01B O ! 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? Ya c : chts J M rad.nlien (Co e D n in s w .s k i w x 1) o Were else guidfalin' e s of Section 5.2 above 'sratisfied? Yes o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +150 F _
.o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10%
o Volt: 110% of rated o- Freq.: 15% of rated - o- Time: +10% of time required following a DBE o ';nvironmental Transients: Initial and dwell at peak temperature applied twice o , Vibration: +10% of response spectrum at mounting point 7.0 AGING o Was aging considered in equipment qualification? Mo
- i. 'o If "NO"..have materials susceptible to degradation from thermal or radiation aging been included in aging list? feu A/efe V o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? Iae No/a 7 i -8.0 DOCUMENTATION o Data is pertinent and auditable? MLr o Documentation supports qualification method? Yar t
I l i O
VALVg NOTOR OPERATORS REVIEW RECORD 01B NOTES
- 1. DHV-5, 6, 34, 35 MUV-56 and 73 were all supplied by B & W.
- 2. Temperature, pressure, and humidity in the Auxiliary Building remain at ambient conditions throughout a PBE (see Section I.1.3 of the IE Bulletin 79-01B Qualification Summary).
- 3. For temperature, pressure, and humidity see Note 2 above. For radiation see Supplemental, page.1.
- 4. See the last paragraph of Section I.1.3 of the EI Bulletin 79-01B Qualification Summary.
I l
- 5. The specified ambient conditions of temperature, pressure, and humidity are enveloped by the test chamber environment (Ref. FIRL
~
Report F-C3271, Figure 3). For radiation see Supplemental, page 1.
- 6. Post-accident operating time is not considered to be a constraint in regards to the specified ambient conditions of temperature, pressure, and humidity. Radiation, however, must be considered in determining the qualified operating time of the valve operators (see Supplemental, page 1, for explanation of radiation).
l 7. Ref. Report F-C3271, Section 3.2 and Supplemental, page 1. l
- 8. Ref. Report F-C3271, Section 3.1 and Supplemental, page 4.
r o Geert/F-
REVIEW RECORD 01B O' ~5-
- 9. Action is being taken to develop an aging list, and to establish maintenance and replacement schedules (Ref. Section I.l.7 of the IE Bulletin 79-01B Qualification Sununary).
O l i i O - Gdbert/Commemmenth l t , _ . . . . _ _ . _ . . _ _ _ . _ _ _ _ _ _ _ _ , , . . _ _ . _ . . _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ - . _ _ _ -
VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. F-C3271 4.2 RADIATION DEFICIENCY Radiation exposure testing not addressed. ANALYSIS Limitorque Corp. indicates that the qualification test report applicable to these valve operators is FIRL Report F-C3271. This test report documents testing in a steam environment only. Radiation testing is not included. CONCLUSION Qualification to radiation exposure cannot be verified by FIRL Report , F-C3271. Ref. Note 9 on page 2-la of IE Bulletin 79-01B Qualification Summary for the action being taken to resolve this deficiency. i
~
O v Geert /P" l l
5.2 FAILURE CRITERIA O-DEFICIENCY Failure criteria not established for the test. ANALYSIS The function of a valve motor operator is to open and close its associated valve, and to provide position indication of the driven valve. Based on these functional requirements the failure criteria can be postulated as follows: The valve shall be cycled to its full opened and closed positions intermittently throughout and subsequent to the qualification testing. Valve operation and-position indication shall be monitored for each cycle. Any material degradation or failure of any electrical or mechanical functions shall be considered as failure of the specimen under test. CONCLUSION Limitorque Test Report F-C3271 indicates that the valve motor operator was energized and cycled periodically throughout the tesst program, and that operator and limit switch functions were observed. The test report documents the performance and results of this testing. Therefore, the omission of established failure criteria prior to testing is acceptable. 4 O Geert/Commonssaan
5.2 TEST EQUIPMENT ACCURACY O DEFICIENCY Test equipment accuracy is not addressed. ANALYSIS Test Report F-C3271, Appendix B provides a list of the test instruments used, and the date of the latest calibration of'some of the test instruments. However, the test report does not provide any specific information in regards to test equipment accuracy. CONCLUSION Since sufficient conservatism exists between the environmental test ! parameters and the specified ambient environmental conditions, and also since some test instrument calibration data is provided, the omission of specific l ) r test equipment accuracies is acceptable. l l 1 i l t
~ , - _
l
l( 5.2 EQUIPMENT MOUNTING AND SEALS DEFICIENCY The valve actuator was not mounted on an actual valve assembly. ANALYSIS Since the valve actuator was not mounted on an actual valve, seat leakage could not be measured when the actuator cycled fully closed. However, the actuator was installed on a mechanism to simulate seating by establishing a thrust load whenever the actuator was cycled throughout the test. CONCLUSION Since the valve actuator performed satisfactorily throughout the testing, it l is considered to have met the specified i..stallation requirements. lO l I l-l l l 1 f I
- 's_)
i Geert/P-1 I
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,i i: f t 1 5 ~' - SECTION 1.11 1
- VALVE MOTOR OPERATORS LIMITORQUE CORP. REPORT NO. B0003 i :
t f f O {. 5 I ) ( l l l l l' f l l l l Geert/c-4 I I
/, /1.
CRYSTAL RIVER UNIT 3 GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. $*e o No h .b Originator M. ,4. 8[ocr/s Date- 1 / 9/C '2. Reviewer b. aan _ Date 4-/2.9/62 Y YES NO_ 4.1 Testing to LOCA conditions inside containment adequate? N/A 4.2 Equipment qualified to service conditions outside YES containment? i 5 . ,1 Qualification method identified? Yes i 5.2 Each test requirement addressed? TES l O 5.3 Is qualification method other than testing adequate? NA 6.0 Margin requirements addressed? 7.0 Aging requirements addressed or replacement schedule gg established? l 8.0 Documentation adequacy addressed? WS COMMENTS: l No(E 1. BSV-3, Y,16,/7, %,3 7 puv-II,t1 Mniv-2.),2 v, y % 2 6,, 2, w g,e l Supptred by e p w, p n-1 g o egy.5, y, zg p,,_,,, ,g , q, , o v , n
"" PN%d UNet Sjoec. $0- 20 0 7, wpy.ssaC ms prefg;g Ytr Spec, go-2,qq 1,
- 2. M i21EviEW 9J.:.cogo Col 0TA8Nf MN/h '/SE.5 WHfCtf Stfoot.P
- 38. MEP n Ft EO. - d% y ,w)y/7[UPgg Supervisory Reviewer Date O
Gaerstcommon e ! ~
' FLORIDA POWER. CORP.
CRYSTAL RIVER UNIT 3 , REVIEW RECORD 01B Equipment Description Vo/ve Nc/cr depra/es-5 hee t/0 I te r b A/c5,) Spec. No.fse A/c b 2. Reviewer (name and date) Mr M , 8 dear /r
'1!9[82-Review Sununary:
4.0 SERVICE CONDITIONS 4.1 LOCA Conditions Inside Containment (1) o ressure profile completely Did the equipment envelope temperature the accident profile?andNp/A fe, NI-fe 3' o If "NO", see (2) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure? Ier/4',/, OA,>-/- 8ccc'?, Lc/jen 4.3 / , (3) o Is the equipment submerged during a DBE7 MO - o If "YES", is it qualified? (4) o Has equipmenc been tested to cisemical spray conditions, (with respect to PPM of boron and spray pH)
~~
h are equivalent to or greater than l those expec'ted for a DBE? A S'e g // eft 3 l l l- 4.2 Service Conditions outside of Containment l t (1) o Is equipment ide (tified as'being necessary to mitigate a HELB7 res / o If "YES" is itJ ualified to Service Conditions (temp., press., humidity)? Tas , S' , A/efe 9 / (2) o Is equipment identified as being necessary to mitigate a LOCA? Yes - o If "YES" is equipment in an area where fluids are recirculated from i inside containment to accomplish long-term core cooling following a LOCA? Yar # o If it is required to mitigate a LOCA, is equipment qualified to 100% humidity, the required temperature and pressure, and expected radiation? Y e s ,. S e e A /o / e $~ '
~
(3) o If. equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it, qualified to environments resulting from loss of HVAC? '[EA 8ee Nofe (' lO
REVIEW RECORD 01B {- 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified?
- a. Test, Type Tes f: sushiljed cry OCR Guidokset. Techess F. / '
- b. Analysis ,' ' '
- c. Both test and analysis,
- d. (Other),
5.2 Qualification by Test M Operability monitored during test? Yo S . Of, fepol-f Seco 3 h e fie n 4. S' a s, d Fia cr e s 18 D k s,,/ t,/. '
'o Test results demonstrate operability'? h s , E t,
~
A'e so rt //cc c3 Sec ticit s 4. T and f; O
.,o Test chamber environment envelopes service conditions? % v' 42 t.
Po onet 8000 T Sm-mn 4.3 as.d s eo A/,./e t,s . t /o Is ' equipment qualified to operate as required for the time necessary l to perform its safety function? Yes. S'ee foca/s,m,,hi/ #iv e 2. ' 4 Test specimen same as equipment bei'ng speciffsd? yo e l 1 pJ Roc Rem-t 60003 Se em s, 1,0 a ud 3. / d Test sequence as specified?Ws Ed nocrt Secc3. hrien 4$, 0
@ Was the same sacple tested to service conditions? ' yc_s For, Poper Y 00003 S'o c fres, 20 l Test Failure Criteria establisfied? Su m,o/em m /a/ peda 3 t /o ' '
4 Test Equipment accuracy requirements addredded? See supple.nu h/ paae 4 l /o Equipment mounting and electrical or sechanical seals represent speci-l fied installation? Ye s . 6'o c A/c/e 7 i 5.3 Qualification by combination of Methods
- 1. Is the equipment qualified for radiation by calculation? Mo 6 If "Yes", does the calculation satisfy postulated service conditions.
- 2. ects of chemicals on the Is equipment qualified by enclosure, gaskets, and seals? analysis for ef(A
/V/
o If "YES", does the analysis satisfy postulated service conditions. O
REVIEW RECORD 01B 3-O. 6.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? N/A INe A/ck M o Were the guidelines of Section 5.2 above satisfied? Yo r o If "YES", no further margin information is needed.
.o If "NO", document the following margins:
o Temp: +15 F _ o Press.: +10%. gauge, but not more than 10 lb F/in' o Rad: +10%
- o. Volt: 110% of rated o Freq.: 15% of rated -
o Time: +10% of time required following a DBE o Environmental Transients:. Initial and dwell at peak temperature applied
- twice o -Vibration
- +10% of response spectrum at mounting point 7.0 AGING o Was aging considered'in equipment qualification? E s
[ Ro C. bn.s-t Beco3 Sec f ton s 1.1.1. 2.1 3. 4. /. d. 2 as,d s 3 l o If '"NO", have materials susceptible to degrhdation from thermal or radiation aging been included in' aging list? o Have maintenance and replacement schedules been escal11shed 3 for equip-ment not meeting lifetime aging qualification?. A//A 8.0' DOCUMENTATION o Data is pertinent and auditable? Ie S o Documentation supports qualification method? Yp_r l l l \
- O
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VALVE MOTOR OPERATORS REVIEW RECORD 01B NOTES
- 1. BSV-3,4,16,17,36,37 DHV-11,12 DWV-160 EFU-3,4,7,8 FWV-14,15,29,30,31,32 MUV-23,24,25,26,27 WDV-405
- 2. DWV-160 EFV-3,4,7,8 FWV-14,15,29,30,31&32 were purchased under Spec. R02809.
WDV-405 was purchased under Spec. R02951. BSV-3,4,16,17,36,37 DHV-11,12 MUV-23,24,25,26&27 were supplied by B&W. . 3. The above listed valves are located outside containment. The qualification test report that is applicable to those valve operators is Limitorque Report B0003 which pertains to outside containment conditions. Limitorque Corp. indicates that Report B003 is also applicable to valve operstors CFV-11,12,15&l6 which are located inside containment. However, because of the more severe environmental conditions inside containment, qualification for these valve operators cannot be verified by B0003 (Ref. pages 2-34 and 2-44 of the IE Bulletin 79-01B Qualification Summary). Therefore, for the purpose of this review record, B0003 is being evaluated in regards to the valve operators located outside containment. Action is being taken to resolve the outstanding items con.cerning CFV-11,12,15&l6 in accordance with Note 9 on page 2-la of the IE Bulletin 79-01B Qualification Summary.
- 4. For Pressure Ref. Report B0003, Sections 2.5, 4.5.1 and Fig. 1. For Humidity Ref. Report B0003, Sections 2.1.2, 4.5.1 and 2.5.2. For temperature see Supplemental, page 1.
VALVE MOTOR OPERATORS REVIEW RECORD 01B NOTES (CONT'D)
- 5. For qualification to temperature, pressure and humidity see Note 4 above. For qualification to radiation see Report B0003, Section 4.3.
- 6. Auxiliary Building -
See the last paragraph of Section I.1.3 of the IE Bulletin No. 79-01B Qualification
- Summary.
Intermediate Building - Effects of loss ~of HVAC are presently being investigated.
- 7. Ref. Test Report B0003, Sections 4.1 and 4.5.
O O O . . . - , . -,-,.,._..c._. _- . . . . , . . . . - . - _ , f
VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. B0003 5.2 EQUIPMENT MOUNTING AND SEALS DEFICIENCY The valve actuator was not mounted on an actual valve assembly. ANALYSIS i Since the valve actuator was not mounted on an actual valve, seat leakage could not be measured when the actuator cycled fully closed. However, the actuator was installed on a mechanism to simulate seating by establishing and thrust load whenever the actuator was cycled throughout the test. 4 CONCLUSION O Since the valve actuator performed satisfactorily throughout the testing, it is considered to have met the specified installation requirements. 6 9
p 4.2 (1) TEMPERATURE REQUIREMENT U DEFICIENCY Test temperature profile does not completely envelope the required , temperature for the valve operators located in the Intermediate Building. i ANALYSIS Figure 1 of Report B0003 indicates a maximum test temperature of 250 F. Figure 4-4 of the IE Bulletin 79-01B Qualification Summary indicates that the required temperature profile reaches an initial peak of 345 F and then decreases to 250 F after 7 seconds and continues decreasing until the temperature reaches 212 F after 40 seconds. CONCLUSION i i-Since the initial peak of the actual temperature profile decreases to the test temperature valve of 250 F in 7 seconds and continues to decrease to 212 F, the valve operators are not considered to experience a surface temperature in excess of 250 F within this short period of time. Consequently, the t est temperature of 250 F is considered acceptable. I \ \ I O , Geert/Commanuseith
, _ - . .__ ., .. - . . .~
. - - . - _ - - - . -= . _ .-. .-
5.2 QUALIFICATION TIME O DEFICIENCY The post-accident operating time of one of the applicable valve operators exceeds the environmental qualification test time. ANALYSIS The required poet-accident operating time for WDV-405 is 30 days. Figure 1 of Test Report B0003 indicates the environmental testing was terminated after 16 days. CONCLUSION WDV-405 is located in the Auxiliary Building where the temperature, pressure and humidity remain at ambient conditions throughout a DBE. Although the environmental testing was terminated after 16 days, WDV-405 is considered qualified for long term operation in the specified ambient conditions. 1 l l-i O c mftm l 3-
i
<~N 5.2 FAILURE CRITERIA
(-sl ,, . DEFICIENCY Failure criteria not estsblished fo$ the test. ANALYSIS Thefunctionofavalvemotoroperaderistoopenandcloseitsassociated valve,andtoprovidepositionindicktion'ofthedrivenvalve. Based bn these functional requirements the failure criteria can be postulated as follows: The valve shall be cycled to its opened and closed positions intermittently throughout and subsec,oent to the qualification testing. Valve operation and position' indication shall be monitored for each cycle. Any material degradation, or failure of any electrical or mechanical functions shall be considered as failure as the specimen under test.
~y CONCLUSION Limitorque Report B0003 indicates that the valve motor operator was energized and cycled periodically thEoughout the test program, and that operator and limit switch functions were observed. This test report documents the performance and results of this testing. .Therefore, the omission of established failure criteria prior to testing is acceptable.
O
'N_/ , ,i Geert/Commoneesith -
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_.___.__.___.___________________J
. . i ,' ! q,] '( . N o= ..
r , t 5.2 TEST EQUIPMENT ACCURACY
, DEFICIENCY ,
.s
\
s Test equipment accuracy is not addressed.' [ ANALYSIS Test Report B0003, Table 1 provides much information regarding the types of test equipment used, and the calibration schedule'of this test equipment. However, the report does not provide any specific information regarding the
~
accuracy of the test equipment. CONCLUSION
. t i
Since sufficient conservatism exists between'the environmental test parameders and the specified environmental parameters, and also, since established calibration schedules are utilized for the test equipment, the c :ission.of specific test equipment accuracies is acceptable.
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(. O 3 4 SECTION 1.12 i VALVE MOTOR OPERATORS, -l LIMITORQUE CORP. REPORT NO. 600456 , O s i. l t l O w . Gdbert/Commonessen
/,73 CRYSTAL RIVER UNIT 3 GUIDELINES FOR TECHNICAL REVIEW 0F THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B Spec. No. 8es Mak. I originator R A. Skag /s '
Date 1/ // / F A
- Reviewer an.
Date 4 /29/A2 Q YES NO
~
4.1 Testing to LOCA conditions inside containment adequate? K 4.2 Equipment qualified to service conditions outside , M[A containment?
- 5. ,1 Qualification method identified? X 5.2 Each test requirement addressad?
5.3 Is qualification method other than testing adequate? N/k 6.0 Margin requirements addressed? 7.0 Aging requirements addressed or replacement schedule N established? 8.0 Documentation adequacy addressed? N COMMENTS: gbit t (AV- 12. 6 WDV- f o,79, 404 $ % 7 forcl.asecl 0 6 5'tec. AC) 95~' l Rcv-// sunked' hy B&w 2.. -ftw=_ TRE.NsE.w hc.oen comios MfN'T5ES kWnc w Smp se 'DE.sW MEE Ran, _Lpp b s/ 4 m n D 4),/r3 L n. c. Supervisory Reviewer Date v Gdbert/ Commonwealth
~ 1 FLORIDA POWER CORP. O carSrit vz unzr 3 REVIEW RECORD 01B L %lve. Motor operators Equipment Description Tay M r. CAV-116 PCV-Il \dDY'-40; 94; 4c6 4- vo7 Spec. No, fa n M/e I Reviewer (name and date) M A //tcud 2. ////#2. r Review Sumary: 4.0 SERVICE CONDITION _S, S 4.1 LOCl Conditions Inside Containment i Did the equipment temperature and pressure profile completely (1) o envelope the accident profile? Yes See A/rfe 2. o If "NO", see (2) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure? U rfgr. fese;t (ocy54,. reef /c,, 4.3 (3) o Is the equipment submerged during a DBE? A/n o If "YES", is it qualified? O (4) - a 19 =6 t c a t ci ic 1 7 c aiti . < ith to PPM of boron and spray pH) which are equivalent to or greater than veet l- those expected for a DBE? Tse,,' fos, , fe,ocef tl'oo4N. flct/en e 4 v.2. 4.2 Service conditions outside of Containment p (1) o Is equipment identified as being necessary to mitigate a HELB? o If "YES" is it qualified to Service Conditions (temp., press., humidity)? (2) o Is equipment identified as being necessary to mitigate a LOCA? o If "YES" is equipment in an area where fluida are recirculated from inside containment to accomplish long-term core cooling following a LOCA? o If it is required to mitigate a LOCA, is equipment qual'.fkad to 100% humidity, the required temperature and pressure, and expected radiation? (3) o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC7 lO
- ' REVIEW RECORD 01B 5.0 QUALIFICATION METHODS 5.1 How was equipment qualified and where was its method justified? ,
- s. Test, Iv'os f~e s / t \u, v/Wtcl par QOR Guidahn s s Sec]/ch C,1 '
- b. Analysi&;
- c. Both teet and analysis,
- d. (Other),
5.2 Qualification by Test-o Operability monitored during test? % s' f g f.oci-/' foowd S u & ,,, ti. u . S esd Tntsto rrt o Test results demonstrate operability? W st #er, fopor r 4 cc K 6 Sec flc st S L+, 4. T. U. E _ 4. A awil f. 6 o TestReece chsaber environmerit t coo ocs nmcos envdlopes 4.u.i servic55onditions? v.$ 3 m,J r,s; YLsnr //p c +cf,
- o Is equipment. qualified to operate as' requifed for the ti'me necessary to perform its safety function? b*/ct,fe.orf"(etM/ . Em o. p /r ""
o Test specimen same as equipment being 'specified? %e '~ fat 2eonVT 60049/ Se ef're n %>O Test sequence is specified? Td?R,f. &e-f (0o454 hhens 43 th O.o o o Was the same sayle tested to service ' conditions? ' Y& 5
- Eat . Ko om + (00</S'{ , feelien /, D i o Test Failure Crit'eria establishdd? Sao S von /cwwa h /' onoo '
I o Test Equipment accuracy requirements addresd4d? See Svenlem M fal PauQ 2. Equipment mounting and elec'trical or meetianical seals represent speci-
~
o
'fied installation? Ya r; Lo A/de 3 5.3 Qualification by Combination of Methods l 1. Is the equa.pment qualified for radiation by calculation? h/o o If "Yes", dr,es the calculation satisfy postulated service conditions.
i
- 2. Is equipment q'ualified by analysis for effects of chemicals on the
- enclosure, gaskets, and seals? h/o o If "YES", does the analysis' satisfy postulated service conditions.
O
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REVIEW RECORD .79-01B O 10.0 MARGINS o Were the guidelines in Sections 4.0 satisfied? Ya f o Were the guidelines of Section 5.2 above satisfied? Er o If "YES", no further margin information is needed. o If "NO", document the following margins: o Temp: +150 F _ o Press.: +10% gauge, but not more than 10 lb F/in' o Rad: +10% o Volt: 110% of rated , o Freq.: 15% of rated o- Time: +10% of time required.following a DBE o Environmental Transients: Initial and dwell at peak temperature applied ' twice o Vibration: +10% of response spectrum at mounting point 7.0 AGING . o Was aging considered in equipment qualification? Yes Au C, feom-Y 6004 V6 . 5% he n s 1. 0 nu2 3./ i O' o If "NO", have ' mater'ials susceptible to degradation from thermal or radiation aging been included in aging list? o Have maintenance and replacement schedules been established for equip-ment not meeting lifetime aging qualification? A/l/A 4 8.0 DOCUMENTATION o Data is pertinent and auditable?' Yey a Documentation' supports qualification method? Ypr R O n 7+~ y. .--.-.9ee- * ,my- - - ,, p ,-w u p.-- , ,-w- ,. - m =
VALVE MOTOR O . OPERATORS REVIEW RECORD 018 NOTES
- 1. -CAV-126 WDV-60,94,406 & 407 were purchased under Spec R02951.
RCV-11 was supplied by B & W.
- 2. Ref. Limitorque Test Report No. 600456, Sections 3.4.2, 4.4.1, and Figures 5 and 6.
- 3. Ref. Limitorque Test Report No. 600456, Sections 3.4.1 and 4.5.
4 o t I 1 f Geert/CommonweeRA
l l l I
< . VALVE MOTOR OPERATORS, LIMITORQUE CORP. REPORT NO. 600456 :
I 5.2 FAILURE CRITERIA DEFICIENC,Y Failure criteria not established for the test. ANALYSIS The function'of a valve motor operator is to open and close its associated valve, and to provide position indication of the driven valve. Based on these functional requirements the failure criteria can be postulated as follows: The valve shall be cycled to its full opened and closed positions intermittently throughout and subsequent to the qualification testing. Valve operation and position indication shall be monitored for each cycle. Any material degradatial or failure of any electrical or mechanical functions shall be considered as failure of the specimen under test. CONCLUSION Limitorque Test Report 600456 indicates that the valve motor operator was
' energized and cycled periodically throughout the test program, and that operator and limit switch functions were observed. -The test report documents
.the performance and results of'this testing. Therefore, the omission of established failure criteria prior to testing is acceptable.
. O Geert/Commonesse
_ , , _ . _ _ _ - ~ . . . _ . . . . . . . _ . _ . . . . _ , _ . . _ _ _ _ _ .
5.2 TEST EQUIPMENT ACCURACY . DEFICIENCY Test equipment accuracy is not addressed. ANALYSIS Test Report 600456, Appendix F, Table I provides information regarding the type of test and the calibration schedule of the test equipment. However, the test report does not provide any specific information in regards to test equipment accuracy. CONCLUSION i Since suff.icient conservatism exists between the environmental test parameters and the specified environmental parameters, and also since j established calibration schedules are utilized for the test equipment, the omission of specific test equipment accuracies is acceptable.
~
4 o O Gdbert/CJunonwesRA
O 5.2 EQUIPMENT MOUNTING AND SEALS DEFICIENCY The valve actuator was not mounted on an actual valve assembly. ANALYSIS Since the valve actuator was not mounted on an actual valve, seat leakage could not be measured when the actuator cycled fully closed. However, the actuator was installed on a mechanism to simulate seating by establishing a thrust load whenever the actuator was cycled throughout the test. CONCLUSION Since the valve actuator performed satisfactorily throughout the testing, it is considered to have met the specified installation requirements. /~% U G O Gdbert/CommonwesRh
l _ i I * ( r
- SECTION 1.13 l
,I 1 i VALVE MOTOR OPERATORS, l i LIMITORQUE CORP. REPORT NO. F-C 2232 1 LO l l f' 4 I-I
- c. +
F l l [ i E t Geert/Commenmesth t
, - , , _ . . . . ..--y,-m_.,--__,-....,.... . , - . . .._____,-.,;..,_.._._-,.__-._,___,-_-, . _ _ . . , _ _ . _ _ _ . _ _ _ , . _ . _ . - . . _ - _ . _ - _ . . . - - . - , . . .
),b CRYSTAL RIVER UNIT 3 3
a GUIDELINES FOR TECHNICAL REVIEW OF THE DISCUSSIONS OF COMPLIANCE WITH IE BULLETIN 79-01B
. . Spec. No. 89e DIE I Originator 9, A 8/coc/s Date 2./3/ G 2.
Reviewer b anc Date 4./36,/92 P YES NO 4.1 Testing to LOCA conditions inside containment adequate? X 4.2 Equipment qualified to service conditions outside containment? y 5.1 Qualification method identified? X
'5.2 Each test requirement addressed?
5.3 Is qualification method other than testing sdequate? N[A 6.0 Margin requirements addressed? N 7.0 Aging requirements addressed or replacement schedule K established? . 8.0 Documentation adequacy addressed? % COMMENTS: NOTE .1 - AHv-IB 9Ic wer e fantwwc/ uwe/oe Seec. Ro262s WDV-3 ovas furc$wrec/ vac/er Spec, goggog OWV-//0 f /// weYs- pumhmc/ under CAV~ l, 3, t/ 1 S NUV- 18, S3,2 7 7, 40, V/, 2.98, 2 79, g.g, o y, g g g ,,., Sufj214ect by B v w, 5 ~ SEMIE& E5ECOP-Q 00MhQth)$ AHA GVMS wmW '** BG. VE R ifs E D, - %ApL /P A>M Y7N# ' #' Supervisory Reviewer Date Geert/CommtowealtA
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l l l l FLORIDA POWER CORP. CRYSTAL RIVER UNIT 3 l i REVIEW RECORD 01B Equipment Description Va/W Nefer Caua/'sr o [ Sate A/a/a 1 tor Tao Mar.) Spec. No. fde Wnfo 2 Reviewsr'(name and date) M M , M [ e cr / r G.[3/#2.- Review Susmary:- 4.0 SERVICE CONDITIONS 4.1 IDCA Conditions Inside Containment MUV- . PE II8# i' A N Y-18 Y IC CAY- O ,Y Y I) fo, W,2.58,23<1,2 Co + 2.6I WDV-3 A1) o Did the equipment temperature andJa, pressure profile completaly L on/omets/a/ peaa i envelope the accident profile? ' " o If."NO", see
- 42) o Has equipment been tested for normal radiation over the equipment life, plus the DBE exposure?
Soo Svog/mson/n/ p3,o ,, 1 W3) o Is the equipment oubmerged during a DBE? No o If "YES", is it qualified? i ! v(4) o Has equipment been tested to citemical spray conditions, -(with respect
- to PPM of boron and spray pH) which are equivalent to or greater than those expected for a DBE? In, hn/.sw o du/ puoo 3 av -
o a 4.2 Service Conditiona Outside of Containment hpp//es to DNV-//0 +/// MUV-l&G1257) (1) <o Is equipment identified as being necessary to mitigate a HELB? Yes
/o If "YES" is it qualified to Service Conditions (temp., press.,
humidity)? Yac. Sie M./o ~J (2) /o Is equipment identified as being necessary to mitigate a LOCA? ur
/o If "YES" is equipment in an area where fluids are recirculated from inside containment to accomplish-long-term core cooling following a LOCA? U_r
/o If it is required to mitigate a LOCA, is equipacnt qualified to '
~
100% humidity, the required temperature and pressure, and expected radiation? 8ea A/a/t d/ (3) /o If equipment is not served by redundant HVAC systems powered from onsite emergency sources, is it qualified to environments resulting from loss of HVAC7 See /W fo E O
REVIEW RECORD 01B 5.0 QUALIFICATION METHODS
~
v5.1 How was equipment qualified and where was its method justified?
- a. Test, T po_ f a sf:' ' jus l14>'cul ocr DOR Gu;clolin o s. Detien s~./
'b. Analysis ,' ' '
- c. Both test and analysis,
- d. ~(Other),
5.2 cualf fication by Test
/o Operability monitored during -test? %r. Pet. F/EL Leid '
F- C2.131 -O/ . S'e cf/ ort ttr', B ___ o Test results demonstr' ate operability? % e r fa t. F/RL Re cort ' f~-C2152-O f Sumas~v en. J % Lik i ud' Test chamber environment envelopes service conditions? ~ [ee JV$ $9 C
/o Is equipment qualified to operate as required for the time necessary to perform its safety function? Jan A/a/a 7
/c Test specimen same as equipment being specified? Yo, . Fas, L;m f rp -
Seoas h (6 0190
~
co n c, L . nu e) fon11/S YSe-Old u lo Test ' sequence as specifiGd? %i. fc t. FlfL fa mn-f F- C113 2.-ci oms z In
~4 to Was the s.une sample tested to service conditi'ons? Yo c .
b A. F1RL 2. ~ A F-Cr2.31.- e I L u% .- v ,
-3 Test Failure Criteria established? So , si on/a..,s u k/ mL- f v6 Test Equipment accuracy requirements addressed?
Sen L os/o uso a fa / be K g o- Equipment mounting and 41ectrical or nischanical seals represent speci-fied installation? Yar F/RL Ea m ef F-( 2.232.-ol, So e //c a 71Z' i
~5.3 Qualification by combination of Methods
- 1. Is the equipment qualified for radiation by calculation? Mo _
o If "Yes",-does the calculation satisfy postulated service conditions.
- 2. Is equipment qualified by analysis for effects of chemicals on the enclosure, gaskets, and seals? A/a o If "YES", does the analysis satisfy postulated service conditicas.
O
REVIEW RECORD 01B 6.0 MARGINS 4 Were the guidelines in Sections 4.0 satisfied? Yes - e.yce f or inelxaitsd' ca Lanlewsenhal wo.is- $ llirv V (Teb N..te M ~ a Were the guideline's' of Section '5/2 above satisfied? yer o If "YES", no further margin information is needed. j o If "NO", document the following margins: r o Temp: +150F _ l o Press.: +10% gauge, but not more than 10 lb F/in' i o Rad: +10% o Volt: 110% of rated o Freq.: 15% of rate ~d o Time: +10% of time required following a DBE o Environmental Transients: Initial and dwell at peak temperature applied twice
- o Vibration: +10% of response spectrum at mounting point 7.0 AGING 4 Was agin,g considered in equipment qualification? No
.c If "NO", have =nterials susceptible to degradation from thermal or
! radiation aging been included in aging list? See Noh. 9 A Have maintenance and raplacem:nt schedules been established for equip-ment not meeting lifetime aging qualification? Saa /afe 9 8.0 DOCUMENTATION o Data is pertinent and auditable? YES o Documentation cupports qualification method? Yer _ O 4
-e - e- --- ~ , , - - , _ - . -n - -,
I VALVE MOTOR OPERATORS REVIEW RECORD 01B NOTES
- 1. AHV-1B&lC CAV-1,3,4&5 DHV-110&111 MUV-18,40,41,53,257,258,259,260&261 WDV-3
- 2. A3V-1B&lC -
Spec. R02821 t WDV-3 .- Spec. R02809 CAV-1,3,4&5 and all listed MU valves - Supplied by B & W , DHV-110&111 - Spec. (LATER)
- 3. Temperature, pressure and humidity in the Auxiliary Building remain at ambient conditions throughout a DBE (sce Section I.1.3 of the IE Bulletin 79-01B Qualification Summary).
l l 4. For temperature, pressure and humidity see Note 3 above.. For radiation see Supplemental page 4.
- 5. Ref. the last paragraph of Section I.1.3 of the IE Bulletin 79-01B Qualification Summary.
I .
- 6. Service conditions are enveloped by the test chamber environment except as noted on Supplemental pages 1 through 4. Ref. FIRL Report F-C2232-01 Section III.B(4), Figure 3, and test data sheets; and Limitorque report 600376A Section 3.1.3.
- 7. The valve operators are qualified to operate for their required post DBE operating times except as noted on Supplemental pages 1 through
- 4. Ref. FIRL Report F-C2232-01 Summary and Table 1, and Limitorque Report 600376A Section 3.1.3. Although the limit switch failed on the test specimens, a material change was instituted to alleviace this problem (Ref. Limitorque Report 600198 Section 7).
Geert/r-
- - - -.-.-,-m, . .--.r. % ,-s w g_myg- _ _ , u,. ,__.- ,,y_, . o mm m, . _ , . _ _,__._.__y ,_._r,,_ - _ ,y . . . , _ , . , . _ . . _ , , , , _ . - , - - .
q VALVE MOTOR OPERATORS REVIEW RECORD 01B 1 The exceptions and proposed corrective actions stated on Supplemental pages 1 through 4 pertain to instances where either the test parameter was not addressed, or the test parameter was maintained for an insufficient length of time. Otherwise the test parameters enveloped the environmental requirements with sufficient conservatism that no further margin information is required. .
- 9. Action is being taken to develop an aging list, and to establish maintenance and replacement schedules (Ref. Section I.l.7 of the IE Bulletin 79-01B Qualification Summary).
O i e O Gdbert/Commoneesnh
. _ . _ _ . _ _ _ - . . . . _ _ _ , _ - _ . _ _ ~ . . . _ , _ _ _ . _ . - _ _ . _ _ . . . - . _ _ . . , _ _ . _ . . _ _ _ _ _ _ _ . . _ . . . - . . - _ _ _ _ _ . _
4.1 (1) TEMPERATURE AND PRESSURE DEFICIENCY Temperature and pressure not completely enveloped.
-ANALYSIS Valve operators AHV-1B&lC; CAV-4&S; MUV-40,41,258,259,260&261 and WDV-3 are only required to operate for one minute Post-LOCA. The qualification time for these valves'then is one hour plus one minute, and for these valves the required accident temperature and pressure is enveloped by the test temperature and pressure (Ref. Franklin Institute Report F-C2232-01 Fig. 3 and Test Data on pages 24 through 27). For CAV-l&3, which must be operational for 30 days' Post-LOCA, the test pressure is adequate (Ref.
Franklin Institute Report.F-C2232-01 Fig 3) but the test temperature is not i documented for an acceptable length of time. l l CONCLUSION Valve operators AHV-1B&lC; CAV-4&5; MUV-40,41,258,259,260&261 and WDV-3 have been subjected to the required temperature and pressure. For CAV-1&3 j the test pressure is adequate, but not the required, test temperature. Action is being taken to resolve this deficiency in accordance with Note 9 on page 2-la of the IE Bulletin 79-01B Qualification Summary. i i I-l l l O i- Geert/Cammesseeth __ . . , , . . . . _ _ . . , _ _ _ . . _ _ . _ . . ~ _ . . _ . _ _ ,..._,_ ._ _._._ _ _, . _ _ . _ , _ . _ - , - _ . . _ . _ . . _ . _ . _ _ _
4.1 (2) RADIATION
- DEFICIENCY Most of the valve operators were not subjected to radiation exposure testing.
ANALYSIS For valve operators CAV-1,3,4&S the supplier states that Limitorque Report 600198* and the radiation portion of Laitorque Report 600367A** are applicable to these operators. For AHV-1B&lC; MUV-40,41,258,259,260&261; and WDV-3 Limitorque Report 600198 is the only applicable report, and 600198 does not address radiation exposure testing.
~ CONCLUSION CAV-1,3,4&5 have been subjected to the required radiation exposure (Ref.
Limitorque Report 600376A Section 3.1.3). For AHV-1B&lC; MUV-40,41,258,359,260&261 and WLV-3 action is being taken to resolve this deficiency in_accordance with Note 9 on page 2-la of the IE Bulletin 79-01B Qualification Summary.
- Limitorque Report No. 600198 summarizes the actual testing documented in FIRL Report No. F-C2232-01.
** Limitorque Report No. 600376A summarizes the actual testing documented in n v-FIRL Report No. F-C3441.
Geert/Commeneenth
gS 4.1-(4) CHEMICAL SPRAY U DEFICIENCY: Chemical spray conditions were not adequately simulated for all applicable valve operators. ANALYSIS The Boron content and the pH of the test spray solution is greater than that of the required spray solution; however, length of time that the test spray was maintained is 4 hours. All the applicable valve operators except CAV-l&3 have a Post-LOCA operating time of less than 4 hours. CAV-1&3 have a Post-LOCA operating. time of 30 days during which the actual chemical spray time could be as much as 24 hours. CONCLUSION ~O The Boron content and the pH of the test spray solution is adequate to verify the qualification of all the applicable valves to the required chemical environment. The duration of the test spray solution is adequate for all the applicable valves except CAV-1&3. For CAV-1&3 action is being taken to resolve this deficiency in accordance with Note 9 on page 2-la of the IE Bulletin 79-01B Qualification Summary. %s Gdbert/Commonseoth
4.2 (2) RADIATION DEFICIENCY The valve operators were not subjected to radiation exposure testing. ANALYSIS Limitorque Report 600198 is the applicable tesst report for valve operators DHV-110 & 111 and MUV-18,53 & 257. Report 600198 does not address radiation exposure testing. CONCLUSION Ref. Note 9 on page 2-la of the IE Bulletin 79-01B Qualification Summary for the action being taken to resolve this deficiency. O o O Geert/Cammoneesith
, g 5.2 FAILURE CRITERIA
]
DEFICIENCY Failure criteria not' established for the test. ANALYSIS
. The function of a valve motor operator is to open and close its associated valve, and to provide position indication of the driven valve. Based on the,se functional requirements the failure criteria can be postulated as follows:
The valve shall be cycled to.its opened and closed positions intermittently throughout and subsequent to the qualification testing. Valve operation and-position indication shall be monitored , for each cycle. Any material degradation, or failure of any 7- - electrical or mechanical functions shall be considered as failure of
\/ the specimen under test.
. CONCLUSION FIRL Report F-C2232-01 indicates that the valve motor operator was energized and cycled periodically throughout the test program, and that operator and limit switch functions were observed. This test report along with Limitorque Report 600198 document the performance and results of this testing. Therefore, the omission of established failure criteria prior to testing is acceptable.
O Gdhert/Commenmeelth
l 5.2 TEST EQUIPMENT ACCURACY DEFICIENCY Test equipment accuracy is not documented. ANALYSIS For the radiation exposure testing of CAV-1,3,4&5 documented in Limitorque Report 600376A, calibration of the dose rate meter and probe is documented in the Radiation International, Inc. report of May 23, 1972.- For all other applicable environmental' testing which is documented in FIRL Report ! F-C2232-01, no test equipment accuracy or calibration information is provided. CONCLUSION , For all the subject valve operators, except CAV-1&3, the test parameters A documented in FIRL Report F-C2232-01 envelope the required environmental parameters with sufficient conservatism that the omission of test equipment accuracy is acceptable. For CAV-1&3, which are located inside containment and are required to be operational for 30 days, test equipment accuracy is of no concern because the testing documented FIRL Report F-C2232-01 is , insufficient to support qualification of these valve operators. l 4 O O L) Geert/Commonweeth 5 1
,, -y yev.--,r-,,,.-,, -~-...-+,-----,---,-e---,--- -.
- a . u - - a .g-O SECTION 2 MATERIAL ACING ANALYSES 4
i e O. W l i l I e f f b O Geert/Commennenth
i O TABLE 1 COULD MOTOR DIVISION - FAN MOTORS O O Geert/Commonesse
O O O TABLE NO. 1 Originator: 22 -- 8df/4 Verifier b [- dl!EP i f i l EQUIPMENT: Fan Motors MANUFACTURER:
- Could Motor Division
- i. TAG NOS.: AHF-15A,15B SCREW REF.: 2-4 I,
RAD. DOSE: 5.6 x 104 i AMBIENT TEMP.: 400 C ! Allowable Radiation Suggested Inspection l Exposure of Materials Acceptable Life of 4 Source of Materials Based & Surveillance ! Equipment Materials Rads Information on Thermal Aging Schedule Comuments l Nomex 1 x 108 Note 1 Aromatic polyamide paper t l Dacron and Mylar 4.4 x 106 Note 2 Note 5 Note 6 Polyethylene l terephthalate i Polyester Resin 1 x 105 Note 3 l l Acrylic Resin 7 x 105 Note 2 Note 5 Note 6 (PMMA) l Glass Cloth I x 1012 Note 4 Fiberglass l Epoxy Varnish 5 x 106 Note 4 Note 5 Note 6 Assumed radiation value of varnish cambric l Silicone Rubber 4 x 106 . Note 4 9 i _
TABLE NO. 1 NOTES
- 1. -This radiation value was obtained from the Appendix C, Table C-1 of
~
1E Bu11etin.79-018. Several other documents present radiation values for L _similar material,.however, the stated radiation dose is directly applicable to materist under'the Nomes trade name. The radiacion dose results in_24% loss of elongation. l-
- 2. The radiation value obtained from EPRI Report #NP-2129 " Radiation Effects on Organic Materials in Nuclear Plant," dated November 1981.
- 3. - Polyester is used in the motor insulation system in a fona of varnish applied in combination with glass cloth and in several layers of final l
i insulation. The listed radiation dose is the lower value for polyester resin (unfilled) obtained from the document referenced in Note 2. This value assures a sufficient degree of conservatism, considering the
-radiation dose accumulated during the motor service life. Higher
( radiation values are documented and available for polyester glass laminates (IE Bulletin 79-018, Appendix C, Table C-1). l
- 4. The radiation value was obtained fras' tables of B&W Aging Assessment, r
Document No. 77-1127001-00, dated July 1981. i
- 5. The severe duty insulation system of Could Motors is Class 'F' with a rated peak temperature of 1550 C. It consists of various insulating materials as identified in the above table and the Gould Electric Motor i Division letter, dated October 8, 1980. To conduct the thermal evaluation and to determine the essential characteristics of the system during the motor service life at the ambient operating temperature of 400 C (1040 F), the following documents were used to provide thermal I
aging data: Wescinghouse Electric Corporation " Evaluation of AC Motor Insulation Systems by 1EEE 275."
,--m-* -+ .- A- ,r-,.-ewyww w w ww- ww--W t--+w -* ew--o-w- ,e-w=--www-wew,wwcotw -w ev ve er+ w.*-e+*eww+w*ew-e-e+w-*o' e we-
- d#,
4 I+ ?# IMAGE EVALUATION g s- ,. 4) res1 1 aeer <m1 33
+ r, 1.0 l;an en gljEIE i,i [m En la 1.25 1.4 1.6 1
4 150mm 4 6" d*%fzz #p
/# 4 ++$' tk*44 4/ , k+
t B&W Document No. 77-1127001-00, dated July 1981. l IE Bulletin 79-01B, Appendix C.
"Underscar. ding Electrical Insulation Life" by James M. Frank, Sorgel Electric Corp. dated October 1, 1970 The referenced documents provide thermal aging data and insulation systems characteristics that can be used only as comparative values.
Differences in the structure of insulation systems and operating modes of
- individual motors do not permit direct determination of the motor service life with respect to thermal age related degradation of the insulation system. Continuous operation near or at the specified HP rating and the rated temperature is a degrading factor considerably decreasing the motor -
! service life. Similarly, motors operating below their rated temperatures
- are expected to have longer service life according to the 100 C rule.
i [ With a respect to various operating conditions and based on. conclusions of referenced documentation it is obvious that the insulation system of Could Motors is~ susceptible to a degradation due to the thermal aging. . To evaluate the' significance of the age related degradation and to assure the motor reliable performance, inspections and surveillance programs are suggested.
- 6. Periodic preventive maintenance shall be in accordance with the manufacturer's recommendations and established cycles. The insulation
; dielectric value shall be measured at least once a year.
An inspection of the motor coils insulation shall be conducted during . each maintenance shutdown or at the time when insulation resistance is 4 measured. The inspection of motor coils shall consist of visual check for cracks, peeling, ncn-adherance, discoloration or other signs of a loss of
- physical integrity.
J
,.--m, -,%. .,,._,..,,.-.,-....,,,.,.,-,,,,.c..+
Maintenance records shall include results of inspections and measuremento of insulation dielectric values. I , CONCLUSION The results of insulation material review for radiation and thermal aging degradation indicate that Gould Co. motors are suitable for environmental , conditions as specified in above table. However, surveillance and maintenance programs shall be adhered to es close as possible to detect any deterioration of the insulation system and thus prevent the equipment failure. Only qualified personnel shall be permitted to evaluate the insulation condition, its dielectric values and eventually recommend the equipment replacement. O O - I, . . _ - - , , . . - - , . .
.. - - ...._.~ . . . __. . - __- - - .. .
4 iO r ] TABLE 2 L WESTINGHOUSE CORMRATION - PUMP MOTORS 4 i 1 . l 6 0 - Gdtert/Commemmesah
. - . . - . . - - - .-. - - -... - -- . ... . .- .. -- - .-. - - = -- - . - --. - -.. --.. - - - -- - - - -
O O O.
~
TABLE NO. 2 Originator: 2 #- ~ [/fM Verifier: $. [- [h 4Ek7 EQUIPMENT: Pump Motors MANUFACTURER: Westinghouse TAG NOS.: BSP-1A, 1B DHP-1A, 18 MUP-1A,1B,1C SCREW REF.: 2-23 2-55 2-141 RAD. DOSE: 1.7 x 105 6.1 x 106 1.2 x 106 AMBIENT TEMP.: 400 C 400 C 400 C , Allowable Radiation Suggested i Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance ! Equipment Materials Rads Information on Thermal Aging Schedule Comments l Material Identification Note 2 FCS 3479 1/18/83 Not Available i i i i 4
TABLE NO. 2 NOTES 1._ Westinghouse Corp. did not provide any qualification documentation or material identification. Inspection and surveillance program is
- suggested and described in Note 2.
- 2. Periodic preventive maintenance shall be in accordance with the manufacturer's recommendations and established cycles.
The insulation resistance shall be measured at least once a year.
~
Inspections of motor coils shall include visual check for cracks,
- peeling, non-adherance, discoloration or other signs of loss of physical integrity.
The inspection shall be conducted during each maintenance.. shutdown or at time of resistance measuring. l.( Maintenance records shall include results of inspections and measurements of insulation dielectric values. - CONCLUSION: l Surveillance and maintenance programs shall be adhered to as close as possible to detect any deterioration of the insulation system and thus prevent the equipment failure. Only qualified personnel shall be permitted to evaluate the insulation condition, its dielectric values and eventually recommend 'the equipment replacement. l l l IO l I
~ , . . , -,---,,.J- , - - - - - , , _ - ~ - - - , - - . - . - - . .
O - TABLE 3 ELECTRIC-MACHINERY CO. - PUMP MOTORS
~
O - 1 l O-l Gdbert/Commonessah i i
~, ,n--. . . _ . - , . , . , . ,,,,._e,, , , , - _ . , , , _ , - . , _ , , , . . , _ _ _ _ , . , , _ . _ _ , _ , , . , _ , , _ _ . , , , . , . , . . . , , _ , , , , , _ _ _ _ , _ _ _ _ _
O O O TABLE NO. 3 Originator: 7I * //#MJ Verifier: . hc/[. b 2Jr/83 EQUIPMENT: Pump Motor MANUFACTURER: E-M TAC NOS.: EFP-1 RWP-2A, 2B RWP-3A, 3B SWP-1A, 1B SCREW REF.: 2-66 2-181 2-182 2-188 RAD. DOSE: 1.0 x 104 5.6 x 104 5.6 x 104 5.6 x 104 AMBIENT TEMP.: 400 C 400 C 400 C 400 C Allowable Radiation Suggested -
. Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments _
Mica & Class Insul. 4.0 x 106 Note 1 Note 3 tapes, C.E. Product No. 77869 Varnish, Sterling Product 5.0 x 106 Note 2 Note 3 Note 4 No. Y-493 Varnish, Sterling U-835 5.0 x 106 Note 2 Note 3 l ' l l
TABLE NO. 3 NOTES
- 1. This value is from Appendix B of the B&W Ag;ing Assessment, Document No. 77-1127001-00 dated July 1981. This docueent indicates that a similar material (mica with shellac) requires a radigtion dose of 4.0 x 106 rads to produce a 25% property change. Since the highest radiation level to which the actual mica and glass insulation tape is exposed to is 5.6 x 104 rads, it is considered acceptable for the specified radiation environment based on this comparison of materials.
- 2. This value is from Appendix B of the B&W Aging Assessment, Document No. 77-1127001-00 dated, July 1981 which indicates that'a similar material (varnished cambric) requires a radiation dose of 5.0 x 106 rads to produce a 25% property change. .Since the highest radiation level to which the actual varnishes are subjected'to is 5.6 x 104 rads, they are considered acceptable for the specified radiation environment based on this comparison of materials.
- 3. The insulation of E-M Co. motors is Class B with rated peak temperature
( of 1300 C. The mica-clad insulation system consists of several layers of insulation material: Polyester glass, vacuum pressure impregnated mica tape, glass tape and multiple coats of. varnish. In order to conduct functional thermal evaluation and to determine the essential characteristics of the system during the service life at thi ambient operating temperature of 400 C, a search in available documentation was conducted to locate identical or similar insulation systems which are
- provided with suitable qualification data or performance characteristics.
The following documents were used for compilation of thermal aging information relative to previously mentioned mica-clad insulation system
- l. materials:
- a. Westinghouse Electric Corporation " Evaluation of AC Motor Insulation Systems by IEEE 275".
I O
----------y ..-,e.,,n- -- w.e..w- n,- -s ..,r..m,,. , , , - , , -r-- m-- ,-,w,--.e.,,,-,,---.wr-...w,-m . . . - - ~- , , - ..,-w-- .y.-, - -- e-,-- - - - - - - -.---we- --e-e -
- b. B&W Document No. 77-1127001-00, dated July 1981.
- c. IE Bulletin 79-01B, Appendix C.
- d. IEEE Transactions on Electrical Insulation, Volume El-8, Number 2, dated June 1973, " Aging Properties of Mica Insulation Systems Impregnated with Solventless Resin for Generator Stator Coils."
- e. " Understanding Electrical Insulation Life" by James M. Frank Sorgel Electric Corp. Dated October 1, 1970.
The referenced documents provide thermal aging data that cannot be used as actual service life but only as comparative values. The service life of insulation materials and systems is directly proportional to operating temperatures according to 100 C rule. Continuous operation near or at the specified rating and temperature.is a degrading factor considerably
~
decreasing the service life. Therefore to determine the qualified life l of insniation materials used in E-M Co. motors, motor operating conditions would have to be evaluated on individual basis. i . From the referenced documents and with the respect to various operating conditions it was assessed that mica-clad insulation system is susceptible to degradation due to thermal aging. To evaluate the significance of age related degradation and also to assure the reliable motor performance, inspection and surveillance programs are suggested.
- 4. Periodic preventive maintenance shall be in accordance with the manufacturer's recommendations and established cycles.
l . The insulation resistance shall be measured at least once a year. Inspections of motor coils shall include visual check for cracks, peeling, non-adherance, discoloration or other signs of loss of physical integrity. C:)
- m. _ __ ___
-The inspection shall be conducted during each maintenance shutdown or at
( time of resistance measuring. Maintenance records shall include results of inspections ~and measurements of insulation dielectric values. CONCLUSION: The results of insulation material review for radiation and thermal aging degradation indicate that E-M Co. motors are suitable for environmental conditions as specified in above table. However, surveillance and maintenance programs shall be adhered to as close as possible to detect any deterioration of the insulation system and thus prevent the equipment failure. Only qualified personnel shall be permitted to evaluate the insulation condition, its dielectric values and eventually recommend the equipment replacement. O. 1
4 l TABLE 4 CENERAL ELECTRIC CO. - PUMP MOTORS 4 4 4 de O e 9 l i e o Geert/Commenesoth e
4
, O .
O O
. TABLE NO. 4 Originator: T/ d I/8MJ Verifier: b.d- b 23!II EQUIRMENT: Pump Motor j MANUFACTURER: General Electric j TAC NOS.: DCP-1A, IB
) SCREW REF.: 2-54 I RAD. DOSE: 5.6 x 104 !. AMBIENT TEMP.: 400 C j Allowable Radiation Suggested { Exposure of Materials Acceptable Life of Inspection i Source of Materials Based & Surveillance i Equipment Materials Rads Information on Thermal Aging Schedule Comments l Motor Insulation System 5 x 105 Note 1 Note 2 Note 3 Material identification Class 'B' not available i 1 l l l 5
TABLE NO. 4 NOTES 1.- Ceneral Electric Co. letter dated September 10, 1980.
- 2. The insulation system of CE Co. Motors is-Class 'B' with rated peak temperature of 1300.C. Since materials used in the insulation system t
were not identified it may be assumed that thermal characteristics of the i system are comparable to characteristics of Class 'B' motors for which at least some thermal aging data are available. The following documents were used in the evaluation of Class 'B' motor insulation system: Westinghouse Electric Corporation " Evaluation of AC Motor Insulation Systems by 1EEE 275."
" Understanding Electrical Insulation Life" by Jerome M. Frank, Sorgel Electric Corporation, dated October 1, 1970.
The thermal aging data provide only comparative values and can not be used in determination of the actual equipment service' life. The service life of insulation systems and materials used is directly proportional to L motor operating temp.ratures according to the 100 C rule. Continuous operation near or at the specified motor rating and temperature is a degrading factor considerably decreasing the motor service life. In order to determine the qualified life of the subject motors, the individual motor operating conditions would have to be evaluated on an individual basis. With the information available in the referenced documents and with a respect to various operating conditions it was assessed that motor insulation systems are susceptible to a degradation due to the thermal aging. To evaluate the signifitance of age related degradation and also assure the reliable motor performance, inspection and surveillance programs are suggested. O
- 3. Periodic preventive maintenance shall be in accordance with the manufacturer's recommendations and established cycles.
The insulation dielectric value shall be measured at least once a year. An inspection of motor coil insulation shall be conducted during each maintenance shutdown or at the time of insulation resistance measuring. The inspection of motor coils shall consist of visual check for cracks, peeling, non-adherance, discoloration or other signs of a loss of physical integrity. Maintenance records shall contain results of inspections and list measured values of the insulation resistance. CONCLUSION: The results of insulation material review for radiation and thermal aging degradation indicate that GE Co. motors are suitable for environmental conditions as specified in above table. However, surveillance and maintenance programs shall be adhered to as close as possible to detect any deterioration of the insulation system and thus prevent the equipment failure. Only qualified personnel shall be permitted to evaluate the insulation condition, its dielectric values and eventually -reconnend the equipment replacement. d O
O 4 t TABLE 5 ALLEN-BRADLEY CO. - LOCAL MOTOR STARTERS AND CONTACTORS l , O f O Geert/Commonessah
O O O TABLE NO. 5 Originator: 22 -- 8N/dt Verifier: 'd- Es/3T
~
EQUIPMENT: Local Motor Starters and Contactors MANUFACTURER: Allen-Bradley (Bulletin 205) TAC NOS.: EFV-11,14 FWV-33,34 ASV-5 32,33 35,36 FWV-161,162 MSV-55,56 MTMC-4,5 MTMC-7 SCREW REF.: 2-20 2-71 2-80 2-81 2-89 2-8 2-9 RAD. DOSE: 1 x 104 1 x 104 1 x 104 1 x 104 1 x 104 AMBIENT TEMP.: 400 C 2.6 x 104 1.6 x 105 400 C 400 C 400 C 400 C 400 C 400 C Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Equipment Materials Source of Materials Based & Surveillance Rads Information on Thermal Aging Schedule Coauments Mfr's UL Years Code Index Fosta 523 (Nylon 6) 8.7 x 104 Ref. 5 32 Note 7.1 Note 8 & 9 R 650 C Ref. 1 Celcon (Polyacetal) 6 x 105 Note 3 >40 Note 7 T 900 C Ref. 1 Durez 16744 (Phenolic) 3 x 105 Note 4 >40 Note 7 M 1500 C Ref. 1 Durez 1544 (Phenolic) 3 x 105 Note 4 >40 -Note 7 E 1500 C Ref. 1 Spauldite (Asbestos Cloth 1 x 109 Ref. 5 >40 Note 7 JJ Phenolic Resin) 1550 C Ref. 1 l Rosite 3250A (Polyester 4 x 108 Ref. 5 >40 Note 7 t Compound 5% Class LL 1300 C Ref. I i Reinforced) I i
O O . O TABLE NO. 5 (Cont'd) Allowable Radiation Suggested . Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments Mfr's UL Years Code Index i Delrin 507 (Polyacetal) 6 x 105 Note 3 >40 Note 7 Y 850 C Ref. 1 Nylatron CSHS (Nylon 6-6) 8.7 x 104 Ref. 5 32 Note 7.1 Note 8 & 9 S 650 C Ref. 1 Cymel 1077 (Cellulose 6.7 x 106 Ref. 5 >40 Note 7 0 1500 C Ref. 1 Filled Melamine) Delrin 500 (Polyacetal) 6 x 105 Note 3 >40 Note 7 W 850 C Ref. 1 i Plenco.500 (Phenolic) 3 x 105 Note 4 >40 Note 7 C 1500 C Ref. 1 Kraft Paper 1 x 105 Note 6 >40 Note 7 Note 9 CC 1050'C Ref. 1 3M #4 Paper 1 x 105 Note 6 >40 Note 7 Note 9 EE 1050 C Ref. 1 l 3M #75 Polyester 105_106 Note 5 >40 Note 7 CG 1300 C Ref. 1 3M #55 Polyester 105_106 Note 5 >40 Note 7 II 1300 C Ref. 1 P100 Phenolic 3 x 105 Note 4 >40 Note 7 VV 1050 C Ref. 1 Rag Insul. Paper 1 x 105 Note 6 >40 Note 7' Note 9 BB 1050 C Ref. 1 Vulcanized Fibre 1 x 105 Ref. 6 >40 Note 7 Note 9 TT 1100 C Ref. 1 Vulcanized Fibre 1 x 105 Ref. 6 >40 Note 7 Note 9 A 1100 C Ref. 1 Fiberite 3628 (Epoxy 2 x 108 Ref. 5 >40 Note 7 1300 C Ref. 1 Q Compound)
TABLE NO. 5 NOTES 1. 1
-Local motor starters to be relocated to the controlled environment therefore maximum ambient temperature is anticipated to be 400 C and the total radiation dose 1 x 104 rads. Refer-to applicable screw sheets, Reference 2.
- 2. . Local motor starters and contaccors contain components made of the same
~
materials as those installed in motor control centers. Manufacturer's codes and U.L. temperature indices for particular materials are taken from Reference 1. 3. Celcon and Delrin are trade names for acetal polymer. Acetal resin, chemically polyformaldehyde and its radiation threshold values are described in Reference 5. The radiation dose of 6 x 105 rads is reported for acotal resins. Acetal polymers under trade names Celcon, Alkon, Durathon, and others show loss of their properties at higher radiation () doses. To obtain a certain conservatism in this evaluation the' lower radiation level for acetal resin is considered. 5A comparison of radiation levels to which local starters or contactors and their components will be exposed during the equipment service life with the radiation level that the Calcon and Delrin materials will safely withstand, demonstrates the materials suitability. l 4. Phenolic resins are generally used in construction of electrical equipment in many forms under trade aames with various designations. Such materials are considered engineered materials, that is, the various compounds can have.their characteristics changed by additives specifically to increase the withstandability to radiation exposure or to prevent oxidation. To include most of phenolic based materials and to establish a sufficient conservatism in this evaluation, the lowest radiation dose found of 3 x 105 rads is concidered. The radiation value j was obtained from Reference 5 and represents the threshold value for L unfilled phenolic resins. The least resistant phenolic resin filled y-nm-a %- - . - . - - ,q s - - ,.. --.---p---m----my.,,,w.v, -
l 1 with linen fabric shows 25% damage when exposed to 3 x 106. rads. The O most resistant was asbestes filled. wit
- 25x dama e after irradiatien ef 3.9 x 109 rads. In addition it is documented that some phenolic laminates have been found uneffected by as much as 8 x 109 rads.
In the analysis of insulation materials used in the construction of motor starters and contactors and with a respect to accumulated radiation doses in their particular plant locations, it.is demonstrated that. phenolic based materials will remain uneffected during the equipment service life.
- 5. Listed range of radiation values was found.in Reference 5 for unfilled polyester resins.
The radiation resistance of polyester resins vary depending on the aromatic contents and the nature of crosslinking monomer. Elongation threshold values for radiation damage to most non-filled resins are 105 to 106 rads. Electrical properties are reported to be stable even at higher radiation doses. Since no detailed information on the contents of electrical tape (polyester film base) is available the elongation threshold value for unfilled polyester resins is considered in this analysis. 6. Reference 8 and 5 provide radiation doses for fish paper.- The listed doses are 1 x 105 and 5 x 106 respectively. Paper products used in the construction of motor starter coils are designated Kraft 3M #4 and rug insulation paper for which any direct radiation threshold values are not; listed in available reference material. For the purpose of this evaluation the lower radiation value is used to assure the least risk of a possible error. 7. Thermal aging is a function of the thermal rating of various materials in consideration. By research in several diverse sources it was found that I ' the U.L. temperature indices are the only source providing some useful data addressing the thermal rating of materials. Underwriters Laboratories have conducted detailed studies on materials that provided basis for published temperature indices. The temperature index is considered the maximum value at which the material can be used S y- - - .- , e- . - - - -,--.1, ,- .,,_..w._-m,
r I continuously. An article entitled "A New Temperature Index: Who Needs It" published in the~ September 1970 issue of " Modern Plastics" (Reference 7) discusses the index and indicates how it was established. The temperature index is the point where the property of impact strength, tensile ~ strength and dielectric strength is reduced to one half of its value at-the conclus' ion of 5 x 104 hours. Various insulation materials and their U.L. temperature indices are listed in the Allen-Bradley submittal entitled " Material Index 798, Serial No. 967929-1971" (Reference 1). Temperature indices are provided for both electrical and mechanical properties of materials. For the
. purpose of this evaluation and to include a certain degree of conservatism into the method the-lower temperature index values are used without further analysis of the particular material whether its function
-requires retention of electrical or mechanical properties.
Considering that Class 1E motor control centers are installed in the mild environment with a controlled ambient temperature it would be reasonable
- -< - to assume that the aging characteristics of materials would follow the 100 C rule. The methodology is taken from the EPRI Report NP-1558 (Reference 3).
The temperature index is a practical tool to estimate the consequences of f a thermal degradation of materials. In some instances, the index may only be applicable to a certain material thickness, therefore the values obtained cannot be directly interpreted as a qualified material life and ! should be considered as a realistic estimate of the material service life. To eliminate a lengthy evaluation of each material or a group of materials with the same temperature indices, e new temperature index for i a hypothetical material will be established by calculation using the i equation of the 100 C rule. The new temperature index would be applicable to a material the service life of which is exactly 40 years. Observation of temperature indices of materials used in motor starters O: i t J
and contactors and a comparison with-the temperature index of the hypothetical material will determine the suitability of particular material'for 40 years of service life at the ambient temperature of 400 C. Reference temperature index of hypothetical material. Following the phylosophy of the 100 C rule the equation M ts
= 2 (Ts - Ta)/10 is used.
where: ta - time associated with the material temperature index (hours) Ta - material temperature index (OK, OC) ts - service time (hours, years) Ts - service temperature (OK, OC) For the purpose of obtaining the reference temperature index Ta the time e associated with the index is 5 x 104 (Reference 7). Service tims is 40 years + 350,400 hours Service temperature is 400 C + 3130K j Taking logarithm of both sides of the equation yields l l log U = I(Ts - Ta)/10 log 2 ts l-Solving for Ta - log U* Ta = Ts - , (log 2 ) x 10-O
Substituting O. '- 5x106 Ta = 313 - ( log 2
- 0) x 10 = 3410K + 680C Reference temperature index is 680C.
If the temperature index of a material to be evaluated is higher than the reference temperature index of the hypothetical ma:erial (680 C), the service life of such material is more than 40 years. Similarly if the temperature index of material in evaluation is less than the reference temperature index, the service life of such material is less than 40 years. Materials with their service lives less than 40 years will be I reexamined and a calculation will be performed to determine the end of their service lives. 7.1 Nylon material used in the construction of component assemblies has the U.L. temperature index 650 C. Since the temperature index is lower than the calculated reference index the end of nylon material service life needs to be found. Considering the ambient temperature of 400 C the service life of the nylon material is determined by similar calculation using the equation of the 100 C rule. t ta ts
= 2 (Ts - Ta)/10 i
j where: ta - time associated with the material temperature index (hours) l Ta - material temperature index (OK, OC) ts - service time (hours, years) Ts - service temperature (OK, OC) i O
Rearranging the equation into usable form s= 2 (Ts Ta)/10 Substituting for ta = 5 x 104 hours Ta = 650 C Ts = 400 C ts = Unknown Than 5 x 104 ts = = 4. urs + 32 years 2 (313 - 338)/10 s
- 8. Results of the materials evaluation for susceptibility to a thermal age related degradation identify materials with lesser service life than desired. The performed calculation demonstrates that nylon material reduces its properties to 50% due to the environmental temperature of 400 C within 32 years. In order to justify the required 40 years service ,
life of motor starters and contactors, the designated component needs to be replaced during that time. The component shall be replaced prior to the end of material life and the replacement is recommended during the 20th year of service. Should the entire motor starter or contactor be replaced, the new unit shall be qualified for Class 1E application according to current NRC requirements and standards. The entire unit can be replaced at any time with a respect to the new unit qualified life but prior to the end of established life of the existing equipment. , O
,. , , - ~ - - - , ,e., ,
- 9. The radiation threshold value for the designated material is less than the total radiation dose accumulated during 40 years of service in the location of the contactor MTMC-7. The component needs to be replaced in this location during the time. The replacement of identical component or the entire contactor whichever is more practical at the end of 20th year of service is recommended.
CONCLUSION: Because of the low radiation level at plant' locations where local motor starters and contactors are installed, with exception of MTMC-7, the equipment will not experience any radiation related degradation. Evaluation of materials thermal characteristics and the performed calculation indicate that all materials except nylon are suitable for 40 years of service life in the given temperature conditions. Considering the complexity of motor starters and contactors a preference is given to the unit replacement in accordance with Notes 8 and 9 rather than establishing an on going inspection and C~ surveillance program. Maintenance cycles and the contents of the maintenance program remains unchanged and in full compliance with manufacturer's s recommendations. 2 l l 9 I e l
TABLE NO. 5' REFERENCES
'l. . Allen-Bradley.Co. Bulletin 798, Control Center - Serial No. 967929 Non-Metal Component List and Material Index, by Harold Heywood,-dated August 31, 1982 (P.O. F-12693).
- 2. Environmental Qualification of Class IE Equipment, IE Bulletin No. 79-018, Qualification Summary, Volume 2, Section 2.
- 3. Electric Power Research Institute, EPRI NP-1558, Final Report, September 1980. A Review of Equipment Aging Theory and Technology.
- 4. Babcock & Wilcox Evaluation of Aging of Class 1E Incontainment Controls and Instrumentation Document No. 77-1127001-00, dated July 1981, by Leon McBee.
- 5. Electric Power Research Institute, EPRI NP-2129, Final Report O November 1981. Radiation Effects =on Organic Materials in Nuclear Plants.
- 6. United States Nuclear Regulatory Commission, 1E Bulletin 79-01B, January 14, 1980, Appendix C.
- 7. Modern Plastics, September 1970, Article "A New Temperature Index: Who Needs It."
- 8. Modern Plastics Encyclopedia 1975-1976, Volume 52, No. 10A, a McCraw-Hill-
. Publication.
l-l 9 i O.
1 1 1 I i
)
- O l
)
I TABLE 6 ALLEN-BRADLEY CO. - MOTOR CONTROL CENTERS Lo ( I-e Geert/Cammemsewin
D O O i 4 TABLE NO. 6 Originator: 7, .8 ' I MMeG Verifier: $. N - ES/33 i EQUIPMENT: Motor Control Centers i MANUFACTURER: Allen-Bradley 1 TAC NOS.: MTMC-3 MTMC-5 MTMC-6 MTHC-7 SCREW REF.: 2-104 2-106 2-107 2-108 ! 4 RAD. DOSE: 1.2 x 105 2.6 x 104 6.1 x 104 1.6 x 105 j AMBIENT TEMP.: 400 C 400 C 400 C 400 C 1 1 l Allowable Radiation Suggested i Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information 'on Thermal Aging Schedule Comument s Mfr's UL Years Code Index SINCLE POLE FUSE BLOCK (PART NO. X66799) i I Durez 16090 B1k 3 x 105 Note 1 >40 Note 8 N/A K 1500 C l (Phenolic) SIZE 3 COIL COVER W/ INTERLOCK (PART NO. X230933) i l Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C l Durez 16744 (Phenolic) 3 x 105 Note 1 >40 Note 8 L 1500 C l Fosta (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C
O O O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested i Exposure of Material's Acceptable Life of Inspection Source of Materials Based & Surveillance
' Equipment Materials Rads Information on Thermal Aging Schedule Comments i Mfr's UL Years Index Code
- SIZE 1 MOTOR STARTER (PART NO. X234345)
Fostr. (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C Plenco 466 (Phenolic) 3 x 105 Note 1 >40 Note 8 N 1500 C i ) Durez 1544 (Phenolic) 3 x 105 Note 1 >40 Note 8 E 1500 C I Spauldite (Asbestos Cloth / 1 x 109 Ref. 5 >40 Note 8 JJ 1550 C Phenolic Resin Laminate)
- Rosite 3250A (Polyester 4 x 108 Ref. 5 >40 Note 8 LL 1300 C Molding Comp. 5% Class Reinforced)
Delrin 500 (Polyacetal) 6 x 105 Note 2 >40 Note 8 N 850 C Le Laminate (Cottom Cloth 3 x 106 .Ref. 5 >40 Note 8 KK 1150 C Phenolic) l Plenco 500 (Phenolic) 3 x 105 Note 1 >40 Note 8 G 1500 C I
O O- O
/ ^1 TABLE NO. 6 (Cont'd) 3 Allowable Radiation Suggested j Exposure of heterials Acceptable Life of Inspection '
i Source of Naterials Based & Surveillance Equipment Materials Rads Information on Thermal Aaina Schedule Comuments f Nfr's UL ] Years Code Index ' SIZE 2 NOTOR STARTER (PART NO. X234516) . ! Fosta (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C i l Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C - I Plenco 466 (Phenolic) 3 x 105 Note 1 >40 Note 8 N 1500 C j Durez 1544 (Phenotic) 3 x 105 Note 1 >40 Note 8 E 1500 C l Spauldite (Asbestos Cloth 1 x 109 Ref. 5 >40 Note 8 JJ 1550 C Phenolic Resin) Rosite 3250A.(Polyester 4 x 108 Ref. 5 >40 Note 8 LL 1300 C i Compound 5% Class Reinforced) Durez 22532 (Phenolic) 3 x 105 Note 1 >40 Note 8 I 1500 C l Delrin 500 (Polyacetal) 6 x 105 Note 2 >40. Note 8 W 850 C Le Laminate (Cotton Cloth 3 x 106 Ref. 5 >40 Note 8 KK 1150 C - Phenolic) l Durez 22532 (Phenolic) 3 x 105 Note 1 >40 Note 8 J 1500 C l I . t
-~ _ -. -- -
O O- O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested Exposure of Naterials -Acceptable Life of Inspection Source of Materials Based & Surveillance ; Equisment Naterials 'e Rads Information on Thermal Aging Schedule Comments
. Mfr's UL Years Code Index SIZE 3 MOTOR STARTER (PART NO. X234579)
Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C Durez 16744 (Phenolic) 3 x 105 Note 1 >40 Note 8 L 1500 C Fosta (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C Rosite 3250 (Polyester 4 x 108 Ref. 5 >40 Note 8 LL 1300 C l Compound 5% Class Reinforced) Spauldite (Asbestos Cloth 1 x 109 Ref. 5 >40 Note 8 JJ 1550 C Phenolic Resin) ; i Durez 1544 (Phenolic) 3 x 105 Note 1 >40 Note 8 E 1500 C ! Durez 17156 (Phenolic) 3 x 105 Note 1 >40 Note 8 - D 1500 C XP Laminate (Laminate 3 x 105 Note 3 >40 Note 8 UU 1300 C Paper Phenolic) Delrin 500 (Polyacetal) 6 x 105 Note 2 >40 Note 8 - N 850 C Planco 500 (Thenolic) 3 x 105 Note 1 >40 Note 8 C 1500 C , i ! Delrin 500 (Polyacetal) 6 x 10 5. Note 2 >40 Note 8 U 850 C G I
O O O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipsment Materials Rads Information on Thermal Aging Schedule Comunents Mfr's UL Years Code Index SIZE 1 MOTOR STARTER (NO. X266926) Fosta 523 (Nylon'6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C Durez 16744 (Phenolic) 3 x 105 Note 1 >40 Note 8 M 1500 C Durez 1544 (Phenolic) 3 x 105 Note 1 >40 Note 8 E 1500 C Spauldite (Asbestos Cloth 1 x 109 Ref. 5 >40 Note 8 JJ 1550 C Phenolic Resin) Rosite 3250A (Polyester 4 x 108 Ref. 5 >40 Note 8' LL 1300 C Compound 5% Class Reinforced) Delrin 507 (Polyacetal) 6 x 105 Note 2 >40 Note 8 Y 850 C Nylatron CSHS (Nylon 6-6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 S 650 C Cymel 1077 (Cellulose 6.7 x 106 Ref. 5 >40 Note 8 0 1500 C Filled Melamine) Delrin 500 (Polyacetal) 6 x 105 Note 2 >40 Note 8 W 850 C Plenco 500 (Phenolic) 3 x 105 Note 1 >40 Note 8 C 1500 C
- O O O i TABLE NO. 6 (Cont'd) l Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Naterials Rads Information on Thermal Aging Schedule Counnents ,
I j Mfr's UL .{ Years Code Indez l j NOTOR STARTER (PART NO. X266949) Fosta 523 (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 R 650 C ] Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C . Durez 16744 (Phenolic) 3 x 105 Note 1 >40 Note 8 M 1500 C Durez 1544 (Phenolic) 3.x 105 Note 1 >40 Note 8 E 1500 C i Spauldite (Asbestos Cloth 1 x 109 Ref. 5 >40 Note 8 JJ 1550 C Phenolic Resin) 1 i Rosite 3250A (Polyester 4 x 108 Ref. 5 >40 Note 8 LL 1300 C Compound 5% Class Reinforced) ! Durez 22532 (Phenolic) 3 x 105 Note 1 >40 Note 8
- I 1500 C Delrin 507 (Polyacetal) 6 x 105 Note 2 >40 Note 8 V 850 C l
Nylatron CSHS (Nylon 6-6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 S 650 C Valox 420 (Polybutylene 4.4 x 106 Ref. 5 >40 Note 8 Z 1400 C Terephthalate Class i Filled) , , Plenco 500 (Phenotic) 3 x 105 Note 1 >40 Note 8 C 1500 C I i i
O O O i TABLE NO. 6 (Cont'd) I Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection l Sourec of Materials Based & Surveillance Information Equipment Materials Rads on Thermal Aging Schedule Comments Mfr's UL Years Code Index i ] MOTOR STARTER (PART NO. X266949) (Cont'd) )
! Delrin 500 (Polyacetal) 6 x 105 Note 2 >40 Note 8 W 850 C ,
i ! Cynel 1077 (Cellulose 6.7 x 106 Ref. 5 >40 Note 8 O 1500 C j Filled Methamine) ' 1 Durez 1544 (Phenolic) 3 x 105 Note 1 >40 Note 8 E 1500 C l ) j COVER RESET ASSEMBLY (PART NO. 220174) j Polypropylene 4 x 105 Ref. 5 >40 Note 8 X 1150 C Celanese (Nylon 6/6) 8.7 x 104 Ref. 5 >40 Note 8 Note 10 RR 750 C l ADJ. OVERLOAD RESET BUTTON (PART NO. Z20811) l Celanese (Nylon 6/6) 8.7 x 104 Ref. 5 >40 Note 8 Note 10 BR 750 C Fosta (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 QQ 650 C t ! Polypropylene 4 x 105 Ref. 5 >40 Note 8 I 1150 C i O n-,
! o o o i TABLE NO. 6 (Cont'd) ' I
+
i Allowable Radiation Suggested , i Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Commen.ts l Mfr's UL j Years Code Index SIZES 1 & 2 STARTER OPERATING COILS (71A86. 72A86) Kraft Paper 1 x 105 Note 4 >40 Note 8 Note 10 CC 1050 C 3M #4 Paper 1 x 105 Note 4 >40 Note 8 Note 10 EE 1050 C 3M #75 Polyester 105-106 Note 5 >40 Note 8 CC 1300 C 3M #55 Polyester 105 -106 Note 5 >40 Note 8 II 1300 C 4 P100 Phenolic 3 x 105 Note 1 >40 Note 8 VV 1050 C Rag Insul. Paper 1 x 105 Note 4 >40 Note 8 Note 10 BB 1050 C Vulcanized Fibre 1 x 105 Ref. 8 >40 Note 8 Note 10 TT 1100 C Vulcanized Fibre 1 x 105 Ref. 8 >40 Note 8 Note 10 A 1100 C Fiberite 3628 (Epoxy 2 x 108 Ref. 5 >40 Note 8 Q 1300 C l Compound) I SIZE 3 STARTER OPERATING COILS (PART NO. 73A86) Kraft Paper 1 x 105 Note 4 >40 Note 8 Note 10 CC 1050 C 3M #4 Paper 1 x 105 Note 4 >40 Note 8 Note 10 EE 1050 C
! 3M #75 Polyester 105 -106 Note 5 >40 Note 8 CC 1300 C i
O O O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested Exposure of Materials Acceptable Life of- Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments Mfr's UL Years Code Indez SIZE 3 STARTER OPERATING COILS (PART NO. 73A86) (Cont'd) 3M #55 Polyester 105 -106 Note 5 >40 Note 8 II 1300 C P100 Phenolic 3 x 105 Note 1 >40 Note 8 VV 1050 C Rag Insul. Paper 1 x 105 Note 4 >40 Note 8 Note 10 BB 1050 C Vulcanized Fibre 1 x 105 Ref. 8 >40 Note 8 Note 10 TT 1100 C Vulcanized Fibre 1 x 105 Ref. 8 >40 Note 8 Note 10 A 1100 C Fiberite 3628 (Epoxy 2 x 108 Ref. 5 >40 Note 8 Q 1300 C Compound) - 2 POLE OPEN TYPE "C" RELAY (PART NO. 700-CO20A1) , XP Laminate (Paper / 3 x 105 Note 3 >40 Note 8 UU 1300 C Phenolic) Durez 1544 (Phenolic) 3 x 105 Note 3 >40 Note 8 E 1500 C Neoprene Rubber 2 x 106 Note 6 >40 Note 8 PP 1500 C , Plenco 500F (Phenolic) 3 x 105 Note 1 >40 Note 8 F 1500 C i Kraft Paper 1 x 105 Note 4 >40 Note 8 Note 10 CC 1050 C l l 1
- O O O TABLE NO. 6 (Cont'd)
Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance ' Equipment Materials Reds Information on Thermal Aging Schedule Comments Nfr's UL Years Code Index l-2 POLE, OPEN TYPE "C" RELAY (PART NO. 700-CO20A1) (Cont'd)
- 3M #4 Paper 1 x 105 Note 4 >40 Note 8 Note 10 EE 1050 C 3M #55 Polyester 105 -106 Note 5 >40 Note 8 II 1300 C 3M #75 Polyester 105 -106 Note 5 >40 Note 8 GC 1300 C Fiberite 3628 (Epoxy 2 x 108 Ref. 5 >40 Note 8 Q 1300 C l
Compound) 3M #75 Polyester 105 -106 Note 5 >40 Note 8 FF 1300 C l P100 Phenolic 3 x 105 Note 1 >40 Note 8 VV 1050 C t i Vulcanized Fibre 1 x 105 Ref. 8 >40 Note 8 Note 10 A 1100 C i
, Rag Insulating Paper 1 x 105 Note 4 >40 Note 8 Note 10 BB 1050 C 8 POLE TYPE "N" RELAY (PART NO. 700-N800A1) 1' Durez 22532 (Phenolic) 3 x 105 Note 1 >40 Note 8 H 1500 C Celanese (Nylon 6/6) 8.7 x 104 Ref. 5 >40 Note 8 Note 10 RR 750 C i ! Valox 420 (PBT Class 4.4 x 106 Ref. 5 >40 Note 8 AA 1400 C Filled)
O O O 4 TABLE NO. 6 (Cont'd) . Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments l Mir's UL J Years Code Index 8 POLE TYPE "N" RELAY (PART NO. 700-N800A1) (Cont'd) ! MRC 477BY (Nitrile 1 x 106 Ref. 5 >40 Note 8 MM 1250 C 4 Rubber) , Polypropylene 4 x 105 Ref. 5 >40 Note 8 Y 1150 C
-Duroy PS Adhesive 1 x 106 Ref. 5 >40 Note 8 00 1250 C !
(Nitrile Rubber) Plenco 732L (Melamine- 3 x 105 ~ Ref. 5 >40 Note 8 P 1500 C , Phenolic Cellulose Filled) j Fosta 512 (Nylon 6) 8.7 x 104 Ref. 5 >40 Note 8 Note 10 SS 700 C ! #84 AB86 OPER. COIL FUR RELAY COMPONENTS 40099-302-02 3M #4 Paper 1 x 105 Note 4 >40 Note 8 Note 10 DD 1050 d , 3M #75 Polyester 105 -106 Note 5 >40 Note 8 FF 1300 C Polyken #762 (Polyester) 105 -106 Ref. 5 >40 Note 8 HH 1550 C Valox (Polybutyl,ene 4.4 x 106 Ref. 5 >40 Note 8 Z 1400 C Terephthalate Class Filled) i
1
- O O O TABLE NO. 6 (Cont'd)
Allowable Radiation Suggasted
, Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information _on Thermal Agina Schedule Comments j
Mfr's UL
- Years Code Index
#84 AB86 OPER. COIL FOR RELAY COMPONENTS 40099-302-02 (Cont'd)
Neoprene Rubber 2 x 106 Note 6 >40 Note 8 NN 1500 C l Fiberite 3628 (Epoxy 2 x 108 Ref. 5 >40 Note 8 Q 1300 C l Compound) Durez 29276 (Phenolic) 3 x 105 Note 1 >40 ' Note 8 EEE 1300 C HEATER ELEMENT COIL FORM (PART NO. F10466) l Ceramic Alsimac 460 1 x 109 Ref. 8 40 Note 8.2 ; l l TRANSFORMER MOUNTED FUSE BLOCK (PART NO. F21529)
~
Rosite 3250A (Polyester 4 x 108 Ref. 5 >40 Note 8 LL 1300 C Compound 5% Class
- Reinforced)
HORIZONTAL BUS SUPPORT (PART NO. F22410) , Rosite 3250F (Polyester 4 x 108 Ref. 5 >40 Note 8 YY 1300 C Compound 5% Class ] Reinforced)
O O O TABLE NO. 6 (Cont'd) ; i d Allowable Radiation Suggested l Exposure of Materials Acceptable Life of Inspection . . Source of Materials Based & Surveillance Equipment Naterials Rads Information on Thermal Aging Schedule Commment s i ! Mfr's UL' l Years Code Index i HORIZONTAL BUS SUPPORT (PART NO. F21565) Rosite 3250C 4 x 108 Ref. 5 >40 Note 8 XX 1300 C 1 l VERTICAL BUS SUPPORT (PART NO. F22411) i
! Rosite 3250F 4 x 108 Ref. 5. >40 Note 8 YY 1300 C VERTICAL BUS SUPPORT (PART NO. F21566)
- Rosite 3250C 4 x 108 Ref. 5 >40 Note 8 XX 1300 C f ANCHOR FOR 2" HORIZONTAL BUS (PART NO. 26179)
Polyester Fiberglass 4 x 108 Ref. 5 >40 Note 8 CCC 1600 C l VERTICAL BUS INSULATION BARRIER (PART NO. F22863) i Clastic UTS (Polyester / 4 x 108 Ref. 5 >40 Note 8 BBB 1300 C l Fiberglass) l RUBBER GROMMET (PART NO. F18871 & F18872) Neoprene Rubber 2 x 106 Note 6 >40 Note 8 DDD 1500 C i l l
; O O O i
i TABLE NO. 6 (Cont'd)
, Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments i
Mfr's UL
! Years Code Index
. PLUC-IN BASE 100 AMP (PART NO. F21564)
Rosite 3250C (Polyester 4 x 108 Ref. 5 >40 Note 8 XX 1300 C 4 Compound 15% Class) l AUX. SW SPANNER PIVOT PIN (PART NO. F24518) i Celcon (Polyacetal) 6 x 105 Note 2 >40 Note 8 T 900 C I AUX. SW OPERATING LEVER (PART NO. F24524) Fosta (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 QQ 650 C CONTACT BIDCK (PART NO. F24525) Durez 22532 (Phenclic) 3 x 105 Note 1 >40 Note 8 AAA 1500 C OPERATINC LEVER (PART NO. F24523) Fosta 523 (Nylon 6) 8.7 x 104 Ref. 5 32 Note 8.1 Note 9 WW 650 C OPERATING LEVER (PART NO. F25306) Fosta 523 (Nylon 6) 8.7 x 104 Ref. 5 32 Note.8.1 Note 9 R 650 C
O O O TABLE NO. 6 (Cont'd) i Allowable Radiation Suggested Exposure of Materials Acceptable Life of Inspection '
& Surveillance Source of Materials Based Equipment Materials Rads Information on Thermal Aging Schedule Comment s Mfr's UL Years Code Inder BUSSMAN FUSES (PART NO. X276124, X276127, X276132, X276126, X276120)
{ Ferrule (Cotton, 1 x 105 Ref. 5 32 Note 8.3 Note 9 650 C
- Cellulose Fibre)
I BUSSMAN FUSES (PART NO. X311980)
- Ferrule (Class Melamine 6.7 x 106 Ref. 5 >40 Note 8 850 C Grade CS)
. 1 l STATES CO. TERMINAL BLOCK M-25023 & M-25018 Polypropylene 4 x 105 Ref. 5 Note 8.4 1050 C
#791 Phenolic 3 x 105 Note 1 Note 8.4 1500 C !
i Laminated Melamine Non-Safety Related- N/A Zytel 101 (Polyamid) Non-Safety Related - N/A i MILWAUKEE TRANSFORMER (PART NO. EX147898. EX183222. EX210922) . ) Kraft Paper 1 x 105 Note 4 >40 Note 8 Note 10 1050 C l Polyester-Mylar 105 -106 Note 5 >40 Note 8 1300 C i
O O O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested *
' Exposure of Materials Acceptable Life of~ Inspection '
Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments Mfr's UL 4 Years Code Inder i
- MILWAUKEE TRANSFORMER (PART NO. EX147898. EX183222. EX210922) (Cont'd) l Fish Paper 1 x 105 Note 4 >40 Note 8 Note 10 1050 C Varnish 5 x 106 Note 7 >40 Note 8 1400 C i
i l INDUSTRIAL ELECTRIC WIRE & CABLE (PART NO. MR5814-402, MR5814-301, MR5814-208) l' PVC 5 x 105 _Ref. 5 >40 Note 8 1050 C ! Polyethylene 3.8 x 105 Ref. 5 >40 Note 8 1050 C - 1 l Vulkene (Cross-Link 5 x 106 Ref. 7- >40 Note 8 900 C Polyethylene) l CENERAL ELECTRIC PUSHBUTTONS (PART NO. CR2940-UA202B, -C, -E) Materials Not Identified Note 12 CHROMAIDX AR-1025 THERMOSTAT 4 Cork 0.5 x 107 Ref.4 Note 11 Neoprene 8 x 105 Ref. 5 Note 11 Phenolic 3 x 105 Note 1 >40 Note 8 1500 C l
t O- O O
; TABLE NO. 6 (Cont'd)
Allowable Radiation Suggested i Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Comments Mfr's , UL Years Code Inder CHRONALOX AR-1025 THERMOSTAT (Cont'd) I Nylon 8.7 x 104 Ref. 5 32 Note 8.1- Note 9 650 C l Noryn N190 (Estimated 1 x 105 Ref. 5 >40 Note 8 Note 10 900 C Ref. 9 j Polyphenylene Oxide) j PVC 5 x 105 Ref. 5 >40 Note 8 700 C Ref. 9 l CHROMAIDX STRIP HEATERS TYPE OT & S 1
- Mica 4 x 106 Ref. 4 >40 Note 8 1300 C Other Proprietary Note 11 e
i TRIPER BAR (PART NO. 94629) Plaskon 446 (Polyester) 105_106 Note 5 >40 Note 8 1300 C Fiberite FM-4004-5 (Epoxy 2 x 108 Ref. 5 >40 Note 8 1300 C Ref. 1 Compound) COVER SCREW INSULATION (PART NO. 94549) Phenolic 3 x 105 Note 1 >40 Note 8 1050 C ' 9
O O O TABLE NO. 6 (Cont'd) Allowable Radiation Suggested . Exposure of Materials Acceptable Life of Inspection Source of Materials Based & Surveillance Equipment Materials Rads Information on Thermal Aging Schedule Coussent s t i
. Mfr's UL Years Code Index j ARC CHUTE FLASH BARRIER (PART NO. 97862) l Melamine Class 6.4 x 107 Ref. 4 >40 Note 8 1400 C Note 13 ARC CHUTE TOP SHIELD (PART NO. 111744) l Melamine Class 6.4 x 107 Ref. 4 >40 Note 8 1400 C Note 13 WASHER (PART NO. 301708) i Teflon-White Non-Safety Function N/A j ARC CHUTES SIDES RT & LT (PART NO. 97372-D -C). ARC CHUTE INSUL. (PART 112811) i
! Helamine Class 6.4 x 107 Ref. 4 >40 Note 8 1400 C Note IS i j FLASH BARRIER (PART NO. 11698) Black Fibre 1 x 106 Ref. 5 >40 Note 8 1150 C - 4 INTER-PHASE SHIELDS (PART NO. 94607) Fibre 1 x 106 Ref. 5 >40 Note 8 1150 C
O O O i TABLE NO. 6 (Cont'd)
. Allowable Radiation Suggested Exposure ni Materials Acceptable Life of Inspection Source of Material e Based & Surveillance Equipsent Materials Rads Information on Ther: sal Aging Schedule Comments Mfr's UL Years Code Index i
) CREEPACE WASHERS (PART NO. 111830) i i Duroid 800 (Estimated 3 x 105 Note 1 >40 Note 8 1050 C Phenolic) BASE MOLDING 'HE' BREAKER (PART NO. 97959), COVER MOLDINC (PART NO. 97956) , l Cyglass 620 (Estimated 4 x 108 Ref. 5 >40 Note 8 1300 C i Polyester / Fiberglass) l Plascon 446 (Polyester) 105 -106 Note 5 >40 Note 8 1300 C l l CONNECTOR BAR (PART NO. 111906) l Class Epoxy 2 x 108 Ref. 5 >40 Note 8 1300 C i, i LOAD TERM SHIELDS O.P., C.P. (PART NO. 113131A & B), LINE END COVER SHIELD C.P. (PART NO. 13133) ! Black Fibre 1 x 106 Ref. 5 >40 Note 8 1150 C LINE TERM SHIELDS O.P., C.P. (PART NO. 114292A & B) Melamine Class 6.4 x 107 Ref. 4 >40 Note 8 1400 C Note 13 t
1 TABLE NO. 6
- NOTES i
- 1. Phenolic resins are generally used in construction of electrical equipment in many forms under trade names with various designations.
Such materials are considered engineered materials, that is, the various .
+
compounds can have their characteristics changed by additives specifically to increase the withstandability to radiation exposure or to prevent oxidation. To include most of phenolic based materials and to establish a sufficient conservatism in this evaluation, the lowest radiation dose found of 3 x 105 rads is considered. The radiation value was obtained from Reference 5 and represents the threshold value for unfilled ' phenolic resins. The latest resistant phenolic resin filled with linen fabric shows 25% damage when exposed to 3 x 106 rads. The
- most resistant was asbestos filled,with 25% damage after irradiation of
! 3.9 x 109 rads. In addition it is documented that some phenolic , laminates have been found uneffected by as much as 8 x 109 rads. O. In the analysis of insulation materials used in the construction of designated motor control centers, including their components and with a j respect to accumulated radiation doses in their particular_ plant j locations, it is demonstrated that phenolic based materials will remain , unaffected during the equipment service life.
- 2. Calcon and Delrin are trade names for acetal polymer. Acetal resin, chemically polyformaldehyde and its radiation threshold value are described in Reference 5. The radiation dose of 6 x 105 rads is reported for acetal resins. Acetal polymers under trade names such as Celcon, Alkon, Durathon and others show loss of their properties at higher radiation doses. To obtain a certain conservatism in this evaluation the low radiation value for the acetal resin is considered. A comparison of radiation level to which motor control centers and their components will -
be. exposed to during the equipment service life and the radiation level that the Celcon and Delrin materials will safely withstand demonstrates i the materials suitabili~ty.
- 3. The radiation value 3 x 105 as stated in Note 1 for unfilled phenolic-resin is considered since no direct reference for phenolic filled with I paper was found in available reference documentation. For the purpose of l this evaluation the radiation value used is the most conservative to assure the least risk of a possible error.
- 4. References 10 and 4 provide radiation doses for fish paper. The doses listed are 1 x 105 and 5 x 106 rads respectively. Paper products used in I' the construction of various motor control center components are described as Kraft, 3M #4, an'd rag paper for which any direct radiation effects data were not listed in the available reference material. For the
- purpose of this evaluation the lower radiation value is used to assure the least risk of a possible error.
- 5. Listed range of radiation values was found in the Reference 5. For unfilled polyester resins, the radiation resistance of polyester resins
, vary depending on the aromatic contents and the nature of' cross-linking monomer.- Elongation. threshold values for radiation damage to most unfilled resins are 105 to 106 rads. Electrical properties were reported i to be stable at higher radiation doses. Since no detailed information on the material contents of the electrical tape (polyester film base) is available, the elongation radiation threshold value for unfilled polyester resins is considered in this analysis.
- 6. A description of rubber based materials with a respect to their radiation resistance is provided in the reference 5. Since there is no radiation threshold value stated for.the neoprene rubber, the logical sequence of-statements from different articles provides almost accurante radiation threshold value for the neoprene rubber.
The article entitled " Adduct Rubbers" specifies the lowest threshold value at 4 x 106 rads sets the upper limit and it becomes obvious that the threshold radiation dose for the neoprene rubber is lower. An article describing Butyl Rubber provides the threshold value of 7 x 105 rads and states that butys are the least radiation resistant
- - . . . _ , - , - .o . - . - . . . _ , . _ , - . .- _. . . . . . . .-,.e, - -_ - - _ . . . _ - - . .
s rubbers known. With the 7 x 105 rads as the lower limit the radiation threshold value for the neotrene rubber may exisits anywhere between the established boundaries. Since adduct rubbers are compared to natural and neoprene rubbers the comparison suggests to assume the radiation threshold dose of 2 x 106 rads for natural rubbers. It may be noted that even butyl rubbers would be suitable for the given radiation environment.
- 7. The radiation value is from Appendix B of B&W Aging Assessment, Document No. 77-1127001-00 dated July 1981 (Reference 4) which indicates that a
- similar material varnish cambric requires a radiation dose of 5 x'106 rads to produce 25% property change. Since the highest radiation level .
to which the actual varnish may be subjected to is 1.6 x 105 rads, the subject varnish is considered acceptable for the specified radiation environment, based on the comparison of materials.
- 8. Thermal aging is a function of the thermal rating of various materials in consideration. By research in several diverse sources it was found that i ~ the U.L. temperature indices are the only source providing some useful data addressing the thermal rating of materials. Underwriters Laborate. ries have conducted detailed studies on materials that provided j basis for published temperature indices. The. temperature index is considered the maximum value at which the material can be used i continuously. An article entitled "A New Temperature Index: Who Needs i
l It" published in the September 1970 issue of " Modern Plastics" (Reference 9) discusses the index and indicates how it was established. The temperature index is the point where the property of impact strength, tensile strength and dielectric strength is reduced to one half of its value at the conclusion of 5 x 104 hours. i Various insulation materials and their U.L. temperature indices are l listed in the Allen-Bradley submittal entitled " Material Index 798, Serial No. 967929-1971" (Reference 1). Temperature indices are provided for both electrical and mechanical properties of materials. For the
' purpose of this evaluation and to include a certain degree of conservatism into the method the lower temperature index values are used L ,e--.-w-, ,,-c.-.->y,, ----y-- *,.
without further analysis of the particular material whether its function _O resuire recencien of etectrical er mech nical eroverties. Considering that Class 1E motor control centers are installed in the mild environment with a controlled ambient temperature it would be reasonable to assume that the aging characteristics of materials would follow the 100 C rule. The methodology is taken from the EPRI Report NP-1558 (Reference 3). The temperature index is a practical tool to estimate the consequences of a thermal degradation of materials. In some instances, the index may only be applicable to a certain material thickness, therefo're the values obtained cannot be directly interpreted as a qualified material life and should be considered as a realistic estimate of the material service life. To eliminate a lengthy evaluation of each material or a group of materials with the same' temperature indices, a new tenperature index for , a hypothetical material will be established by calculation using the equation of the 100 C rule. The new temperature index would be l applicable to a material the service life of which is exa.ctly 40 years. Observation of temperature indices of materials used in notor control centers and a comperison with the temperature index of the hypothetical material will determine the suitability of particular naterial for ' 40-years of service life at the ambient temperature of 400 C. Reference temperature index of hypothetical material. Following the phylosophy of the 100 C rule the equation t,a = 2 (Ts - Ta)/10 is sed. ts - where: ta - time associated with the material temperature index (hours) 1 - material temperature index (OK, OC) O
ts - service time (hours, years) Ts - service temperature (OK, OC) For the purpose of obtaining the reference temperature index Ta the time associated with the index is 5 x 104 (Reference 9). Service time is 40 years + 350,400 hours Service temperature is 400 C + 3130K Taking logarithm of both sides of the equation yields log ts U= (Ts - Ta)/10 log 2 Solving for Ta log U i Ta = Ts - (log 2 ) x 10 1O l Substituting 5x106 Ta = 313 - ( 50400) x 10 = 3410K + 680C log 2 l Reference temperature index is 680C. l If the temperature index of a material to be evaluated is higher than the reference temperature index of the hypothetical material (680 C), the
- service life of such material is more than 40 years. Similarly if the temperature index of material in evaluation is less than the reference.
temperature index, the service life of such material is less than 40 years. Materials with their service lives less than 40 years will be reexamined and a calculation will be performed to determine the end of their service lives.
8.1 Nylon material used in the construction of component assemblies has the (~} (_f U.L. temperature index 650 C. Since the temperature index is lower than the calculated reference index the~end of nylon material service life needs to be found. Considering the ambient temperature of 400 C the service life of the nylon material is determined by similar calculation using the equation'of the 100 C rule. ta ts
= 2 (Ts - Ta)/10 where: ta - time associ.ated with the material temperature index (hours)
Ta - material temperature index (OK, OC) ts - service time (hours, years) Ts - service temperature (OK, OC) i Rearranging the equation into usable form 8 ' 2 (Ts Ta)/10 Substituting for ta = 5 x 104 hours - Ta = 650 C Ts = 400 C ts = Unknown Than 5 x 104 = 8 urs + 32 years ts = . 2 (313 - 338)/10 The result of the calculation demonstrates that the nylon material reduces its properties to 50% due to the environmental temperature of 400 C in 32 years. In order to justify the 40 years of service life of 73 Class 1E motor control center assembly, the replacement of nylon
\~-) components or the entire part, whichever is more practical is necessary.
i 8.2 Heuter element coil form according to information provided by the manufacturer is a ceramic material designated Alsimac 460. Since no U.L. temperature index is available a search through the reference documentation was conducted. Babcock & Wilcox evaluation of aging of Class 1E incontainment controls and instrumentation, Document No. 77-1127001-00 (Reference 4) indicates that ceramic material of ! , insulators in Westinghouse NI detectors has 40 years potential for significant degradation due to the thermal aging. Assuming that the
-ceramic material properties are comparable it is concluded that the Alsimac 460 is suitable for 40 years of ser rice life.
8.3 States Co. terminal blocks M-25023 and M-25018 are not U.L. listed. According to States Co. these terminal blocks were tested to 1EEE-323 and IEEE 344 standards. Considering operating temperature of materials involved it is obvious that terminal blocks are suitable for 40 years of . service life. Refer to Table 7 of this document for more detailed i analysis.
- 9. Results of this evaluation identify materials susceptible to radiation and thermal age related degradation. To justify the required 40 years service life of the Class 1E motor control centers the designated component needs to be replaced at least once during that time and prior l; .to approaching the material radiation or thermal threshold values. It is reconnended to' replace the identified component or the entire part whichever is more practical at the end of the 20th year of service. ,
, 10. The radiation threshold value for the designated material is less than the total radiation dose accumulated during 40 years in the location of motor control centers tag no. MTMC-3 and MTMC-7. The component needs to be replaced in those two motor control centers during the 40 years of L service. .It is recommended to replace the identified component or the l ,
entire part, whichever is more practical at the end of 20th year of ( service. t !LO l L.
- . - ~ . -. _- .-. - .-. .
t
- 11. The incomplete material information of thermostats and heaters would
() - require surveillance and inspections possibly replacement in order to assure the reliable component performance as required for Class IE equipment. Since heaters do not perform any safety related function it is recommended to separate heater circuits from their power sources in accordance with IEEE 384-1980 and degrade-their components from Class 1E to non-safety reisted. The re' commendation appears to be more economical than results of unsufficient analysis caused by lack of information. l i
- 12. All possible steps were taken to obtain an identification of non-metalic materials used in G.E. pushbuttons. Refer to G.E. letter dated April 19, 1982 addressed to Allen-Bradley Co., CAI Letter FCS-3366 dated
,- February 2, 1983 and FPC tesponse to FCS-3366 dated March 11, 1983. As indicated in referenced correspondence C.E. Co. pushbuttons are not qualified for use in Class 1E assemblies. Since the material identification is not available because of proprietary concerns no analytical evaluation of equipment anticipated service lif. can be ! conducted. Considering an econcaical impact of surveillance and i () maintenance programs it is recommended to replace existing G.E. Co. pushbuttons with qualified units.
- 13. Arc chutes, barriers, top shi, elds and sides do not function in electrical circuitry as isolators. Therefore che U.L. temperature index used in this material evaluation for the melamine glass is applicable to mechanical properties.
b O S 4
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CONCLUSION: O This study was performed to evaluate non-metalic materials utilized in the construction of Allen-Bradley Class-1E motor control centers. The evaluation ~ includes materials of components which were supplied by other subcontractors and installed in motor control center assemblies. .05)tained results provide basis for the d'etermination of the equipment service' life in given environmental conditiens of CR3. Components with lesser service life than life desired are identified and replacement schedule suggested. It was concluded that nylon materials are not suitable for 40 years in the specified environmental conditions. These materials under various trade names are Fosta 523 - Manufacturer's Codes - R, QQ, WW Nylatron CSHS - Manufacturer's Cedes - S Celanese 1000-2 --Manufacturer's Codes - RR Fosta 512 - Manufacturer's Codes - SS l Other material susceptible to the radiation age related degradation are paper , and fibre products designated as: Kraft Paper - Manufacturer's Codes - CC
- 3M #4 - Manufacturer's Code - EE, DD Fish Paper -
Rag Insulating Paper - Manufacturer's Code - BB Vulcanized Fibre - Manufacturer's Code - A, TT With regard to Note 9, the following is a summary of parts of motor control centers MTMC-3, HTMC-5, MTMC-6, and HTMC-7 with a potential to radiation and thermal are related degradation and therefore recommended for replacement. Size 3 coil cover with interlock, Part No. X230933 l - Size 1 motor starter, Part No. X234345 l l 1 Size 2 motor starter, Part No. X234516
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Size 3 motor starter, Part No. X234579
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Size 4 motor starter, Part No. X266926 Motor starters, Part No. X266949 Adj. overload reset button, Part No. Z20811 Auxiliary switch operating lever, Part No. F24524 Operating lever, Part No. F24523 . Operating lever, Part No. F24306 Bussman fuses, Part No. X276124, X276127, X276132, X276126, X276120 With regard to Note 10, the following is a summary of parts of motor control centers MTMC-3 and MTMC-7 with a potential to radiation age related degradation and thus recommended for replacement. Cover reset assembly, Part No. Z20174 Sizes 1 & 2 starters operating coils, Part No. 71A86 and 72A86 (if'not replaced with the motor starter) Size 3 starters operating coils, Part No. 73A86 (if not replaced with the motor starter) 2 pole, open type "C" relay, Part No. 700-C020A1 8 pole, type "N" relay, Part No. 700-N800A1 L
#84AB86 operating coil for relay - Components 40099-302-02 (if not replaced with the entire relay)
Additionally refer to Note 11 for recommendation to modify heater circuits and l Note 12 for replacement of non qualified C.E. Co. pushbuttons. Recommended replacements and modifications or compatible action shall be taken to support analytical justification of the equipment service life and satisfy related requirements of NRC 1E Bulletin 79-01B. O
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l l , TABLE NO. 6 REFERENCES
- 1. Allen-Bradley Co. Bulletin 798 Control Center - Serial No. 967929 Non-Metal Component List and Material Index, by Harold Heywood, dated
, August 31, 1982 (P.O. F-12693). -
- 2. Environmental Qualification of Class 1E Equipment 1E Bulletin No. 79-01B Qualification Summary, Volume 2, Section 2.
- 3. Electric Power Research Institute, EPRI NP-1558, Final Report, September 1980, A Review of Equipment Aging Theory and Technology.
- 4. Babcock & Wilcox Evaluation of Aging of Class 1E Incontainment Controls and Instrumentation. Document No. 77-1127001-00, dated July 1981, by Leon McBee.
- 5. -Electric Power Research Institute, EPRI NP-2129, Final Report
)O . November 1981 Radiation Effects en Organic Materials in Nuclear Plants.
- 6. Engineering Compedium on Radiation, Shielding, Volume II, Springer-Verlag, Berlin /Heidelberg (1975) pp 311-314.
- 7. " Insulation and Jackets for Control and Power Cable in Thermal Reactor Nuclear Generating Stations", R.B. Blodgett and R. C. Fisher, Okonite Co.
Institute of Electric and Electronic Engineers - June (1969).
- 8. United States Nuclear Regulatory Commission, 1E Bulletin No. 79-01B, January 14, 1980, Appendix C.
1
- 9. Modern Plastics, September 1970, Article "A New Temperature Index: Who Needs It."
10.' Modern Plastics Encyclopedia 1975-1976, Volume 52, No. 10A, a McGraw-Hill Publication.
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b EQUIPMENT: Terminal Boxes (States Co. Terminal Blocks) MANUFACTURER: Multi-AMP Corporation . TAC NOS.: AS-1 BS-5,6 CA-1,2,3 CF-1,3,4 CF-2 CI,2,3,4,9 EF-3,4 FW-3,4' SCREW REF.: 2-22 2-27 2-41 2-49 2-50 2-53 2-73 2-84 RAD. DOSE: 1 x 104 4.5 x 104 1 x 104 1.2 x 106 1 x 104 1.2 x 104 1 x 104 1 x 104 AMBIENT TEMP.: 400 C 400 C 400 C 400 C 400 C 400 C 400 C 400 C TAC NOS.: FW-11,20 FW-22 MS-5,6 MS-7 MS-8 MS-17 MS-18 MU-4,5 SCREW REF.: 2-85 2-86 2-98 2-99 2-100 2-101 2-102 2-161 RAD. DOSE: 1 x 104 1 x 104 1 x 104 1 x 104 1 x 104 1 x 104 1 x 104 8 x 104 AMBIENT TEMP.: 400 C 400 C 400 C 400 C 400 C 400 C 400 C 400 C TAG NOS.: MU-11 MU-21 MU-22 SW-3 SW-4,3,19 SW-6 SW-7 SW-8 SCREW REF.: 2-162 2-163 2-164 2-203 2-204 2-205 2-206 2-207 RAD. DOSE: 2.8 x 104 1.8 x 105 1.7 x 106 1.7 x 104 1.2 x 104 1 x 108 1.2 x 106 1.2 x 106 AMBIENT TEMP.: 400 C 400 C 400 C 400 C 400 C 400 C 400 C 400 C TAG NOS.: SW-9 SW-10 SW-11,12,13 SW-14 SW-15 SW-18 WD-3 WS-2 SCREW REF.: 2-208 2-209 2-210 2-211 2-212 2-213 2-223 2-227 RAD. DOSE: 1.2 x 106 1.2 x 104 1.2 x 104 1 x 108 1.2 x 106 1.2 x 104 1 x 108 1.2 x 106 AMBIENT TEMP.: 400 C 400 C 400 C 400 C 400 C 400 C 400 C 400 C TAC NOS.: .WS-3 SCREW REF.: 2-228 RAD. DOSE: 1.2 x 106 AMBIENT TEMP.: 400 C ( l I l-
l O O O ). 2 TABLE NO. 7 Allowable Radiation Suggested ! Exposure of Materials Acceptable Life of Inspection l Source of Materials Based & Surveillance Equipment Materials Reds Information on Thermal Aging Schedule Comments ! General Purpose Phenolic 1.3 x 108 Note 1 Note 3 N/A
- Durez #791 Polypropylene RTP 150 4 x 105 Note 2 Note 4 N/A i
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l TABLE NO. 7 NOTES
- 1. The attached sheets of Micro-switch Engineering Report No. LTR-15027-1 schmitted by Hooker Chemical, Durez Division to GAI provide qualification test data for phenolic materials. Materials tested are not exactly durez #791 but they were of the same general purpose compounds.
Dures #791 is a general purpose phenolic filled with wood flour as the main ingredient. The report demonstrates similarity of materials with . respect.to comparable reactions to radiation as evidenced on the enclosed data sheet and copies of arrhenius curves. The radiation levels shown on the data sheet are total integrated doses and it was concluded that the material exposure to 1.3 x 108 rads caused the phenolic to be brittle but without affecting performance properties of the component. The qualification program of Multi-amp, States Co. includes the test for terminal blocks withstandability to radiation values of 2.2 x 108 rads. , However, no documentation is available at this time. L ' O v 2. EPRI NP-2129 report " Radiation Effects on Organic Materials in Nuclear
. Plants" provides the radiation threshold value 4 x 105 rads for polypropylene. The value was determined on the basis of similarity to polethylene.
- 3. The attached sheets of Micro-switch Engineering Report No. LTR-15027-1 submitted by Hooker Chemical, Durez Division to GAI contain evaluation of durez #791 material temperature / life expectancy. Arrhenius methodology was used to describe the temperature dependance of the velocity coefficient of a chemical reaction to approximate the relationship between material life and temperature. It should be noted that parameters (time and temperature) were applied to establish failure criteria relative to flexual and impact strengths. Dielectric property of the material remained within acceptable levels without any failure.
4 0
Using the established regression line equation for the material thickness tr 1te e lua o , Y = 5130.14 X - 8.203 Where Y - log of insulation life as function of X X - operating conditions as independence variable l t To establish material life at the ambient temperature of 400 C the equation can be written as: I 1 L = 10 0.14 333 - 8023 Where L is approximate material life in hours Solving for L yields 2.33 x 108 hours + 26,598 years The approximate material life at 400 C ambient temperature is 26,598 years. It is demonstrated that t.he durez #791 material exe.eeds the required performance.
- 4. Heat stable polyprophylene material has a U.L. temperature index of L 1150 C. Refer to Allen-Bradley Co. Bulletin 798 Control Center - Serial I
l No. 967929 Non-Metialic Component List. The U.L. temperature index is considered the maximum temperature at which the material can be used continuously. An article entitled "A New Temperature Index: Who Needs It" published September 1970 in " Modern Plastics" discusses the index and how it was established. The temperature index is the point where the property of impact strength, tensile strength and dielectric strength is reduced to one half of its new value at the conclusion of 5 x 104 hours. Following the phylosophy of the 100 C rule as utilized in previous j calculations evaluating the lives of various materials in motor control centers and their components (Tables 5 and 6) it is concluded that the , approximate life of the polyprophylene material is more than 40 years. ,
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l CONCLUSION: V Non-metalic materials used in the construction of Multi-amp, States Co. terminal blocks are evaluated for the suitability in the-specified environment for the duration of desired service life of 40 years. The States Co. conducted qualification tests to meet requirements of IEEE 323-1974, but no data or test results are known or published. Several independent analyses were conducted to determine the equipment qualification and it is ex'pected that test results when released would only confirm results of these analyses. Information provids:d by the ranufacturer indicates that the tenninal blocks were succassfully tested under postulated environmental conditions of DBE. Terminal blocks in several locations of CR3 will be exposed to higher ., radiation doses during the equipment service life than the radiation threshold value of polypropylene material. Polypropylene is used for terminal barriers and their failure is not expected to affect the Class 1E function of the terminal block. For this reason no surveillance program or replacements are p suggested. U O -
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n NORTH To N AW AN D A. NEW -Y o R K 14120 - 716-696-6237 December 16, 1981 Mr. Darrell Grantham GILBERT ASSOCIATES P. O. Box 1498 GH II-162 Reading, PA 19603 Dear Mr. Grantham As discussed on December 4, enclosed are the technical write-ups on radiation testing of materials for Mic.ro Swit.ch Divi-sion of Honeywell. Also enclosed is & summary of similar in-formatlon on other plastic materials from the Public Service Company of Colorado. D Although the materials l'18, 154, and 791 were not among those tested for Micro Switch, I believe that they would react-in much the same manner as those that were tested. Durez 118 and 791 are general purpose compounds with wood flour as the main filler ingredient. It seems as though similar materials (') v react in similar ways to radiation, as evidenced on the en-closed data and Arrhenius curves. In summarizing the second page of the Micro Switch report the 1SM1 used a mineral filied phenolic similar to Durez 156, the V3-1 used a similar compound, and the BZ-2R/BA-2R used a cel-lulose filled material. The other switches are either of all metal construction,or,in the 1SEl-3 and lEN1-6, were enclosed switches with the phenolic switches encased in them. I hope this information will be of use to you. Very truly yours HC4- Y< , J;1mes E. Kuenzie Senior Product Engineer JEK:df Enc. O v
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w ., ENGINEERING REPORT i LTR4 15o27 .1 past - 1 e, _ _ 12
SUBJECT:
.?[
T Permanent Effects of Gamma Radiation on Various Switches.
! ~OBJECT: '
To determine the effer:ts of Gamma radiat' ion on subsequent performance of the svitches li'sted ou page 2 of this report. ABSTRACT OF RESULTS: See page 2.
. Note:
Performance tests were conducted after, not during, the radiation exposure. {l v l', l t THIS REPORT CONTAINS PROPRl[TARY INfDRuATDN AND IS TH[ PACPERTY or antae swsitE . A civistoN of alNNEAPous-mMErwrit REcutAroR co. TNissWITCE or altae REPoRr is NOT TO DE COPtED OR USED WITHOUT TNT APPROVAL O 31880 Swif tB ENGINEERING TEST LABORATORY f tST 87_ Men listed on Dage 12 me apenovtosv__ggffMC#vf,J y. l i n.m n,,. .p
p
- a Amount of Ganna Radiation Exposure Expressed u Roentgens, Total Integrated Flux p* .
6 Swit'ches . 10 r 107r 100r 6 r 1SM1 No effect at 1.0 X 10 No effect at 1 5 X 107 r At 1 3 % 100 r the case material was becoming brittle. ISEl-3 No effect at 3 0 X 106r At 1 5 X 107 r there was At 1 3 X 10" r the increase noted !m an increase in operating at 1 5 X 107 r were further 52 jB and release force and Y9 I= magnified due to seal boot harden-pretravel. ing. I Z "" V3-1 No effect at 2.6 X 106 r No effect at 1 3 X 107r At 1 3 X 100 r the cover material m m No Test was becoming brittle, At 1.2 X 100 r we suspect that mga, V3-1301 No test y a =g the case naterial is becoming ,,, brittle. =4 BZ-2R '* No effect at 1 9 X 106 r No effect at 1.2 X 107 r At 1 3 X 100 r the only detri- 2 ek[}# mental effect noted was the case i Qpa - c/ material.becoming brittle. O BA-2R N No effect at 2 3 X 106 r No effect at 1.4 X 107 r At 1 3 X 100 r the only detri- 2 mental effect noted was the case lEN1-6 No test No effect at 1.0 X 107 r materialbeepngbrittle. At 1 5 X 10 r there may have been some deterioration of the teflon. 2EP2-E No test At 1.25 X 107 r there was At 1.24 X 100 r the seal becomes a slight decrease in oper- brittle and breaks on first ating and release force and operation, differential travel. lLS1 No test No test At 1.2 X 100 r no effect on switel but rubber seals had hardened, l os = lHS1 No test No test No effect at 1 3 X 100 .r. "
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St 3 -c' - -12 Irradiation Tests Facilities The switches irradiated in this program were exposed to ga= radiation free cobalt 60 sources. Two differenty reactcirs were used in these tests.
One reactor is located at the University of &nnesota anti is a 1000 carle cobalt 60 source with a 10 feet X 13 feet X 10 feet test cell. The second test reactor used was the Argonne National Labeestcries reactor leested in Chicago, Illinois,vbich is a cobalt 60 high level gama facility, with an attenuated flux of about .795 X lOb r per br. These reactors will produce equivalent test results on the basis of integrated flux exposures. The integrated flux is the product of the attenuated flux (r per hour) and the time duration (bours) of the test.
~
TEST PROCEEURES: The svitches to be tested were checked initially for operating characteristics and insulation resistance and sent away to be irradiated. Upon their return they were checked for operating cbsracteristics, insulation resistance, dielectric strength, and mechanical and electrical:-Jife vbere applicable. The megohm insulation resictances were measured at 500 v.D.C. on a 1 to 100,000 test unit. Dielectric strength was measured on test equipment having a maximum voltage output of 6,000 volta A.C. and current limited to about .250 amperes. TEST DATA: It should be noted that the radiation level figures shown on the data sheets are as total integrated flux. It should also be noted that the mechanical and l electrical life figures shown do not necessarily indicate that the switch 1 vas. inoperable but rather that it was removed from test at that time. i General Comments: 1I31 Switches There did not seem to be any change in the switch performance properties vbich could be attributed directly to the radiation exposure. A closer examination of the switch parts did disclose the fact that the fubber seal rings in the irradiated switches had lost much of their resiliency. This l could contribute to a leakage problem. The types of mechanical failures noted were, according to laboratory information, comon for the period during vbich these switches were manufactured. l
- O l
l l
,~ e CICR0 SWITCC """"""' '* "
3 i' 6aas I LTM 15o27 _1 ENGINEERING
-.. REPORT
. O 4 o, - la BZ-2R Switchas There did not seem to be any change'in the switch performance properties which could be directly attributed to irradiatiog. It was noted however, that the group of switches subjected to 13 X 10 r (switches #9 and 11) i had cracked or chipped cases and the case material seemed to be very brittle. The broken cases may have resulted from rough handling during shipping. BZ-2R Switches There.did not seem to be any change in the switch performance properties which could g be attributed to irradiation although a total integrated flux of about 10 r did seem to make the plastics brittle. lHS1 Switches There were no changes in the switch performance propertiss which could be attributed to -irradiation. Early leakage occurred in both the irradiated
. and the control samples.
i 1SML Switches s There were no changes in switch performance properties which eguld be attributed to irradiation. The radiation exposure of about 10 r appears to make the switch plastics brittle.
- i V3-1 and V3-1301 n< itches i
i There were no change in switch performance p'roperties which co d be attributed to irradiation. The tadiation exposure of about 1 r does appear to make the, switch case materials brittle. 2EP2-E Switches An exposure of 1.25 X 107 r did seem to cause a slight decrease in svitch operating and release forces and in differential travel. The other properties remained unaffected. 0This exposure did not cause premature seal cracks. Exposure to 1.24 X 10 r caused seal breaks on the first operation. The
- seal break of courdwould cause decreases in operating and release forces.
lEN1-6 Switches Due to variations in the measurements of the switch operating characteristics it is impossible to make a definite statement as to the effect of radiation on these characteristics. We can say that the insulation resistance and
' dielectric strength of the switch is unaffected. No extreme variations of differential travel or pretravel were noted. The variations in overtravel
' measurements could well have been due to the operat6th variation in pressure ^ during this measurement. We can not however adequately acount for the operating force and release force variations. It should be noted that the variations occurred even on the control units. In general the performance properties of the switch did not seem to be affected by irradiation.
,5 m CICR0 $WITCN , '" '"'"*" " ' "
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-- 6335
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REPORT eur 5 or 12 1EN1-6 Switches (continued) There vag some rust noted on the plungers of the switches exposed to 1.3 x 10 r total integrated flux. This may have developed from a deterioration of the teflon viper liberating free fluorine but this could not be verified. 1SEl-3 Switches Irradiation exposures of 3 x 106 r did not seem to cause any significant changes ~ in evitch performance properties. Exposures of 1 5 x 107 r and above caused very definite increase ic operating and release forces' as well as an inc:wase in pretravel. Them were no detri*nental chan6es in electrical properties or switch life detected. It was noted that the seals of the irradiated svitches had lost some of their resilience and probab4 would have leaked after fever operations than vould the control switches although no leakage test.s were conducted. Insulation Fesistance Variations: i m The' insulation resistance of the BA, BZ, IS and HS type switches were
) improved after irradiation. This does not necessarily indicate that the improvement was due to irradiation. During the radiation exposure
' the switches are simultaneously exposed to a somevbat elevated temperature. (usually around 100*F). This etevated temperature exposure-alone could have caused the increase in insulation resistance. A more extensive' test program would be required to determine vbetber radiation exposure or elevated temperature exposure had produced these results. INITIAL DISI'RIBUfION:
- 1. 'As Reimer 11. G. Rogers
- 2. C. Christensen 12. V. High
- 3. R. Kobimeier 13. A. Ensign
- 4. R. Pashby 14. W. Smith
- 5. E. Leird 15. C. Forth l 6. V. Hageman 16. V. Warne i 7. L. Burgener 17. P. Krevdo
- 6. J. Sanders 18. W. Martin l 9. J. Lockwood (2) . . ,
- 10. Gs Garry?
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File E 39252 Page T2- 3 Issued: 11-20-78 o(~ V ANALYS7S AND EVALUATION OF DATA: Analysis of Data - After accumulating the necessary data, it was necessary to evaluate the insulation material
. in terms of temperature and life expectancy.
Method of Evaluation - For this evaluation, the life expectancy is considered to be a function of temperaturea It has been found tuat the Arrhenius equation, which describes the temperature dependance of the " velocity coefficient" of chemical reactions, can be used to approximate the relations ship between life and temperature. This equation as applied in this case, indicates that the logarithm of insulation life should be a linear function of the reciprocal of the absolute temperature. To determine the best estimate of the slope and intercept of the straight line that relates the logarithm of insulation life to the reciprocal operating temperature, l regression analysis is used. The Arrhenius equation may be stated as: L = AeB/T ' i where: I L = life of the insul'ation in hours l T = temperature in degrees Kelvin l' () ( e A
= base of the natural logarithm and B are parameters of the insulation material in question l
The data points obtained by determining the number of hours to "end of life" in the laboratory when specimens of an insulating material are exposed to elevated temperatures, 3 allow a determination of the values of A and B for that g material. Then, by a process of extrapolation, an estimate 5 can be made of the expected life of the insulating material, h eliminating actual testing at other operating temperatures p which would result in insulating material life that would be g too long to test for practical reasons. In addition, a good estimate can be made of what the maximum allowable temperature for the material should be in a specifi'c application, given that its expected life should not be less than a certain number of hours, again too long to test to completion in the laboratory. The evaluation of the insulation material is completed by the regression analysis. This method of analysis is con-corned with the study of the relationship between two or more variables. In this instance, a study is made of the relation-ship between insulation life and operating conditions. 4 0 r -% , - , - - . . , . - , . . - - - . . , , . --
q - W File E 39252 Page T2- 4 Issued: 11-20-78 insulation life is denoted as the dependent variable represented by the latter Y, and the operating condition is a known as the independent variable, represented by the letter X. Thus, the regression analysis becomes a study of Y, log of insulation life, as a function of X, operating condition. For the test data, there is plotted a line, defined by the regression equation, which represents the most probable relationship of life versus temperature that can be derived from the test data. The graphs of the "end-of-life" versus " oven condition-11:g temperature" are plotted on logarithmic-reciprocal abso-lute temperature paper. For a more complete explanation of the regression analysis method, reference should be made to the IEEE publication " Report On Guide For Statistical Analysis of Test Data", No. 101. e 2 A a. 5. e l
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r 1 TABLE 8 ERIE CO. TERMINATION TYPES T-INS-HT AND T-5NS-HT 4 k' O t l l O Geert/%
" " ' ' " ~- - ___ _______
O O O i TABLE NO. 8
- Originator: 2 / Id ffM Verifier: - [ - [w A .5/7/r>
EQUIPMENT: Termination Type T-1NS-HT and T-5NS-HT j MANUFACTURER: Kerite Co. 1 TAG NOS.: N/A - SCEW REF.: 2-130, 2-131, 2-138 RAD. DOSE: 1.0 x 105 AMBIENT TEMP.: 400 C 4 ALLOWABLE RADIATION ACCEPTABLE SUCCESTED EXPOSURE OF MATERIAL LIFE INSPECTION AND , EQUIPMENT MATERIALS BASED ON SURVEILLANCE 1 MATERIALS RADS INFO. SOURCE THERMAL ACING SCHEDULE COMMENTS 1 )' BISHOP BISEAL #3 3.8 x 105 NOTE 1 > 40 YEARS CROSS-LINKED POLYETHYLENE NOTE 2 , SCOTCH 33+ 2 x 106 NOTE 1 > 40 YEARS VINYL ELECTRICAL TAPE NOTE 3 1 - [ d I l
TABLE NO. 8 NOTES
- 1. The radiatics threshold value for the material in evaluation was obtained fram the EPRI NP-2129 Final Report " Radiation Effects on Organic Materials." It is used to' confirm material radiation withstandability that was stated in the Kerite Company letter from November 3,1980. The manufacturer claims that the material will withstand radiation levels up to 0.1 megarads without significant damage. This value is therefore used to limit splice installations to areas where the total radiation dose ,
accumulated within the desired life is 1 x 105 rads or less. The difference between the limited value and the material threshold value provides a sufficient conservatism in the material suitability for a given environment. 1
- 2. The Bishop Electric Company provides technical data including the maximum continuous temperature of 950 C and the emergency overload temperature of
() 1300 C (100 hours / year) in the Biseal No.'3 product publication. To establish time relative to continuous temperature rating when the material , properties are reduced, the U.L. temperature index of 900 C for ( cross-linked polyethylene is considered. The temperature index is the i point where the material property of impact strength, tensile strength or dielectri.c strength is reduced to one half of its value at the conclusion of 5 x 104 hours. Considering that terminations are installed in the mild environment,'it would be reasonable to assume that the material aging characteristics follow the 100 C rule. The methodology is taken from the i ! EPRI Report, NP-1558 "A Review of Equipment Aging Theory and Technology." Aging analysis of non-metalic materials utilized in the construction of Class 1E motor control centers (Qualification Sannary, Volume 3, Section 2, Table 7) establishes a temperature index of 680 C for a hypothetical material, based on 40 years of service life. The ' mathematical equation of the 100 C rule was used to calculate the temperature value. Comparison of the temperature index of the material in j evaluation with the temperature index of the hypothetical material
' () determine. the suitability of the evaluated material for 40 years of l
l l
- - - . - - . - . - - . - ~ _ - - . _ . . - . - . . _ . - _ - - , - _ . - , - _ _ .
- .. . ~ _ . . . . .
O 4 B&W COMPANY EVALUATION OF AGING OF CLASS 1E INCONTAINMENT CONTROL AND INNSTRUMENTATION FOR B&W 177 FA SCOPE OF SUPPLY, DOCUMENE No. 77-1127001-00 ! ) l O Gdtert/Commoneenth
- - - . . . . - ~ . - . , . . . . . . . . . . - . , _ _ _ ,. , , _ . . _ _.- _ ,, ,_ , _,_.
- TABLE NO. 8 NOTES (Cont'd) service life at the ambient temperature of 400 C. Since the temperature index of the cross-linked polyethylene is 900 C which is higher than the calculated reference index of material with an exact service life of 40 years, it is concluded that the service life of cross-linked polyethylene is more than 40 years.
- 3. The same method as described in Note 2 is used in thermal aging evaluation of vinyl electrical tape. Temperature rating of the product is
-1050 C according to the manufacturer's technical bulletin. Comparison with the reference temperature index of the hypothetical material indicates that the service life of the vinyt material is more than 40 years at the ambient temperature of 400 C.
CONCLUSION: (~~1
~' The purpose of the insulating tapes is to provide coverage of the exposed portion of the section of terminal lugs which connect cables. They serve to provide an air-tight seal to keep moisture out of the termination and the stranded conductor. If the insulation tapes become soft due to the l environmental conditions, they could still perform their function as long as L
they were properly installed. The result of the aging analysis demonstrates that the terminations are capable of providing a reliable performance during their service life. l 1 LO l
kP W)t.s
, .y1 -. -
Babcpck & Wilcox soci.., po.., con., :on oi,,, ion a uc rmott company p/
~' July 20, 1981 sais oia Forest noaa P.O. Box 1260 ESC-805 $"4f[84$Et Mr. E. E. Renfro Nuclear Operations Materials Manager Florida Power Corporation P. O. Box 219 Crystal River,-Florida 32629
Subject:
Crystal River Unit 3 Master Services Agreement Effective Date: May 10, 1978, B&W No. 582-7087 Task 163 - Electrical Equipment Qualification: Delivery of Final Report on IEB 79-01B Aging Assessment Attention: Mr. K. B. Baker Gentlemen: Enclosed is the final report on the aging assessment of generic electrical p equipment items which B&W has performed to support the 8&W Owners' response to (x~))/ the NRC's IEB 79-01B. A draft version of the report was distributed at the April 9 Qualification Subcomittee meeting; the final report incorporates comments received since that time. Delivery of this report constitutes completion of the subject task, including any revisions or' additions thereto. If you have any questions on this report, please let me know. Sincerely yours, b R. W. Dorman ! Product Manger j Owners Group Engineering Services RWD/leh t w/o Attachment ! cc: D.C. Poole l E.C. Simpson ! W.P. E11sberry j P.Y. Baynard P. Wagner
,q G. M. Makely 1 L%)
l l 1 f
I
- l i
.l O 3 4 The distribut > 2n of this material is restricted to the i authorized participants for a period of eighteen (18) months unless the material has been made public by one or more of the participants.
1 i 1 I EVALUATION OF AGING OF CLASS IE l INCONTAINMENT CONTROLS & INSTRUMENTATION
. FOR B&W 177 FA SCOPE OF SUPPLY Document No. 77-1127001 -00 July 1981 I
Prepared by: Leon McBee i for - a ' The Owners Group of Babcock & Wilcox 0
1 . CONTENTS I. SCOPE
-E II. INTRODUCTION l
III. SENSORS
~
- 1. Westinghouse NI Detectors
- 2. Rosemount Transmitters -
1 3
- 3. Foxboro Transmitters
! 4. Bailey aP Transmitters Motorola Transmitters
% 5.
- 6. Rosemount RTDs
- 7. Mercoid Pressure Switch IV.
SUMMARY
AND RECOMMENDATIONS (O I . APPENDICES O l1 O C w i O D d Page 2 of 76 i
l I I. SCOPE j This study was performed to evaluate the materials of construction ) j of the B&W controls and instrumentation located inside the containment and used as Class 1E equipment ( In~ addition, a pressure switch used to monitor the containment pressure, specified for location either in the auxiliary building or the penetration room of the containment was included. l II. INTRODUCTION
. The informatica contained in this report was obtained from several diverse sources and represents an extensive effort to secure information !.
i that was neither available, required, nor even existed. These sources include engineering judgement, vendor assistance and personal knowledge i by cognizant individuals. l s The specific information was based on current knowledge of material composition, NRC input via the 0.0.R. guidelines, piece part procurement, i.e. by function without referen'ce to specific performance requirements and on a " build to print" basis. Purchase orders originally specified materials of construction for process wetted application and specified performance for the remainder. . l The materials of construction provided three general classes of materials. I
- 1. Metals, ceramics & glass.
- 2. Electronics and electrical components.
- 3. Rubber and rubber-like materials.
Materials in classification I were found to have 'no detectable damage due to radiation in the integrated dose levels of concern. The detectable levels l 12 for metals was greater than 1 x 1012Rad, for ceramics greater than 1 x 10 Rad,
\
Page 3 of 76
I 9 and for glass greater than 1 x 10 Rad these values were found to be in overall agreement between several sources that were used to evaluate P radiation effects. These materials were then reviewed to determine the effects of elevated temperature on the metals. Aluminum had a listed data point below 3000F, this was at 212 F with a change in tensile strength g of 4%. Metals, subjected.to neutron exposure, were evaluated-(neutron detectors) and found not to be degraded in the range of the service conditions. In summary, items in classification 1 (metals, ceramics, glass) would I not be a limiting factor in determining useful life. g Items in classification 2, electronics and electrical components, were found to be influenced by radiation (detectable change in characteristics) . from 1 x 104 to 1 x 10 Rad. 8 The effect on performance and useful life, however, will depend upon the application location and shielding afforded the particular component. < - l j Selection and use of a material, based on the most sensitive property found in a literature search, is not usually sufficient criteria, although it may be necessary. Radiation effects on material are both transient and permanent l and vary according to the composition of the material. For example, it has been found that dose rate, total exposure and environmental conditions of temperature, j pressure and humidity can all change these effects. These factors may also be interdependent and the resulting effects could be extremely complex. Thus, it beccmes necessary to carefully examine the specific application, performance and function, before a decision can be made relative to material acceptability. fiast of the experiments relating to radiation changes in the properties of electrical insulating materials have been designed to measure changes in structural properties. Parameters such as tensile strength, impact resistance, Page 4 of 76
~ s hardness, capture cross section, gas evolution and crystal structure changes have been emphasized. -Cata cn changes in alectrical_. proper-ties-is-not readily~- agiatr}e-for-the.many different materta'Is prdiently-in-use. yhere 11 a.-definite-relationship be_ tween the degradation of physical _ proaertiesJ.nd the electr-ical-characteristier of-insulating -material, since
-come_ changes -in-chemical-and phyrfdT" parameters--do-affect-electr-ical-properties ,
. ,s_uch n e.lectr.ical..ces.istance.
Unfortunately, these changes are very difficult to determine, quantitatively, the results that have been sumt.arized in this report are on a case basis relative to the property of significance. Items in class 3, the rubber and rubber-like material, are reported as a qualitative rather than quantitative basis resulting from inconsistencies in e test acceptance criteria and parametric specification.uThese_ matetiA1.sJ.re . gens.liered_.engineerad..matetials.. that is,.the-various -compounds- can-ha.ve.,their _characteti:Lti.gi_ctLan.ggd by additiyesu s peciSical-ty:-to-prevent oxidatiort, influeage_gf. raJ11atioEtn inhibit.. compression-set;-etc. For example, for g' sana N the d1!tectable change due to radiation can be changed from 1 x 10 5Rad to 2 x 10 7Rad by changing the additives used, ra" +he-puposa of-this cepoet the most,. conservative-criteri-arfrom a-
-least-licensingisk s.tandpgin.t wete_. selected-in-thragfnTWaTita~tton-- Thus,
, a design base of 40 years at 25 0C was useLt: detemine-.the effect-of. opera. ting Jh enmnane.nts at 45 0C. %e-pcimary. methodology-being-the-Arrhenius-.model
) i, take_n_ f. tom _the._EERLtepott ..N2:.1558 Ibe actixation energymused-to-evaluate
_ardn_g.was selected-from-the-instrument ' vendor's current aging program. The levels currently being used are from .5 to .75 ev. -The actual in service temperatures p10s the actual activation energy values, for a particular application,
~.should-be-considered =in order ta.detennine a more rea14stic-est-imate-of,useful 4tfe--and to rebove= excess,conserva.t., <
ism. N , Page 5 of 76
R j The methodology used to evaluate radiation was to use the sample calcu-(' 1ation in 79-01B " Guidelines For Evaluating Environmental Qualification of I} Class lE Electrical Equipment in Operation Reactors" Appendix B. The specific parameters used were: Reactor Power Level - 3,0d0 MWth 6 j Containment Volume - 2.5 x 10 Ft 3 Compartment Volume - 8000 Ft 3 , Thickness of Compartment Shield Wall - 24" Time Required to Remain Functional - 1 hr. 1 This methodology produces an integrated dose for one hour of 3 x 10 5Rads. j The specific values for a particular plant application should be factored into the final dose requirement to determine the validity of a particular limiting dose that may have been found from the more conservative case given in the
" Guidelines". ,
I 1 1
.y 4 .
l l 0 l* Page 6 of 76 l
g 1. WESTINGHOUSE N1 DETECTORS EVALUATION Each of the three models of the NI Detector has a common part that effects the service life of the detector. _Ihis enmnn-pac.t is,,,t_h,e._connstan_ j -Thu xn3M&va-pant-of the-conne.ctor-is-the silicone rubber "0" ring gaskets
's and seal washers. To aid in preventing detector failure due to the connector sensitivity to elevated temperature and humidity a redundant seal of epoxy resin is put on the connector at installation. . Anytime tl1ese connectors are opened these seals and the epoxy resin are recomended to be replaced. The j high voltage insulation in the connector is Rexolite which is a proprietary form of polystrene. This material was checked for degradation by testing a used NI connector that was removed from reactor service and found to be acceptable at the defined end of life of the detector. The Rexolite material has a radiation threshold of 1 x 1010R integrated dose and has been tested to 2.2 x 10 10 Rad.
lA. START-UP RANGE DETECTOR (WL-23683/WL-23682A) The start-up range detector service life is defined as a sensitivity. change of 10%. This change in sensitivity is due to the moderator neutron damage and BF3 depletion. Tests performed on removed start-up detectors has extended the j defined service life of the' moderator to 4-100% power years. The recommended ! change out of the detector and connector is every other fuel cycle.
. 18. INTERMEDIATE RANGE DETECTOR (WL-23635)
The intermediate range detector is a compensated detector and is. equiped i with a moderator of polyethylene. The rated end of life is due to moderator neutron damage and is, defined as a 10% change in sensitivity. The detector itself has a defined life of 6-100% power years. The connector defined life is every other fuel cycle and the moderator defined life of 4-100% power years. P Page 7 of 76 I
j IC. POWER RANGE DETECTOR (WL-23636) The power range detector has the same characteristics of life as the (] intermediate range detector.
'"'"**^""'***"'****"''"'"'"'d**''***'"""
E seals and gaskets contained in!Ahe connectors. These seals are necessary to k prevent corrosion and electrical leakage caused by the elevated temperature and high humidity of the environment. The seals are rated at 550"F continuous 6 with a radiation threshold of 1 x 10 Rad integrated dose. The NI detector's materials of construction (Table 1) list the piece parts by vendor part number and the radiation susceptability of the materials. j Comon parts are listed only once in the table. Materials already on a recomended replacement schedule are listed. b i 1 1 - 1 . O o Page 8 of 76
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USE: hInput to RPS Tdd 1 MATERIAL.S 1IST FOR 79-0IRfr) AGitlG
)
Ef)UIPilfilT: NI Oetector Westinghouse WL-23682/WL-23682A (Start-up Range) PAGE ,1, Of _ _4 _ P01EllTIAL FOR RADIATI0tt ALSO SIGNIFICANT SUSCFPTIBILITY C0t4P0tiEllT GENERIC KNOWit AGING (TilERNAL) RAOS DESCRIPTION PART inJMBER HATERIAL AS 10 YRS 40 YRS GAlstA BASIS Housing 37-779 - Aluminun (1100-0) Nuclear Grade " *
>1x10 R12 Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT e4.8 KPSI (Ref.11) Yleid Change
>1x10I2R Top Cap 40-2805 Aluminum (1100-0) Nuclear Grade
- Detectable liigh Purity (Ref. 5) Change 20 2.4x10 tiVT +4.8 KPSI' (Ref.11) Yield Change Bottom Cap 40-2689 Aluminum (1100-0) Nuclear Grade * >1x10 R 12
- Detectable liigh Purity (Ref. 5) Change
- 20 2.4x10 ftVI 64.8 KPSI (Ref. 11) Yield Change Lower Plate 40-2898 Aluninun (1100-0) Nuclear Grade
>lx10 R 12 Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT +4.8 KPSI (Ref.11) Yield Chang e Detector Assembly WL-23055 Aluutnum (1100-0) -
Nuclear Grade *(l) >1x10I2R Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT t4.8 KPSI (Ref.11) Yield Change Insulator , 24-1510 , Ceramic ~
>1x1012R Detectable (Ref. 5) Change I
2.73x10SV1 <1% Demin. (Ref.11) Change Insulator 24-1508 Ceramic
>lx1012R Detectable (Ref. 5) Change fRbk N!nkS*I"*
(1) Two fuel Cycles Page 9 of 76 m -...
" *
- M
- M M M h hue M M d. he, hr ag, m USE: Input to RPS MATERI Al.S l.IST FOR 79-01Mc) AGING EQUIPHEtlT: NI Detector Westinghouse HL-23682/WL-23682A (Start-up Range) PAGE J_ _ 0F 4 POTEllTIAL FOR RADIATI0tl ALSO SIGrilFICAtlT SUSCEPTI8ILITY COMP 0tlENT GENERIC KNOWii AGING (TilERMAL) '
RADS DESCRIPTION PART NUMBER MATERIAL AS 10 YRS 40 YR$ GAWlA DASIS Insulator 24-1512 Ceramic . * >1x1012R Detectable (Ref. 5) Change I 2.73x10 3dVI <1% Demin. (Ref.11) Change Plate 40-2834 12 Aluminum (1100-0) fluclear Grade *
>1x10 R Detectable liigh Purity (Ref. 5) Change . ,
2.73x10IkV1 >1% Demin. (Ref.11) Change Tubulation 37-46 Aluminum (1100-0) Nuclear Grade * >lx10I2R Detectable liigh Purity (Ref. 5) Change I 2.73x10 l4V1 >1% Demin. (Ref.11) Change 40-2819' >1x10I2R Cap Aluminum Nuclear Grade
- Detectable liigh Purity (Ref. 5) Change I
~
2.73x10 91V1 >1% Demin. (Ref.11) Change Insert 12 Titanium 40-2835 * >1x10 R Detectable (Ref. 5) Change Triax Cable Jack 42-856 Brass Gremar 19414-1 i *
+4.2x1013R Threshold Rexollte Insulator ** (Ref.g)
>4.2x10 R Threshold (Ref8 11)
Epoxy Sealant (1)
- 5x10 R Threshold Silicon Gasket (1) * (Ref8' 5x10 R Threshold n (Ref.11) I (1) Appendix A -
Page 10 of 76
M M M N $ h hast asma m -amw > amme mind m > .-=. - USE: Input ta RPS HATFitIAIS IIST Folt 79-010(c) AGitlG 3 0F PAGE 4 EQUIPHEtlT: NI Detector Westinghouse WL-23682/WL-23682A (Start-up Ranqe) POTENTIAL FOR RADIAT10tl ALSO SIGNIFICANT SUSCEP!!BILITY GENERIC KNOWN AGING (THMM) - RADS COMP 0tlEllT DESCRIPT!0ft PART NUMBER MATERIAL AS 10 YRS 40 YRS GANIA BASIS l Triax Cable Ass'y 35-5250 Quartz /SST'L
-
- 2.2x1015R No Effect (Re f. 11) 20 7.8x10 NVT +59.4 KPSI (Ref.11) Vield Changt
>1x1012R Detectable Eyn Bolt 42-807 Stainless Steel (Ref. 5) Change - ,
20 2.4x10 NVT +4.8 KPSI
, (Ref.11) iteld Change SI-eve 37-20765 Stainless Steel * >1x1012R Detectable (Ref. 5) Change ,
20 2.4x10 NVT +4.8 KPSI (Ref.11) field Changt
>1x1012R Screw 42-10016 Stainless Steel
*
- Detectabie (Ref. 5) Change -
20
. 2.4x10 NVT 64.8 KPSI (Ref.11) Yield Chang (
- I2
>1x10 R Detectable Belt Spring 38-928 Stainless Steel (Ref. 5) Change 20
. 2.4x10 NVT +4.8 KPSI !
(Ref,11) VieldChangd Spacer, Spring 36-3443 Steel * >1x1012R Detectable (Ref. 5) Change - 12 Wire Rope Thimble 42-873 Steel * >1x10 R Detectable ! (Ref. 5) Change l Cable Clamp 43-1036 Steel * >1x10I2R Detectable! 1 (Ref. 5) Change Page 11 of 76
sand seg . mag h aan ned. hist amiL Add M M M M M M Tculo 1 Wh M USE: Input to RPS MATERIALS IIST FOR 79-OlBir) AGit!G EQulPHEtiT: NI Detector Westinghouse WL-23602/WL-23682A (Start-up Range) PAGE 4 0F 4 POIEllilAL FOR RADIAT!0tl ALSO SIGNiflCANT SUSCEPTIBILITY C0t4P0ftElli GENERIC KNOWN AGING ( EE M L) . DESCRIPTION RADS PART NUMBER . MATERIAL AS~ 10 YRS 40 YRS GAMMA BASIS 3/16 Dia. Wire Rope 43-1033 ' Stainless Steel *
>1x1012R Detectable (Ref. 5) Change Lock Ring 40-2688 Aluminum Nuclear Grade * >lx10I2R Detectable
~
liigh Purity (Ref. 5) Change 2.4x102gVT +4.8 KPSI (Ref.11) Yield Changi , Sleeving 940-60206-94 Fiber Glass
- 12
>1 R Detectable
/(x10Ref. 5)Change
\
Page 12 of 76
Jet . $ M. hea__W _bill6 .IE -E .te gn ,m. % M .._ M .__. m .. M .x q . W ...Iun Tchle 1 ' USE: Input to RPS MATERIAtS IIST FOR 79-010(c) AGING fQUIPHEllI: NI Detector Westinghause WL-23635 (Intermediate Range) PAGE 1 0F S POIENTIAL FOR RAufAT10tl ALSO SIGNIFICANT SUSCEPTI8ILITY COMP 0tlEllT GENERIC KNOWii AGING (TilERMAL) RADS DESCRIPTION PART NUMBER HATERIAL AS 10 YRS 40 YRS GAMMA 8 ASIS llousing 37-780 12 Aluminum 1100-0 Nuclear Grade * -lx10 R Detectable liigh Purity . (Ref. 5) Change 20 ' 2.4x10 NVT +4.8KPSI (Ref.11) Vield Change Top Cap 28-790 Aluminum 1100-0 Nuclear Grade . * -lx10I2R Detectable ' liigh Purity (Ref. 5) Change 2.4x1020 NVT +4.8KPSI (Ref.11) field Change Collar 40-3249 Aluminum 1100-0 Nuclear Grade
- l2
>l x10 R Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT +4.8KPSI (Ref.11) field Change llolding Ring 40-3248 12 Aluminum 1100-0 Nuclear Grade * >1 x10 R Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT +4.8KPSI (Ref.11) field Change Comp. lon Chamber 148-23084 Aluminum 1100-0 Nuclear Grade See Sheet #(5) liigh Purity Bottom Cap 40-2639 Aluminum 1100-0 Nuclear Grade See WL-236J6 liigh Purity .
Tubulation 37-912 Aluminum 1100-0 Nuclear Grade See WL-23636 liigh Purity Cap 35-7431 Aluminum 1100-0 Nuclear Grade See WL-23636 liigh Purity i Page 13 of 76 ,
. . M ... .M .'~ b .l M C M - U M N ( = -- I - - -
USE: Irput to RPS MATERI AI S I IST FOR 79-01Mc) AGIflG EQUIPMEtiT: NI Detector Westinghouse WL-23635 (Intermediate Range) 2 PAGE 0F 5 POTENTIAL FOR RAlllATI0li ALSO SIGNIFICAfiT SUSCEPTIBILITY COMP 0flENT GENERIC KNOWtl AGING (TilERMAL)' DESCRIPTION PART NUMBER MATERIAL RA05 AS 10 YRS 40 YRS GA!V1A BASIS
' Spacer 40-2971 -
Aluminum 1100-0 Nuclear Grade See WL-23636 Iligh Purity Cable Plate 40-3081 Aluminum 1100-0 ' Nuclear Grade
- lx1012R Detectable
' liigh Purity (Ref. 5) Change 20 2.4x10 tiVT +4.8KPSI (Ref.11) Yield Change Crimp Sleeve 37-995 Aluminum 1100-0 Nuclear Grade * , lx10I2R Detectable liigh Purity , . (Ref. 5) Change 20 2.4x10 NVT +4.8KPSI (Ref.11) field Change Insulator 24-1632 Ceramic See WL-23636 Insulator 24-1509 Ceramic See WL-23636 Insulator 24-1713 Ceramic See WL-23636 Insulator 24-1508 Ceramic See WL-23636 insulator 24-1510 Ceramic See WL-23636 Adapter 40-2813 Stainless Steel - See WL-23636 Screw 42-11066 Stainless Steel See WL-23636 ,. Page 14 of 76
W. -W .. W .--ad_.- h ..heb W w p .w .me w -- - w - m - - - --- m ,=(_ ) --- - USE: Inp to RPS Taba-i g MATERIAIS IIST FOR 79-01Dfc) AGING EQUIPMENT: NI Detector Westinghouse WL-23635 (Intermediate Range) PAGE 3 0F S POTENTIAL FOR RADIATION ALSO SIGNIFICANT SUSCEPi!BILITY COMP 0NENT GENERIC KNOWN AGING (TilERMAL) RADS DESCRIPTION PART NUMBER MATERIAL AS? 10 YRS 40 YRS GAMMA BASIS
- Washer 42-11068 Stainless Steel See WL-23636 Lockwasher 42-11067 Stainless Steel See WL-23636 Lock Nut 40-2839 Stainless Steel -
See WL-23636 Set Screw 42-10019 Stainless Steel See WL-23636 Screw 42-10027 Stainless Steel See WL-23636 Sleeve 37-835 Stainless Steel See WL-23636 Washer 42-10096 Stainless Steel
. See WL-23636 ,
Wire Rope Thimble 42-873 Stainless Steel See WL-23636 Cable Clamp 43-1036 Stainless Steel - See WL-23636 Screw 42-11205 Stainless Steel See WL-23636
.19 Dia. Wire Rope 43-1033 Stainless Steel See WL-23636 Page 15 . o f 76
med s. m- med ans.e - her w u anse km w mm e ans4 W ased- amas er ame . anew USE: Int ~ to RPS MATERI Al.S LIST FOR 79-Oln(c) AGirlG ' EQUIPMENT: NI Detector Westinghouse WL-23635 (Intennediate Range) PAGE 4 _ _ 0F S. POTENTIAL FOR RADIATI0tl ALSO SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TilERMAL) DESCRIPTION RADS PART tlUMBER MATERIAL AS 10 YRS 40 YRS GAMMA BASIS Screw 42-11201 Stainless Steel l See WL-23636 Washer 42-10743 Stainless Steel' See WL-23636 1.D. Tag 43-1548 Stainless Steel See WL-23636 - Retainer 42-11069 Titanium ' See WL-23636 Support Rod 40-2958 Titanium 12
* >1x10 R Detectable (Ref. 5) Change I9 5x10 NVT +8.9KPSI (Ref.11) Yield Changt Insert 40-2021 Ti tanium See WL-23636 Insulator Tape 950-90691-08 Kapton Il-Film N/A See WL-23636 Modera tor 24-2325 liigh Density 9 4-100% 3x10 R 10% Change Pwr Yrs in sensitivi:y
- Poly Ethylene 1x10;9NVf 1.7% Change in hydrogen Triax Cable Ass'y 35-6198 Aluminum 0xide
- 2.2x1015R No Stainless Steel Effect Triax Cable Jack 42-813 Amphenol
- See WL-23636 52975-1051 1
Page 16. of 76
w ---w-- w w USE: Is to RPS me.a w _ .ame M . _ M .. M .. W .. . M _. . W T 21 MATFRIAI.S LIST FOR 79-010(c) AGittr. EQUIPMEllT: NI Detector Westinghouse WL-23635 (Intennediate Range) Of _5__ PAGE . 5 POTENTIAL FOR RADIATI0ft ALSO SIGfilflCANT SUSCEPTIBILITY COMPO!1ENT GENERIC KNOWN AGIflG(TilERMAL) DESCRIPTION PART NUMBER RMS MATERIAL AS: 10 yns 40 YRS GAMMA BASIS Compensated
>lx10I2R Aluminum Nuclear Grade ion Chamber Detectable Neutron Sensitive liigh Purity * '
(Ref. 5) Change Material Gas Fill Boron (B ) Nitrogen 6 .100% 2.4x1020fiVT e4.8 KPSI Pwr Yrs (Ref.11) Yield Changt I i
' l t .
g , Page 17. of 76 _
l M h b-M M M M M b M M M M M M "E" MATERTAI.S IIST FOR 79 Olpfc) Ar,1Nr.
'} NIER. ,
EQUIPl1ENT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 1 0F 6 POTENTIAL FOR RADIATION ALSO SIGNIFICANT SUSCEPTI8isITY COMPONENT _ GENERIC KNOWN AGING (lllERMAL) ' RADS DESCRIPTION PART NUMBER MATERIAL AS. 10 YRS 40 YRS GAi44A BASIS
' lousing 32 37-833 Aluminum 1100-0 Nuclear Grade * > lx10 R Detectable liigh Purity -
(Ref. 5) Change 20 2.4x10 NVT 44.8KPSI (Re f. 11 ) Yield Chang ( Top Cap 40-2809 Aluminum 1100-0 Nuclear Grade * > lx10I R Detectable High Purity (Ref. 5) Change 20 2.4x10 NVT +4.8KPSI (Re f. 11 ) Yield Changa Collar 40-2895 Aluminum 1100-0 Nuclear Grade '* > lx10I2R Detectable liigh Purity (Ref. 5) Change - 20 ' 2.4x10 HVT +4.8KPSI (Ref.11) Vield Changt ilolding Ring 40-2828
- 12 Aluminum 1100-0 Nuclear Grade > lx10 R Detectable liigh Purity (Ref. 5) Change ,
20 2.4x10 NVT +4.8KPSI (Ref. 11) Yield Changt uncompenstated 148-23497 Aluminum 1100-0 Nuclear Grade ,
* > lx10I2R Detectable ion Chamber liigh Purity (Ref. 5) Change .
20 2.4x10 NVT +4.8KPSI (Ref.11) Yield Changt Bottom Cap 40-2689 Aluminum 1100-0 Nuclear Grade * > l2 lx10 R Detectable liigh Purity (Ref. 5) Change 20 2.4x10 NVT +4.8KPSI (Ref,11) Yueld Changt e 8 Page 18 of 76 !
M M-M- M M M M M M M ',M U M M M "~ USE: snput to RPS cble 1 MATERIAtj LIST FOR 79-OlB(c) AGillG EQUIPMEtiT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 2 0F 6 POTENTIAL FOR RADIATION ALSO SIGNIFICANT SUSCEPTIBILITY COMP 0tlEilT GENERIC AGING (THERMAL) KNOWN DESCRIPTION PART NUMBER ItADS MATERIAL AS 10 YRS 40 YRS GAMMA BASIS Tubulation 37-921 Aluminum 1100-0 Nuclear Grade
- 12 i >1 x10 R Detectable liigh Purity (Ref. 5) Change f 20 2.4x10 NVT +4.8KPSI
.' (Ref,11) Vield Change Cap 35-7431 Aluminum 1100-0 Nuclear Grade * >lx1012R Detectable liigh Purity (Ref. 5) Change
- 20 2.4x10 NVT +4.8KPSI
'(Re f. 11 ) field Change Cable Plate
>lx10I2R 40-3082 Aluminum 1100-0 Nuclear Grade
- Detectable liigh Purity (Ref. SjO Change 2.4x10 NVT '4.8KPSI
[Ref.11) (ield Change ! Spacer 49-2971 Aluninum 1100-0
- 12 I
Nuclear Grade * >1x10 Detectable liigh Purity Change (Ref. 5)O 2.4x10 NVT +4.8KPSI (Ref.11) field Change Crimp Sleeve
>lx10I2R 37-995 Aluminun 1100-0 Nuclear Grade
- Detectable liigh Purity [Ref. Sj0 Change 2.4x10 NVT 84.8KPSI
, [Ref.11) (teld Change
- Insulator 24-1632 Ceramic
- 12
>1x10 R Detectable 24-1713 Ceramic N"I 19 24-1508 Ceramic 7 NVT 1% emin.
[Re f. 11 ) Change 24-1510 Ceramic
. Page 19 of 76
- and _ _ _ M _ smeh - S M - B W - h . M Shm g has M han % DEL hA( 4A(G, 336 bdh USE: Iryput to RPS TibW I U *
~
MATERIALS 6?ST FOR 79-010(c) AGillG EQUIPMEllT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 3 0F 6 PQTENTIAL FOR RADIATI0tl ALSO SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TilERMAL) i RADS . DESCRIPTION PART tlUMBER MATERIAL AS~ 10 YRS 40 YRS GAMMA BASIS Adaptor 40-2813 Stainless Steel * >lx10R R Detectable (Ref. 5) Change 2.04x10I0NVT +54.1 KPSI (Ref.11) Yield Changi - 2 Screw 42-11066 Stainless Steel * >1x10 R Detectable (Ref. 5)jg Change 2.04x10 NVT +54.1KPSI '
, (Re f. 11 ) Yield Changt Washer 42-11068 Stainless Steel
* >1x1012R Detectable (Ref. 5)j9 Change 2.04x10 NV1 +54.1 KilS I (Ref. 11) Yield Changt Lock Washer 2 42-11067 Stainless Steel * >1x10 R Detectable (Ref. 5) Change 2.04x10'9NVT +54.1KPSI (Ref.11) field Chang (
Lock flut 40-2839 Stainless Steel >1x1012R Detectable (Ref. 5)j9 Change 2:04x10 NVT +54.1KPSI (Ref. 11) Yield Changt
>1x1012R Set Screw 42-10019 Stainless Steel
- Detectable (Ref. 5)j9 Change 2.04x10 fiVT +54.lKPSI
. (Ref. 11 ) Yield Chang (
Washer 42-10743 Stainless Steel
- 12
>1x10 R Detectable (Ref. 5)jg Change
. 2.04x10 flVT +54.lhPSI j
(Ref. 11 ) field Chanot. . Page. 20 of 76 0 __
E ... N ~U- U , U.U t M i
% h . M ^Ind. U. .k _ U ~ M~~ U N Y"
MATERIALS IIST 9 010(c) AGirlG EQUIPMENT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 4 __ 0F 6 POTENTIAL FOR RADIAT10ft ALSO SIGflIFICANT SUSCEFTIBILITY AGIllG(TilERMAL) COMP 0NEllT GENERIC KNOWN RADS DESCRIPTION PART NUMBER MATERIAL AS 10 YRS 40 YRS GAMMA BASIS 12 Screw 42-10027
- Stainless Steel - * >1x10 R Detectable (Ref.Shg Change 2.04x10 NV1 +54.1KPSI (Ref.11) (teld Change Sleeve 37-835 Stainless Steel' * >!x1012R Detectable lRef. 5)j9 Change -
2.04x10 NVT +54.1KPSI
;Re f. 11) Yield Change Washer .75 0.D. 42-10096 Stainless Steel
* >1x1012R Detectable lRef. 5);g Change 2.04x10 NVT
+54.1KPSI
'Ref. 11) field Change Wire Rope Thimble 42-873 Stainless Steel
- 1x1012R Detectable lRef. 5)j9 Change 2.04x10 NVT +54.1XPSI lRef. 11 ) field Change 12 Cable C1dmp 43-1036 Stainless Steel * -1x10 R Detectable Ref. 5)jg Gange 2.04x10 NVT tS4.1KPSI (Ref.11) field Change 1x1012R
.19 Dia. Wire Rope 43-1033 Stainless Steel
- Detectable (Ref. 5);9 Change 2.04x10 NVT +54.1KPSI (Ref.11) field Changt Screw 42-11205 Stainless Steel *
- 1x1012R Detectable (Ref. lig g Change 2.04x10 NVT *S4.lKPSI (Ref.11) field Change
_ _ _ _ _ _ _ a - _ _ - -
__N__ - U -- - N.. .U --U: W -- t b -M M M - W --M -- M h Table 1 , USE: Input to RPS HATERIAIS IIST FOR 79-Olpfr) AGING 5 EQUIPMEllT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 0F _6 POTENTIAL FOR RADIATIO 1 ALSO SIGNIFICANT SUSCEPTIBILITY GENERIC KNOWN AGING (TilERMAL) COMPONENT RADS DESCRIPTION PART NUMBER MATERIAL AS- 10 YRS 40 YRS GAMMA BASIS 12 Screw 42-1033 Stainless steel * . l.x10 R Detectable
' Change (Ref. 5);9 2.04x10 NV1 +54.lKPSI (Ref. 11) (ield Changt
>1x10I2R i ID Tag 43-1548 Stainless Steel Detectable I (Ref. 5)j9 Change -
2.04x10 NV1 +54.lKPSI (Ref.11) field Change Retainer 42-11069 Titanium * >lx1012R DetectabYe Change (Ref.jg)VT 5x10 N i8.9KPSI (Ref. 11) (ield Change 12 Support Rod 40-2824 Titanium g >1x10 R Detectable Change (Ref.jg)VT 5x10 N +8.9KPSI (Ref.11) (ield Change 12 Insert 40-2821 Titanium * >1x10 R Detectable Change
- (Ref.jg)VT 5x10 N +8.9KPSI (Ref. 11) (ield Change pelt Spring 38-928 Spring Stael Carbon Steel * >lx10I2R Detectable
- Change
* (Ref.jg)VT 5x10 N 18.9KPSI (Re f. 11 ) Yield Changt 8'
Insulating Tape 950-90691-0B Kapton Il-Film - 5x10 R Limiting Dose e 25 of 76 _____ _____!
M W -- M - M W M - W -- k . g W - M - M M-M-M , g M M Table 1 USE: Input to RPS MAlfRI AI S I IST FOR 79-010(c) AGirlG ~ EQUIPMEllT: NI Detector Westinghouse WL-23636 (Power Range) PAGE 6 0F 6 __ POTEtiTIAL FOR RADIATI0tl ALSO SIGilIFICANT SUSCEPTIBILITY COMP 0tlEtiT GENERIC KNOWN AGING (TilERMAL) RADS DESCRIPl;0tl PART tlVMBER MATERIAL AS:- 10 YRS 40 YRS GAMMA BASIS Triax Cable Ass'y 35- 6197
* >3. 3x10 R +59.4KPSI Aluminum StainlessSteel(331 0xide(AL0}) .
7.8x10 NVT field Change No significar t change in (AL230) 6 Triax Cable Jack 42-313 Silicon Rubber Gaskets (l) Amphenol
- lx10 R Threshold 52975-105) (Re f. 11) -
~
8 Epoxy Sealant (1)
- 5x10 R Threshold (Ref.11) 9 Rexolite Insulators
- 4.2x10 R Threshold (Ref.11)
Brass
- 4.2x10I3R Threshold (Ref. 11)
I s tiote 1: Appendix A . Page 23 of 76
I d
- 2. ROSEMOUNT TRANSMITTER The Rosemount transmitter contains integrated circuits and piece part electronics, such as, resistors, capacitors, diodes and transmitters.
These parts are mounted on printed circuit boards. The printed circuit
.g boards are mounted in a "0" ring sealed stainless steel housing. Continuous j
service at elevated temperature and humidity is dependent on maintaining the rings are housing in a sealed condition. To ensure sealing, the housing "0" recommended to be changed at each calibration / maintenance action. This action is not the result of only observed radiation / thermal aging characteristics, but is a conservative measure to ensure proper sealing. Evaluation of the transmitter piece parts (Table 2) for radiation suscept-j- ability using the , materials of construction and the 00R Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactor, o h Appendix B and the sample calculation, the materials are acceptable for the service. The transmitter, as supplied by B&W, was specified to remain functional 6 to an integrated dose of 7 x 10 Rad. 4 It was type tested to 5 x 10 Rad. The 5 example used from the guidelines produces a integrated dose of 3 x 10 Rad. The electronics are the most sensitive materials to thermal aging using l the Arrhenious equation from reference 7, page 3, equation 6 to evaluate the o E- chenge in usefui ,4fe. when the env4ronment is chenged from 2 soc to 4s C its life is reduced to 6.69 years. . 1 For reference " Aging of I&C: A Practical Generic Solution to a Preplexing l Problem" the quation form used is: Ea l 1 A = exp g ( g - g) l A = Exceleration Factor l TS = Service Temperature l ( E Page 24 of 76 y
TA = Aging Temperature Ea = Activation Energy i
' KB = Boltzmann's Constant (8.617 x 10-5 ey/og)
Assume Ea is equal to .70 ev A = exp h x 10-5 -( - h) A = 5.97 Acceleration Factor ." j Life = 40 rs or 6.69 years at 45 0C
,/
.j ,,
?
} .
b I l ~ 1 l
~1 I 1 1
3 Page 25 of 76 l1
an s w w w - w - _ _ - - __ _ _. USE: Input t3 RPS MATFRIAIS IIS OR 79-01Mc) AGirlG EQUll'r4EllT: Rosemount 1152 GP9 Transmitter PAGE ,1 0F 1_ POTENTIAL FOR RADIAT10tl SIGliiF! CANT SUSCEPfIBILITY ALSO AGING (TilERMAL) COMP 0f!EllT GENERIC KNOWN RADS DESCRIPT!0tl PART NUMBER HATERIAL AS 10 YRS 40 YRS GAMMA DASIS
- 5 AMP. Ckt. Bd. 4-20na 01151-0057-0001 Electronic Ass'y 1x10 R Threshold (Ref 5) Damage Calib. Ckt. Bd. 01151-0059-0001 Electronic Ass'y
- lx10 bR Threshold (Ref 5) Damage Connector Ckt. Bd. 01151-0066-0001 Electronic Ass'y
- lx10 5R Threshold (Ref.5 Damage Sensor Mod. (0-3000) 01152-0003-0092 316SS/ Silicone Oil "Q" Cell
- 5.0x10)R 25% Viscostl y, (Ref. 5) Change .
Elect. Ilousing 01151-0060-0009 316 Stainless Steel * >lx10I2R Detectable (Ref. 5) Change
>1x1012R Elect. Cover 01151-0126-0001 316 Stainless Steel .
- Detectable (Ref. 5) Changs 12 Process Flange 90043-0050-0002 316 Stainless Steel .
* >1x10 Rads Detectable (Ref. 5) Change 12 Blank Flange 01152-0017-0001 316 Stainless. Steel * >1x10 Detectable (Ref. 5) Change 12 Valve Stem & Seat 01151-0028-0112 316 Stainless Steel * >1x10 Detectable (Ref. 5) Change 12 Adjust. Screw 01151-0029-0001 Steel *. >1x10 Detectable!
(Ref. 5) Change 12 Retaining Ring 01151-0029-0001 Steel * >1x10 Detectable (Ref. 5) Change 7 "0" Ring /Adj. Screw 01151-0032-0001 Buna N 4x10 25% Change (Ref. 3) In Property in Air Page 26 of 76
a %- amed w w w w w - - - - - : - - - - - - --- T I 2 i ) T USE: Input to RPS MATFRIAtS IIST FOR 79-010(c) AGiflG
^ '
EQUIPHENT: Rosemount 1152 GP9 Transmitter POlENTIAL-FOR RAulAT10ft ALSO SIGilIFICANT SUSCEFilBILITY C0tiPO!!EllT GENERIC KNOWN AGING (TilERMAL) - RADS DESCRIPTION PART NUMBER HATERIAL AS. 10 YRS 40 YRS GAMMA BASIS 7
"0" Ring for Elect. 01151-0033-0002 Buna N~ 4x10 25% Change Cover (Ref. 3) In Property in Air 6 "0" Ring for Process 01151-0034-0007 Ethylene Propylene 5x10 Threshold Flg. (Ref. 5)
Leak-Lock Thread C10163-0002 UNK . Sealant Elec. Ass'y Hardwart 01151-0Q30-0001 12 Standoff 01151-0030-0001 Steel *
* >1x10 Measurable 5 Change (Refl2 )
Standoff 0110030-0001 Steel * >1x10 Heasurable Change Washer 01151-0030-0001 Steel .
* (Refl25 )
>1x10 Heasurable Change Steel * (Refl25 )
>1x10 Heasurable Screw 01151-0030-0001 5 Change Screw 01151-0030-0001 Steel
* (Refl2 )
>1x10 Heasurable Change
* (Refl25 ) Measurable Locknut 01151-0030-0001 Steel >1x10 5 Change (Refl2 ) Heasurable Process Flange: ------
316 Stainless Steel .* >1x10
+ . 5 Change Bolt 01151-0031-0004 Steel * >1{Refl2 x10 ) Measurable
' ' 5 Change flu t Steel * (Refl2 )
>1x10 Measurable 5 Change Mounting Bracket 01151-0036-0004 Steel * (Refl2 )
>1x10 Measurable with Bolts (Ref. 5) Change Page 27 of 76 l
1 M l {J W. l
- 3. FOXBORO E11GH TRAf;SMITTER EVAL.UATI0ft The Foxboro pressure transmitter is made up of piece part. electronics, I that is, resistors, capacitors, diodes, and transistors mounted on printed circuit boards. The electronics are mounted inside a "0" ring sealed housing, continuous service at elevated temperature and humidity is dependent on a
maintaining the housing in a sealed condition. The Foxboro transmitter materials of construction (Table 3) lists the piece parts by vendor part number and the radiation susceptability of the materials. To evaluate radiation 79-01B " Guidelines for Evaluating Environmental Qualification of Class 1E Equipment in Operating Reactors" Appendix B was used. The sample presented was used to arrive at an integrated dose for 1 hour of 3 x 105 . This was used to evaluate the radiation susceptability from Table 3. Foxboro transmitters were type tested by B&W to meet the B&W (]) - 4 requirement of 4 x 104 Rad by. testing .the transmitter to 4.6 x 10 integrated dose. Foxboro, as part of their "lE" program, has tested the transmitter to 8 Each owner should use the example to determine the one hour over 1 x 10 Rad. 1 dose for the transmitter location. J , , The most sensitive materials to thermal aging is the solid state electronics. l 8 . Using the Arrhenious equation from reference 7, page 3, equation 6 and evaluation 0 l the effect in aging from 25 C to 45 C and using an estimated activation energy 1 of .7 ev. 1 . Page 28 of 76 1 1 E I . -
1 I A=exp'h(h-h) A = Acceleration Factor TS = Service Temperature TA = Aging Temperature 's KB = Boltzmann's Constant (8.617 x 10-5 eyfog) , Assume Ea is equal to .7 ev
.7 1 1 A = exp C6 x 10-5 (3TE ~ 297)
A = 5.97 g Evaluated for 40 years at 25 0C = 6.69 years at 45 0C 1 . b . !1 1 1 1
~
l1 1. l l1 Page 29 of 76
M st. iu M ESM M M M had MT 3 M M M M M M W M M (Foxboro). MATERIALS _[IST 79-018(c) AGirlG - EI)UIPMEN1 : E 10 Series Transnitter (EllGH) PAGE 1 0F 6 __ POTENTIAL FOR RADIAT10fi ALSO SIGflIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (THERMAL) DESCRIPTION RADS PART NUMBER HATERIAL AS- 10 YRS 40 YRS GAMMA DASIS Cover N0141YW Aluminum 214
- 1x10 " Detectable (Ref. 5) Change Lubricant (for threads of cover) X114AA Dow Corning DC-710 N/A Transmitter Amplii?ier Ass'y N0138Q Solid State Electronics
- 5 lx10 R(Ref. 5) Threshold 8-32 x 3/8 Ilex. * >lx10 12 Detectable Socket Screws X116MP Steel *
. (Ref. 5) Change '
5/16-24 x 3/4 Nex. N0141PY Steel
- 12 Socket Screws
>1x10 Detectable (Ref. 5) Change Base Assembly N0999LL Cast Iron
- 12
>1x10 Detectable (Ref. 5) Change Zero Sha f t N0141EX Steel
- 12
>1x10 Detectable
' (Ref. 5) Change 0-Ring, 1/4" ID C127FT Viton
- 6 Flucro Carbon (l) SJ.0 Detectable x 3/8" OD Elastomer (Rsf. 3) Change Sleeve N0141SC Steel 0-Ring Nil 9WR Viton
- 5x10 6
Fluoro Carbon (l) Detectable Elastomer (Ref. 3) Change 5-40 x 3/16 Set X100TK Steel 4 >1x1012R Screw Detectable
* (Ref. 5) Change Hylon Washer M146SM Nylon Polyamide (1) *
+4x10 rad 25% property (Ref. 5) Change in Compression Zero Coupling "lx10I2R Ass'y N0143PN Steel Detectable (Ref. 5) Change Retaining Ring X106BK ' Steel
- lx10 12 Detectable (Ref. 5) Change (1) Appendix A Page 30 of 76 1
{ .., . .gr.4 , e >. + g A . MAT QlfLS LIST FOR 79-018(c) AGIflG PAGE 2 0F 6 EQUIPMENT: E 10 Series Transmitter (E11GH) POTENTIAL FOR RADIATI0il ALSO SIGilIFICANT SUSCEPTIBILITY COMP 0tlEllT GENERIC KNOWN AGING (TilERMAL) RADS DESCRIPTION PART NUMBER MATERIAL AS: 10 YRS 40 YRS GAMtiA BASIS Cable (used with integral amplifier) N0986LL Nylon (assumed) Polyamide (1) *
!4xid 25% Change (Ref. 5) in Compres-sion 6
0-Ring, 3/8" 10 x 0100RP Viton Fluoro Carbon (l) 5x10 R Detectable 1/2" Ob . Elastomer (Pef. 5) Change Washers Steel
- I2 Detectable N119RL >1x10 R (Ref. 5) Change 10-32 x 1/2 Ilex. X116KX Steel
- ilx1012R Detectable Socket Screws (Ref. 5) Change Force Bar and Base Steel *
>lx10l2R Detectable Assembly (Ref. 5) Change I2 3-48 x 1/8 Ilex. N0141ER Steel *
>lx10 R Detectable Socket Screws , (Ref. 5) Change
- 8 Sealant (between X117AX Silicone RTV Silastic (1) 5x10 R 25% Change Base Assembly and (Ref. 5) in Compress.
Body) Lubricant X0118CC- Dow Corning - DC 710 Silicone 011(2) N/A N/A Junction Box N0143SF Cast Iron >1x1012R Detectable (Ref. 5) Change 12 Coupling N0143SE Stainless Steel * >1x10 Detectable (Ref. 5) Change 12 3/4-16 Ilex. Nut B116TW Steel * >1x10 R Detectable
, (Ref. 5) Change Retaining Ring 49820 Steel * ,lx1012R Detectable (Ref. 5) Change (1) Appendix A *
(2) Used to assemble unit Page 3i of 76
Y "
~Y-Y "
Y Y Y ~Y& 3 Y '~ Y * * ~ ~ ~~
#ffx$ho HATFRIALS IIST FOR 79-01Bfc) AGING EQUll'HENT: E 10 Series Transmitter (EllGH) PAGE 3 0F 6 POTENTIAL FOR RADIAT10tl ALSO SIGNIFICANT SUSCEPTIBILITY COMP 0NEllT GENERIC AGING (THERMAL)
KNOWN DESCRIPTION PART NUMBER RADS HATERIAL AS 10 YRS 40 YRS GAMMA BASIS Tenninal Block NUl41XI Phenolic (assumed)
- 7
>1x10 R(Ref 5)?5% Change 8-32 x 1/4 Pan H. X100PM Steel - *
>1x10I2R $$tbEa0le Screws (Ref. 5) Change 6-32 x 7/8 R.H.
Screw 3 34476 ^ Steel *
>1x10I2R De tec table (Ref. 5) Change force Bar Ass'y Part P0120NK Steel * .;x1012R Detectable (Ref. 5) Change Nut Dil4CZ Steel ~* I2
~ >1x10 R Detectable (Ref. 5) Change Screw N0141TL Steel *
>lx1012R Detectable
. (flef. 5) Change Bracket N0141Fil Steel *
>1x10 R 12 Detectable (Ref. 5) Change 8-32 x 1/4 Hex. X100ML Steel *
>lx1012R Detectable Socket Screws *
(Ref. 5) Change Flexure Assembly N0141EF Steel *
>1x1012R Detectable (Ref. 5) ' Char.g e Washers X1020X Steel *
>1x10I2R Detectable (Ref. 5) Change Screws fl0143LY~ Steel
- 12
>1x10 R Detectable (Ref. 5) Change 5-40 flut 34308 Steel *
>1x10 R I2 Detectable (Ref. 5) Change
>lx10I2R-Bracket N0141Kt1 Steel
- Detectable (Ref. 5) Change Column N0141KC Steel *
>1x10 R I2 Detectable (Ref. 5) Change
~
Page 32 of 76
- - - -- r
s * ~j h / ., e _n J MSE: ut h Esl O ~ M ~ M ,gd Fcxboro x ~
N M 3 E
- MATERIAI.S 1IST vit -79'010(c) Ar,1rla
.m - M M -m --M-g i4a M
/ PAGE 4 0F 6 .~
EQUIPPEM: E 10 Series Transmitter (E11Gil) _
/
POTENTIAL FOR RADIATION !! '
'~ '
~ '
SIGNIFICANT .. ALSD. SUSCEPTIBILITY
' COMP 0tlEllT . ' GENERIC _ KNOWN AGItiG(TilERilAL)
RADS DESCRIPTI0tV - PART NUMBER 1 "HATERIAL _ AS' _ 10 YRS 40iYRS GAMMA BASIS 12 Base i.E . ' sul41CP, Cast Iron -
>lx10 Detectable .[
(Ref6 5). 7 Change . 0-Ring h0143XN . Viton. - " flouro Carbon *
. 5x10 Detectable
=' .
Change
'c ~
7 . f, Elastomer (1) , (Refy) 3 6x10 u . -
.-- 25% Change '
(Rep._3) In Elong. , , Force Motor Ass'y N0150EC Magnetic Coil Formvar(assumed) 9.?x10It 25% Change EllGil, El Bobbin Assembly InsulatedWig (Ref; 5) in elong. Steel.
- 12 5-40 x 5/32 Pan 11. X100ZB >1x10 Detectable Screws Changa (Ref. 5)
Steel
- Cover Plate Moldin! N0143LZ > 1 x1012(Ref5) table Column fl0141tJP Phenolic
- 7 1x10 R gtg$e 25% C ange (Ref. 5) in elong.
Steel
- Terminal Block Ass) N09998R Ix1012(Ref 5) Detectable thnge Steel
- Bracket N0141EM -lx1012(Ref 5) Detectable Change 5-40 x 1/4 Socket .
- 11. Cap Screws X116ET Steel
- lx10 I2 Detectable Detector Ass'y N0999EY Steel (Ref. 5) Chan<ie
' 7 Armature Ass'y N0999FA Magnetic Coll Fonnvar(assum d)
- 9.7x10 R 25% Change Plate N0143PC Steel
- I2 lx10 R b"etYcS"1Me (Ref. 5) Change 3-56 ilut X104EF Steel * >lx1012R Detectable (Ref. 5) Change 3-48 x 1/8 Socket N0141ER Steel * ,lx10I2R' Detectable II. Cap Screws (Ref. 5) Change 12 Levcl Assembly N0141 Ell Steel
- lx10 R Detectable (Ref. 5) Change (1) Appendix A ,
(2) Appendix B , Page 31 of 76 1 -
~
USE:
~
InputtoESgSxboro
~
l MATERIALS LIST FOR 79-OlB(c) AGING PAGE 5 0F _g _ EQUIPMENT: E 10 Series Transmitter (E11Gil) POTEtJTIAL FOR RADIATI0tl SIGNIFICANT SUSCEPTIBILITY ALSO KNOWN AGING (THE W RADS GENERIC COMP 0tlEllT BASIS PART NUMBER HATERIAL AS' 10 YRS 40 YRS GAMMA DESCRIPTION 12
* >1x10 R Detectable Screws U104PP Steel (Ref. 5) Change Steel
* >lx1012R Detectable Flexure Assembly N0141TE (Ref. 5) Change 12
* >l x10 R Detectable Bracket fl0141FK. Steel thange (Ref. 5)
Steel
* >lx1012R Detectable Block (fl0lSOMA) N0141FF (Ref. 5) Change Steel
* >1x1012R Detectable Block (fl0150EC) P0120TX (Ref. 5) Change I2 Detectable Steel
* >l x10 R Bracket fl0141FM (Ref. 5) Change Steel
* >1x1012R Detectable Screws N0141PZ (Ref. 5) Change Steel
* >1x1012R Detectable flexure N0141KT (Ref. 5) Change Steel
* >lx10l2R Detectable Plate N0141MZ (Ref. 5) Change 12 Detectable Steel
* >1 x10 R Washer 39833 (Ref. 5) Change 12 Steel
>1x10 R Detectable Screw - fl0141ET (Ref. 5) Change
- 8 Dow Corning DC 710 Silicone 011(1) 5.0x10 R Viscosity Lubricant X0ll8CC - Change I2 Detectable Steel
* >l x10 R :
Lever fl0141CB Change (Ref. 5) (1) Used to assemble unit 00 @ @ ____ . _ _ _ _
i .
' ~ -
Ta U E: Inpd o ES MATERIALS tIST FOR 79-Olll(c) Ar,1Nr. ox o PAGE 6 0F 6 EQUIPMENT: F 10 Series Transmitter (E11Gli) POTENTIAL FOR RADIATION SIGNIFICANT SUSCEPTIBILITY ALSO AGING (TilERMAL) RADS COMP 0NEtiT GENERIC ~KN0.WN PART NUMBER HATERIAL AS 10 YRS 40 YRS GAMMA BASIS DESCRIPTION I2 Detectable 5-40 x 1/4 Pan 11. X100SY Steel
* > 1x10 R (Ref. 5) Change Screws Clamp Spring N0141FX Steel * > lx1012R Detectable
- (Ref. 5) Change
- 12 Bushing N0141FA Steel >1x10 R Detectable (Ref. 5) Change Coil Assembly N0141MN Steel
* >1x1012R Detectable (Ref. 5) Change Zero Screw Assembly N0141CR Steel
- 1x10I2R Detectable (Ref. 5) Change
* >lx10 R I2 Detectable Spring Assembly N0141CZ Steel (Ref,5) Change Tubing 21942 Steel
- lx1012R Detectable (Ref. 5) Change 12 Plate N0141TK Steel
- lx10 R Detectable (Ref. 5) Change 12 Clamp N0143WM Steel
- lx10 R Detectable (Ref. 5) Gange llarness (cable) N01480R 7
Insulator N0141LR Nylon polynmide (1)
- 4x10 R 2.5% Change ef. 5) in compress.
4-40 x 3/16 Pan 11. X116BK
- Screw Clamp N0143LE Steel
* >l x1012R Detectable 5
Column N0141LF Steel , ,x0 Re 12 ) e able (Ref. 5) Change (1) Appendix A . Page 35 of 76 _
W
- 4. BAILEY "BY" C0fEERCIAL/ NUCLEAR TRANSMITTER EVALUATION The Bailey differential pressure transmitter is made up of piece part i
electronics, such as, transformers, resistors, capacitors, diodes and transistors mounted on printed circuit boards inside a sealed housing. The i' 4, housing is sealed using ar) SBR rubber gasket and a feed-through connector. To ensure sealing integrity the SBR gasket should be replaced each time the transmitter is opened for service / calibration. This recommendation is not due to observed degradation but as a prudent conservative measure. To make sure the electronics housing is sealed from the environment, test connections are supplied with the transmitter to enable the owner to test the housing for leaks. The "BY" transmitter materials of construction (Table 4) lists the piece parts by vendor part number and the radiation susceptibility of the materials. The most radiation. sensitive material in the transmitter is teflon. Teflon is used in two forms, wire insulation and as the sealing material in the feed-through connector. Evaluating the radiation resistance of teflon used as: wire insula' tion and using a 25% change in elongation as a critical property for insulation, the 25% level will be reached at .003 x 107R (Ref. 5). Acceptability of the transmitter with teflon used as wire insulation seals is plant specific depending on exact device location, ambient radiation levels and the required period of operability. l
- Using the DOR Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactor, Appendix B, the sample calculation 5
produces a integrated dose of 3 x 10 Rad. Each owner should determine the n integrated dose for the specific service application. The transmitters, as specified by B&W, was required to remain functional for an integrated dose of 2 x 10 Roentgen. O Page 36 of 76
During the qualification program the transmitter was type tested to 7 8.5 x 105 Rad and was irradiated to failure of 4.8 x 10 Rad. The ultimate i failure was caused by shorting of the teflon insulated wire. The electronics are the most sensitive parts of the transmitter to thermal aging. Using the Arrhenius efuation from reference 7, page 3, equation 6 to evaluate the change in useful life when the environment is changed from 25 C to 45 C. Its life was reduced to an estimated 6.7 years.
- From reference 7 " Aging of 1 & C: A practical generic solution to a j preplexing problem" the equation form used is:
A = exp h ( h - ) A - Acceleration Factor TS = Service Temperature I TA = Aging Temperature l Ea = Activation Energy l dp l KB = Boltzmann's Constant (8.617 x 10-5 eyjog) Assume Ea is qual to .7 ev l A = exp h x 10-5 ( h ~- h ) A = 5.97
= 0 "5 r 6.69 years at 45 0C .
5 7
't.
8 X X Page 37 of 76 (f . M
M h - M M ... M En ' L16 h M -M M-M-M~M- M M USE: Flow Input RPS T e4 MATFRI At S I IST F0ft 79-Oln(c ) AGirlG - EQUIPMEHT: Bailey "BY" Coarmercial/ Nuclear Transmitter (BY3X41X-A) PAGE. j, _ 0F ,1_4,,,
. POTENIIAL FOR RADIATION ALSO SIGillflCAilT - SUSCEPIIBILITY C0f4PONENT GENERIC KNOWN ACINCIlHE E LI gads DESCRIPTION PART NUMBER MATERIAL AS 10 YRS 40 YRS GA41A BASIS Label 1962411-2 Aluminum * >1x1012R Detectable (Ref. 5) Change 7
Resistor 194841 Carbon Comp. * >1x10 R Detectable (Ref. 5) Change 5 Diode, IN4383 1942333-1 Silicon * >lx10 R De tec table (Ref. 5) Change - Name Plate 1962399-1 Aluminum * .>lx1012R Detectable (Ref. 5) Change Nut 197443-6 Steel ASTM A194 * >1x10I2R Detectable
. (Ref. 5) Change
>1x1012R
~
Lockwasher 197444-1 Steel ASTM A194
- Detectable GR.2il (Ref. 5) Change 12 Nut 197463-2 Stainless Steel .
* >1x10 R Detectable (Ref. 5) Change "0" Ring 5311428-26 Buna N Polymer Nitrile * .4x10 7R 25% Change NBR (1) (Ref. 5) In Compress 12 Seal Bushing 6619679-1 Stainless Steel ASTM * >1x10 R Detectable A182 GR-F316 (Ref. 5) Change
- 6 Backup Ring 6620555-1 Teflon (1) .03x10 R 25% Change
. . (Ref. 5) In Elong.
7 Pull Plug 1945750-1 Polyethylene lieat t 9x10 R 25% Change Resistant (1) (Ref. 5) In Elong. l Travel Stop 6620811-1 Stainless Steel 302 * >lx10I2R Detectable l (Ref. 5) Change Trust Bearing 6621395-1 Torrington Cat. # * >1x1012R Detectable TRA-1018 (Ref. 5) Change Appendix A Page 38 of 76 __ _ _ _ _ _ _ . ,
~ ~
~
USE: Flow Input RPS MATfRIAIS IIST FOR 79-0IP,(c) AGING PAGE 2 or 14 EQUIPMENT: Bailey "BY" Comercial/ Nuclear Transmitter (BY3X41X-A) POTfliTIAL FOR RADIATION SIGilIFICANT SUSCEPTIBILITY ALSO AGING (THERMAL)- GENERIC KNOWN RADS COMPONENT PART NUMBER HATERIAL AS 10 YRS 40 YRS GAMMA BASIS DESCRIPTION 12 6621396-1 Torrington Cat. # * >1x10 R Detectable Trust Race Change TRA-1018 (Ref. 5) 7 "0" Ring 1951414-008 Viton Fluoro Carbon * >1x10 R Detectable Elastomer (1) (Ref. 5) Change 7 Viton Fluoro Carbon * >1x10 R Detectable ! "0" Ring 1951359-3 Change Elastomer (1) (Ref. 5) - 7 "0" Ring 1951359-4 Viton Fluoro Carbon
- Plx10 R Detectable Elastomer (1) (Ref. 5) Change 7
Viton n Fluoro Carbon * >1x10 R Detectable "0" Ring 1951414-226 Change Elastomer (i) (Ref. 5) Seal 6619678-3 Viton B80V Flucio Carbon * >lx10 7R Detectable Elastomer (1) (Ref. 5) Change 7 l 6619678-4 Viton B80V Fluoro Carbon * >1x10 R Detectable Seal Elastomer (1) (Ref. 5) Change . 12 Coil Retaining 6619965-1 Stainless Steel * >1x10 R Detectable ASTM A313 (Ref. 5) Change Spring Pipe Plug 195148-3 Stainless Steel 416 * >lx1012R Detectable (Ref. 5) Change Stud 6619967-1 Steel ASTH A354 GR.BD
>lx1012R Detectable (Ref. 5) Change 12 Wavy Washer 6619971-1 Stainless Steel 316 * >1x10 R Detectable Spring Temper (Ref. 5) Change
>1x10I2R Seal Bushing 6619973-1 Stainless Steel 316
- Detectable
. 5 Change
* (Refl2
>lx10 R) Detectable l Coil Stud 6619975-1 Stainless Steel 303 (Ref. 5) Change (1) Appendix A -
t Page 39 of 76 ,
E( E -E E S Table 4 USE: Flow Input RPS MATfRIALS I IST FOR 79-010(c) AGlilG EQUIPMEtlT: Bailey "BY" Conunercial/ Nuclear Transmitter (BY3X41x-A) PAGE 3 _ OF 14 POTENTIAL FOR RADIATION ALSO. SIGNIFICANT SUSCEPTIBILITY COMP 0NENT GENERIC KNOWN AGING (TilERMAL) RADS DESCRIPTION PART NUMBER MATERIAL AS 10 YRS 40 YRS GAMMA BASIS Coil Retaining 6619976-1' il Steel Plate' * >1x1012R Detectable Plate . (Ref. 5) Change Coil Adj. Screw 6619977-1 #20 CR Steel * >1x10I2R Detectable (Ref. 5) Change Spacer 6620262-1 Phenolic Tubing
- 1.0x10 7R 25% Change In Elong.
Seal Ring 6619972-2 Viton V1418 (1) * - 7
>1x10 R Detectable (Ref. 5) Change I!ousing Gasket 6625485-1 Rubber Garlock Packing
- 6 SBR (1) >lx10 R Detet. table
'. (Ref. 5) Change Cover Gasket 6625495-1 Rubber Garlock Packing SBR (1) *
>lx10 6R Detectable (Ref. 5) Change Was'her 197466-3 Dyna Seal Cat. #110-1/4
- 6
>1x10 R Detectable (Neoprene) (1) (Ref. 5) Change Bolt 5/16-18x1.25 llex. Soc.110. CD - * >lx10I2R Detectable Plate Steel (Ref. 5) Change Bolt 1/4-20x1.50 llex. Soc.llD. CD * >1x1012R Detectable Plate Steel (Ref. 5) Change Washer Type A #12 CD Plate Steel- 12
>1x10 R Detectable
, (Ref. 5) Change SEMS Extension .190-32x.438 Pan 110. Stainless Steel
- 12
>1x10 R Detectable (Ref. 5) Change llex. Soc. .190-32x.500 CD Plate Steel * >1x1012R Detectable (Ref. 5) Change SEMS Extension .190-32x.250 Stainless Steel *
>1x1012R Detectable (Ref. 5) Change (1) Appendix A Page 40 of 76
h h Aand DEL &mde ems Emi. 8an, 6 8mL has, h h W. M- W tsaa I"E" ' MATfRIAtS tIST FOR 79-01Bfc) AGirlG EQUIPMEtiT: Bailey "BY" Consnercial/ Nuclear Transmitter (BY3X41X-A) PAGE 4 0F 14 POTENTIAL FOR RADIATI0tl ALSO SIGNIFICANT SUSCEPTIBILITY COMPONEflT GENERIC KNOWN AGING (TilEltMAL) ' RADS DESCRIPTION PART NUMBER MATERIAL AS~ 10 YRS 40 YRS GAMMA BASIS FRMG Screw .187x2 Stainless Steel * >1x1012R Detectable (Ref. 5) Change Washer .312 Type A CD Plate Steel *
>lx1012R Detectable (Ref. 5) Change Priiner 16653-10 Loc Quic Primer (1) Cyano Acrylate
- N/A Activator 16653-3 Loctite 271 (1) Cyano Acrylate
- N/A - '
Sealant 16653-8 Loctite PS/T (1) Cyano Acrylate
- N/A Lubricant 16673-7 Parker 0-Lube (1) Silicone Oil
- 5.8x10 8R Viscosity
~
(Ref. 5) Change Silicone Rubber 16686-1 6 TRV-162 (GE) (2) - 4x10 R 25% Change (Ref. 5) In Compress. Silicone Grease 16652-4 Silicone Grease Dow #4(1) 8 5.8x10 R Viscosity (Ref. 5) Change Cement 16566-21 Tite Seal Gasket & Joint N/A Compound (1) Lubricant 16256-4 Anti-Seize Compound (1)
- 3x10 R 0
rio Detectabl e Change Subassembly 6620519 (Bellows Ass'y) 6620516-2 AM 350/INC 718 * >lx10I2R Detectable Upper Bellows ' Change (Refl25 ) 6620516-3 AM 350/IllC 718 *
-lx10 R letectable Change Bellows 6620610-1 AM 350/INC 718
- lxlC R letectable (Ref. 5) :hange Bellows 6620518-1 AM 350/INC 718
- lx10 R 12 Jetectable (Ref. 5) :hange (1) Appendix A (2) Used to assemble unit Page. 41 of 76
is re m-IIC EE E E E E GL E n -E M "E M-EOR R USE: Flow Input RPS MTfM S I IST FO 79 0h-) Ar,1NG EQUIPMEllT: Bailey "BY" Comercial/ Nuclear Transmitter (BY3X41X-A) PAGE _ 5 0F 14 _ POIENIIAL f0R RADIAT10tl ALSO SIGNIFICANT SUSCEPTIBILITY C0!!PONEtlT GENERIC KNOWN AGING (TNER M ) RADS DESCRIPTION PART NUMBER HATERIAL AS' 10 YRS 40 VRS GAmlA BASIS
- Lower Bellows End 6620517-1 AM 350/INC 718 * >lx1012R Detectable (Ref 5) Change Subassembly 6619838 (Regulator & OSC.
Ass'y) 6 ! Leadwire Teflon Insulated Copper * .03x10 R 25% Change , (Ref. 5) In Elong.
>1x1012R Nut 4-40 CD. PL. Steel
- Detectable (Ref. 5) Change 12 Screw 4-40x3/4 CD. PL. Steel *
* >1x10 R petectable (Ref. 5) Change
- 12 Screw 4-40x1/4 CD. PL. Steel >1x10 R Detectable (Ref. 5) Change 7
Resistor 194841-88 Carbon Comp. * >1x10 R Detectable (Ref. 5) Change 7 Capacitor 1943404-19 Mylar *
- 1x10 R De tec table (Ref. 5) Change 12 Spacer 69118-4' Aluminum
- 1x10 R Detectable (Ref. 5) Change 9
PC Board 66)9837-1 Nema GR-10 Epoxy Glass * -
>1x10 R Detectable (Ref. 2) Change Resistor 1942051-12,90, Metal Film * >lx10lIR Detectable 38,9,144,96,137, (Ref. 5) .
Change 174 6 Zener Diode 1944329-223 Silicon IN9698 * >1x10 R Detectable (Ref. 5) Change Page. 42 of 76
mans mass. m m W m m w. j ,4 w. a. hana, asuna. asas, hmme. anno amen.
' '"E" '
~
HATfRIAIS IIST Fbn 79-ninic) AGIrlG . EQtilPilCilT: Bailey "BY" Conmercial/ Nuclear Transmitter (BY3X41X-A) PAGE 6 0F 14 POTENTIAL FOR RADIAT10ft ALSG SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TilEie:AL) RADS DESCRIPTION PART NUMBER HATERIAL AS. 10 YRS 40 YRS GAtttA BASIS
- 6 Zener Diode 1944329-113 Silicon IN9628 >1x10 R Detectable (Ref. 5) Change
- 7 Capacttor 1943404-4 Mylar >1x10 R Detectable (Ref. 5) thange 6
Zener Diode 1944329-562 Silicon IN7S2A * >1x10 R Detectable (Ref. 5) thenge ,
- 6 Diode 1942333-1 Silicon IN3193 *
>1x10 8 Detectabl~e (Ref. 5) thange
- 0 Transistor 1944285-1 Silicon IN3019 -
>1x10 R Detectable
. (Ref. 5) thange Spool Term. 6611793-2 Brass -
* >lx1012R Detectable (Ref. 5) Change
- 7 Tran. Coil 6619919-1 Hag. Wire .
9.7x10 R 25% Change (Ref. 5) In Elong. Resistor 194841-64,73
- 7 Carbon Comp. , >1x10 H Detectable (Ref. 5) Chage Filter Choke Hag. Wire 7 1944526-l .
- 9.7x10 R 25% Change (Ref5 5) In Elong.
Transistor 1942781-1 2N2270 * >1x10 ft Detectable 5 Change Iransipad 1942778-1 White Nylon * (Ref.7
.4x10 R
) 25% Change (Ref. 5) In hupact Strength Clamp
- 9 6619918-1 Phenolic Laminate >lx10 R Detectable (Ref. 5) Change Cushion Pad 6619918-1 #401 Pressure Sensitive * >i2x10 7R 25% Chan9e Tape (Ref. 5) In Elong.
P499 43 of 76
-U Table 4
$- hhh j USE: Flow Input RPS MATFRIAtS IIST FOR 79-010fc) AGirlG 0F 14
~
EQUIPMErlT: Bailey "BY" Commercial / Nuclear Transmitter (BY3X41X-A) PAGE 7 POTENTIAL FOR RADIAT10ft ALSG SIGfilFICANT SUSCEPTIBILITY ! COMP 0flEllT GENERIC KNOWN AGINOOU # l) ' RADS DESCRIPT10ft PART NUMBER MATERIAL AS 10 YRS 40 YRS GAMMA BASIS i i Subassembly 6621370 (temp. comp. ass'y) Leadwire Teflon insulated Copper *
.03xlG 6R 25% Change (Ref. 5) In Elong.
Di' ode 1943925-1 6 Gennanium IN270 *
>1x10 R Detectable '
(Ref. 5) Change < Resistor 1942051-91, 121 Metal Film *
>lx10lIR Oetectable 35 (Ref. 5) Change PC Board 6621369-1
- 9 Nema GR 10 Glass Epoxy 1x10 R Detectable (Ref. 2) Change Subassembly 6625480 (AtlP. Ass'y)
Chassis 6619916-1 #2 Sheet Steel * * >lx10I2R Detectable (Ref. 5) Change 6 Term. Blk 1942813-5 Molded Phenolic and NI *
>5x10 R Detectable Plt. Brass (Ref. 5) Change fuse Post 6 1941504-1 flolded Phenolic *
>5x10 R lietectable (Ref. 5) Change Fuse 1941504-1 Glass / Metal Comp. N/A 9
Potentiometer 1944919-5500 Wire Wound . >1x10 R Detectable (Ref. 5) Change Term. Blk 6 1944464-8 Molded Phenolic with HI
- 5x10 R Betectable Plt. Brass (Ref. 5) Change 7
Shaf t Lock 1942329-3 flylon Shaf t with Brass
- 0.4x10 R 25% Change Insert (Ref. 5) In impact itrength Page 44 of 76 i
I ,N U U E k M hML ES, h ama. m sama. A m w -
*4 USE: NowInputRPS g g,g mnM Am PAGE 8 OF 14 EQUIPMEllT: Bailey "BY" Conunercial/ Nuclear Transmitter (BY3X41X-A)
POTENTIAL FOR RADIATION SIGNIFICANT SUSCEPTIBILITY ALSO AGING (TilERMAL) RADS GENERIC KNOWN COMPONENT 40 YRS GAMMA BASIS PART NUMBER MATERIAL AS 10 YRS DESCRIPTION 7
* >lx10 R Detectable Trini Pot. 1942530-1,3 Cennet Change (Ref. 5)
- 1x1012R Detectable Filter Board 6622458-1 #2 Sheet Steel Change (Ref. 5)
Bracket 5 Detectable
* >lx10 R Transistor 1944357-1 2N3054 Change (Ref. 5) ,
Aluminum (5052-H32)
* >lx1012R Detectable lleat Sink 6619913-1 (Ref. 5) Change 12 Detectable lx10 R Spacer 6621385-1 Steel Change
. (Ref. 5)
>lx1012R Detectable Jumper 6621384-1 Sheet Brass Change (Ref. 5) 6
- * >lx10 R Detectable Gromnet 67125-12 Rubber Change (Ref. 5) 12 Detectable
* >1x10 R Screw .138-32x.62 CD PL Steel
- Change (Ref. 5) 12 Detectable
* >1x10 R Screw .138-32x.38 CD PL Steel Change (Ref. 5)
* >1x10 R I2 Detectable Screw .086-56x.75 CD PL Steel '
Change
~
(Ref. 5) CD PL Steel
* >1x10129 Detcctable Screw .ll2-40x.25 (Ref. 5) Change 12 Detectable CD PL Steel
* >1x10 R Screw .ll2-40x.78 (Ref. 5) Change
>1x10I2R Detectable Screw .ll2-40x.44 CD PL Steel Change (Ref. 5)
I Page 45 of 76
W .Ys Yo N5YYY > Y.55SS S S U USE: tlow Input RPS g pp, EQUIPMEllT: Bailey "DY" Coranercial/fluclear Transmitter (BY3X41X-A) PAGE 9 0F 14 POTEtiTIAL FOR RA01AT10fl ALSO SIGNIFICANT SUSCEPTIBILITY
, COMP 0tlEtlT GENERIC Kt1014ti AGIflG(TilERMAL) .
' RAOS OESCRIPTI0tl PART tlUMBER MATERIAL AS. 10 YRS 40 YRS GAMMA GASIS tlu t .112-40 CO PL Steel * >1x1012R Detectable (Ref. 5) Change Wa her .112-40 CO PL Steel *
>lx1012R Detectable (Ref. 5) Change Subasseinbly 6621383
- (Comp. Dd Ass'y) -
Tenninal 1941665-1 Brass . >1x10 R12 Detectable (Ref. 5) Change P.C. Board 6621382-1 Nema GR 10 Epoxy *
>1x109R Detectable Laminate .
(Ref. 2) Change Subassembly 6620609 (Tenn. Bd Ass'y) Bracket 6620607-1 Sheet Steel * *
>lx10I2R Detectable (Ref. 5) Change
. Terminal 66859401 Silver Plt. Brass *
>1x1012R Detectable j
(Ref. 5) Change j Tenninal Board 6620608-1 Epoxy Laminate
- 9
>lx10 R Detectable (Ref. 5) Change l Rivet R3800X5/32 Brass *
>1x1012R Detectable (Ref. 5) Change Subass'y B/M 663208(AMP. Housing ,
Ampli fier Cover, LVOT Cover) LVOT Cover 6625482-1 Aluminum *
>1x10I2R Detectable (Ref. 5) Change 1
l Page 46 of 76 ,
N M N M M h M M g4 *L am ,M M E K E [] M M USE: Flow Input RPS MATERIALS l.IST FOR 79-OlB(c) Ar.IrlG EQUIPl1ENT: Bailey "BY" Connercial/ Nuclear Transmitter (BY3X41X-A) PAGE 10 0F 14 P0TENTIAL FOR RADIAT10tl ALSO SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TitEPJiAL) . RADS DESCRIPTION PART NUMBER MATERIAL AS '. 10 YRS 40 YRS GAmlA BASIS LVDT Cover 6622678-111 Aluminum * >lx10I2R Detectable
- (Ref. 5) Change 12 AMP. Ilousing 6625483-1 Aluminum * >1x10 R Detectable
.(Ref. 5) Change AMP. Ilousing 6622680-111 Aluminum *
>1x1012R Detectable (Ref. 5) Change 12
- AMP. llousing 6625484-1 Aluminum * >1x10 R Detectable (Ref. 5) Change AMP. Cover 6622679-211 Aluminum *
* >1x1012R Detectable (Ref. 5) Change 12 Name Pl' ate 1962400-1 Aluminum * >lx10 R Detectable (Ref. 5) Change i Subassembly 6619841 j (Amplifier Ass'y)
Spacer 6620548-l' Stainless Steel * >1x1012R Detectable (Ref. 5) Change Steel
- I2 Detectable Ring 1944602-15 >lx10 R (Ref. 5) Change 6
Spacer 6622151-1 Phenolic GR. LE * >5x10 R Detectable (Ref. 5) Change
>1x10I2R Sems Ext. CD Plt. Steel '* Detectable 4-40x3/16 j ,
, (Ref. 5) Change Subassembly 6619896 i (LVDT Coil Ass'y)
Coil llousing 6619893-1 Stainless Steel * >lx1012R Detectable (Ref. 5) Change
. Page 47 of 76
W wie. 3- e #. . .
~
Table 4 i USE: Flow Input RPS MATERIALS LIST FOR 79-018(c) AGING EQUIPt1EllT: Bailey "BY" Coninercial/ Nuclear Transmitter (BY3X41X-A) PAGE 11 0F 14 l ! POTENTIAL FOR RADIAT10tl Ai.50 SIGNIFICAllT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TiiE.T.L) RADS [ DESCRIPTION PART NUMBER MATERIAL AS :- 10 YRS 40 YRS GAMMA BASIS 9 Met Coil 6619895-1 Polythermaleze Hag. Wire *
>1x10 R Detectable I (Assumed) (Ref. 5) Change 12 i Cover 6619894-1 Stainless Steel * > 1 x10 R Detectable (Ref. 5) Change 7
Rubber Bushing 6629501-1 Neoprene .6x10 R 25% Change (Ref. 5) in Compress. 12 Terminal 1941342-1 Brass * >1x10 R Detectable (Ref. 5) Change insulation Tube R9023-0117 Fiber Glass >lx10I2R Detectable (Ref. 5) Change Cement 164101-1 Epoxy Resin N/A N/A Subassembly 6619968 ~ (Filter Ass'y) Filter Retainer 6619970-1 Stainless Steel #316
* >lx1012R Detectable (Ref. 5) Change 12 Filter 6619969-1 Inconel 600 * >1x10 R Detectable (Ref. 5) Change Subassembly 682389 (Vent Valve Ass'y)
Vent Valve Body 682387-1 Stainless Steel #316 *
, >1x1012R Detectable (Ref. 5) Change Vent Valve Stem 682388-1 Stainless Steel #316 - * >1x1012R Detectable Change Subassembly 6619978 (Core Rod Ass'y)
Nut 197463-2 Stainless Steel
- 1x1012R Detectable (Ref. 5) Change Page 48 pf 76
M M b. hadt W. ten.4 h, amant,
,4 emma . ham.a . ansa. had, hast. see. - amus . ause USE: Flow Input RPS . MATERIALS 1.IST FOR 79-OlBfc) AGING PAGE 12 OF 14 _
EQUIPMENT: Bailey "BY" Conmercial/ Nuclear Transmitter (BY3X41X-A) POTENTIAL FOR RADIATION ALSO SIGNIFICAllT SUSCEPTIBILITY AGING (TilERMAL) COMP 0NEllT GENERIC KNOWN RADS DESCRIPTION PART NUMBER MATERIAL AS: 10 YRS 40 YRS GAMMA BASIS 12 Core Rod 6619979 Inconel 600
- lx10 R Detectable (Ref. 5) Cliange Subassembly 6619963 .
(llousingCover) 7 0-Ring 1951359-1 Viton * >1x10 R Detectable (Ref.g) Change 6620555-2 Teflon * .03x10 R 25% Change Backup Ring (Ref. 5) In Elong. - 12 Valve Plug 6620810-1 Stainless Steel * >1x10 R Detectable (Ref. 5) Change Weld Plug 6620813-1 Stainless Steel * >1x10I2R Detectable (Ref. 5) Change flousing Cover 6619963-20 Steel
* >lx10I2R Detectable (Ref. 5) Change Subassembly 6622691 (Tube & ilousing Ass'y)
Bellows I2 llSG Ext. 6622688-1 Stainless Steel
- lx10 R Detectable 5 Change
* (Ref12 1x10 R) Detectable Tube & ilousing 661998402 Stainless Steel (Ref. 5) Change
- Ass'y . Subassembly'6622457 (Filter Bd. Ass'y) 12 Terminal .1941665-1 Brass
* >1x10 R- Detectable (Ref. 5) Cliange 9
Nema GR 10 Epoxy
* >1x10 R Detectable Filter Board 6622456-1 Change Laminate (Ref. 2)
Page 49 of 76
m = w w w w. w nm. I" 4 saa mm. med am, ans, mas, num nas W ans USE: F Input RPS ' MATfRIAI.S LIST FOR 79-010(c) AGirlG EQUIPflEllT: Bailey "RY" Commercial / Nuclear Transmitter (BY3X41X-A) PAGE 13 0F~ 14 _ POTENTIAL FOR RADIATI0ff ALSO SIGNIFICANT SUSCEPTIBILITY COMP 0NEttT GEllERIC AGING (TilERMAL) Kit 0Wti RADS DESCRIPTION PART NUMBER MATERIAL AS. 10 YRS 40 YRS GAMMA BASIS Subassembly 6625481 1 (PowerSupply) Diode 1942333-1 Silicon Rect. IN4383 *
>lx10 5R Detectable (Ref. 5) Change Capacitor 1944345-1,3,4 Electrolytic 5
- lx10 R Detectable (Ref. 5) Change .
Style Plate 1962398-2 Mylar N/A N/A Capacitor 1942574-2 Metal Mylar
- 7 12x10 R Detectable (Ref. 5) Change Circuit BD. 6619839-1 Nema 17A GR 10 Glass
- 9
>lx10 R Detectable Epoxy (Ref. 2) Change
! Terminal 666369-3 Bra's s 12 i
* >1x10 R Detectable (Ref. 5) , Change Ti.cminal 668594-3 Silver PL firass 12
- 1x10 R Detectable (Ref. 5) Change
! Eyelet 1942117-2 Gold PL Brass * >lx10I2R Detectable (Ref. 5) Change Coating 16776-2 Urethane
- 8
>5x10 R Flexibility (Ref. 2) Change Subassembly 6619915 '
l (MTG. Plate Ass'y) Spacer lx10I2R l 6610842-4,5 #20 CR Steel *
- Detectable (Ref. 5) Change MTG. Plate 6619914-1 Sheet Steel
- lx10I2R Detectable (Ref. 5) Change i
Page 50 of 76 E
USE: F1 Input RPS - MATFRIAt.SIISTFON'~7 0 B(c) AGirlG
~
EQUIPMErlT: Bailey "BY" ConrnerciaONuclear Transmitter (BY3X41X-A) PAGE 14 0F 14 POTENTIAL FOR RADIAT10tl ALSO SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TilERMAL) RADS DESCRIPTION PART NUMBER MATERIAL AS. 10 YRS 40 YRS GAMMA BASIS Subassembly 6619836 - (Demod & AMP. Ass'y) CRCT Bd. 6619835-1 Nema GR 10 Glass Epoxy
- lx10 9R Detectable (Ref. 2) Change Diode 1944329-153 Zener Silicon IN9658 *
>1x10 R 5
Detec table (Ref. 5) Change Resistor 194841-15,73 Carbon Comp. *
>lx10 R 7
Detectable (Ref. 5) Change Transistor 1344581-1 Silicon 2tl2510 >1x10 R 5 Detectable (Ref. 5) Change Resistor 1942188 Wire Wound *
>lx10 R 9
Detectable (Ref. 5) Change Transistor 1944285-1 Silicon 2N3019 *
>lx10 5R Detectable (Ref. 5) , Change Recti fier 1942333-1 Silicon IN4383 *
-1x10 R 5
Detectable (Ref. 5) Change Trans. Pad 1942778-1 Nylon *
.4x10 R 7
25% Change (Ref. 5) In Impact Leadwire Teflon Insulated Copper *
.03x10 R 6
25% Change (Ref. 5) In Elong. Page 51 of 76
_= 1 I g 5. MOTOROLA 56PH TRAi1SMITTER a The motorola pressure transmitter is made up of piece part electronics, j such as, resistors, capacitors diodes, transistors mounted on printed circuit boards with part of the electr'nics o assembly being encapsulated. (See Table 5.) These assemblies are mounted in an "0" ring sealed housing, continuous service at elevated temperature and humidity is dependent on maintaining the housing in a sealed condition. .These "0" rings should be changed at each calibration maintenance action. This recommendation is not made due to observed radiation / thermal degradation, but as a prudent conservative measure l to ensure sealing. The electronics are the most sensitive part of the transmitter to radiation with detectable change level of 1 x 10 5. The transmitters were qualified for a radiation environment by type testing to 2.2 x 106by the vendor. The transmitters as specified by B&W were required to remain functional to 2 x 10 4 Roentgen. Using the 00R Guidelines for evaluating environmental qualification of Class 1E electrical equipment in operating reactors, Appendix B and the sample calculation, the transmitters are acceptable. The example referenced above produces a integrated dose of 3 x 10 5Rad. Each owner should use the example to determine the one hour accident dose for the transmitters location. The electronics are the most sensitive part of the transmitter to thermal degradation. Using the Arrhenious equation from reference 7, page 3, equation 6 to evaluate the change in aging from 250C to 45 0C. Using an estimated activation y energy of .75 the change in useful life is reduced from 40 years to 5.9 years. 5, Page 52 of 76 1
/
c Using Reference (7) " Aging of I and C: A Practical Generic Solution to a Preplexing Problem" Page 3, Equation 6. Ea 1 1 A = exp KB ITX TS) A = Acceleration Factor ,
'\
TS = Service Temperature TA = Aging Temperature Ea = Activation Energy KB = Boltzmann's Constant (9.617 x 10-5 eyjog ) Assume Ea is equal to .75 ev
$ .75 4 A = exp B3T7 x 10-5 (3TE 1 1 H6)
A = 6.79 Acceleration Factor Service at 450C = 5.9 years s
~
t 1 1 l l . I Page 53 of 76 P
l' tile "
/a .
USE: Id RI'5 MAlfRIAl.5 t.lST F0 -010(c ) Ar.Ittr. 1y - PAGE 1 0F 3 ', / EQUIPliENTY Motorola 56 PilTransmitter (56 PH1224-0301) POTENTIAL FOR RADIATI0fl sigil!FICAtlT SUSCEPTIBILITY ALSO AGIflG(TilERMAL) RMS COMP 0NENT GEllERIC Ki10WH DESCRIPTION PART t10MBER MATERIAL AS. 10 YRS 40 YRS GAtttA BASIS 12 Amplifier llousing 15D466811101 Aluminum
* >1x10 Rad Detectable 1/2 NPT Flug 46N45118C02 Steel
* >hibl2bd he'k'2able
[ 5 Change Steel
* (RefI2
>1x10 Ra )d Detectable t ac n hardware Ol-47738A01 5 Change Screw, pan head, Steel
* (Refl2
>1x10 Ra )d Detectable (Ref. 5) Change 6-32 x 1/2 03N45477808 12 Steel
* >1x10 Rad Detectable-Screw, slotted, Change 2-56 x 3/16 03N45477809 (Ref. 5)
>lx10I2Rad
- Detectable Bolt, hex, Change i
Steel (Ref. 5) 1/4-20 x 1/2 03N45115C06 12
* >lx10 Rad Detectable Washer, external Change lock 1/4 04S7678 Steel (Ref. 5) 7
.6x10 Rad 25% Compres: .
0-Ring, 3.8 inch set change diameter 32N47959A06 fleoprene (Ref. 5)
* >1x10 Rad I2 Detectable Cover, housing Change Steel (Ref. 5)
(blind) 01-47782A01 Amplifier, 24 Vdc OIC47799A01 Solid State Electronics R pgjgggable Mylar ;x10 Rai Detectable Capacitor 08CF7323F01 Change i Refl 5) Detectable Capacitor 21tl46937A03 Mica ' g10Raq
- 7 dd able Capacitor OuCF7323F25 Mylar Capacitor 08CF7323F03 Mylar gp d pgjgggable Capacitor 08tl46912A48 Metal, Mylar RC Jgtectable Capacitor 08CF7323Fll Mylar g t aale Detectable
- x10 7 ad Capacitor 08N46934A02 Polycarbonate .
Change LRef. 5) Page 54 of 76
U I to S la MATFRIAl.S l.IST FOR 79-01B(c) AGirlG PAGE 2 0F 3 EQUIPMENT: Motorola 56 Pil Transmitter (56 Pill 224-0301) POTENTIAL FOR RADIAT10ft ALSO SIGilIFICANT SUSCEPTIBILITY C0!1P0NEtiT GENERIC KNOWfl AGING (TilERMAL) ' RADS DESCRIPTION PART NUMBER MATERIAL AS' 10 YRS 40 YRS GAMMA BASIS 7 Capacitor 08CF7323F07 - Mylar
- lx10 Rad Detectable Diode, 50130,
- Ryf5jjp @fn0[able matched set 48AF7532F01 Silicon (Ref. 5) Change 6
Diode, zener, lx10 Rad Detectable 6.2V, S0119 48A46875G01 Silicon (Ref. 5) Change
- 6 Diode, zener, lx10 Rad Detectable ISV, IN52458 48N46938A94 Silicon (Ref 6 """U" Diode, IN914 48tl46967A08 Silicon h #f "
h$$$9e Diode, 50107 48A46125F01 Silicon hl$aggable 6 Diode, zener, 33V,
- 1x10 Rad Detectable lil973A 48N46938A77 Silicon (Ref. 5) Change
.. 6 gn fi Jack, Test 28tl46922A24 Phenol formald $ Rad Choke 24N45171C01 R
{gjgge abSe Transistor, MPS 1x10 Rad Detectable 6513 select 48AF7726801 Silicon (Ref 5) Change lx10 6Rad Detectable Transistor, MPS (Ref. 5) Change 6513 48tl46929A21 Silicon 7
- lx10 Rad Detectable Resistor 06S124C97 Carbon 5 Change
* (RefjjRa)d lx10 Detectable Resistor 06N47930857 Metal Film 5 Change Resistor 06N47930868 Metal Film * (RefllRad 1xjo ) Detectable Resistor Metal Film 5 Change 06N47930858 * '(Refjj lx10 Ra)d Detectable Resistor 06fl47930816 Metal Film (Ref9 5) Change Potentiometer,10
- 1x10 Rad Detectable turn 18BF7505F02 Llire Wound (Ref. 5) Change Page 55 of 76 l .
. , g
.gg . ~ .
.h -- m **a=
m m h M 'M M M O MATERIAtS l.IST 79-010fc) AGIflG EQUIPMEll9.Itotorola56 Tra nsmi t ter PAGE 3 0F 3 POTEllTIAL FOR RADIATION ALSO SIGNIFICANT SUSCEPTIBILITY COMP 0flENT GENERIC KNOWN AGING (TilERMAL). DESCRIPTI0tl PART NUMBER HATERIAL RADS AS' 10 YRS 40 YRS GNelA BASIS PotenLicmeter,10 .
- 9 turn 1x10 Rad Detectable 18BF7505F01 llire llound (Ref. 5) Change Resistor 06N47930818 Metal Film
- lx10lIRad Detectable (Ref. 5) Change Pressure llead ;
Part Nairie Primary Element Body 416 Stainless Steel *
>lx10l2Rad Detectable Brackets- Steel (Ref 5 Change l
>lxlC l2 Ra)d Detectable JRef Diaphragm 5 Change 17-7 Stainless Steel * >fx10l2Ra )d (Note 1) Detectable
. Fill Material Silicone Oil *
(Ref8 5) Change 2x10 Gelation (Ref. 5) f J j Page 56 of 76 e
() v 6. ROSEMOUNT RTD'S 177 lul's & 177 GY's The Rosemount RTD's are constructed of materials, primarily metal, glass and ce: amics, for use ah process temperatures up to 700U F and for environments up to 140 F. The materials that will degrade with temperature are located in the. connection head. The lead exit area to' the RTD has high temperature epoxy resin (Epoxylite 6203) which is used to hold the leads i to prevent vibration. The most sensitive material to thermal degradation was the connection head "0" ring. The material rating in Ref. 10 indicates the j material can be used for up to 10,000 hours at 132 0C. With the operating 0 & temperature of the head at 60 C no problem should exist for the gasket from k one calibration cycle (refueling) to another. ?. To ensure operation at elevated temperatures and humidity the head [ P
/T -
i V should be sealed from the environment. To ensure sealing the "0" 5 ring is & recommended to be changed each time calibration / maintenance is performed. f This recormiendation is not due to observed degradation due to radiation or j thermal but as a prudent conservative measure. I Table.6 lists the materials of construction and their radiation ' susceptability. The only materials that were found to have a threshold r 8 less than the type test level (3.8 x 10 R) was located in the connection head. This material has a listed property change at 5 x 106R.T.I.D. Using the - 00R Guidelines for Evaluating Environmental Qualif; ation of Class lE l } Electrical Equipment in Operating Reactors, Appendix B and the sample calculation, k> which indicates this material is acceptable, the integrated dose. is 3 x 10 , 5 ; Each owner should use the sample calculation to determine the expected dose L for their own equipment. '
^T (V (
1 4 Page 57 of 76 f, h
i *\
]
The principal degradation mechanism of the RTD is the change in etime response. This change is brought about not due to the change in material property but by a change in thermal coupling between the sensor element, though the sheath or well to the process being measured. og n F n it i ? h, t \ ,- , 5 e P
~
w
~ -
n s, . . a. e- - Page 58 of 76_,
,gy),
(-] ' EQUII'lttil s
} Ar, J rir, Mall RI At_u lM Fth-Jll1} f e Rssemount 177 ffW RTD 1. 2. 3 and 4 1 2 POTENTIAL FOR RAlll ATI0li ALSO SIGNIFICANT SUSCEPTIBILITY COMPONENT GENERIC KNOWN AGING (TNE N.L)
DESCRIPTION PART NUMBER RADS MATERIAL AS 10 YRS 40 YRS GAMMA BASIS Q-Felt C508-1 Felted Micro-quartz
- 9 lx10 (Ref.5) Detectable Varglas Tubing Change C8782-5 Fine Dralded Fiber-Glass * >lx10 12 Detectable Wire C10211-2,-5,-9 Nickel Clad Copper with (Ref. 5) Change 8-10 an Inorganic Fiber Insulation. * >lx10 12 Detectable Flexitallic Gasket C9996-1 304SST with Canadian (Ref. 5) Change Asbestos filler. * ' jp
> 1x10 Detectable' Never Seez C9999-1 (Ref. 5)
Change Meets MIL-A-907 manu- (1) factuper #NSBT-8N nuclear 8 Viscosity grade ' (NS-165)
- 5x10 Change Theminal Block 104-511-1 Porcelain
- 12
>1x10 Detectable Epoxy C561-1 #6203 Epoxy (made by (Ref. 5) Change Epoxyli te) 9 (2)
- 1x10 Detectable Silicon Grease C6713-1 Stiff, nonmelting silicon (Ref.5) Change
("0" Ring Lubricant) 0-Ring. C10984-70-153 Ethylene Propylene (2)
- 6
, 5x10 Elongation Reduce 48%
- 11eader 177-384-1 Stainless Steel Shell
- lx10 9 Detectable l with a Glass Seal .
(Ref. 5) Change PBX Solvent &
- Cement C94-1, -2 Inorganic Ceramic Cement * > lx10 12 Detectable llousing (Refl2 ) 5 Change 104-996 Aluminum Alloy 214 * . 1x10 Detectable (1) Nickel Based Luiricant (2) Appendix A Page 59 of 76
u.. sne.g-Su as MMI HIM 5 t ISI mu'hol i r ) F.In i 7 3 EQUIPitENT.(,asemount 177 HW RTD - 1. 2, 3 and 4 w PAGE _,2 0F 2 (y POTEliTIAL TOR RADIATI0il ALSO SIGilIFICANT SUSCEPTIBil.lTY COMP 0flEtlT GEllERIC KNOWil AGING ( M t W RADS DESCRIPTI0ft PART tlUMBER MATERIAL AS 10 YRS 40 YRS GAMMA BASIS Connection'ilead 104-996 Aluminum Alloy 214
- 12
> 1x10 Detectable (Ref. 5) Change acrew 104-55 Brass
- 12
>lx10 Detectable (Ref.j Change Washer 104-26-1 Brass *
> 1x10 [ Detectable (Ref.q Change Connector Plate 104-512 * >1x10) Detectable Screw (Ref. 5) Change .
C10329-2-1006
-1004 Brass
- 12
>1x10 Detectable (Ref.q Change Ident Tag 104-852-2 300 Series SST * >1x10[ Detectable 5 Change (Ref'83x10 R )
Sensor Ass'y 177-383 Reference Grade
- Resistance Platinum Change I -
l 1 Page 60 of 76 t -- _ _ n m. . m a---- m - m e- .. . . . m . _ _ _ _ _. _ m 6
. ~
Cs t s - I to Mrs ~ MAfrRf As s t IM l / (r) AGING EQUIPHE Rosemount 177GY RID ._ j g.c [ ,5 [ _f, POTENTIAL FOR RADIAT10tl e.
+
ALSO SIGilIFIChiiT . SUSCEPTIBILITY ff COMP 0tlENT AGitiG(T)lCRit4L)[ g 7-
~
GENERIC Kil0Wtl - DESCRIPTION PAi!I NUM8ER .. MATERIAL AS 10 YRS -90 YR$il GAMMA ' J ASIS Element Ass'y 177-382 ~
' '
- 8
>3x10 R Relis tance Change -
Coil 177-800-64 Platinmn' - i X-94 / Cement (PBX) Ceramic' ' Wire PT. X-60 Platinum
. . - ;7J Wire PT.
X-262 Platinum ' ~ I Solder X-174 High Temperature Solder .
"Q" Fel t X-508 Quartz Housin3 with Lead Mount 177-386 30455 *
>1x1012R Detectable (Ref. 5) Change lleader (Feed Thru) 177-384 304SS (Shell) *
>1x1012R Detectable (Ref. 5) Change Pins Glass Fill Adapter, Housing 177-380 304SS *
>1x10I2R l)etec table (Ref. 5) Change Filler X-4437 Silicone Rubber (1)
- 6 4x10 25% Change In Com-pression set Spring, Strain '
Relief 177-385 Spring Steel *
=1x1012R letectable (Ref. 5) :tange Leadwire X-7392-2,5,9,10 Platinum *
>lx1012R .)etectable (Ref. 5) :hange (1) Appendix A Page 61 of 76
_ __ . .. - .x - - - - I
ust: f~~~t tA ) to WS. MATERIALS I151 r 9 lit (c ) Ar,ine,
~'
EQUIPHL.Pri R semount 177GY RTD PAGE 2 Of a POTEtiTIAL FOR RADIAT10t1 ALSO SIGillFICAt(T SUSCEPTIBILITY C0tT0tlEtlT GEllERIC Kil0Wil AGliiG(TilERNAL) l DESCRIPTI0ti PART liUMBER RADS HATERIAL AS 10 YRS 40 YRS GAiVIA BASIS Leadwire (cont'd) . Insulation Tubing (shrink) X-2965 . Cross Link Polythylenq *
>1x10 R 8
Detectable (11 (Ref. 5) Change Solder X-532 liigh Temperature Solder *
>1x1012R Detec table (Ref. 5) Change Lugs titckel Plated Copper *
>1x1012R Detectable (Ref. 5) Change .
Coupling 104-170 304SS *
>1x10 R 12 Detectable (Ref. 5) Change liipple_
104-476-120 304SS *
>1x10I2R Detectable (Ref. 5) Change Connection llead "0" Ring 6 104-858 Ethylene Proplene (1)
- 5x10 Elongation (Ref. 5) Reduction 48%
Reducer Bushing 7960-13 304SS'T * >1x1012R De .a (Ref. 5) Chang; Terminal Block 105-511 Ceramic (Porclain) *
>lx1012R Detectable (Ref. 5) Change Connector Plate 104-512 flickel Plated Brass *
>1x1012R Detectable (Ref. 5) . Change Washer 104~-26 flickel Plated Brass * >1x1012R Detectable (Ref. 5) Change Screw (4-40) 104-56 titckel Plated Brass *
>1x1012R Detectable (Ref. 5) Change (1) Appendix A Page 62 of 76 I
u: .t. : tr~t to kP5 q
# MATERIAIs tist F' EQtilPl4Li.ORosemount 177GY RTO pagg 3 0F 3 POTEllTIAL FOR RADIAT10tl ALSO SIGilIFICAtiT SUSCEPTIBILITY C014P0llEflT GEllERIC Kil0Wtl AGIflG(Tilffd'AL )
DESCRIPT10fi PART tlUMBER MATERIAL RADS AS 10 YRS 40 YRS GAMMA BASIS Tenninal Block (cont ) Screw (6-32) 104-57 Nickel Plated Brass *
>1x10I2R Detectable (Ref. 5) Change Screw (8-32) 19 Nickel Plated Brass *
>1x1012R Detectable (Ref. 5) Change Mounting tiut 177-381 304SS'T
- 12
>1x10 R Detectable (Ref. 5) Change' Flexitalic Gasket C9996-1 304SST with Canadian
- 12
>1x10 R Detectable Asbestos Filler (Ref. 5) Change
't Page 63 of 76 1 . b
- 7. MERC0!D PRESSURE SWITCH The mercoid pressure switch is supplied in a waterproof configuration for servjce outside of the containment or in an area that will not be pressurized I by the accident. In containmegt radiation and environmental levels do not apply to this sensor; however, the sensor was evaluated for radiation sen'sitivity by examining the reported radiation susceptibility of the vari.ous materials of constructio1. The pressure switch as specified by B&W was to perform in a
. radiation environment of 25 mr for the life of the plant. This produces an integrated dose of less than 1 x 104 rad T.I.D. The only material evaluated 6
that was less than 1 x 10 rad T.I.D. was the Teflon used to coat the stainless steel diaphragm. This material is not essential for this service. Each owner should evaluate the radiation environment for the pressure switch for the specific location. The material of construction were reviewed for :hermal aging with the most a sensitive material being the terminal strip and the switch body of molded phenolic. This material has a rated continuous service temperature of 1400C using the Arrhenious model to predict aging at 45 0C and EPRI NP-1558 (Ref.10) report produces a change in life from 40 years to 3.45 years which is overly conservative. The switch and terminal strip should not age to 'the point of failure due to 0 operating in a 45 C environment. The fish paper used as tenninal strip separators
, and as wire clamp is not a functional part of the pressure switch for this application, degradation of the fish paper will not prevent the pressure switch from performing its design function.
The pressure switch is sealed from the environment with gaskets made of neophrene. These geskets should be changed each time there is cahibration or maintenance performed on the switch. This recommendation is made not due to any observed radiation /or thermal degradation but as a prudent conservative measure. Page 64 of 76 i
USE: I ng' )toRPS&ESFAS HATFHl.A1S $b F R DIR(c) AGING / EQUIPHCllI: Mercold Pressuro Switch (Typ2 APW-7041-lS3-Ringa 36) PAGE 1 Of 1 POTErlTIAL FOR RADIAT10tl ALSO SIGilIFICANT SUSCEPTIBILITY COMP 0tlENT GENERIC Kil0Wtl AGIflG(TilERMAL)
! RADS DESCRIPT10tl PART tlUMBER HATERIAL AS 10 YRS 40 YR$ GAMMA BASIS ,
Pressure Switch APW-7041-153 Range 36 Bottom Housing Aluminum (214) *
>1x1012R Detectable (Ref. 5) Change Top Cover
- Steel *
>1x1012R Detectable 3
(Ref. 5) Change
>lx10I2R Diaphragm 316 Stainless Steel
- Detectable -
(Ref. 5) Change Diaphragin Coating (Note 1) Teflon
- 3.7x10 5
25% Change j (Ref.13) In Elong. l Switch (Body) Phenolic
- 2.2x10'R 25% Change (Ref.14) in Elohg.
Spring Spring Steel
- 12
, >lx10 R Detectable j
(Ref. 5) Change
! Adjustment Steel
- 12
>lx10 R Detectable (Ref. 5) Change Gasket Neop rene
- 6x106R 257, Change (Ref.14) In Compress.
Terminal Board y Set
, Phenolic
- lx10 25% Change (Ref. 14) In Flexural Wire Insulation Silicone Rubber
- 6 bl"*"9th i -
4x10 R 25% Change (Ref.14) In Compress. Set Terminal Barrier Fish Paper (Note 1)
- 5x10 6
25% Change and Lead Clamp In Flexural Strength Note 1: Not essential for this service. Page 65 of 76 i , i
t .I IV.
SUMMARY
AND RECOMMENDATION l o 1. WESTINGHOUSE NI DETECTORS ; l The NI Detectors have a component maintenance and replacement schedule 4 which includes consideration for the aging characteristics of the detectors, moderators and the connectors. The connectors for all three ranges of detectors are to be refurbished after two fuel cycles. The moderator,s are to be changed
-h on the Startup and intermediate range detectors after 4 years of effective full
. power days. ~The startup range detectors should be changed after two fuel cycles. The intermediate and the power range detectors should be changed during the core refueling shutdown which is closest to six years'o'f effective full power days. At the present time no further action-is required for the neutron detectors. , ; .2. TRANSMITTERS - ROSEMOUNT (1152GP9), FOXBORO (E11GH), BAILEY '(BY), AND MOTOROLA (56Ph) , All of these transmitters contain electronic parts that must be protected when exposed to elevated temperature and humidity. In order to maintain this 1 protection, seals and gaskets ar.e recommended to be changed each time they are
, disturbed during calibration or maintenance.
- Evaluation of the materials of construction for thermal rating and radiation susceptability made use of ttables included as appendices to this evaluation.
The age / environmental temperature table is provided in Appendix C for the Customer to use to evaluate expected life. This study did not attempt to evaluate the life of a sensor located in a specific plant due to differences i . inreaciorbuildingtemperatures. The Owner should determine the themal aging factors that applies specifically for the sensor location. This determination
~
will provide a refurbishment / replacement schedule for the sensors based on plant specific conditions.
~O Page 66 of 76
~
* *-- v-e- ayr.ew+---*w-r%-- d ~ p s- t ' Mr 9- Wm-----erv- wr--+ c-m--***,ewy --*--w w wor r m =- ,e----,w= - -m-w'
. . _- . =_. - _. -- . . . --
i
- 3. ROSEMOUNT RTD'S O l The RTD's materials of construction from the connection head down to the sensor tip is made from classification 1 materials that is: metal, ceramic or glass and not subject to normal thennal degradation or radiation damage.
The major degradation mech'anism for fast response RTD's is the' change in thermal conductivity between the platium element and the. well due to thermal cycling. .The B&W NSS is designed to be a nearly constant temperature system
-so this degradation is not a major concern.
Time response of the RTD's should however, be verified as a routine part of a prudent maintenance program. The RTD connection head is supplied with a "0" ring seal which should be replaced each time the seal is disturbed due to calibration or maintenance.
- 4. MERCOID PRESSURE SWITCH .
l This pressure switch was supplied to be installed in a area not subject to pressurization from the accident condition to be monitored. The materials of f construction were reviewed using the tables supplied as Appendices A&B and other sources as identified in the references. g The pressure switch contains no materials that will be sensitive to the N specified environment of the auxiliary building. The switches should be evaluated for service life based on specific location and the service conditions. Appendix I C'was supplied to aid the owners in developing a service life rating for the i specific plant environment. - f 1 Page 67 of 76
. a p . -
1
REFERE!!CES USED DURING AGING DETERMINATION
- 1) Military Standardization Handbook (Mil-HDBM-217C) Reliability Prediction of Electronic Equipment, Septamber 20, 1974.
- 2) Radiation Effects Handbook S-146 IEEE, June,1963.
- 3) Space Materials Handbook NASA-SP-3051, July,1968.
- 4) Handbook of Components for Electronics, C.A. Harper,1977.
- 5) Fundamentals of Nuclear Hardening of Electronic Equipment, L.W. Ricketts,
, 1972.
- 6) Military Standardization Handbook (Mil-HDBK-149A) Rubber and Rubber-Like Materials, 1962.
- 7) Sailey Controls Technical Paper Titled - Regulatory Guide 1.89 Aging of I&C: A Practical Generic Solution to a Perplexing Problem ANS 1980 International Conference.
- 8) B&W #58-1017454-00, Verification of Maximum Radiation and Environmental Ratings for the W IGTD Ex-core Detectors.
- 9) LRC #LR:80:7342-01:01, Polyethylene Power Moderator Sleeves.
r 10) A Review of Equipment Aging Theory and Technology, EPRI NP-1558,. September, 1980. <
- 11) Verification of Maximum Radiation and Environment Ratings for the IGTD
.Ex-core Detector Types WL-23635, WL-23636, WL-23682 B&W Doc. ID No.
58-1017454-00. (
- 12) Military Standardization Handbook Rubber and Rubber-Like Materials -
(Mil-HDBK-149A) June,1965. ' i
- 13) Survey and Evaluation Report in Radiation Damage to Plastic Materials (
(DC-55-5-90)1962.- ,
- 14) Nuclear Engineering Handbook, Section 10-5 Page 10-141 Para. 3.5, McGraw Hill and Co. l I -
i l 1 I i
]
lLO Page 68 of 76 I
. )
i 0 L .
=
l APPENDIX A O DATA SHEET FOR MAXIMUM SERVICE TEMPERATURES OF PLASTICS AND RUBBER RangeOF RangeOF Materials High Low Materials High Low Molded Silicones >700 >600 ,8 Polyvinylidene Chloride Silicone Foams 650 500 \* Film TFE Film 290 --- 585 566 Polycarbonate Silicone Rubber 550
'275 250 Melamines, Fabrica-Plastics Laminates, Low Filled Pressure 250 --- . 500 250 Melamines, Shock Res. 250 ---
TFE Fluorocarbons 500 --- Nitrile Rubber Polyester Film 250 --- 490 --- Nylongs 6 & 11 Ciallyl Phthalate 250 200 450 300 Polyethylene Film Fluorinated Acrylic 250 200 Polysulfide Rubber 250 --- Rubber 450 --- Neoprene Rubber Phenolics, Shock & Hit 240 --- Urethane Rubber 240 --- Res. 450 250 Polyallomer 230 280
'diton Rubber 450 ---
Polyphenylene Oxide Cellulosic Films, 225 --- 400 140 Polyvinyl Chloride 220 140 Epoxies (cast) Ht Res. 400 --- Acetal Copolymer 220 ---
'FEP Fluorocarbons .400 ---
Vinylidene Chloride "elamines, Glass-Filled 212 170 e 400 300 Melamines, GP 210 --- Nylon, Glass-Filled 400 300 Bu-tadiene-Acrylonitrile Phenolics (molded), Foams l) 210 --- fhock 400 350 Rubber Hydrocloride M tics&Laminates, Heat Film j 205 --- ' f Elec. 400 160 Acrylics 200 Polyinide 140 400 --- Polystryrenes, Glass- i Jrethane Foamed-in- Filled 200 190 ' Place, Rigid 400 --- PVC-Nitrile Rubber Melamines, Cellulose or j Blend Film 200 --- - Miniral-Filled 395 205 Urethane Foams, CFE Fluorocarbons 380 j Flexible 200 ---
*flon
. 6 Film 380 ---
Modified Polystyrenes 190 120 Alkyds, High Str. 350 --- Acetal Homopolymer 185 --- 4 Phen 211cs (molded), GP 350 4 300 Polystyrene Foamed-in- - l Prefoamed Cellulose Place, Rigid 185 --- 8 Acetate, Rigid 350 200 Natural Rubber 180 --- Alkyds, GP 345 295 Neoprene Faoms 180 --- Polysulfone 340 --- Polystyrenes, GP 180 $ 140 Allyls (cast) 300 --- - Polyvinyl Chloride Film 180 150 Butyl Rubber 300 --- Styrene-Butadiene-11 allyl Phthalate, Rubber 180 --- f Orlon-Filled 500 300 Epoxies (cast), GP 175 --- Nylons 66 & 610 300 225 Phenoxy $ 175 --- ' Phenolic Foamed-in- - Prefoamed Polystyrene, i Place, Rigid 300 --- Rigid 175 155 j 3olypropylene Film 250 --- Polyvinyl Formal 165 130 ; Rubber Phenolics 300 212' Butadiene-Styrene
?lastics Laminates, GP 295 245 d
Foams, 160 --- i 295 245 Natural Rubber Foam 160 --- {J*] ester (cast, Rigid) SSUE DATE: PAGE69 0F 76 SERIAL: f Babcock & Wilcox
a . APPENDIX A DATA SHEET FDR MAXIMUM SERVICE TEMPERATURES OF PLASTICS AND RUBBER RangeOF Materials High Low Cellulose Nitrate 140 120 $ Polyvinyl Butyral 115 --- - 3 - 3 1 Range: From Vendor information supplied to Material Engineering 1971, Reinhold, Stanford, Conn. ISSUE DATE: PAGE 70 0F 76 SERIAL: Babcock & Wilcox +
_m APPENDIX B i' U DATA SHEET FOR Radiation Da= age to Electrical, Electronic, and Mechanical Systems l Dosa6e Levels To Radiation- Most Radiation- Give 25% Type Of Susceptible Actual Materials Susceptible No. System Change, Cemnonents A, Used Procertiesa 107 rsds 1 Disconnects Base insulation ' Paper-filled T.E,S I 2.2 phenolformald 2 Asbestos-filled T E,I. 100 phenolformaid 3 Gasket (pressure Buna-S E SAB,C,SAF type) 1.3 L e Natural rubber SAB 2.6 ' t 5 Fuse holders Base insulation Linen-filled E,I 0.3 phenolformaid 6 , Paper-filled E,I 0.8 ' phenolformaid 7 Light bulbs Glass envelope Glass [ Light 0.1 > b transmission 8 Magnetic Core damping Silicone oil [ Viscosity >50 amplifiers fluid g 9 Core insulation Nylon I 0.4 C 1,0 Intervinding Kraft paper' h
,, insulation " E.T.I
~ ~ ~ ~ ~ ~- ~'
0.5 ~ i ) Mylar ET 12 [(
.V Potting com- Silastic H
pound C 0.4 0 '. 3 Terminal board P, aper-filled E,I h 0.8 p, phenolformaid '4 Unfilled phenol- E - 1.0 ) formaid '5 Wire insulation Formvar :
.6 E 9.7 /
Teflon E 0.003 .7 Motors and Brush holders Linen-filled ; selsyns E,I 0.3 g phenolformaid iS 3 Paper-filled E,I - 0.8 phenolformaid h .9 Grease seal Neoprene 7 l0 C 0.6 P Buna-N SAB,C 0.4 Il h
- 2 Felt E.T.I 0.5 g Leather I 0.4 13 Insulating tapes Rubberized cloth R 14 E.T,I (cloth) 0.5 #
Polyvinyl chloride E 12 Natural rubber SAB,C g .6 2.6 v Teflon-coated E (Teflon) 0.003 [i fiber glass
- 7 E Fiber glass and P11 ability >50 .
silicone resin l,, a n b Q). R ISSUE DATE: PAGE 71 0F 76 SERI Al.: A Babcock & Wilcox If
l APPENDIX B C DATA SHEET FOR Radiation Damage to Electrical, Electronic, and' Mechanical Syste=s Dosage Radiation- Levels To Most Radiation- Give 25% Type Of Susceptible Actual Materials Susceptible 3,. System Change, Cc=tonents '\ Used Procertiesa 107 rsds 18
- Acetate cloth 29
, E,I 1.6 Buna-N-treated SA3,C (Buna- 0.4 fiber glass N) ,
30 End punchings Teflon-coated E(Teflon) 0.003 and slot insula- fiber glass tion 31 Shaft insulation, Fiber glass mel- TE 6.4 f etc. amine e 32 a Mylar E.T 12 33 Teflon E 0.003 e 35 Mica with shellac I 0.4
' 35 Mica with mylar E.T (Mylar) 12
- 36 Paper-filled E,I 0.8 phenolformaid 37 Asbestos-filled E,I 53 phenolformaid 38 Kel-F r
E,I 1.7 39 Fiber glass with C 0.4 , ,f^T silicone rubber ex _,/ Fish paper i E.T.I 0.5 41 '~ Varnished cambric l . E.T.I 0.5 Folisinyichlorfde l 42 ~E 12
- 43 Cellulose acetate E,I 1.6 44 Wire insulation Teflon E .
0.003 45 Forsvar E 9.7 46 Fiber glass and Pliability >50 silicone resin 47 Nylon E,I 0.4 48 Neoprene C 0.6 49 Paper E,T,I . 0.5 50 Relays and Base insulation Paper-filled E,I 0.8 switches and shell phenolformaid 51 Linen-filled E,I 0.3 phenolformald 52 Asbestos-filled T,E,I >100 phenolformaid
- 53 Unfilled phenol- E 1.0 formaid
$4 Thermo- Wire insulation See Motors (Wire couples Insulation)
- 55 Transformers Wire insulation See Motors (Wire -
Insulation) l 1 . , - ISSUE DATE: PAGE 720F 76 SERIAL: l ' Babcock & Wilcox
r APPENDIX B ( ') DATA SHEET FOR Radiation Damace to Electrical . Electranic. and 'fechanical Svstem Dosage Levels To Radiation- Most Radiation- Give 257. Type Of Susceptible Actual Materials Susceptible Change, N3 System Co=conents ! Used Procertiesa 107 rads 56 Oils . Chlorinated Viscosity >100 hydrocarbons 57 Dichlorobiphenyl Viscosity >100 58 Gaskets Buna-N rubber S AB , C- 0.4 59 Hycar-PA SAB 0.3 60 Base insulation Paper-filled E,I 0.8 phenolformaid 61 Paperboard E.T.I 0.5 Elcetronic 62 Capacitors' Dielectric Paper E.T.I 0.5 63 Paraffin E,I 9.0 64 Base insulation See Relays-(Base
. Insulation) 65 Coaxial cables Wire insulation Polystyrene T,E,EM,S I >500 66 Polythene E,I 9.0 67 Rayon E,I 1.6 68 Polyviny1 chloride E 12 69 Neoprene C 0.6 Connectors Base insulation Polystyrene T,E,EM,S,I >600 Polyetheylene E,I 9.0 e . Paper-filled E,I 0.8 phenolformaid 73 Asbestos-filled E,I 53 phenolformaid 74 Ion chamber Base insulator Unfilled phenol- E 1.0 formaid 75 Polystyrene T,E,EM,S.I 600
[ 76 Polyethylene E.I 9.0 77 Teflon E 0.003 l 78 Methyl meth- T,E 1.0 l i acrylate , 79 Printed Base insulation Urea formalde- T,E,S 3.0 s l circuits hyde ! 80- Melamine form- T,E 6.4 aldehyde l 81 Paper-filled E,I 0.8 phenolformaid - 82 Conductor binder Epoxy resin S 100 83 Resistors Base insulation Paper-filled E,I 0.8 ) phenolformaid j 84 Asbestos-filled T.E,I >100 phenolformaid
.h "
SUE DATE: PAGE 73 0F 76 SERIAL: Babcock & 7tilCOX l
APPENDIX B
') DATA SHEET FOR Radiation Da= age to Electrical, Electronic, and Mechanical Systems Dosage
Levels To Radiation- Most Radiation- Give 257, Type of Susceptible Actual Materials Susceptible Change, Ns System Comuonents .t Used Procertiesa 10I rads 85 P'aperboard . E, T, I 05 Y 86 Thermistors Wire
- See Electric M Insulation Motors (Wire) f 87 Transducers Wire See Electric
- Insulation Motors (Wire) 88 Da= ping Fluid Silicone Oil Viscosity >50 g 89 Vacuum tubes Tube bases Paper-filled E, I 0.8 Phenolic 90 Unfilled phenolic E 1.0 f Mechanical
( 91 Conbustion 0-rings Neoprene C 0.6 j Engines 1, 92 Shaft seals Leather 1 0.h 93 Fan Belts Cloth-backet E,T,I 05 neoprene 9h Lubricant SAE-20 Viscosity >100 95 Antifreeze Prestone Viscosity >0.02 96 Gaskets Cork E,T,I 05 7 Cork-impregnated E,T,I 0.5
' Cloth 98 Neoprene C 0.6 99 Thiokol C 0.1 100 Filter Cloth E,T,I 0.5 101 Paper E,T,I 05 102 Hoses Neoprene C 0.6 I 103 Cloth-backed E, T, I (cloth) 05 L
neoprene f10h Starter See Electric Generator Motors I
- 105 Fluid dis- 0-rings Buna-S E, SAB, C, SAF 1.3 connects l106 Gaskets Neoprene C 0.6 4 107 Thiokol C 0.1 g J08 Silicope Rubber C 0.h
;109 Gauges Diaphragm Neoprene C O.6 110 Leather I 0.h
'111 Hydraulic Hydraulic Di(2-ethylhexyl) Viscosity > 50 System Fluid sebacate
" 112 Seals, o-rings Nylon I 0.h J , 113 Neoprene C 0.6
, lik Buna-S E, SAB, C, SAF 1.3 m
)
SSUE DATE: PAGE74 0F 76 SERIAL: Babcock & Wilcox
'l 9
APPENDIX 3 DATA SHEET FOR Radiation Da= age to Electrical, Electronic, and Mechanical Syste=s Dosage Levels To Radiation- Most Radiation-
- Type Of Susceptible detualMaterials Susceptible ""E*j, 7 ,
No. Syste= Components Used Properties 115 Buna-N SAB, C 116 0.h Hoses Neoprene
- 117 C 0.6 Buna-S E , SAB , C , SAF 1.3 118 Buna-N 119 SAB 0.4 Cloth-backed E, T, I (cloth) 0.5 neoprene 120 Cylinder cups Leather 121 I 0.h Neoprene C 0.6 122 Couplings Leather 123 I 0.h Neoprene C 0.6 12h Pneu=atic (Similar'to Hydraulic System except Syste=s hydraulic fluid is replaced by air) 125 Pressure Diaphrag Neoprene Switches
- C 0.6
'q,126 Nylon 127 I 0.h-Leather I 0.h 1128 Pu=ps Packings, Neoprene C 0.6 shaft seals,
(] gaskets _[ 129 Natural rubber ( 130 SAB 2.6 Buna-N SAB, C 0.h 131 Thiokol C 0.1 132 Silicone Rubber 133 C 0.4 Teflon E 0.003 13h Cotton E,T,I 0.5 135 Rayon 136 E, I 1.6 Paper E,T,I O 13T Leather , 130 I 0.k Kel-F E, I 1.7 139 Butyl rubber 140 Valves C 0.h f Packing, See Pu=ps
~
Seats, , Gaskets "T = tensile strength, E = elongation, S= shear strength, I = i= pact strength, SAB = sst-at-break, C = cc=pression set, SAF = strain at h00 psi, EM = elastic =odulus. Decrease in foot-candle output. Jersrence: Fundamentals of Nuclear Hardening of Equipnent Ricketts , C. W. (Wiley, New York) V fr ISSUE DATE: I PAGE 750F 76 SERI Al.: BabC0Ck & WilCOX
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u - -l 1 i f ( SECTION 3 i SUPPORTING DOCUMENTATION , i i i O 9 l i e 9
- O SECTION 3.1 COULD INC. ELECTRIC MOTOR DIVISION,
- LETTER DATED OCTOBER 8, 1980 .
1 O t I 2 b ' O . Geert/Commanuseth m +aw~
* ~~~~~ Gould loc.. Electric Motoe oiri, son "l
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. October 8,1980 L K' T>4pN Mr. D. A. Rhoads .
Electrical Engineer . Gilbert Associates, Inc.
- P. O. Box 1498 Reading, PA 19603
Dear Mr. Rhoads:
This letter is in answer to your request concerning the environmental qualifications of our motor with part number 6-331645. ,
. We don't have any worthwhile information on the affects of radiation on our motor construction, but I have attached a list of materials used in this motor. I hope this will be helpful.
I'm sorry it has taken so long to respond. - Sincerely, . Gould Inc. Electric Motor Division I
~
fef . Ray okerst - Product Manager AC Motors RJ:am Attachment , cc: June Mitchell -- Philadelphia . O e
? - M GOULD 182T-FRAME CLASS F SEVERE' DUTY INSULATION SYSTEM i .
- 1. Slot insulation: t
, , DuPont "Nomex" aromatic polyamide pape r.
- 2. Coil Separators:
DuPont "Nomex" aromatic polyamide paper. I
- 3. Topsticks:
Dacron mat / Mylar / Dacron mat laminate (Dacron fibre and Mylar film are polyethylene terephthalate polyesters).
- 4. Magnet Wire:
Nylon overcoated polyester coated magnet wire / NEMA Class MW24C. S. Connection and Cross-over Insulation: Acrylic resin coated braided glass sleeving.
- 6. Tie Cord:
0 8 raided Decron coze. I 7. Phase Insulation:
. Modified polyester varnish coated glass cloth. -
' 8.
- Imad Wire: .
Silicone rubber with glass braid jacket. ,
- 9. ' Varnish:
The first varnish coat is a phenolic modified polyester baking varnish
, applied by dipping.
Vardish: ' -
- 10. ;
,
- The second varnish coat is a phenolle modified epoxy baking varnish applied by dipping. .
- 11. Varnish:
The third varnish coat is a modified alkyd polyester air drying varnish ' containing a fungicide and is applied by brushing. ,
- 12. Rotor Surface:
The rotor O.D. is painted with an iron oxide /zine chromate pigmented air drying alkyd.
- 13. Exterior Finish:
0 ^11 exterior surraoe are covered with a grim e oeatios or the pae=otio modified epoxy baking varnish followed by a sprayed coat of an amine cured air drying epoxy paint with non-toxic pigmentation.
O i-SECTION 3.2 ELECTRIC MACHINERY COMPANY, LETTER DATED SEPTEMBER 15, 1980 1 i O 1 l O Geert/Commommesan
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p d EN v ELECTRIC MACHINERY MFG. COMPANY 80o CENTRAL AVENUE . MINNEAPOLIS. MINNESOTA . 55413 September 15, 1980
.F. J.-fomazic, Project Manager Gilbert Associates, Inc. M. &ll8
. P. O. Box 1498 Reading, PA. 19603 ' 7 YC. N *$h)t,:.)
FLORIDA POWER CORP. Crystal River Nuclear Unit #3 ' ( )7do Motor Serial No. 69-1940-13, -14, -16, -17 7 /ag/g g We have received your letter of June 23, 1980 requesting certificatiori of these motors to meet the Nuclear Regulatory Commission IE Bulletin 79-018 Qualification Requirements. We have reviewed the requirements and find no' reason to believe that the insulation -and systems furnished on these motors would not be capable of withstanding your environmental conditions. I After a thorough review of the contractual requirements, I could not' find l Q, any reference to the NRC bulletin 79-018 to which you refer, however we are aware of your need to address this request to provide information regarding the materials susceptible to degradation due to the thermal and radiation aging. - The materials susceptible to the thermal and radiation aging would be t'he insulation materials used. As far as I know, no dat.a regarding the i radiation dosage characteristics of our insulation system exists however we are able to certify the specific manufacturer and product number for l the insulating materials which were used on these motors. The materials l used are as follows: l Mica and glass insulating tapes - General Electric " Mica Mat" - i product #77869 l Coil varnish - Sterling - product #Y-493 Dip varnish - Sterling - U-835 The product numbers and manufacturers names enable identifying the chemical composition of the insulation which can be related to handbook - properties providing the radiation and thermal characteris. tics of these materials. - If I do encounter any additional-information, I will be happy to forward m it to you. If you have any other questions or if, we can be of any further Q assistance, feel free to conutact us. LitCt h , c!h BRUCE A. BONDOW vJ f,,
i I i SECTION 3.3 CENERAL ELECTRIC COMPANY, LETTER DATED SEPTEMBER 10, 1980 I
.O I
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O Geert/Commenneenn
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~N I G E N E R A L (<j E LE CTRIC stscraic uritiry SALaS DIVISION
% GENERAL ELECTRIC COMPANY . . . . . . . . . . 3 PENN CENTER PLAZA PAILADELPHIA, PENNSYLVANIA 19102 RE: ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT NRC.IE BULLETIN 79-01B C RIVER UNIT 3 NUCLEAR PLANT LORIDA SUB#118gWERCORPORATION j . -
/
September 10, 1.980 Gilbert Associates Inc. P.O. Box 1498 Attn: Mr. D. A. Rhoads Reading, PA 19603 Electric.al Engineer l - I Gentlemen.
) This is in response to your letter dated At ;ust 11, 1980, Your statement is correct in that the specified mot'rs o were manufactured by General Electric Co. and furnished in r package by Ingersoll-Rand Co. for the Crystal River Unit #3 Plant, We have determined that the motor in question, Model.No. SK445AK364, Serial Number undetermined, is a Class B insulated motor,- dripproof enclosure and standard grease was used'. With the exception of the '
motor lubricant, we would have rated the insulation sygtem as being able to withstand or absorb a radiation dose of 5 X-10D rads of gamma radiation. This exceeds the specified total dose of 5.6. X 10 4
~
i rads by some safe amount. l The specified level 5 X 10 5 rads of gamma radiation was not established by specific test, but is based on a literature survey and the incipient damage level. The sources referred to at the time included "The Use of Plastics and Elastomers in Nuclear Radiation - Parkinson and Sisman, Nuclear Eng. & Design 17, 247 . 280 (1971)". " Radiation Effects-Design Handbook; Section 3; Electrical Insulating Materials and Capacitors, C.L. Hanks, et al. Battelle Memorial Inst., Columbus, Ohio July 1971", and others.
G EN ER AL (]) ELECTRIC Mr. D. A. Rhoads September 10, 1980 g~) (_ Page 2 More recent artigles of' a similar nature would indicate that our rating of 5 X 103 is still a reasonable and conservative estimate. We havg indicated that the lubricant used was not included in the 5 X 103 rating. While the lubricant used has some moderate level of radiation resistance and presumably would be satisfactory based on motors being relubricated, its capacity to withstand any significantly high dose would be questionable. We would recommend changing the motor lubricant to Chevron SRI 2 or G.E. specification D6A2C13. Tests hav in excess of 1 X 10g beenrads run by Chevron of gamma and have radiation. Theshown a capability. customer should~ request the radiation resistance test data from Chevron. Data or tests beyond that stated herein may require testing and other evaluation and could result in a charge. We hope the preceeding data fully responds to your letter. Very truly yours, E. F. HARRISON ELECTRIC UTILITY S ES DIVISION O -
. BY Y- W. R. CASPER lD WRC:bw g
~
ec: F. J. Tomazic', GAI, Project Mgr. l l l O e m O
. ~ . -. - .~ . .. ._ .~ - _- - ._- . . _ ____ _ _. .- ._., . ..-. .
4 O : i i .1 -- SECTION 3.4 i l l ALLEN-BRADLEY CO. BULLETIN 798, C0t".ROL CENTER I SERIAL NO. 967929 NON-METALIC COMPONENT LIST l t l LO l i l i t
.O Geert/Canunenmese i
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@ ATLEN-BRADLEY ALLEN BLRADLEY COMPANY 1201 South Second Street 3 .
Milwaukee. Wisconsin 53204 USA Telephone 414/671-2000 August 31,_1982 Florida ^ Power Corporation
-Nuclear Operations P.O. Box 14042 St. Petersburg, FL 33733 -
Re: P.O. F-12693 Attn': . K'. B. Baker - EThis mailing contains. aflist of the materials we have been able
-to identify to our 1971 bulletin 798 control center construction,
~
in accordance with your purchase _ order requirement. - The data submitted here is proprietary.in nature, in so far as identification of generic-materials to our'part number is con-cerned, and we therefore request that you restrict its availa-bility to those persons directly involved'in this project. The list submitted is not complete, since we have two' suppliers who have not given us.the requested;information regarding their products, to date, however the major portion.of the non-metallic
- (). components 1tst is represented'in this report.
Thein-houseitems.kproductsmanufacturedbyAllen-Bradley) are
. tabulated on the "NON-METALLIC COMPONENT LIST",.which has the
. cross-referenco letters marked'thercon under the heading MICL -
Material Index Code Letters. The code letter listing is on the ' forms identified as the MATERIALS INDEX, which contains the descriptive data for the materials used to manufacture the components _on'the COMPONENT LIST. l 'The circuit breakers were furnished.to us by ITE CIRCUIT BPEAKER CO. and their response to our request was not made on the form we furnished to them. To date we have expended a total of 72 man-hours, plus conputer
-time, on this project. The data submitted here. represents the major portion of the control center components of concern.
o L . . , .
- We will complete the component data list as quickly as we receive
~
responses from the remaining suppliers. l 'Very truly yours,
/bJb 7ic" l
Harold eywood
Enclosures:
3 copies of report l I '
'cc: _ F.P.C., Nuclear Operations, P.O. Drawer 219, Crystal River Attn: W. C. Davis, Sr. , Nuclear Buyer Quality industrial controle . control systems . electronic components magnetic materials
j- ALLEN-BRADLEY CO. BULLETIt7 798 CONTROL CENTER - SERIAL NO. 967929
% NON-METAL COMPOMENT LIST -
[4ATERIAES ~NDEX C_ ODE _ LETTER CROSS-REFE'RENCE (MICL) ITEM MICI eM , MICL NO. Ope ra ting Devi.cc Part No.: IT
- )fri,; M 4 18. Cover Plate singie Jgig_jja,jllo,ch,_ _ _ _
F2.D407 Componnnti fuse Block Base 19. Contact Actuatet c
- 1. . 440023-067-01 K F20346 Nameplat Reset But' ton. T 20.
Ta 41010-061-04 B F20354 Label Overload Indicator g C 21* F21105 ('Part of 42 above)
- 22. Ba B1 k E Size 3 Coi w/Interlocp 2
~
i Pivot Pin l 23. Cover Plate KK g* T - F25406 F23989 L 24. Cover Plate KK 5* Coil Cover - F25407 F24008 . Oper. LeveA' R 25. Contact Actuator g
- 6. F20346 F24121
/m V - X234345 -
Size 1 Motor Starter 8
- 26. Reset Button F20354 T
Operating Lever R l - X234516 - 7* Size 2 Motor Starter F24I20 8 Pivot Pin T 27. Operating Lever R F23988 F24120 9* Coil Cover N 28. Pivot Pin T F24006 F23988 . _ . - = - - -. Arm Retainer E 29* Coil Cover N
'O*
F20178 F24006 _ - _ _
'l. . Yoke Retainer gy 30. Armature Retainer E F20179 F20178 Ar Hood Spacer 31. " Yoke Retainer yy 12**
F20597 LL F20179 3.3 . Arc Hood LL 32. Spacer LL
'0' __
v'>0110. __
~
L4. Cross Bar 33* contact crossbar . I E F20323
.. . _ _ ~ . ..._F.2_0_5 9.8 .,'
o . Overload Trip Indicator g
- 34. Arc Hood LL
'd' F21105 '!
_F20337
= - - - = - - _ _ _ . . _ . . _ _ ).. .
Base Block Overload Indicator H i.6 . E 35. F21628 F21102 36 Base Block E ty. - 1 . U.$
ALLEN-BRAULCY CO. B U w. . . .i ,Jo CUU1nUL CLfi'rLR - SE RI AL t.V.
., , :2 4 )
' NON-FETAL COMPGIENT LIST -
~ -
._MATERI ALS IIIDEX C, ODE _ LETTER CROSS-REFERENCE (MICL)
MIC h MICL t . 234516 i' con t ' d) Cover en
' To ve r P late KK 56. F20742 5,7' F25408 38, Cover Plate KK 57. Indicator W F25409 F21131
- 39. Contact Actuator J 58. ContactAhtuator G F20462 F20346 .-
Overload Relay Reset Button Reset Button F20354 T 59*
=
F20743 . W 60. Base Block E
- 41. O. L. Indicator F20741 F21102 4, Base Block E 61. Cover UU
.F21630 F20742 Cover Plate KK 62 Indicator w ~ / F21131 F25408 Cover Plate KK 63. Contact Actuator g F25409 F20346 n
U C5. Contact Actuator J 64* Reset Button F20743 j _ F2_G,4_6 2
- X266926 -
- 46. Roset, Button T Size 1 Motor Starter F20354 Operating Lever R
.- X234579 - 65. F24000
. size 1 EO. tor S tarter _.. _ _ . .
Pivot Pin T 66. Pivot Pin T 47* F23989 F23988 48 Coil Cover L 67 C.?tt Cover M F24908 . gp07 Operating Lever 49a F24121 R 68. 8 ;< Retainer E
,_ 00178 .
59 Spacer -
'LL 69. Yoke Retainer JJ s Y2d4a4 __
F29170 . . . . Y ke Retainer JJ Arc Hood Spacer LL 51* F20432 7o* _ __ _ _ m ,s _ _ _ _. .._ Arm Retainer E 71. Arc Hood LL 52* F20433 F20.595.__ 5 3.- Contact Cross-Bar D 72. Crossbar E
- F20527 F20598 Interlock Cam V 74 Arc Hood LL 73. F20708 F20426 E 74. S
~
- e- Base Block Roller (2)
ALIEN-BRAULCY Co. BULLE.i. s .... ,r.it - a t. im m ..v. m.,9
% NON-MET AT. CO"DONENT T.TST -
_ MATERIALS INDEX C, ODE _ LETTER CROSS-REFEItENCE (MICL) ,
- ITEM MICL NO. MICI 266926 - cont'd) Reset Button Roset Button o 95. F20879 o 76* F20879 Outer IIousing (Relay) E Outer Housing E 77 96*
F20817 F20818 Base Block - E - 220174 - 78* F20819 Cover Reset Assembly
- 79. Indicator W Button Stud F21103 97* F21025 X Contact Actuator asket
- 80. G 98* F21043 RR F20821 X266949 - - Z20811 -
l Adj. Overload Reset Button
~
Oper. Dever Gasket 81 F24000 R 99. F21043 RR Button Stud 82 Pivot Pin T 100. F21083 CO F23988
/%
("* ) Coil Cover Button Stud M 101* F21025 X p24007 84 Arm Retainer 102- Bushing Spacer RR F20178 E F21206 103. S 85 Yokep g g ner JJ RR 71A86 and 72A86
~
- 86. p$h
~ ~~
t LL - Sizes 1 & 2 Starter Oper. Coils
~
6 oil WrEp'~Materfals
- 87. Contact Crossbar I 104. 40099-302-04 CC F20323 Kraft Paper 88 Arc Hood LL 105. Black Electrical Tape EE s
' F20337 89*.
Interlock Cam y 106. F20708 Polyfilm Tape GG 90./91. Roller (s) S 107. White Polyfilm Tape II F20486 91A Pawl Support Z 108. Coil Tube W 401BS_.012.-al ____ F20266 y, Base Block E .109. Size 1& 2 Coil Insulation BB
' F20 819 F21256 93 Contact Actuator 110. Terminal Insulation F20821 G TT F21623 94 Indicator ,.,
111. Grey Fibre Strip A
ALLEN-BRADLEY CO. DI1LLETIN 79 8 CONTPOL CEMTER - SERI AL I40. 967929 NON-METAL COMPONENT LIST - M_ATERIALS I_NDEX C, ODE _ LETTER CROSS-REFERENCE (MICL)
/~ NM ITEM (i MICL NO. MICI
~
ucG_J _7_2A9G_ G411s) donf,'dr --. Gummed Strip
.12 BB 129. ^
Natural Mraf t Paper F25286
,y3, Encapsulating Material 130. Coil Support Insulation 33 Black Epoxy Q F25284
- 73A86 - 700-N800Al Size 3 S tarter Oper. Coil 8-Pole Type "3" Relay 131. Cover (2),
' 14
- 40099-302-04 Same as: CCEE F21699 H I tems 104 through 107 GG7y Coil Tube ,,, Sorina Retainer (2)
- . 15. F20339
,,Y
" ^~* '
F21703 RR Shunt Insulation BB 133. Operating Button 16* F21266 F21704 I
= _.
e ushion g3 Ll7 Terminal Insulation lTT 134. F21625 i F22821 f L10 Gray Fibre Strip A 135. Operating Button f F23170 Natural Kraft Paper 136. Armature shion OO
- h. 'BB L20. Encapsulating Material : 137. Contact Block P Black Epoxv l0 F21701 l
- 700-C020Al - I l 138. Spanner Guide SS 2 Pole , Open Type "C" Relay ! F21702 (2)
Insulation 139. Contact Block p L21* F14907 ' l UU e F21700 l L22 Contact Crossbar jE 140. Rela Housing l F21487 ! F2 697 8 123. Vibration Damper 14y* Top Block H F10723 fpp ' F21698 12 4 Plunger Guide #8 W 86 Oper. Coil For Relay- DD p 142* Components 40099-302-02 FF F21585 HH 1 L25. Molded Base . E 143* Black Elect. Tape DD F14925
#85A86 Oper. Coil for RelayF CC y 144. Polyester Elect. Tape FF L26* Components 40099-302-03; Seb II~d. 145. Electrical Tape HH Items 104 tYroliifh lD7,~ aiid' '
~ -
146. Rear Coil Plate F25044 !Z g include Epoxy Black - Index:: Q 147. Front Coil Plate F25045 LZ 148. Coil Pad F22820 NN 127 Electrical Tape FF ,. 149. Coil Encapsulation 0
'78. Coil Tube . . , , ien ,. : , r. e 4 - --
_ ALLUff-BRADLEY CO. BULLSTIH 798 CONTROL CE!1TER - SEEIAl. NO. 967929 -
NOfi-!!UTAL CO?iPONENT LIST -
!!ATERIALS INDEX C_ ODE L_ETTER CROSS-REFERENCE (MICL)
ITEtt - 11SCELLAMEOUS CO!!PONENT T.ISCELLANEOUS COMPONENT !!ICL IO. ITU .:S :!I( ITEMS- [ ...:.u.i:P MI,!:t CtJT . COIL FORM ky'jj.h 168. TEF241NAL HLOCi' 4 016 <'; - 0 7 3 - 01 rlu4oo* 460 .. - .. ..._..- Z f,
.2 VERLOAD !!LNh.st ELEtiENT USING 'Fil467**
;3 apj;NMhjiSRMTD) LL F21529 .
HORIZONTAL DUS SUPPORT YY
- 34. -.
F22410.
- 15. HORIZONTAL DUS SUPPORT XX F21565 .
- 6. VERTICAL BUS SUPPORT YY F22411 .__ ...
- 37. VERTICAL BUS SUPPORT XX F21566
;3. ' ANCIIOR FOR 2" IIORIZ DUS CCC F26179 A ..3 g ._-
' %,/ . . BDB
- 39.
- VERT.' BUS INSUL. BARRIER F22863 .
1 DDD
'3 0 . -EUEBgggMMET .-.. . - .- -..... -.
- 51. ~ GROM14ET DDD F18871 - . . . .-- ...... .. -
PLUG-IN BASE (100 A!4P) XX i2 F21564
.T
- 53. AUX.-SU. SPANNER PIVOT PIN _
F24518 . . L64. AUX. SU. OPER. LEVER QQ - F24524 --.
= CONTACT BLOCK 65w F24525 AAA . - . _ . - .
- - . . = _ -
- 66. OPSR. LEVER WW F24523 OPER.' LEVER R F25306
'*TitIS'COILFOpil IS USED ON ALL IIEATER 1 LEttEt TS IDENTIFIED WITli A-B .PART D
d NUl!BERS NN4 111ROUGli N12
- - - - - - - ~ - - ~ - -
UEATE tt ELGENTS INDENTIFIED WIT!!
* *TilIS COVER OR HOUSING IS USE.i .:13ONPCm ALL ;lESSIt :;LY Tl!ItOUCI! N33.
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