ML20138N821
| ML20138N821 | |
| Person / Time | |
|---|---|
| Site: | South Texas, 05000000 |
| Issue date: | 07/07/1981 |
| From: | Gary Arnold IMPERIAL PROFESSIONAL COATINGS |
| To: | |
| Shared Package | |
| ML20138M609 | List:
|
| References | |
| FOIA-85-59 505-81, NUDOCS 8511060051 | |
| Download: ML20138N821 (32) | |
Text
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#505-81 TITLE RADIATION TOLERANCE AND DESIGN BASIS ACCIDCIT RESULTS ON NUTEC CONCRETE COATDiG SYSTEMS FOR SOUTH TEXAS 1ROJECT CUSTOMER CONDUCTED BT: OAK RIDGE NATIONAL LABORATORIES Submitted by:G aid E. Arnold Md y: B Date:
July 7, 1981 SOUTHERN IMPERIAL COATINGS CORPORATION, INC. P. O. Box 29077,
- New Orleans, t.ouisiana 70189 Phone: (504) 254 1433 f .
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_ yyw._._.,g y..y. ,fa mwrc:r. ,ry;m SCOPE: The purpose of this test was to evaluate the performance of I:nperial's Nutec concrete coating system per the new South Texas Project require-ments (attached). This test also demonstrates that !{ucac 115 can be applied to unblasted concrete surfaces at film thicknesses up to 105 .
< mils.
s SUMARY: A
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Five concrete specimens were irradiated and design basis accident tested at Oak Ridge National Laboratories. All five specimens have
< - met the acceptance criteria as established by the South Texas Project ANSI N5.12, and ANSI N101.2. ,
PROCEDURES: Five concrete coupons, measuring 2x4x2" in size, were prepared as outlined on the attached panel preparation sheets. The following table sunmarizes the surface preparation, critical film thicknesses, and the test procedures utilized. Attached are copies of ORNL's test procedures. t O O. 9 4 4 e. g%98 , 9 4 A9Me ,p- ppMgW3g69gegg g
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" Technical Report i 505-81 Page 2 j Radiation Tolerance and Design Basis Accident i
j/ y Results on Nutec Ccacrete Coating Systems L M
- Test Coupon # Surface Preparation System DFIS Designation n
(Mils)
'i .
I A 31 115/1201 40 (HS) 3.5x10 rads 115/n/1201 40 (11S) 291*7, 70 PSIG 3 roomed Mace . HS/nS/1201 65 (US) f]
; - was abrasive-
"sveep" blasted to r m tance.
A 36 oder surfaces were nS/11S/1201 75 (n S) stoned fonowed by 11S/nS/11S/11/1201 105 (115) 100 psi compressed nS/1201 25 (11S) air. 8703 .nS/11/1201 27 (US) 17 (H) All surfaces 13 (1201) vere abrasive "svept" blasted
@ 8706 '
n/1201 16 (n) 8 2x10 rads 291*F. 70 PSIG 13 (1201) 8m .. nS/11/1201/1201 27 (11S) 16 (n) 13 (1201) RESULTS: Refer to individual ORNL results sheets. Coupon # . Irradiation Level /Results DBA Results A 31 3.5x10' rads /No defects No defects 9 A 36 3.5x10 rads /No defects No defects 0 8703 2x10 rads /No defects #8F on side 4 No other defects 0 8706 2x10 rads /No defects No defects 8715' 2x10 rads /No defects No defects
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Technical Report #505-81 Page 3 1-
)RadiationToleranceandDesignBasisAccident
\ v 'Results on Nutec Concrete Coating System 4
CONCLUSION: Test results indicate that the Nutec concrete coating system successfully met the acceptance criteria per ANSI N101.2 and ANSI N5.12 when subjected to radiation exposure levels of 2x108 rads to 3.5x109 rads and design basis accident conditions of 291*7. and 70 PSIG. This tech 4r=1 report should be reviewed concurrently with technical report #495-81. which describes an earlier test series for the South Texas Project. Both reports deal with concrete coating systems tested per the STP requirements, applied over various perpared surfaces and higher film thicknesses than previously qn= M fied. r% fy 9 0 t i S
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TEST PAm. PRErmTION Dm . . . j L. V' UCT TO BE TESTED: Nutec 11S/Nutec 11/Nutee 1201/ Nutee .11S/1201 1 Siret 2x4y ?
. TYPE SUBSTu m : Concrete
- 13. SURPACE PREPARATION (Describe): Carborundum stone used to re nove hinh 11ches n~f knw particles, broomed surface blast swept to remove efflorescence. Cleaned with 100 est ene- .
', pressed air . . %. PRODUCT DATA: SAMPLE BO.(s): A-31
- 5. $ ATE AND TIME CURING Ct2fPOUND OR PRTMP2 APPLIED: N/A PRODUCT APPLICATION CONDITIONS THICKNESS TIME & DAT COAT PRODUCT CODES 3ATCH f METHOD R/M(*P)TR.$. (ins.) APPLIED
~
Nutec 11S 2519/2530/2517 Squeegee 66*P/53%
- 2/4/81 3:00 p.m.
Nutec 115 2519/2530/2517 Squeegee 60*F/85I ** 2/5/81 9:00 a.m. Nutec 11S " 2519/2530/2517 Squeegee 64/55 *** 2/9/81 9:30 a.m. Nutec 11 2476/2102/2444 Squeegee 62*P/43% **** 2/13/81,2:00, Nutec 1201 9772/1959 Spray 73*P/52% ***** 2/16/81,3:00-FILM THICKNESS TOP VIEE OP (ins.) 115
- 119 ** 119 *** 11 **** 1201 ***** COUPON
.003 .005 Sid,1 .035 .040
.004 '.003 .005 4 2 Sid,2 .025 .040 .001
.015 .025 .030 .040 .003 .005 Sid,3 Numbered'and
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! Sid, 4 .030 .040 .
TOTAL DET FILM THICKNESS RANGE - Side 1.038 .045 Side 3 .048 .070 Side 2 .029 .049 _ Side 4 .033. .055 , CURING CONDITIONS: AMBIENT TDfP. 70 sin ' *P REL. EUMIDITY 45-65 I MINTMt1M CURE 7 DAYS TEST PROCEDUR'E: DBA/ Radiation Tolerance i ( ) ORNL DATE SUBMITIED 5/1/81-
;TE.% s PERFORMED BT:
APPROVED /eM O i TEST REPORT NO. 305-81
W M N T' W Q\9 %5?" % T M *W
- ) .
TEST PANEL PREPARATION DATA
- . TO BE TESTED: Nutec 11S/Nutec 11/Nutec 1201. Nutee 11S/1201 sin. 2y 4y 9
. TIPE SUBS 11tatur concrete
,. SUEFACE FREPARATION (Describe): _ Carborundum stone used to remove hirh if ehen ama ino.,
particles. broomed surface blast swept to remove afflorescence. Cleaned with 100 nei erwn-pressed air
- q. yacDUCT DATA: SAMPLE NO.(s): A-36
^ -
DATE AND TIME CuaING COMPOUND 0E FBIMER APPLIED: N/A
- 6.
Faconcr AFFLICATION COND M ONS THICENESS TIME & DA CODES 3ATCH ( METHOD 1/M(*7)Z1.E. (ins.) APPLIED
- OAT PRODUCT Nutec 115. 2519/2530/2517 Squeegee 66*F/53%
- 2/4/81 3:00 P.m Nutec 115 2519/2530/2517 Squeegee 60*F/85% ** 2/5/81 9:00 a.m.
- a. Nutec 11S 2519/2530/2517 Squeeges 62*7/55% *** 2/9/81 44 - 9:30 a.m.
Nutec 11 2476/2102/2444 Squeeges 62*7/43% **** 2/13/81.2:0( Nutee 1201 9772/1959 Spray 73*F/52% ***** 2/16/81.3:0( FILM MCENESS TOP VIEE OF (ins.) lis -
- lis ** ils *** 11 **** 1201 ***** COUPON Sid,1 .025 .035 .030 .040 .003 .005 3
~
4 2 Sid,2 .020 .025 .030 .040 .030 .040 .001 .004 .003 .005 1 Sid, 3 .020 .025 .030 .040 .003 .005
- Numbered *and
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.004 008 broomed surfa Sida 4 TOTAL DEI FIDi MCKNESS BANGE - Side 1.058 .08f Side 3.053 .070 l <
Side 2 .084 .113 Side 4.024 .033 - CURING CONDITIONS: AMBIENT TDfP. 70_go ' *F REL. HUMIDITY 45-65 % - MINTMim CURE 7 DAIS
.Iyy ' OCEDUldt: DBA/ Radiation Tolerance DATE SUBMITIED 5/1/81' G PERFORMED 3T: .ORNL
{ APPROVED TEST REPORT NO. 505-81
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. *- DBA AND RADIATION TOLERANG TEST PANEL PREPARATION DA3 NUTEC #11S/NUTEC #11/NUTIC #1201
- 1. PRODUCT TO BE ESTED: ,
- 2. TYPE SUBSTRAM: CONCREE SI22: 2" X 4" iC 2" -
- 3. SURFACE PREPARATION (Describe): Water cured (total innersion) for 11 days. Brush blasted
'l D with G40 grit.
'4. _ PRODUCT Dan : SAMPLE NO.(s): : :- T 8703
~
';i;5. can AND TIME CURING COMPOOND OR PRIMER APPLIED: N/A PRODUCT ' APPLICATION CONDITIONS MICENESS TIME & DATE COAT PRODUCT CODES BATCH # METNOD R/M(OF) % R.R. (ins.) APPLIED 1 NOTEC #113 2519/2530/2516 Squeegee 74/87 See below 12/8/80 12:4J l NUTEC #11 2476/2058/2444 Squeegee 72/62 12/10/80 10:45 3 NOTEC #12 1 1958/1959 Spray 52/70- 12/12/80 10:15 n #115 #11 '#1201 1 Sid7 C IMi.nimum .015 .016 .009 .010 .003 .004 g Sid::s Average .021 .022 .012 .012 .007 .008 d 'b AsB
- l Sidn D Maximum .026 .027 .016 .017 .012 .013 Number and T3TAL DRY FIIM THICKNESS RANGE - Side C.027 .030 Sides A & B .040 .043 broomed surfa Side D.054 .057 *
- 3. CURING CONDITIONS: AMBIENT TEMP. 50-75 F REL. HUMIDITY 60-90 4 MINIMUM CURE 33 DAYS
[ TEST PROCEDURE: DBA / Radiation Tolerance
- 1. u. mag PERIVRMED BY: Cak Ridge National Iaboratories DATE SUBMITIED 1/14/81
. APPROVED:
TEST REPCRT NO. 505 .-81 PREPARED BY: /h WR gg /
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, TEST PANEL PREPARATION DATA
; 1. PRODUCT TO ,BE ESTED: NUTEC #11/NUTEC #1201 -
- 2. TYPE SUBSTRAM: CONCRETE SI23: 2" X 4" X 2"
- 3. SURFACE PREPARATION (Describe): .,.._,,,..a r.,n 3 4_.,. 4 n,,3 pn,- 11 Anve. l n m ah blasted with G40 grit.
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.. 4. PICDOCT DATks-. SAMPIZ NO. (s): -
8706
- 5. DATE AND TIME CURING COMPOUND OR PRIMER [APPIZED: N/A PRODUCT APPLICATION CONDITIONS MICKNESS TIME & DA n N PPODUCT CODES BATCH # METHOD R/M(OF) % R.H. (ins.) APPLIED L NUTIC #11 2476/2058/2444 Squeegee 70/68 See below 12/10/80 9:30 2 NUTIC #1201 1958/1959 Spray 52/70 12/12/80
, 10:15 V.i,;
I 3 TOP VIEW OF
#11 #1201 .
CCCPON Sid7 C Minimum - .009 .010 .003 .004 e SidO3 Average .012 .013 .007 .008 d ,1 A&B " Sida D Maximum l.015.016 .012 .013 , Number and TOIAL DRY FII.M THICKNESS RANGE - Side C .012 .014 Sides A & B .019 .021 broomed surfac Side D .027 .029
!5. CURING CONDITIONS: AMB N TEMP. co-70 F REL. HUMIDITY 60-70 %
MINIMUM CURE 31 DAYS 1 TEST P. N : onA / Radiation Tolerance
- 1 1 1 h amG PERFORMED BY: Oak Rides National Laboratories DATE SCBMITI D 1/14/81 APPROVED: b TEST aEPORT NO. _ 505_m PRIPARED BY: M/f#7f , ,/A-i
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?l . .- '\. a. DBA AND RADIATICN TOLERANG 7 TEST PANEL PREPARATION DATA 1 . I
; 1. PRODUCT TO ,BE TESTED: NUTEC #11S/NUTEC #11/NUTEC #1201 .
j 2. TYPE SUBSTRATE: CONCRETE SIZE2 " X 4" X 2" * { 3. SURFAc PREPAPATION (Describe): Water cured (total immersion) for 11 days. Brush blasted f) with G40 grit.
- 4. PRODDCT DATA SAMP2 NO. (s) : -..% % 8715 i
~
- 5. DATE AND TIME CURING COMPOUND OR PRIMER" APPLIED: n/a PRODUCT APPLICATION CONDITIONS TSICKNESS TIME & DATE
~ COAT PRODUCT _ CODES BATCH # METHOD R/M(CT) % R.H. (ins.) APPLIED 1 NUTIC #115 2519/2530/2516 Squeegee 74/87 See below 12/8/80 12:45 p.m.
2 NUTIC fil 2476/2058/2444 Squeegee 70/68 12/10/80 9:30 a.m.
~3 NUIEC #1201 1958/1959 Spray. 52/70 12/12/80
. (Mist coat) 10:50 a.m.
4 .. NUTEC #1201 Spray 53/70 12/12/80
'Z 11:15 a.m.
_ c. TOP VIEW OF l Inf f 3l #11S #11 #1201(Mist) #1201 COUPON
'Sid1 C iMinimum . 015 . 016 ,
.010 .011 .001 .0015 .005 .0055 e Sidro Average d fb AsB .021 .022 .012 .013 .001 .0015 .008 .0085 a i
1 Sido D Maximum .026 .027 .015 .016 .001 .0015 .011 .0115 Numbere+d and TOTAL DRY FIIM THICKNESS RA$GE - Side C ,031_,g33 Sides A & B .042 .045 t 3 CORING CONDITIG 3: AMBIENT TEMP.Side Den_3c
.053 .05f F REL. HUMIDITY a n;_ on %
MINIMUM CURE 13 DAYS l .
'. TEST PROCEDURE: DBA / Radiation Tolerance
;. TESTING PERFORMED BY: cale Ride. Natienal Laboratories DATE SUBMITIED 1/14/81
. APPROVED: '!
TEST REPORT NO. 505-81 , PREPARED BY: //c7 A *A -9/ t
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t r; Manufacturer: Imperial Ana'lytical Chemistry Division j Oak Ridge National Laboratory ' i New Orleans, Louisiana Date: June 17, 1981 1 REPORT OF IRRADIATION AND DBA TESTING . I 1 The irradiation and design basis accident (DBA) tests are conducted, !
/ respectively, in accordance with Bechtel Corporation specifications CP-951 !
;?. and CP-956 in Standard Specification Coatings for Nuclear Power Plants (or {
with modifications as noted in Table 2, DBA test conditions). The tests are I
~
~ designed' to meet specifications set in both ANSI report N 101.2-1972, 1 Protective Coatings (Paints) for Licht Water Nuclear Reactor Containment i
- Facilities, and M 5.12-1974, Protect' ve Coatings (Paints) for the Nuclear p
. Industry. The DBA test spray solution and the test condttions are listed in ,
Tables L and 2. After both the DBA and irradiation tests, coatings are 1 examined for signs of chalking, blistering, cracking, peeling, delamination, i and flaking, according to ASTM standards where applicable. All test panels are returned to the coating manufacturer. The irradiation tests are run using a spent fuel assembly, removed from j the High-Flux Isotope Reactor at ORNL, as the source of radiation. These fuel assemblies are stored under 20 ft of domineralized water. The fuel is 93.% enriched U-235 as U 03 8 combined with aluminum. The spen.t fuel as- ) semblies are removed after each 23-megawatt-day peri od. . Irradiation is done using the gamma energy from accumulated mixed fission products. This more readily simulates conditions arou'd a reactor than does a cobalt
-@ Also, the higher gama activity n
affords shorter irradiation time to s ou rce.. achieve accumulated doses. The dass rate four days after removal of a fuel assembly from the reactor is 1 x 100 rad /h. The fuel assembly is 20 in high. A 20-ft-long,. 3-1/2-in.-diameter pipe, with one end capped, is used for air irradiation tests. The capped end is lowered into a 4-in. opening at the center of the fuel assembly. The open end, above water level, is covered with an 0-ring-sealed flange to which is attached a steel cable and an air outlet hose. The air inlet is i located at the bottom of the pipe. Test specimens are connected to the
- bottom of the cable and lowered into the radiation field. Also at the ,
center of the fuel assembly is a stainless steel-clad cadmium tube used as a neutron absorber. This prevents contamination of the test specimens by i induced radiation. 4 4 Evaluated .<.t,( . ,U Approved . I j
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' New Orleans, Louisiana .q
.- v l ORNL Log Book No. A9675, A6-2-1 . Table 1. OBA solution cogosition, distilled water lf Reagent Concentration U, d Boric acid, H B03 0.28 M 1 3 Required to adjust pH to 9.5 Sodium hydroxide, NaOH '
*A Table 2. OBA test conditions Tegerature Pressure (psig) Coments Time (*F)
Autoclave preheated. Start 150 . Solution injected at 260*F., 10 min 150-291-70 Pressure maintained by relief valve,. 20 min 291 45 min 291-260 . 260 39 Pressure adjusted with N2-80 min 120 min 260-220 180 min 220 20 210 min 220-160 160 5 21 h 125 2 Placed in fresh solution in constant 10 d - temperature bath. End of test - . Evaluate'd /.rs,/_ , Approved [. / , , h .- l g, _ Mww=g es e
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Manufacturer: Imperial Analytical Chemistry Division New Orleans, Louisiana Oak Ridge National Laboratory Date: June 17, 1981
, SYSTEM IDENTIFICATION Steel panel.
x Concrete block f 11S/11/1201 g . RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; Bechtel Corporation Specification No. CP-951; ORNL Log Book No. A9675, A5-28-1 . Initial dose rate: 1.2 x 107 rad /h Test conducted in: x air water
- ';, ; ~
Sample No. Cumulative dose Test results A-31 3.5 x 109 rad Coatings intact, no defects all areas. A-36 3.5 x 109 rad Coatings intact, no defects all areas. O e
- cvaluated Approved
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Manufacturer: Imperial - Analytical Chemistry Divistor Oak Ridge National Laborator) New Orleans, Louisiana Date: June 17, 1981
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. SYSTEM IDENTIFICATION Steel panel x Concrete, block -
; , 115/11/1201 l
, . . } RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; Bechtel Corporation Specification No.. CP-951; ORNL Log Book No. A9675, A5-26 1 .
- . Initial dose rate: 1 x 107 rad /h Test conducted in: x air water
- Sample No. Cumulative dose Test results 8703 1 x 108 rad Coatings intact, no defects. .
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; Manufacturer: Imperial Analytical Chemistry Divisic 1
Oak Ridge National Laborator New Orleans, Louisiana Date: June 17, 1981 [V . i . SYSTEM IDENTIFICATION Steel panel x Concrete block
- 11/1201
~;- J RADIATION TOLERANCE TEST ORNL Master Analytical Manual Method No. 2 0921; Bechtel Corporation Specification No. CP-951; ORNL Log Book No. A9675, AS-26-1 . Initial dose rate: 1 x 107 rad /h , Test conducted in: x air water Sample No. Cumulative dose . Test results 8706 ,, 2 x 108 rad Coatings intact, no defects. l
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_. .=_- . . . , ,mn - : - .,_. . g --- _~m.. -g, Manufacturer: Imperial Analytical Chemistry Division-Oak Ridge National Laboratory 3
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SYSTEM IDENTIFICATION Steel panel x Concrete block 115/11/1201
. RADIATION TOLERANCE TEST
.- ORNL Master Analytical Manual Method No. 2 0921; Bechtel Corporation
- Specification No. CP-951; ORNL Log Book No. A9675, A5-26-1 .
J Initial dosa rate: 1 x 107 rad /h Test conducted in: x air- water 3 _b Sample No. Cumulative dose Test results 8715 2 x 108 rad . Coatings intact, no defects. t e
- Evaluated .4 / .
A< Approved [ [ ~-1 - - I
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O Steelpanei x Concrete , block '
. SYSTEM IDENTIFICATION i
115/11/1201 1 08A TEST ORNL Master Analytical Manual Method No. 2 0922. ORNL Log Book No. A9675, A6-2-1 .
- q:
Sample No. 08A pha::e Test results spray
- Coatings intact, no defects all areas.
A-31
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- Coatings intact, no defects all areas.
A-36
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Manufacturer: Imperial Analytical . Chemistry Division Oak Ridge National Laboratory New Orleans, Louisiana Date: June 17, 1981 SYSTEM IDENTIFICATION Steel panel x Concrete block 115/11/1201 7 08A TEST ORNL Master Analytical Manual Method No. 2 0922. ORNL Log Book No. A9675, A6-2-1 . Sample No. DBA phase Test results 8703 . sp ray
- Coatings intact, no defects after 28 h.
Blisters #8 few, side 4 at end of test. No other defects. *',
- Irradiated.
d
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Imoerial . Analytical Chemistry Division Manufacturer: Oak Ridge National Laboratory
- New Orleans, Louisiana Date: June 17, 1981 SYSTEM IDENTIFICATION Steel panel x Concrete block ,
11/1201 08A TEST ORNL Master Analytical Manual Method No. 2 0922. ORNL Log Book No. A9675, A6-2-1 . Samole No. DBA phase Test results 8706 spray
- Coatings intact, no defects all areas.
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.o Manufacturer: Imperial ' Analytical Chemistry Division Oak Ridge National Laboratory New Orleans, Louisiana Date: June 17, 1981 SYSTEM IDENTIF.! CATION Steel panel x Concrete block '
115/11/1201 , 08A TEST 4
- ORNL Master Analytical Manual Method No. Z 0922.
4 ORNL Log Book No. A9675, A6-2-1 . , i Sample No. 08A phase Test results 8715 spray
- Coatings intact, no defects all areas.
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, AttacNnent 4 PROTECTIVE COATINGS SYSTEM DESIGN ff "
. AND SELECTION CRITERIA ,
1.0 INTRODUCTION
1 1.1 PURPOSE AND SCOPE
- 1.2 All surfaces to be finished with a coating, surfacer, or paint type product will be included in this technical reference document:
System Design and Selection Criteria, under one of the following Service Level Classifications: SERVICE LEVEL. I - Pertains to those coating systems, applied to structures,' systems, and components, which are essential to the 1 prevention of, or the mitigation of the cons'equences of, postulated accidents that could cause undue risk to the health and safety of. the public. SERVICE LEVEL II - Pertains to those coating systems which are essential to maintain the intended normal operating performance or, coating systems that are applied to surfaces which can be directly contEminated by spraying or flowing contaminated liquids. SIRv1CE LEVEL III - Pertains to these coatings systems, applied to systers and components, that have not been designated to be coated with Service Level I or Service Level Il coatings , including all of the balance of plant subject to environmantal, service condition, workmanship and the "best practice" of the trade, state of the art, censiderations. 1.3 The design criteria is defined and the test standards for coating materials are considered. 1.4 The qualification o'f protective coating suppliers and applicators is
- considered. .
1.5 The interface activities with purchasing, quality assurance, and quality control are considered. 2.0 , GENERAL DESIGN REQUIREMENTS 2.1 The coating system design goal for Service Level 1, Service Level II ( ~ G
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. T i and Service Level III areas is for a service life of 40 years. The t
coating systems to be selected are maximum life materials. The g coatings materials will serve 40 years with proper maintenance. j 2.2 The coating systems to be used in Service Level I areas are to be . tested by the supplier in an independent testing laboratory in
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accordance with the DBA conditions established by this technical reference document in section 3.0. Service Level I coatings must also satisfactorily pass the requirements of sections 5, 6, 7 & 8. l Q-{ The manufacturers and suppliers are to establish QA and QC procedures Z.3 and documentation to certify that materials tested are the same formula and of the same quality as those to be supplied to the project. The materials are to be tested for reliability and quality using tests and test procedures in accordance with appropriate Federal Standards ASTM, and other special product tests as applicable. 2.4 All coatings material to be used for Service Level II will be subject to testing according to sections 5, 6, 7 & 8, as well as all of the
- QA requirements as required for reliability and quality.
2.5 All fabricated metal such as structural steel, piping, vessels and liner plate will be mechanically blast'ed and coated with an Inorganic Zinc-Rich Coating or will be hot dip galvanized. The Inorganic Zine coating and/or galvanizing may be top coated as required. The documentation and traceability shs11 be in accordance with the intent of ANSI N101.4 as interpreted in the coating specifications. 2.6 Electrical equipment and instrument items will be supplied ccepletely finished with the manufacturers. standard finish. Suitability of coating sifall be reviewed by Materials Engineering. Colors shall be as specified in purchase documents, as well as necessary instructions relative to the documentation and traceability of the coating product used on this, equipnent. ) 2.7 Other equipment items will be supplied either prime coated only, usina Inorganic Zinc, for finish coats in the field or they may be completely shop coated. Certain types of equipment may require specialty or additional painting and will be painted as required according to the service conditions and class of environment to which Ge equipment will be exposed. - 2.8 Above ground uninsulated piping for service up to 200 F will receive the same coating as' the structural steel in the same area, where practical. Damaged, rusted, and field welded areas will be cleaned and primed to correspond with the original coating system applied. 2.9 Uninsulated pipe and equipment operating between 200'F and 750 F will be mechanically blasted and coated with an Inorganic Zine Rich Coating. 9
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2.10 All uninsulated piping or equipment operating above 750"F shall y receive, if required, a special coating based on the exposed Q environmental conditions for the specific area. 2.11 All concrete surface subject to radioactive contamination will be j coated with an epoxy, phenolic, or any other appropriate generic type of coating to improve ability to decontaminate. The concrete j 3:. surfaces will be prepared to receive the final coat using an approved curing compound / sealer, and compatible surfacer. Th'ese concrete
* - surfaces will be smooth and free of porosity as required, for the
,' application of topcoats. . - 2.17 The curing compound, if used, for concrete is to be applied as soon as; practical after the forms. are removed prior to the. occurance of surface contamination. All top coating as required by the appifcable coating specifications is to be accomplished in accordance with ANSI NS.12-1973. , 2.13 Architectural concrete surfaces, walls, floors, and roofs will be 3 protected with a penetrating surface sealer.where spe'cified. In most applications, the sealer will not change the natural appearances of the concrete, but will be a sealer for waterproofing. 2.14 Other architectural surfaces will receive at least two coats of latex or alkyd paint finishing colors, to be specified on the architectural A drawings. . 2.15 Coatings for balance of plant, or Service Level III, will require good quality control practice to see that they are applied in accordance *
' with the general painting specification for the area. Quality Assurance and Quality Control,100% Inspection, that is used in the >
contai'hment and other safety related areas, will not be used for the balance of plant. Balance of plant or Level III area is subject to the best practice of the industry, state of the art considerations, A listing of surfaces coated and coatings used will be maintained for the use of plant operating personnel. 2.16 All coating systems are to be applied in the correct sequence of events to assure accessability and the availability of an area in order to attain a high quality application. . 3.0 OSA TF.ST CONDITIONS ' 3.1 The coatings for Service Level I are to withstand DBA conditions as described by the project DBA temperature and pressure vs. time curves for PWR reactors. The chemical spray environment consists of a boric acid solution with a PH of 4.0 to 10.5 maximum adjusted with sodium hydroxide. The solution is to contain 2000 to 4000 ppm boric
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acid, 0.15 ppm maximum chloride, and 0.15 ppm maximum flouride. Make D .
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- Page 4 of 11 up water quality is to be the same as the reactor coolant systems make up water, 3.Z The general exposure conditions are set by the design basis accident *
. as identified in Brown & Rcot criteria document IE019RQ j
are outlined below: Temperature - 291'F . h s 8 /fe7I Pressure Humidity56.5 psig
- 100% for 30 days, / .M y ,,,, W_
Relative: 7.7 Testing for the carbon steel and concrete test panels shall be in accordance with ANSI N101.2-1972. 3.4 Each coated panel to be DBA tested is to be exposed to all test media ?. consecutively with the radiation testino to be last in the series. Conversely, panels tested individually on only one environment will not be accepted. 4.0 ACCEPTANCE CRITERIA 4.1 As a minimum the following physical characteristics shall be used to determine a nuclear coatings acceptability, 4.2- Flaking - shall be evaluated in accordance with ASTM 0772-47 " Standard Method of Evaluating Degree of Flaking (Scaling)*of Exterior Paints". Flaking or peel,ing shall not be permitted. 4.3 Blisterinq - shall be evaluated.in accordance with ASTM 0714-56 Blistering
" Standard Method of Evaluating Degree of Blistering of Paint". 'E shall be limited to size 4 intact blisters not exceeding a " frequency of a.few" as shown in ASTM D714-56 photographic reference standards.
4.4 Checking *shall be evaluated in accordance with ASTM D660-44 " Evaluating Checking is permitted: Degree of Checking of Exterior Paints".however, checking shall
- ASTM D660-44 photographic reference standards.
4.5 Cracking - shall be evaluated in accordance with ASTN D661-44 " Evaluatin Degree of Cracking of Exterior Paint". Any evidence of cracking seen with the unaided eye shall constitute unacceptability. ' 4.6 Chalking - shall bh evaluated in accordance with ASTM Chalking shall D659-74 not exceed " Evaluating Degree the No. 8 of Chalking with Exterior Paints". standard as contained in standards. 4.7 Delamination - or peeling generally indicates a loss of adhesion of the t 1 n =r * ,.m n _
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['- 1 j l \ l system to the , substrate and therefore shall not be pemitted. 4.8 Discoloration - would be expected for some formulations but, does not mean tne system has failed, therefore discoloration shall be permitted. Evidence of tackiness or softening of- the coating system, sufficient
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4.9 7 to impair the function or serviceaDility of the containment linerThe te shall not be .pennitted. i ~ Z hours after removal from the test chamber for the defects listed ; 4 . above. Any other defects ce changes. in coating properties which will render the coating system nonfunctional will be cause for rejection. N 5.0 RA01ATION EXPO 5URE ' 8 Nomal Operation I 50 x 10 Rads STP Calculated LOCA 8 2 ' .33 x 10 Rads Irradiation 9 30 days Total '.83x'168 Rads
References:
8
- 1. IEEE STD 383-1974 recommends a value of .50 x 10 Rads 1 as the normat- 40 year design value. -
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- 2. Brown & Root Calculation A479NC130 8 However, IEEE STD 323-1974 suggests the use of 1.50 x 10 Rads .
Fr.P conservatism the nuclear coatings from LOCA f rradiation. specified for the containmenMiner will 8 be qualified at: ' Normal Operation .50 x 10 Rads 8 LOCA Irradiation , 1.50 x 10 Rads
- 8 Total 2~. 0 x 10 Rads Testing of the carbon steel and concrete test panels shall be in accordance with ANSI N101.2-1972.
ACCEPTANCE CRITERIA - As. a minimum the acceptance criteria specified in section 4.0 shall determine a nuclear coatings acceptability. _u 6.0 DECONTAMINATION FACTORS Decontamination faktors for the Containment Liner as a minimum a as follows:
- a. 1(ater 9 25"C DF=5 -
"- b. Acid 9 25 C OF = 1.3
- c. Acid 9 80 C DF = 1.3
- d. Overall CF = 10
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. ) TABII I COORDINATES FOR STP DBA CURVES .
4 TIME TEMPERATURE PRESSURE j (Seconds) *F (psir) EVENT 0 65-120 0* Break 16.5 255 34 Core Flood Tank
- Injection Begins 23 261 38.5
- Peak Containment Pressure During Blowdown 25 260 38 ECCS Injection Begins End of Blowdown 52.5 270 41 Beginning of Fan Cooler Operation 111.5 271 47 Beginning of Containment Spray Injection
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V c. 48 End of Core Reflood 142.1 274
- f. 7m*= 221 .
275 48.4 Peak Containment Pressure 1,550 ,, 255 - 37 Beginning of Recirculation r 3,820 260 . 39 End of Steam Generator Energy Release fa k 9,000 ' 220 20 Containment Pressure is 50*' Of Design Value J/4% 75,600 160 5 Hoe Leg Injection Initiated CSS Stopped 1,000,000 125 2 End of Transient
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