ML20129F134
| ML20129F134 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/15/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| U-600192, NUDOCS 8507170242 | |
| Download: ML20129F134 (8) | |
Text
e U-600192 L30-85 (07 -15 )-L 1A.120 ILLIN0/8 POWER COMPANY July 15, 1985 Docket No. 50-461 Director of Nuclear Reactor Regulation Attn: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Unit 1 Illinois Power Company Endorsement of Visual Weld Acceptance Criteria (VWAC), Revision 2
Dear Mr. Butler:
Please find attached for the Staff's review, advanced copies of revised Clinton Final Safety Analysis Report (FSAR) pages, which incorporate Illinois Power's adoption of Visual Weld Acceptance Criteria (VWAC) for AWS Structural Welding at Nuclear Power Plants, Revision 2.
This revision of VWAC, which was prepared by the Nuclear Cotatruction Issues Group (NCIG), was accepted by the NRC Staff on June 26, 1985, and has been endorsed by our designer, Sargent & Lundy, for use at Clinton Power Station (CPS). On the basis of these endorsements, we are adopting this revision and will be incorporating the enclosed pages into the CPS-FSAR. This incorpora': ion will take place in Amendment 34, which is currently scheduled for publication later this month. Your timely review and approval of this material is requested to support implementa-tion of these visual weld acceptance criteria at CPS by August 10, 1985.
Please contact us if you have any questions regarding this matter.
Sincerely yours,
/
Q.
h i
F. A. Sp igenp erg i
Director Nullear L :ensing and Configuration Nuclear Station Engineering i
RTR/ lab Attachment cc:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety
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8507170242 850715 PDR ADOCM 05000461 A
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4 CPS-FSAR AMENDMENT 34 JULY 1985 TAhlJ: 1.8-4 (Cont'd)
EPECI.
SPrefrlCATION PICATION OR
. Ri.rl*tWl:
STANDAND NisMot.R IW:;lGNATi oN T i T1.l:
t.h l T 8 'sd D i '4 Al' E 22 AISI Specification for the Destqn of I W.3 o r 19N Light Giqu Cold-Fr amod Steel Structural Memborn 21 AH.i bl.)
St ructur.al Weld inq Oatle 19 7(. or 19'?
St' 8 th 't e I twith required visual tempec-tion Lased upon VWAC,
_. Revision 2) 24 AWS Dl2.1.61 Reconnended Pract ice for Weldinq 1961 Reinforcing Steel, Metal insetts and Connection in Reinforce 1 Concretu Construction 2%
ASME ASME tw>t ler and Pressurty Vessel 1971 with For Containannt Locks Code,Section III Division 1, NE Summe r o f and Hatches 197) Addunda 25a ASME ASME Holler and Pressure Vessel 1974 with For Drywell Locks and Code, Sectnon III, Division 1, NE Summer of Hatches 1976 Addenda 25b ASME ASME Holler and Pressure Vessel 1974 with For Reactor Pedestal Code, Section !!!, utvision I, NP Winter of 1975 Addenda 25e ASME ASME Do11er and Pressure Vesse 1 1977 Fo r rue l Pool Ga t es Code, Section Ill, Davision 1, ND 2$d ASME ASME Ho t lur and Pressure Vessul 1977 For Fuel Pool Liners Code, Section !!!, Division 2 2 f.
(Deleted) 27 (Deleted) 28 ASTM Annual Books of ASTM Stand,trds l
29
( the l e t ed )
Jn (buleted)
II Uhc Uniform Duildinq Codo 19 70 o r 19 7')
l 12 (De le t ant )
11 (Deluted) 14 (Deleted) 15 hhc Roqulatory Mechanical Cadweld Splicus an
~ rob.~ 1, 1971 6al hdrawn by the JRC Ouido 1.10 Reintoteinq liars of Concreto 7/8/81
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Containments 3h
'Utt' Ra w f u l<s t o r y Instrumentation for Ea r t hquakes vev.
1, i
Guado 1.12 Ag,r. 1974 17 NRC Regulatory Fuel Storaqo racility Desl<pt bev. 1 Guido 1.1) ika s a n (n.c. 197%
18 Nke Requiatory Testing of Roinf ot einq Das s Dec. 28, 1972 Withdrawn by the NRC Guide 1. ! '2 For Concrete !:t ruet ur es 7/8/81
,trevision II l
39 NPC flequlatory Structural Acceptance Test for Dec. 28, 1972 Withdrawn by the flRC j
Guidu 1.18 Concreto Pt im ar y 6eactor Con-7/8/01 tainments (lievtston 1) 40 NkC Regulatoay Nondest ruct ive Fxamih a t tons of Aug. II, 1972 Withdrawn by the 11RC Gokde 1.19 Ptimary Containment Liner Welis 7/0/81 titevision 1) 41 NPC kequlatory Qualit y tiroup Classif icat iona Pev. 3 Guld 9 1.26 and St and.o rds reb. 1976 42 flPC Regul.atory Ul t e nka t e llea t Sink bev. 2 Guado 1.27 J.an. 1976 41 llPC Regulatory Ucle.mic Design Class i fication Pev. 3 Gulde 1.29 Sept. 1978
- 6. F-( l Theet 2 of 1
CPS-FSAR AMENDMENT 34 JULY 1985 T/.111E 3.8-4 (Cont'd)
EPl:Cl-SPLCIPICATION FICATION OR kEP!;kLNCE STANDARD NUHHER Dt:SIGNATION T I TI.l; FDITION HFMARKS 44 NPC Regulatory Control of Stainless Steel ROV.
le Guido 1. 31 Wolding Apr. 1970 45 (I*leted) 46 CHS!
Manual of Standard Practico 1973 47 ANSI N45.2.5 Proposed Supplementary QA 1974 Requirements for Installation, inspection and Testin.1 of Structdral Concrete and Structural Stre! d. rawi Con-struction Pha4e of Nuclear Power Plants 40 NI4C Requlatory Concrete Placement in Category Rev.
O, Withdrawn by the NRC Guide 1.55 1 Structures Juno 1973 7/8/81 4 ')
NRC Regulatory Design Liriaits and loading Juno 1973 Guide 1.57 Combinations for Metal Primary Reactor Containnwnt Systenis and Components 5J NRC Regulatory Materials for Concrete Contain-Rev. 1 Guide 1.136 ments (Article CC-2000 of the Oct. 1978 Cmle for Concrete Reactor Vessels and Containtunts)
Explanation of Ibbrevaations ACI American Concrete Instituto AISC American Institute of Steel Construction AISI American Iron and Steel ins,titute ANSI American Nation.s! Statulards Institute API Ametlean Petroleum Institute ASME American Society of Mechanical Engineers ASTM American Society for Testin.1 and Materials AWS American Welding Socacty CRSI Concrete Reinforcinq Steel Institut o NB:C National Electric Code NPC Nuclear Regulatory Consnission Utte Unif orm Du11 ding C<xto VWAC Visual W.rld Acceptanco Crtturia ho't i:S 1.
Clatification to and deviation from portions of AWS D1.1 (and VWAC Fevision 2 fcr visual inspection of wolds made to the requirements of AWS Dl.1) are made based on engineering evaluattons, Ehret I of 3 1.h 02
lp i
),
o CPS-FSAR AMENDMENT 34 1
JULY 1985 B.3 STRUCTUltAL STEEL lf l
B.3.1 Structural Steel Materials Structural support steel was ASTM A36-75, ASTM A572-76, Grade 50 and ASTM A588-75 Grade 50 high strength, low alloy corrosion-resistant steel.
B.3.2 Structural Steel Connections and Connection Material l
B.3.2.1 Bolted Connections l
High strength structural steel connections used ASTM A325 and ASTM A490 friction-type high strength bolts.
These connections conform to AISC Specifications.
For other types of connections ASTM A36 l
material was used for threaded rods, ASTM A307 was used for headed l
bolts and ASTM A307 or A563 material was used for nuts.
l i
l B.3.2.2 Welded Connections Standard welded beam connections conformed to Table III or IV of AISC Manual, Seventh Edition.
Shop and field welding procedures were in accordance with AWS Specifications listed in Table 3.8-4.
(
Selection of electrodes and recommended minimum preheat and interpass temperature were in accordance with AWS requirements.
All wclders and welding operators were certified by an approved testing laboratory and were qualified under AWS procedure as stated in AWS Specifications.
B.3.3 Quality control B.3.3.1 General l
Quality control requirements were applied to the fabrication and testing of structures and components.
Certified material test reports were furnished stating the actual results of all chemical analysos and mechanical tests required by ASTM specifications.
Identifying heat numbers were furnished on all structural steel to trace the steel to the specific heat in which the steel was made.
B.3.3.2 Tenting and Inspection of Weldments One hundred percent of all complete penetration groove welds for beams, girders, and columns had complete radiographic i
f D.3-1
. s
1 L
c CPS-FSAR AMENDMENT 34
(
JULY 1985 i
examination, except that welds impractical to radiograph were examined by ultrasonic and either magnetic particle or liquid penetrant methods, t
The above nondestructive test methods were in compliance with spplicable sections of the following ASTM specifications:
i a.
E94-68, " Recommended Practice for Radiographic l
Testing,"
L b.
E142-77, " Controlling Quality of Radiographic Testing,"
c.
E164-74, " Recommended Practice for Ultrasonic
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Contract Examination of Weldments,"
i d.
E109-63, " Dry Powder Magnetic Particle Inspection,"
e.
E138-63, " Wet Magnetic Particle Inspection,"
f.
E165-75, " Recommended Practice for Liquid Penetrant I
Inspection Method," and 6
g.
AWS Dl.1. (as clarified VWAC, Revision 2).
l L
All other weld joints including fillet welds, were 100% visually examined.
The visual examination conformed to all applicable requirements of AWS Dl.1 through July 1985 Visual welding inspection after that date was performed to the criteria contained in VWAC Revision 2.
Clarifications to and deviations from portions of AWS Dl.1 (and VWAC Revision 2) are made based on engineering evaluations.
B.3.3.3 Fabrication I
The fabrication of structural steel conformed to AISC
" Specification for the Design, Fabrication and Erection of Structural Steel for Buildings," 1969 or 1978.
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B.3-2 1
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CPS-FSAR AMENDMENT 34 JULY 1985 B.4 REACTOR PEDESTAL-SHIELD WALL B.4.1 Type of Construction' i
The reactor pedestal and the reactor shield uall are shell-type i
structures fabricated from steel plates.
s The materials, fabrication, erection, and examination procedures for the reactor pedestal conformed to the requirements of 2
Articles NF-2000, NP-4000, and NF-5000 of the ASME Boiler and 3'
Pressure Vessel Code,Section III, Division 1, 1974 Edition, Winter 1975 Addenda and applicable code cases acceptable to consulting engineers for a plate and shell-type Class I com-l ponent support.
The pedestal was not inspected by the authorized f
nuclear inspector (ANI) nor stamped in accordance with Section 1
III of the ASME Codo.
)
1 B.4.2 Materials Materials used in the reactor pedestal and reactor shield wall p
conform to the following specifications:
s
{
Reactor Pedestal Application Specification Vj Shell plates and diaphragms A588, Grade A or Grade B Plates highly stressed in the A588 made by electroslag through-gauge direction remelt process i
Ponctration sleeves SA-333 SA-316 Shield Wall Aoplication Specification Shield plates and diaphragms A588, Grade A or Grade B Reactor Holddown Bolting Materialc Specification Studs-nuts SA-540, B-23, Class 4 1
1 B.4.3 Uciding i
B.4.3.1 Reactor Pedestal The reactor pedestal was fabricated in accordance with the requirements of NP-4000, ASME Code,Section III, 1974 Edition, Wintor 1975 Addenda.
Shop and field welding procedures were in h
accordance with the requirements of ASME Section III and Section h
IX.
Recommended minimum prohcat, interpass temperature and 5
postweld heat treatment woro in accordance with ASME Sectica III requirements.
All wolders and welding operators woro qualified in accordance with ASME Section IX.
(
9 a
n B.4-1 1
U-600192 SUBJE,CT:
IPC Endornm:nt of Vicual W ld L30-85( -
)-L Acceptance Criteria (WAC),
1A.120 Revision 2
~
be W. C. Gerstner, B-13 D. P. Hall, V-275 H. E. Daniels, V-650 J. S. Perry, V-275 l/[
S. B. Fisher, V-913
)
i hJ.W. Wilson,T-31
(
J. H. Greene, V-130 I
U
(
. R. Victor, V-928 q
,j b W. Connell, V-923 /8. 1" hvi 4
J. R. Patten, V-922 i
A. E. King, V-500
[
L. W. Osborne, V-900 J. C. Cook, T-31 1
R. E. Wyatt, V-914 y
C. D. Schaefer, V-913
[
(@ etS $ly$
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/
J. S. Spencer, V-920 F. A. Spangenberg, V-926 446 ') f,.35 Q
y R. E. Campbell, V-923 1
K. B. Roys. V-645
]
D. K. Schopfer, V-270
/
J. Greenwood, V-600
/
H. M. Sroka, S&L (Atten: R. C. Heider)
S. A. Zabel, Schiff, Hardin & Waite q q G. L. Edgar, Newman & Holtzinger P. J. Telthorst, IPC (Newman & Holtzinger) ho h Q f. kh '.
CPS Central File, T-31 hR.T.Reese,V-920 Author (s)
}{ (fc SL S 51% tidd Ghh5 wbW ei g
CO q cae c4wtc,
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Technical Validators J. Ynrr, V 423 l
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- 2. J. M. Scott, V-928 4 $1 g(
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r-U-600192
SUBJECT:
IPC End:rc: ment of Vicual W21d L30-85(
)-L Acceptance Criteria (VWAC),
lA.120 Revision 2 b
W. C. Gerstner, B-13 D. P. Hall, V-275 H. E. Daniels, V-650 J. S. Perry, V-275
/[
S. B. Fisher, V-913 hJ.W. Wilson,T-31 I
. H. Greene, V-130 o
7
. R. Victor, V-928 i
W. Connell, V-923 6 A h A
J. R. Patten, V-922 i
A. E. King, V-500
[
L. W. Osborne, V-900 J. G. Cook, T-31 p
R. E. Wyatt, V-914 v
C. D. Schaefer, V-913 J. S. Spencer, V-920 t
8 6
(h
/
h F. A. Spangenberg, V-926% 'l 3.%5 @009I'ily R. E. Campbell, V-923
$y K. B. Roys, V-645 D. K. Schopfer, V-270 J. Greenwood, V-600 H. M. Sroka, S&L (Atten: R. C. Heider) y('
S. A. Zabel Schiff, Hardin & Waite q,d G. L. Edgar Newman & Holtzinger P. J. Telthorst, IPC (Newman & Holtzinger) h D,f. M ',
CPS Central File, T-31
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hR.T.Reese,V-920 Author (s)
} { (&c SL S 5 % M GW% *bkA es g
( o n c=ecente.
Technieni Validators g,.J.xa,,,v-923/e%@ff,e w#
- 2. J. M. Sc tt, V-928 I
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