ML20012B970
| ML20012B970 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/21/1990 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19293A228 | List: |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 GL-88-01, GL-88-1, NLS-90-036, NLS-90-36, TAC-67592, TAC-69128, TAC-69129, NUDOCS 9003190239 | |
| Download: ML20012B970 (48) | |
Text
n n
o Catedna Power & Upht Company SERIAL: NLS-90-036
[
en nox issi. Rwee. N c. ersar FEB 211990 A. B CUTTER Vee Pres! Cent Nuclear Servces Department United States Nuolear Regulatory Commission t
ATTENTION:
Document Control Desk Washington, DC 20555 I
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 IGSCC INSPECTION RESULTS - REFUELING OUTAGE 8
References:
1.
Letter from R. A. Watson (CP&L) to Nuolear Regulatory Commission dated June 15, 1989, "IGSCC Inspection Plans (TAC No. 67592)"
2.
Letter from R. A. Watson (CP&L) to Nuclear Regulatory Commission dated August 21,1989, " Revision to IGSCC Inspection Plans" 3.
Letter from E. G. Tourigny (NRC) to L. W. Eury (CP&L) dated December 21, 1989, "GENEHIC LETTER 88-01, NRC POSITION ON IGSCC IN BWR AUSTENITIC
. STAINLESS STEEL PIPING (TAC NOS. 69128 AND 69129)"
4.
Letter from L. I. Loflin (CP&L) to Nuolear Regulatory Commission dated June 29,1989, " Response to Staffs Request for Additional Information Pertaining to Carolina Power & Light Company's Response to Generio Letter 88-01, Units 1 and 2 (TAC Nos. 69128 and 69129)"
Gentlemen:
Carolina Power & Light Company (CP&L) apprised the NRC Staff of the Company's plans for the inspection and/or modification to the recirculation piping, and any other piping susceptible to Intergranular Stress Corrosion Cracking (IGSCC) in the Brunswick Steam Elcotric Plant, Unit 2 (BSEP-2) in Refer-ence 1.
These plans were revised (Reference 2) following CP&L's decision to replace the Reactor Coolant Recirculation System (RCRS) discharge risers, safe ends, and nozzle butter.
The scope of actions to be taken, which are complete, were divided into four (4) categories:
(1) NUREG 0313, Rev. 2 Inspections; (2) Reactor Water Cleanup (RWCU) Piping Replacement; (3) Hydrogen Water Chemistry Implementation; and (4) RCRS Pipigt Replacement.
l contains:
(1) a description of the repair / mitigative actions taken as a result of the NUREG 0313. Rev. 2 Inspections, (2) a description of the replacement.of the remaining 4-inch diameter IGSCC susceptible portion of l
the RWCU system piping, (3) the, current status of the Hydrogen Water Chemistry Control System installation, (4) a description of the replacement of the RCRS discharge risers, safe ends, and nozzle butter, (5) an updated classification 9003190239 900221 l
i I
PDR ADOCK 0 34 h4/W >
\\
\\
G
h -
.g 1
3 ad,
m b
il ?
Document Control Desk (NLS-90-036) / Page-2 v~
of IGSCC. susoeptible welds based upon the replacement of the RCRS and RWCU piping replacemente and the sitigative/ repair actions taken during the BSEP-2
. refueling outage 8. (Table 1), and (6)'a conclusion-that includes a basis for i"*
Loontinued operation of BSEP-2 until the next refueling outage presently.
1 scheduled to.begin in May 1991. -provides the design reports from 1
Structural Integrity Assoointes,.Inc., concerning: the weld overlay repair and RHR valves modification.
Enclosures 3 and 4~ provide the SMC O'Donnel1~ & '
Assoolates, Inc. (ODAI), report on the Mechanical Stress Improvement Process application on the RCRS piping (proprietary) and the ODAI affidavit -trans-f sitting that report, respectively.
Please refer any questions regarding this submittal to' Mr. M. R. Oates at (919)'546-6063.
Your very tru
/
/
A. B. d ter
\\
A l't'
,DBB/eoo Attachments
'co Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. 0.-Tourigny l-a k,
!? : o it i.
t h.
k I
);
I k
. gn j
h ENCLOSURE 1
[
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 P
NRC DOCKET 50-324
[
OPERATING LICENSE DPR-62 IGSCC INSPECTION RESULTS - REFUELING OUTAGE 8 i
(1) REPAIR / MITIGATIVE ACTIONS TAKEN AS A RESULT CF NUREO 0313, REV. 2' 1
INSPECTIONS UT Process l
3 i
The Ultrasonic Testing (UT) was performed by General Electrio (GE) UT personnel who have been qualified in accordance with the EPRI/BWR00/NRC requirements, including the latest requalification program.
The examinations
[
were completed usi?B the fully automated GE."1 MART UT" Image computer driven L
data acquisition :,ystem and ALARA reacte scanning devise. Manual examinations were performod on welds which could not be scanned using the SMART UT system, and to supplement the SMART UT examinatiores.
UT Results A total of one hundred thirty-nine (139) welds were inspected per CP&L's L
approved (Reference 3) NUREO 0313, Rev. 2, IGSCC Inspection Program. During the examination of welds in the original inspection scope, indications were
't identified'in 10S00 Category
'C' weld no. 28B10. Since more than 50% of the b
Category 'C' welds-were already included in the inspection scope, it was 3
impossible to expand the sample to ".-.. approximately equal in number to tho original samplo" as recommended in NUREG 0313. Rev. 2.
Further, the NUREG t
e' states that the expanded sample should be similar in distribution (e.g., pipe size) as-the original sample. Thus, the sample was expanded to include eleven (11) additional Category 'C' welds.
This resulted in forty-two (42) of forty-eight (48) Category 'C' welds being inspected.- During the inspection of the l
additional eleven (11) welds in the sample expansion, a flaw was detected in weld no.-22AM1. Per NUREG 0313, after cracks were found in the second sample.
f CP&L expanded the sample to include all the Category 'C' welds.
No other 4
flaws were identitled in any of the remaining inspections, in any of the IGSCC i
inspection categories.
The resolution of the flawed welds is as follows:
Weld 28B10
- During the ultrasonio examination of this weld with the SMART UT system i
0 utilizing a 45 shear wave transducer, eight (8) previously unrecorded indications were identified.
Supplemental examinations were performed 0
0 manually utilizing 45 shear wave, 45 refracted longitudinal (RL) and 60 l
RL transducers which confirmed the indication location and size.
The i
indications we"e characterized as axial reflectors with the maximum j
through-wall depth of any indication being 0.24" (20%) and the maximum length of 0.55".
. Based on the crack growth analysis of these indications, 1
a weld overlay was applied to this weld.
1 t
s
- r s-Weld 22AM1 0
During the ultrasonio examination of this weld with the SMART UT system
_ utilizing a 45 shear wave transducer, one (1) previously unrecorded indication was identified.
Supplemental examinations were performed 0
0 v
sanually utilizing 45 shear wave and 45 RL transducers which oonfirmed L
the indication location and size.
The indication was characterized as a-l-
circumferential reflector with the maximum through-wall depth of 0.18" l
(165) and the length of 2.4".. Based on the flaw evaluation performed for D
this weld which concluded that conservatively, the plant may be operated for the next fuel / operating cycle with the weld in its present unrepaired condition, this weld did not receive an overlay, and will be reinspected and re-evaluated during the next refueling outage.
I Inspection of Welds 24A12 and 24B13 p
In response (Reference 4) to the NRC Staff's request for additional information concerning the limited inspections occurring on welds which '
fi were part of the Inspection Program, ~it was stated that ten (10) of the twelve (12) welds would be eliminated by the RCRS piping-replacement.
Regarding the remaining welds, 24A12 and 24B13, several alternate examination techniques were being considered.
However, it was impossible to improve the -inspectibility with the application of alternate-examination techniques only.
It was determined that the method of choice E
was to machine the valve body at the point nearest the weld joint in order to provide a " flat land" large enough to perform a 100% inspection from one side of the weld.
This machining was accomplished in accordance with the design analysis performed by Structural Integrity Associatea, Inc.
(Enclosure-2).
An ultrasonio examination was performed of these welds with the SMART UT system utilizing a 45 shear wave transducer, with no indications recorded for either weld 24A12 or 24B13.
(2) REPLACEMENT OF THE 4-INCH DIAMETER RWCU SYSTEM PIPING The remaining susceptible portion of the RWCU system piping (4-inch return:
line from the, regenerative heat exchangers to valve-2031-F042 at the RCIC/Feedwater system tie-in) was replaced using-low carbon austenitio stainless steel materials.
As a result of the pre-service UT, examination performed on all replacement welds the IGSCC classification of the replacement welds is Category
'A'.
(3) HYDROGEN WATER CHEMISTRY CONTROL SYSTEM INSTALLATION The BSEP-2 Hydrogen Vater Chemistry Control System installation activities 7
are complete and will be operated during this fuel / operating cycle.
L(4) REPLACEMENT OF REACTOR COOLANT RECIRCULATION SYSTEM PIPING By Reference 2 CP&L advised the NRC Staff of it's decision to replace the
+
_ RCRS discharge risers, safe ends, and nozzle butter.
The replacement was performed by General Electric Company during this refueling outage.
The existing 304SS risers and Inconel 600 safe ends were replaced with 316NG 4
'SS material.
In addition to the material change, the new safe ends were designed to eliminate the thermal sleeve attachment weld and the crevice j
7 se
.O condition inherent to the old design which was an IGSCC initiation site.
The existing Inoonel 182 nozzle butter and cladding was removed and replaced with ER309L SS weld material.
The replacement materials were selected in accordance with the recommendations of NUREG 0313, Rev. 2, and l-in addition the piping and safe ends were electropolished and received preoxidation treatments.
The welding process used to compl6te the L4 -
replacement, controlled the. heat input to the weld a*
1.65 megajoules,-
E which reduces the residual welding stresses and enhances the materials resistance to IGSCC. Further IGSCC mitigation was accomplished by the
^ application of the Mechanical Stress Improvement Process (MSIP) to all replacement welds.
The MSIP was performed by O'Donnell and Associates, Inc.
A pre-and post-MSIP UT examination was performed on all replacement welds with no rejectable indications being observed.
As a result of the L
s RCRS piping replacement,. twenty-eight (28) weld overlay repairs were removed from the system.
l'
-(5) UPDATED CLASSIFICATION OF IGSCC SUSCEPTIBLE WELDS The updated classification of BSESP-2 IGSCC susceptible welds is conthined in Table 1.-
The table has been updated to reflect new welds which are L
part of the RCRS and RWCU piping replacements.
(6) CONCLUSION.
L Carolina Power & Light Company has completed the IGSCC inspections and repairs, and the replacement of the RCRS discharge risers, safe ends, and nozzle butter, and the remaining susceptible portion of the RWCU piping system.
The Mechanical Stress Improvement Process was successfully applied to.the thirty-six (36) RCRS replacement welds.
Pre-and Post-MSIP UT ' examinations i
were completed on all RCRS replacement welds with no rejectable indications observed.
l 1
)
UT examinations were performed on one hundred thirty-nine (139) weldments in. IGSCC categories A, C, D, E, and F of NUREG 0313, Rey, 2, employing E
both the GE SMART UT system and Manual UT techniques.
The original scope of examinations and resulting sample expansions were in accordance with Carolina Power & Light Company's approved NUREG 0313.- Rev. 2 Inspection i
Program; 5
Based on the results of the mitigative actions taken, the state-of-the-art '
inspections performed, Carolina Power & Light Company believes that the
[
start up and continued operation of BSEP-2 until the next refueling outage, currently scheduled for May 1991, is justified and will not h
adversely affect the. health and safety of the public, and Carolina Power &
Light Company intends to proceed with start up of BSEP-2 as currently i
scheduled on March 8,1990.
4 4 5; l~
4 Pag 3 1 of 2 TABLE 1 BRUNSWICK STEAM ELECTRIC PLANT - UNIT NO. 2 i
REACTOR RECIRCULATION (B32) AND RPV (B11) BYSTEMS IGSCC INSPECTION CLA881FICATIONS
_Catecorv A 22AM3BCA 4A2 4A10 4B9 2B32FF-12-FW805*
22AM3BCB 4A3 4B2 4B10 2B32FF-12-FW806*
22AM5BCA 4A4 4B3 2B32FF-12-FWRRB10A*
2B32FF-12-FWRRB13A*
22AMSBCB 4A5 4B4 2B32FF-12-FW802*
22BM1BCA 4A6 4B5 2B32FF-12-FW803*
2B32FF-12-FWRRB14A*
22BM1BCB 4A7 4B6 2B32FF-12-FWRRB11A*
22BM3BCA 4A8 4B7 2B32FF-12-FW804*
22BM3BCB 4A9 4B8 2B32FF-12-FWRRB12A*
2B32FF-12-FWRRA10A*
2B32FF-12-FWRRA12A*
2B32FF-12-FWRRA14A*
2B32FF-12-FWRRA11A*
2B32FF-12-FWRRA13A*
2B11N2A-RPV-FWABA*
2B11N2F-RPV-FWABA*
2B11N2B-RPV-FWABA*
2B11N2G-RPV-FWABA*
2B11N2C-RPV-FWABA*
2B11N2H-RPV-FWABA*
2B11N2D-RPV-FWABA*
2B11N2J-RPV-FWABA*
2B11N2E-RPV-FWABA*
2B11N2K-RPV-FWABA*
- Denotes new weld added during BSEP-2, refuel outage 8.
j Cateaory C 28A2 28A12 22AM3 28B9 24B13 28A12BC 28A3 28A14 22AM4 28B12 22BM2 28A15BC1 28A5 28A15 22AM6 28B13 22BM3 28B12BC1 28A6 28A16 22AM6 28B14 22BM4 28B15BC1 28A7 28A17 28B2 28B15 20A1 28A9 28A18 28B6 28B16 20A1BC 28A10 24A12 28B7 28B17 20A2 28A11 22AM2 28B8 28B18 Cateaorv D Cateaory E Cateaory F o
28A9BC1 28A4 28B10 28A1 28B9BC 28A8 28B11 28B1 28A13 22BM1 22AM1 4A1 22AM5 4A11 28B3 4B1 28B4 4B11 28BS
'A Paga 2 of 2 TABLE 1 BRUN8 WICK STEAM ELECTRIC PLANT - UNIT NO. 2 RWCU PIPING (G31) IGSCC INSPECTION CLASSIFICATIONS Catecorv A 2RWCU-R9 2G31-2149*
2RWCU-1992 2G31-2056 2G31-2095*
2RWCU-1991 2G31-2058 2G31-2096*
2RWCU-1990A 2G31-2059 2G31-2097*
2RWCU-1989 2G31-2060 2G31-2098*
l 2RWCU-1988 2G31-2062 2G31-2099*
2RWCU-1987 2G31-2079 2G31-2100*
2RWCU-2007 2G31-2081 2G31-2101*
2RWCU-2006 2G31-2082 2G31-2102*
2G31-2083 2G31-2103*
2G31-2084 2G31-2104*
2RWCU-2003 2G31-2085 2G31-2105*
2RWCU-2002 2G31-2074 2G31-2106*
2G31-2075 2G31-2107*
Cateaorv D 2G31-2051 2G31-2037 2G31-2066 2RWCU-1954A*
2G31-2053 2G31-2038 2G31-2068 2RWCU-1960 2G31-2054 2G31-2039 2G31-2069 2RWCU-1948A 2G31-2042 2G31-2040 2G31-2070 2RWCU-1608 2G31-2043 2G31-2076 2G31-2071 2RWCU-1609 2G31-2044 2G31-2077 2G31-2072 2RWCU-1611 2G31-2045 2G31-2078 2G31-2073 2RWCU-1613 2G31-2046 2G31-2086 2G31-2052 2RWCU-1617 2G31-2047 2G31-2087 2RWCU-1610A 2G31-2048 2G31-2063 3RWCU-1618A 2G31-2035 2G31-2065 2RWCU-R10A
- Denotes now weld added during BSEP-2, refuel outage 8.
' CORE SPRAY (E21) SYSTEM IG8CC INSPECTION CLASSIFICATIONS Catecorv C Cateaory D 10NSA 2E11FF-4-FWRNSA 10NSB 2E11FF-8-FWRN6A JET PUMP INSTRUMENTATION (B21) IGSCC INSPECTION CLASSIFICATIONS Catecory C Cateaory D 4N8A JPI-22-1 4N8B JPI-22-2
p~a #
gi bf. 5
^
h?'
u.
.c i
I ENCLOSURE 2 BRUNSWICK STEAH ELECTRIC PLANT, UNIT 2 5
t NRC DOCKET 50-324 OPER ATING LICENSE-DPR-62 10 SCC INSPECTION ~ RESULTS - REFUELING OUTAGE 8
[
F
[.
DESIGN REPORTS - STRUCTURAL INTEGRITY ASSOCIATES, INC.
,U
'i bl PCR-89-097
" Transmittal of Weld: Overlay Designs for BSEP-2 ;
Welds 28B10 and 22AM1" (5 pages) b HLO-90-001
" Flaw Evaluation for~ Weld 22AM1" (2 pages)_
i L'
l HLO-90-004
" Weld Overlay Shrinkage Evaluation for Weld 28B10" i_
(1 page) i SIR-90-003:
" Redesign of-Area Between the RHR System Return-Valves and Reactor Reoirculation System Tees" (9 l
pages).
l, l
RAM-90-009
" Redesign of Area Between the RHR System' Return
.i Valves and Reactor Reoirculation-System-Tees - As-l L
Built Reconciliation" (18.pages) 1 L
f 4
O
\\
, 8 k.
s o
i 4
?
J
-. A 4
f 5
l b
t p
~-
4 PCR-89-097 pngo 1 of 5 3150 Ahmedea L ai Suite 226 Ibeat P! ant Operemons Saaloos.CA 95118 October 26, 19 W 3*sth Miller Road l
3 00) 978 8200 pm '83a,op7,y Susie 10 mu :w17 muct Aboa, Ohio 64313 1
ru ta; rSam (216)8864006 1
ru. mis okwI h
Mr. Terry Pitchford Carolina Power & Light Co.
c Brunswick Steam Electric Plant
}
Leonard Street Extension Southport, NC 24461
Subject:
Transmittal of Wald Overlay Designs for BSEP-2 Welds 28-B-10 and 22-AM-1 3
Dear Terry:
Enclosed please find design drawings for the subject weld overlays.
The design basis for overlay thickness for both is the
" standard" approach per NUREG-0313 Rev. 2, which assumes that the original pipe wall is cracked through-wall for 360* of the pipe circumference.
For overlay length, we have used a conventional approach for the 28-inch pipe-to-elbow weld, but have opted.for an asyr. metric design for the 22-inch pipe-to-valve veld, to tvoid welding on the cast valve body.
This approach has been used in similar applications in the past, and is made possible by the relative immunity to IGSCC of the casting side of the weld.
It would also be possible to modify the design so as to taper the weld overlay smoothly into the step in the valve casting.
Both approaches have their pros and cons, which we would be happy to discuss with you.
{
As we discussed, we are also proceeding with a heat transfer analysis to justify welding both of these overlays without water in the pipe.
We expect to *have preliminary results of this analysis by Wednesday of next week.
Please call if you have any questions or comments, or would like to discuss these designs in more detail.
V y
ou I
eter C. Riccad ella cct R. Hanford A. Giannuzzi / CPL-09Q Project File l
l r
. ~..
.. ~
..s PCR-89-097 pag 3 2 of 5 t
I J
I i
1 I
i=
- ---=-
I d
~
e i
y.
s, -
a.. sj..-
t, w=
I M 6__
I
$*'t't ' / t's 's't's's't'o 't't
/
% l t fi a,oj.r.ify < s. i r.r i./ r.h i
$\\
\\
i
/
/
l i
1 l
e 1 i f" 8
- \\
e' M M ",'./
i i
~,:-. s1 n
L.
./.,'_-
.,_,,.,n
.--.y...
A I.
i l.:::Cy..vesi-3:
<=-.-
s, y,,y...
?..= a C. y 9. ; 3. I. ;6 6..
a.-
.44....
.....,..........N.
1 e..ew.
i e
i I
i i
23 3 2 -RR - 2 0 - A.v.- 1
! 1 Circumferential 0.40" 10.125" 3.! Standard Desi n
' Length: 2.4"
' 3 asis Per Oepths I S P.
See NURI",-0 313,
{
Note Revision 2 i
(4)
I l
l i.
i
- ! ut; p.
- Art
- tsca:Pt::'ai M g h'- %
[
feh g /y9 Reactor Recir:01ation 20" Header Cross-Tie Valve to Pup Pie:e Wei:
- :: :x
.?
- Af' l
W
/
10 1 N
..:s,c.
s v.ast e :stri I
- ~/
CPL-09Q 3:unsvick Steam Electri:
0 j
lke gyggg P'. ant, Unit 2 h @:_:.u.- -.;_ _. _: %,c
- . I
, Fiat sc, i.; nei t
1 C?L-090-201 i CPL-09Q-002 1
2
j,.
1."
~~
~
~
\\
?'r
'PcR-89-097' p go 3 of 5 14 '
l:
,i n c i.
I l
I NOTES I
1 L
(1)
Prior to_ ' welding, the area to be welded and one-i*'
(1) inch of the base rnaterial on either-side D
shall be liquid penetrant (PT) examined.
Any indications 'shall be reported to engineering for l
' resolution.
i (2)
The first weld overlay layer deposited shall contain a delta ferrite content of 7.5 FN i
minimum.
Engineering shall be notified in the event that the delta ferrite is <7.5 FN.
f-(3)
Weld layers to be applied in accordance with CP&L Approved Contractor Welding Procedures.
i l
I (4)
The repair is-to begin at least 0.125" from the existing weld fusion line- (Dimension 'A*)
~
and the full thickness length of the overlay l
is to cover the centerline of the pipe to I
valve weld, as shown.
Because of the stiffness l
l of the valve, it is recommended.that welding l
l proceed in the direction away from the ' valve.
l i
Drawing No.: CPL-090-002, Revision 0 7 STRUCTURAL
+
Page 2 of 2 INTEGRITY
/ e 5 5CCI ATil S, I N C
- A.
.s PCR-89-097 pago 4 of 5 i L
i t
t
[
A
,
8 ~'
FLOW l
45' MIN l
1iv,:
I t
f
.l kh,....h,,$$......
i i
\\
N I
PIPE ELBOW.
I
-t q WELD l
w.__i.,.j/.u,_Ay 4
REPAIf DETAILS i
o i
i 4
(
i.Aw
!CE5iGN OIMENSICNS, l
,.. 3 #.__#'
y, _ _
iCHARACTER!ZATIONl t
1 A
l
'S i
t 2332-RR-28-B10 l 8 Axials, Max 0.44" 3.1" 3.1" Standard Design Depth 20%
Basis Per
,NUREG-0313, j Revision 2 I
I i
I l
a I
i i
e
'[.
li
- E*ARE: 3Y
-0 ATE ESCRIPT!:N l
[ '[-
[
/8/26/g9 Reactor Recirculation Loop Si l.
28" Pipe to Pump Suction Elbow Weld 08:.< E '
i 0Af~
1 l0126/ i9
.~
!.:9 NC:
?'. ANI / 'JNIT :
(
$$'/
i l
CPL-09Q Brunswick Steam Elsetric 0
l L
Plant, Unit 2 6
{
7:.I Not
- '.G Noi 4
g SHI l
CPL-090-301 CPL-090-001 1
Cr 1
k PCR-89-097 ptg2 5 of 5 i v q. -.
}
NOTES l
a 3
(1)
Prior to welding, the area to be welded and one s
(1) inch of the base material on either side-.
shall be liquid penetrant (PT) examined.
Any indications' shall be reported to engineering for resolution.
I i
(2)
The first weld overlay layer deposited shall l
contain a delta ferrite content of 7.5 FN minimum.
Engineering shall be notified in the event that the delta ferrite is <7.5 FN.
(3)
Weld layers-to be applied in accordance with CP&L Approved Contractor Welding Procedures.
i ll i
l 1
Drawing No.: CPL-090-001, Revision 0 STRUCTURAL-g Page 2 of 2
/ ! g y q R,l_T y i
.C.
3, INC l
1 9
_ _. _. ~ _..
y;J
~V H14-90-001 p go liof 2 O
i 31to Almodse '. ---,
Fossil MAW OPershons -
Suin 235 January *22, 1990 86 South Miller Hood p
San Jose. CA 96118 HI4-90-001 Seim 10 3
l (403) 373 3300 Aboa Oluo 44313
. nux neelt muct (216) 064 8086 fax res)r5mse rAx ms)emust
)
?
i Mr. Terry Pitchford i
Carolina Power & Light o
Brunswick Steam Electric Plant Leonard Street' Extension f
~ Southport, NC 28461
)
l
[
Subject:
Flaw Evaluation for Weld 22AM-1 L
P
Reference:
l'. General' Elect'ric. Company Report, " Brunswick Units 1 & 2. Recirculation Piping Analysis",
Report 23A5485, Revision 0, October 1, 1985.
- 2. General Electric Indication Resolution Sheet
~
Number R-070, Revision 0, October 16, 1989.
j u
Dear Terry:
Structural Integrity Associates has completed a flaw evaluation of the weld 22AM-1 in the Brunswick Unit 2 recirculation system, The conclusion of this evaluation is that the observed flaw will t.
not-grow to - a, depth corresponding to the allowable flaw size a
permitted by.Section XI, IWB-3641-5 in less than 24 months, even L
under-a.
conservative'-
set of-assumptions which
. include consideration of ' stresses 'potentially : introduced by. the fit-up and installation-of the new -recirculation risers.
Without
' consideration. of these
- stresses, which.are not -technically.
applicable to allowable flaw size determination or flaw growth calculations, the remaining acceptable service life is in the vicinity of 56 months.
Both sets f of flaw growth calculations were performed using the residual stress correlations and the flaw growth correlation contained in NUREG-0313, Revision 2.
Applied stresses were taken from the' General Electric Co. Stress Report-[1] for the concerned-location.
The initial flaw characterization was taken from Reference 2.
These results. confirm that the system may be conservatively operated for the next fuel / operating cycle with veld 22AM-1 in its present unrepaired condition.
The weld should be reinspected
- ?
and re-evaluated during the next refueling outage.
h5 x
HI4-90-001 p g3 2 of 2
.~4~
i Page 2 1
i.
1
' The-calculations supporting this result will be transmitted along with all of our design records upon project completion.
If you have any questions regarding this letter, please call me.
Sincerely, ill
/W w
+
H. L. Gustin, P.
E.
. /mc cc: CPL-09Q i
e 9
l-t h
e 0
i ASSOCIATESINC
-HLG-90-0041 pngo 1 of 1
-ll 11'
[
- i l+
J l
>t';<
W.
3150 Almoden Espreeeway bed Plant Opwahons Susw 226 January,31, 1990 66 South Mala Road Son Jose. CA 95118 HLG-90-004 Suiw 10 (408) 9 4 8200 Akron, Ohic 44313 tuzx inmit m ueT (216) 864 8886 rAxtemssase rAx ca m ess w t
'Mr. Terry Pitchford Carolina power and Light Company
'T Brunswick Steam Electric Plant 14onard Street Extension Southport, NC 28461
Subject:
Weld Overlay Shrinkage Evaluation for Wald 28B10
Reference:
CPL Data Sheet 6-1, Wald Number 2-B32-840, ISI Number 2BB10, pnges 1 & 2, dated 1-29-90.
Dear. Terry:
SI has reviewed the shrinkage data provided in the referenced data sheet, and has determined that this reported shrinkage will have no signifiernt effect on the stress state at any location in the recirculation system.
This conclusion is based upon the observation that the average reported shrinkage at this location
'is 0.0705", which is comparable to shrinkages reported at other 28" locations.-
(For example, weld 28B5 had a reported shrinkage of 0.083", and. weld 28B11 had a reported shrinkage of 0.085".)
the' weld overlay shrinkage induced stress in 28" locations in the recirculation system due to all of the weld overlays applied throughout the system is typically of the order of a few hundred.
psi..or less.
The weld overlay-. repairs applied to'the 12" risers generally make the largest contribution to this' stress.
These welds have all been removed as a part of the riser replacement project.
Consequently, the stresses-in the remaining piping due to remaining weld. overlays are expected to be conservatively bounded by the previous analyses.
These-stresses only play a role in the evaluation of unrepaired flaw ~-locations.
Brunswick Unit 2 only has-three such locations remaining, and shrinkage stresses of a few hundred psi will have no significant impact on the acceptance of these locations.
- If-you have any questions regarding the above, please contact us.
i Sincerely, 9tL E H. L. Gustin, P.
E.
/jj
SIR-90-003 ' pig 3.1 of'9 1.n j
1 P
v 3150 Almaden Espreneway Famil Plant Opwabons Sune 22C January 12 1990 06 South Milla Road Saa Jose, CA 96118 RAM-90-004 Sune 10 l
(408) M8200 SIR-90-003, Rev. O h o W 44313
.TQIX letal?e3Uct (216) 864 M86 --
j r u Hos)r s essa ru ras)esmst i
Mr. Terry Pitchford
. Carolina Power & Light Company Brunswick Steam Electric Plant O
. Leonard Street Extension b
p Southport, NC 28461-
Subject:
Redesign.of Area Between the RHR System Return Valves l1 and Reactor Recirculation System Tees q
i
References:
- 1. " Design Report Recirculation Piping -
Loop A and_B - B31.1 Power Piping Code",
General Electric Company, Revision 0, October'1, 1985.
- 2. Carolina Power & Light Company Drawing No.
0-FP-06014, Revision A, January 18, 1989.
l
' Flanged Fittings", USA Standard..
-j.
4.
ASA B16.'10-1957, " Face-to-Face and End-to-End'
' Dimensions of Ferrous Valves", American. Standard.
j 5.-ASME Boiler and Pressure Vessel Code,Section II.,
- E-4 1986-Edition.
- 6. ANSI B16.34-1981, " Valves - Flanged and Buttwalding End", American National Standard.
j l=
Dear. Terry:
s
. Carolina Power Light Company (CP&L) is undertaking more L
extensive in-service inspection of the reactor recirculation (RR) l' and residual heat removal (RHR) systems at the Brunswick Steam
. Electric Plant, Unit 2, in order to comply with the requirements R
~of U.S.
NRC NUREG-0313, Revision 2.
In order.to ultrasonically (UT) examine the weld between the reactor recirculation system
. tees and' the " residual. heat removal system return valves, the
- valve bodies must.be reduced in thickness at the weld location in order, to provide at least a
2-1/2 inch- " flat" land for manipulating the transducer.
Structural Integrity Associates (SI) ' was contracted -by CP&L to provide the technical justification for reducing ~ the valve body thickness at this l
location.
i The General Electric Company (GE) performed a reanalysis of the i
RR system-in 1985, and documented their results in the Reference
- 1 Design Report.
Although the purpose of the GE Design Report
)
.Y SIR-90-003 p:go 2'of.3 Page 2 January 12, 1990 T.
Pitchford RAM-90-004 was to qualify the RR system, it also provided stress information at the location currently being evaluated.
Per Figure 14 (1),
nodes 769 and 509 (Loops A and B) are of interest herein.
Pages 234 and 283 (1) report the maximum stress ratio (i.e.,
computed i
stress / allowable stress) for all reported load combinations of 0.511, with a modeled thickness of 1.388' inches.
Therefore, if a.
j wall thickness of 1.388 inches is maintained, modification of the GE Design Report is not required.
Drawing. number 0-FP-06014 (2) provides a general arrangement of the valves to be examined.
Per note number 1, they were designed to B16.5 (3).
'Since the = Reference 2 drawing was initially issued in
- 1971, the 1968 version of the standard is the 1
" Code-of-record".
Reference 3 further references B16.10-1957 (4) for face-to-face and end-tc-end dimensions.
These two documents, therefore, form the basis for the original design of the valves.
1 Per Reference 3, Table 27, the minimum thickness required is 2.28 inches for the 24 inch 900 pound gate valves.
This is confirmed per the Reference 2 drawing, that states "2-1/2 min wall (2.280 min. wall USAS B16.5)".
Per Reference 4, Table 5,
the standard end-to-end dimension is 61 inches, or 30.5 inches from the centerline of the valve to the edge of the weld preparation.
The
- geometry, of the weld preparation is governed by Figure 10 of Reference 3 (included here as attached Figure 1).
Reviewing the-drawing for the subject valves,-however, indicates that the actual end-to-end dimension is 59 inches.
It is not clear from this review what the original basis was for this exception to the design Code.
However, at this time,'the current standards governing valve design can be applied - to determine a t
less restrictive length requirement.
The 1986 version of Section III of the ASME Boiler and Pressure Vessel Code was chosen (5).
The design for the valve body is as follows:
e Per NB-3512.1,
" Standard Design Rules" are contained in 1
NB-3530 through ND-3550.
L l ~
e NB-3542 references B16.34 (6) for minimum body thickness.
l*
This standard requires a minimum thickness of 2.28 inches.
NB-3544.8 provides weld transition and contour requirements
('
similar to those required in Reference 3,
but does not provide specific requirements on end-to-end dimensions.
e NB-3545 provides -limits on primary and secondary stress to ensure that ba' sic ASME Section III safety margins are:
maintained.
arre a rrt ASSOCWESINC
-e
+
SIR-90-003 p ga 3 of 9-Page 3-January 12, 1990 T.
Pitchford RAM-90-004 Primary membrane stresses are limited by the body-neck crotch region, which is stated to be the most highly stressed portion of the valve-body under internal pressure.
The only effect of thickness reduction at the weld joint on this stress limit is whether the " area" in the pressure area method used to calculate crotch general primary membrane stress has been reduced.
Per NB-3545.1 (a ) ( 3 ) and Figure NB-3545.1(a)-1 (included here as Figure 2),
Lg = 0.5d - Tb = 9.16" 1
where:
L = the reinforcement limit along the g
valve body-from the outside surface of the neck d
% 24" T 2 2.R4" (average) b Per the attached as-built sketch (Figure 3), the length of full thickness valve wall available for "L " e@als 2-9/16" g
+ 9" +
0.5", or 12-1/16".
Therefore, 2-1/2" can be removed in order to provide a flat land for UT inspection, without violating the above L re@hement.
g e
Concerns regarding secondary stresses are again. focused in the. crotch region.
There is no apparent effect of valve end-to-end length or thickness of the weld ends in ~ these calculations.
Therefore, the modification described herein l
will have no effect on secondary stresses or the associated fatigue evaluation.
l It is, therefore, acceptable to machine the valve body per the attached Figure 4,
provided that a minimum length of 9.5 inches is maintained from the outside diameter of the neck to the top of the transition contour.-
l L,
4 SIR-90-003 p go 4 of 9
.h p
Page-4 January 12,.1990
' T.
Pitchford RAM-90-004 If you have any questions on the information contained in this 1etter report, please do not hesitate to contact us.
Very truly yours, ddskD R. A. Mattson
.R e
d 1
n
/
bY
- 7. ' ~C. RiccafdE1Tav' Approved by
- A. J),'Giannutzi
/'
Projenct Manager
/mc cc:
CPL-09Q Project File L.
s l
l ASSOCIATESINC
, N bs: -
l SIR-90-003 p;go 5 cf 9-
-h wLti:.1 j7 i
TELDNG E.CS i
t e
vo :a. st:.oNs - urts
/
ve'.4. st: ions -uc t J c.
h y
y'
[ VAR 3.0*! LINE wax 8.C*t LINE g
s s s
^ N e
e
's s N
'.---
- t :*
Ugsty-N 's %,u-
\\,
.,e f
%a.,..
l N,a
......m.
f - N **:'us 7
)
uns x -
l uanar.
L
(
.g.
- d. j i
t g
4 v "".., '.. lt.
y..
iH.,.a; i
u: ts" N:3'
- 2-I
9 i* t i
'It B
- . 3i.
no tw ->
a-FIG.9 rea wA;; Twi:<Ngas k' 34s *: 3a IN..
FIC.lo Foa wAU.Ei:MNE$$(t) GREATER TMAN 4/4 IN.,
IN0' V$ivt. rNsGt cN ga e:S vst wlTH pastog coNToga som ust wtTM spuT SACKING
$*.:i BACKING a:NG 08 WITe0wT RING 04 wtTMOV* SA; KING RING SAOKING RINO 1
e r
I.
e 60 %
}
r3:* w's l
p, 1,.. -r-[, y b
~.No---::wV, f\\
'r-e t
e l
4,4 1
.. v a: C ri wN C
.)
s
- 1 fj$
(
S NC*f:; f aN::
N n:rs: IaN::
t e,
p e
t I..
.1860.11 INSIOE CONT:ut 8:n ;J3E wiian FIC.12 IN5::E 00***0bR 8:8 VSE WITm TA854 EA:niNs REOTAboGg. AS $ A*AING RING RING A e Nemanel outenee saametee of welding ese.
R e Nemanei tae nee esennetee of pies.
C = A = 0.031 e 1.?$ t
- C.0 3 0 t a P emanos well sneeanees of piee.
0 c3: = Wesses tenerense on C er eine to AE*w Seesaficassen A104. etc.
- 1. *!
= Minamism tell of si n/?*. of nomano!==e13 (permittee ty A1TW Seesafiestion A10 4, etc.)
multie.es to =e to e saven into teems of eaemeter.
0.010 m Plus televense on caemeier (See Par. ?.4.3) i,t
' Nste 1 Runeut of a meanines senece to anaise diameter of volve Note a See Pet. 4.4 and ?.4 ter esteals ans tenerensee.
to neve sie eerwer enente in eestaen. ineaee naametee of veswe mov ee eithee larger er ese11er snan piee snease
- 4. emet e r.
Note $ % an. eem based en use of U. an. wise beehang nns.
I Nste 3
""he eviaise ar.e anease of enee of weaves one13 he es.
tences base in one menner withan the mesamum one Note 6 See Fag.13 ene 14 fee wending end estade of weisang munamum eleoe lanes andaestes. The tensataen shall be e nesa fleases.
l eneoe avoisang enere ee. entrant ens. e one setupt l
enentes in eseee. The eeefaae of the outenee senteur l
enell se se fuse nnee ey the manuieetwe6peevices soeve Note ? Fee samenesene see Teene it.
a sonettaene are met.
l U
i
y, SIR 90-003 -p;g3 6 of 9-3 y
W o25 3.
(f= sac 4 or>ec) '
j]
- l TEl. DING ENDS Tobie 11 (Cont's0 hensions of Weldin8 Ends (ke Fip,es 9 to 14 inclusive) j 1
1 2
1 3
1 4
1 5
t 6*
I 7
j n
l A
Nonanst th..
n eicing Ne.ckl Tending E.nd Pipe Site be.
l 73,ng,,i, y a},,, e, B8 C 8.'
t8 j
SO 14.000 14 1/4 13.250 11.305 c.375 40 13.124 13 15:
C.436 X5' 15.000 13.064 C.500 60 10.814 10.9 1 C.593
- t.....
8: -
12.500 12.646 C.750
.14 100 10.126 12.319 C.937 1 20 11.E14 2L046 1.093 1
140 11.500 11.771 1.250 16C 11.188 11.496 1.406 SO 16.000 16 1/4 15.250-15.303 C.375 4C 15.000 15.064 C.500 60 14.688 14.811 0.656 16 60 14.314 14.464 C.643 100 13 935 14.135 1.051 120 15.564 13.E:7 1.:18 140 13 124 15.44:
1.45B 16:
10.814
!!.171 1.5r 3 SO 1E.000 18 9/3:
17.250 1 7.30 )
C.375
- XS 17.000 17.064 C.500
)
40 16.676 16.575 C.56 60 16.500 i
16.646 0.750 16 6:
16.126 i
16.319 CJS7 15.956 1.156 1 00 15.688 12C 15.250 l
15.!!5 1.375 14:
14.676 i
15.::5 1.56:
160 14.435 l
14.64:
1.7El j.
- .000 20 5/16 19.050-19.503 C.5'5 X3 19.000 19.064 C.500 4.
1E.514 IEJ:1 0.!95 60 1E.376 1E.556 C.E1:
20 80 17.938 IE.125 1.031 100 17.436 17.717 1.281 12; 17.000 17.354 1.500 140 16.500 16.896 1.750 160 16.064 16.!!!
1.966 50 24.000 24 3/8 25.:50 1
25.303 0.575 XS 23.000 23.064 C.500 5:
- .576
- .S?!
0.56 4C
- .616 i
- .?*?
C.6E7 60
- .064 01265 C.966
., 4 6
1.564 01.E:7 1.216 10C 20.93E
- 21. $0 1.551 1 20 20.576 20.788 1.E12 140 19.676 2C.!50 0.06:
160
- 19.314 19.259 0.543
, An e.
- n..n. si w. in a n...
r.n.,m in..i....
n.c i...
.,,n.n.
v,..
J Deue=u.a. p.,4 nm. s nas c.ns vs As ass.ie af fin" * =a.a.: i. * *"* 8., s e.=.au.a.
i j
- -e e s..nu,e a c:
w...n....
xxs. t ca.si na w w m..u..
.., n.r.n.. n.one..n..r....
na.
s s ;eu u...
o t im sia : mc; Tn.aa...
., ri.ne i c..i.
nen : ta
...-m.
s F., i.i e.n...... P.s...
u.no m...n......... in ni n. e. -
,g,,,,,,,,,,3,n,,,,,,,,,,,,,,,,,,g,ng3
,n n..is...
n e m m in = i. = i......
..........n.., A., n. i... o. in. c.. o.,
- i. i..,
....e....a.
.n..
1 i,n..
1 i.
... e is.s.... u......ne....
.no.,n
- u.... i....,i,......ni.. i n.
si ne
.u n. u n. si.c
... u...n.r.......n m.
.... e i.in,ec. in.
un,.....suna.n1.
,....... i.
u.n en,
. e..
- ..n. u...t
.,,in.,,,..,.......,,......mn....
.n
. ni.n in...
.. m.....n.
in
. m..u..
, r..n... n in.::.. i.~
1,.e l
in.. i.
.u.n. F.e un.us.. u..s.a.ia..: m.nw.
- m.,. a ng....t. Hop. n... u..a n. J i. 1.
J 30
SIR-90-003 p2g3 7 of 9 l
fit o12 ar 1996 Edities NB.3000 - DE.51GN fi8 NB'3*dI l'**I i
e no.--
a
-o-l l
1
?u
\\ *k( L
'* 'e *~
A t
)
d h
f, q \\
A
- a ---+
l Y
y,,,,
j/
/
/
/
ty
/pN N r,
/
M h-c l
L
.-*\\a?*-
ini 7
I r,.-
EN t
- 2
/
3 %
==.
t L
Au
(
\\
'A P
~*
/
\\
(c) l l
f1G. NB-3545.1(abl FRESSURE AREA METHOD l
101 1
l l
a
...n--.=
.am'-
1 A%.s.
SIR-90-003 paga 8 of 9 J
A Fiwan. 5 4
7 i
_h t'/si,*
LI M *)
i Q 2.44c'-
T 9 4_.'. _...................,.. _.,,
i e
. g 1.,
- w. t.u'
{
I 9,g_.(,
?9'ei.*-1
.34 e'
, r,4 4
ir
...., 5.#-
_8 6
l
.l e
i l
i t
i OM i
\\/ALVE 1
I I
i s.
.J l
g e
C i 1
W &' 'Y
.I l
1, i
W 5
E e
g
.v-
Eii
~
(
. s SIR-90-003 p*_ga 9-of--9 n'r h
- L 4_
.s i
sp'
=
- c. '
'AeI -
[
~
- 7..
s to e.m.
.a g
g)t L O PmL*
N n
0 E.
1 i
c h
i t
.i l.ht&" u n d, TWic.KtJ L45
_ _ V4 W L E.D.
U l
4 3
L F $. f.
a b
1 a
D 40 WLVE I.
THlCAMES$
~
I l.
.,. ii
l RAM-90-009 pagi 1 of \\u i
i OdlRE 3150 Abneden Espreeewof.
Fossil Plant Operstmas
. Sune 226 January 31, 1990 86 South Maler Road Sen Jose, CA 96118 RAM-90-009 Sune 10
- (408) 978 8200 Abon, Ohio 44313 tuzx lean smuct (216)064 4006 fax (as)rtees
- rAx als>seSusi Mr. Terry-Pitchford
^
Carolina Power & Light Company 4
Brunswick Steam Electric Plant 1
Leonard Street Extension Southport, NC 28461
Subject:
Redesign of Area Between the RHR System Return Valves and Reactor Recirculation System Tees As-Built l
Reconciliation L
Reference:
Structural Integrity Associates Report SIR-90-003, Revision 0, dated January 12, 1990 i
i
Dear Terry:
J The referenced ' report (Attachment 1) provided Carolina Power &
Light Company (CPEL) with the technical justification for
~
reducing the valve body thickness.at the subject location.
The
. modifications' described in the report have-been implemented, and i
CP&L has forwarded as-built data for both the Loop "A"
and Loop "B"
locations (Attachments 2
and 3,
respectively).-
Mot:t
.I geometric. requirements - contained in the - referenced report were satisfied.
However, the minimum wall thickness requirement of i
1.388" was not met - at all locations.
Per - Attachment 2,-
the
. minimum' measured wall thickness for the "A"'RHR valve is 1.12* ;
i and.per Attachment 3, the minimum measured wall thickness for the d
"B"'RHR valve is 1.28".
There are also two. localized thin spots l
on the "B" RHR valve.
However, the minimum measured thickness at these: locations is 1.16",
and thus will not govern this as-built reconciliation.
In f addition,- the minimum dimension from the outside surface of the neck to the top of the transition contour (9 1/2") was also violated for the "A"
RHR valve.
- However, a more precise interpretation of the referenced report indicates that the actual j
requirement is ' 9.16" versus the 91/2" called out in the last paragraph on page 3.
Therefore, the 9 3/8" actual dimension for l
the "A" RHR valve is acceptable.
Regarding the thickness reduction, it is stated in the referenced report that the maximum stress ratio at the location of interest is 0.511, which equals the computed strest, divided by the
..7 allowable stress.
This stress ratio is based upon the minimum pipe wall thickness of 1.388",
and an outside diameter of 24.346".
Stresses in the pipe are a
function of its J
RAM-90-009' pnga 2 cf 18
?
-Page 2 January 31, 1990 Mr. T. Pitchford RAM-90-009 cross-sectional area and section modulus.
For the as-built dimensions of 1.12" thickness and [24.346 - (2) (1. 388 - 1.12) )
=
- 23. 81"' outside diameter, the - as-built area is 80 square inches i
versus the designed area of 100 square inches.
The minimum as-built section modulus is 433 cubic inches, versus the designed j
value of 544 cubic-inches.
s The computed stress ratio in the as-built configuration is, 4
therefore, less than or equal-to (0.511)(544/433) = 0.64 This is below the maximum allowable stress ratio of 1.0.
Therefore, all stress criteria! are satisfied for the as-built configuration;. and the geometry shown in Attachments 2 and 3 is acceptable.
A detailed calculation package documenting the reconciliation is included as Attachment 4.
If you have any questions on this letter, or the attachments thereto, please do not hesitate to contact us.
It is suggested that this-letter be filed with CP&L's records pertaining to the RHR and_ reactor recirculation systems.
Very truly yours, R.
A. Mattson R
1, by:
f Approved by:
/
t 5s
/
P. C.
RiccardelTa A.
. Giannuzzi
/~
Pr act Manager
/33 cc:' CPL-09Q-102 CPL-09Q-401
[
i.
> e :.
se
- A Ibc
RAM-90-009 pSg3 3 of 18
^^
. g, g.
I F ri 4
)
W.
M hhWW_
M b Operatons
. 3140 Almoden E.
a, Suin 226 January 12, 1990 I6 M h Rood.
Sea }ose, CA 95118 RAM-90-004 Sune 10 h OW 44313 j
(408) 978-8200 SIR-90-003, Rev. O mzx isen muer (216) 064 8886-1 ru res)rsom ru me)unes 1
.]
Mr. Terry Pitchford Carolina Power & Light Company Brunswick Steam Electric Plant Leonard Street Extension Southport, NC 28461
Subject:
Redesign of Area Between the RHR System Return Valves and Reactor Recirculation System Tees
References:
1.
" Design Report - Recirculation Piping -
Loop A and B - B31.1 Power Piping Code",
i General Electric Company, Revision 0, October 1, 1985.
h
- 2. Carolina Power & Light Company Drawing No.
l 0-FP-06014, Revision A, January 18, 1989.
Flanged Fittings", USA Standard.
- 4. ASA B16.10-1957, " Face-to-Face and End-to-End Dimensions of Ferrous Valves", American-Standard.
- 5. ASME Boiler and Pressure Vessel Code,Section III, is E
1986 Edition.
L
- 6. ANSI B16.34-1981, " Valves - Flanged and-Buttwalding-End", American-National Standard..
Dear Terry:
Carolin'a Power Light Company (CP&L) is undertaking more extensive in-service inspection of the reactor recirculation-(RR) and' residual heat removal (RHR) systems at the Brunswick Steam Electric Plant, Unit 2, in order to comply with the requirements of U.S.
NRC NUREG-0313, Revision 2.
In order to ultrasonically (UT) examine the weld between the reactor recirculation system taas and the residual heat removal system return valves, the valve bodies must be reduced in thickness at the weld location in order to provide at least a
2-1/2 inch
" flat" land for 3
manipulating the transducer.
Structural Integrity Associates (SI) was-contracted by CP&L to provide the technical l=
justification for reducing the valve body thickness at this
-location.
The General Electric Company (GE) performed a reanalysis of the RR system in 1985, and documented their results in the Reference 1-' Design Report.
Although the purpose of the GE Design Report W
mi
-.i m
.a m
'?
RAM-90-009. p2g3 4 of 18' 1
Page 2 January 12, 1990 T. Pitchford RAM-90-004 j
was to qualify the RR system, it also provided stress information
)
at the location currently being evaluated.
Per Figure 14 (1),
nodes 769 and 509 (Loops A and B) are of interest herein.
Pages-1 234 and 283 (1) report the maximum stress ratic., (i. e.,, computed j
stress / allowable stress) for all reported load combinations of O.511, with a modeled thickness of 1.388 inches.' Therefore, if a wall thickness of 1.388 inches is maintained, modification of the GE Design Report is not required.
Drawing number 0-FP-06014 (2) provides a general arrangement of the valves to be examined.
Per note number 1, they were designed to B16.5 (3).
Since the Reference 2 drawing was initially issued in
- 1971, the 1968 version-of the standard is the
" Code-of-record".- Reference 3 furt'aer references B16.10-1957 [4]
.for face-to-face and end-to-end dimensions.
These two documents, therefore, form the basis for the original' design of the valves.
Per Reference 3, Table 27, the minimum thickness required is 2.28 inches for the 24 inch 900 pound gate valves.
This'is confirmed per the Reference 2 drawing, that states "2-1/2 min. wall (2.280 min. wall USAS B16.5)".
Per Reference 4,
Table 5, the standard end-to-end dimension is 61 inches, or 30.5 inches from the centerline of the valve to the edge of the weld preparation.
The geometry of the weld preparation is governed by Figure 10 of
' Reference 3 (included here as attached Figure 1).-
. Reviewing the drawing for the subject -valves, however, indicates that the actual end-to-end dimension is 59 inches.
It is not clear from this review what the original basis was for this exception to the design Code.. However, at this time, the current standards governing valve design can be applied to Catermine a less restrictive length requirement.
The 1986 version of Section III of the ASME Boiler and Pressure Vessel Code was chosen (5).
' The design for the valve body is as follows:
e-Per NB-3512.1,
" Standard Design Rules" are contained in NB-3530 through NB-3550.
e NB-3 542. references B16.34 (6) for minimum body thickness.
This standard requires a minimum thickness of 2.28 inches.
e NB-3544.8 provides weld transition and contour requirements similar to those' required in Referenca 3,
but does not provide specific requirements on end-to-end dimensions.
NB-3545 provides limits on primary and secondary stress to ensure that basic ASME Section III safety margins are maintained.
O aa EELNa URIAL N
ASSOCIATESINC
i RAM-90-009 pag 3 5 of 18 j
e l
Page 3 January 12, 1990 T. Pitchford RAM-90-004 o
Primary membrane stresses are limited by the body-neck crotch region, which is stated to be the most highly stressed portion of the valve body under internal pressure.
The only effect of thickness reduction at the weld joint on i
this stress limit is whether the " area" in the pressure area method used to calculate crotch general primary membrane stress' has been reduced.
Per NB-3 54 5.1 (a) ( 3 ) and Figure NB-3545.1(a)-1 (included here as Figure 2),
L = 0.5d - Tb =.9.16" 1
3 4
k=thereinforcementlimitalongthe where:
valve body from the outside surface of the neck d 2 24" T 2 2.84" (average) b e-Per the attached as-built sketch (Figure 3), the length of full thickness valve wall available for "L " equals 2-9/16" g
+ 9" +
0.5", or 12-1/16".
Therefore, 2-1/2" can be removed in order to provide a flat land for UT inspection, without violating the above L requirement.
g e
Concerns regarding secondary stresses are again focused in the crotch region.
There is no apparent effect of valve end-to-end length or thickness of the weld ends in these calculations.
Therefore, the modification described herein will have no effect on secondary stresses or the associated fatigue' evaluation.
It is, therefore, acceptable to machine the valve body per the attached Figure 4, provided that a minimum length of 9.5 inches is maintained from the outside diameter of the neck to the top or the transition contour.
maasAfauuRI.
N ASSOCUJESINC
- ~
RAM-90-009-pag 3:6 of 18
-Page 4 January 12, 1990 T. Pitchford RAM-90-004 If - you =have - any questions on the :information' contained in this letter report, please do not hesitate to contact us.
Very truly yours, R. A. Mattson R
e d
j JA Y
P. ' ~C. Riccafd611aV' I
Approved by:
^! '-:?d$'
A. Jf, 'Giannuz zi.
/'
Proyect Manager
/mc cc:
CPL-09Q Project File -
1' l.
l t
l 1
) r* ;i se IWA INC i
l-
(-
e RAM-90-009 p g3 7 of 18
-I Z wk L I
TILDING ENDS
(
es 4.(e f ve'04. st:*;oNs -u: t J vo :Aw st:*.oNs - vet J j
h y
y,
- AE !.i *1 ' 54E wa 560*t LtNE qs e
i s
s r
's
/
.e
\\
s N wc* s '.
e e
y k "'N "8 8Vs e
e a
e e
inam ac*-
[
uas 2:e.
l
'j t
't i
(
%.,, r -
- I e.
-t j
A A
i
~'}'
ijt-r@2[
j N:?tJ.' # du: J E*2*
I
,,* T ~l l'
i l
f.
'It B
hC*tt:Idu0J e*
.l,, 8 5,,
f 1 t
t i
FIG.9 8:n wag eu:<Ntss(. 3A ": 3; IN.,
Plc.ic poa WAD.EiOxNEss(t) Gatcra %AN als iN.,
I iNO '.'3tvt. INS:{ ::he?
.,8 8 8 J$t WI7i'i INSIDE OQN*O'JR 804 US[ WEm $9;,l7 gAGKING
$8.:* 3a:<sNcaiNs :p wt?m
,,t asNG om wiim g? 3A KING RING
- .8
~ * **
bA:nINO Ate.0 e
?
l r
ke 4
C
\\
l 3,
-:==
e e
h,T' -l -
7
% .A- ~--
e.
i\\
I l
e i..
e-I
, - 3. s \\%n* M y
j C
C
.3,
.. w.
n: n. us:?
\\**=2 221si i l
V
"=!2 i
~CT!!: i.Lv:.'E js t
{
e t
.gt t
t
?
i DIG.ll INS':t 0 NT 'JS * *3 'Jst w1*m Flc.12 Ns::t ::NTO'.,8 8:8 USE wtia TAPER BA:<iN3 RF. Tares., As 3A AiNs a:NG AiNG a = Nemmes emeise eine eie, et..ieing ens.
m = Nomines insiee e emete, et eien.
C e A *0.038*1.?3t*0.010 t a Semanea een taaseneet of oise.
C.031 m Manus tenerense en 0; et esee to As u Sooeitteetten A104. etc.
1.*3
- Minemum sell et at L/:*. of nemene. well tooemittee ey ASTM Speeatheetten A104. ets.1 multie.ee os two se essveer anse terwe of eaemetee.
0.010 m Pinne toneeense en esemetee C (See Pet. *.4.31 i
Ntee 1 Runeut et a meanines suneee to anesse elemete' of *elee Note a See Poe. 6.8 ans ?.4 fee setene ens te.ecenses, te nave no eseuse sannge an eestaen. Insiee aimmetet of weave mer me entnee Larger se smauer than see inease Note S % in. sesta seees en use et % an. usee seemans ring.
g,.,,,
Nste 3 *he outease one anesee el ense of volves enell be es.
tensee mees in ent morewe witaan tne mesamum one Note 6 See Fig.13 and 14 fee =eising one seteue et te.nq manunum etese lanes in44eates. The tronettaen anell De e mees flanges, enene eessaans ensee ee.enteena one.ee one serust enseiges na steee. Ine oestaae el sne outease sentout ene&a s es tum.enee er the men.deetude soevisee neees Note i For samenesene see Tasse :
eenettaene see met, n.
ee m
~
s RAM-90-009 p':g3 8 of 18 NcEA:. 3.
(f sx4 etC)
T'II. DING ENOS I
Enes (See Fi vee 9 to 14 inciviive)
ToWe 11 (Cont's') Dimensions of Woloin8 8
I i
2 1
3 1
4 1
5 l
6' i
7 3
l A
Noaans)
.. s !teliing Necirl tending.T.nd Se.nn u p!p, s;2, N* -
l Tist.g e r'.* l Valves '.*
l' C '.'
t8 SD 14.000 14 1/4 13.250 P 3C3 C.375 l
40 13.124 13.15:
C.438 1
.X3
!!.000
- 3.064 C.500 6
1.t;4 12.f:1 C.!r3
{
- 1.....
80 10.500 12.646 C.750 j
14 150 10.126 10.319 C.f37 1:0 11.E;4 1*.046 1.093 140 11.500 11.771 1.250 160 11.188 11.496
.406 SO 16.000 16 1/4 1*. 50 15.303 C.375 i
4C.
15.000 15.064 c.500 -
60 14,688 14.811 C.656 16 80 14.314 14.4&4 C.843 lo:
13.E38 14.!!5 1.031
- 20 13.364
- 3.t:7
- .:Is 140 13 ; 4 13.44:
1.436 16
- .E 4
!!.'.71 1.593
- 7.3
- 3 C.375 SO-
- i.000 18 9/3
- 7.050 XS 17.000 l
17.CB4 C.500 4:
16.576 l
16.975 c.56:
l 60 16.500 l
16.646 C.750 1$
8:
16.;26 i
16.!!9 C.E37 10:
1*.685 15.F56 1.:56
- 0
!!. 50 15.!!!
- .375 140 14.576 15.:05 1.562 i
160 14.4 3E 14.54*
1.7El 19.303 I C 3'5 SO
- .000 20 5/16
- 19. 50 i
X3 19.000 1
19.064 C.500 6C l
1E.376 15.f::
0.593 j
40 15.S14 i-12.!38 0.S;:
20 8
j.
17.938 1E.!!5
.031 100 17.436 17.7;7 1.251 17.000 17.334 1.500 1
140 16.500 16.896 1.750 160 16.064 16.!!!
1.968 SO 04.00C 43/8
- 3 :50 1
23.303 C.375 X5
'3.0 00 l
03.064 C.500 30
- .576 i
- .f75 C.56:
40
- .6:6 i
- .?$7 C.657 6C
- .064 l
- .:f!
C.968
.*4 8
01.564
- .E 7 1.218 100 20.f3E 21.230 1.531 1
- 0 00.376 20.785
- .S;;
140 19.576 20.!$ 0 1.06:
i 160 10.!!4 19.259
- .343 ane.=a aa.
- .... u....a.
n.
- s. n i.,,
,a..a....
(
's. nea.u.a....e..a ia sa.....
A, w. s nas c.a..s4s an.no
- '84 a= a un *: a u m2 aa te : r.'ea==
.a m.
.....c m.
ei.
- -e. si.a..,. s:
w.
xxs. t me. sw.as.;; :
a....
n.a iio..
...: m..u a
.a..:....
- u. t. si,u s o u: :n.n a...
., ri.ne.. s.. c sa.a un : ia m. ins m u.au iaa.a n,..am u.. in.
.m....,,,,,,,,,,,a.,.,,...a.3 F., su ma. n... p,..
'.*.*.."."..*n*.***i.'.'.'.'i."uc.'.ii===.""'
- '****a
a ai....a m.
..ea. ne mm iam i. a.
i.
....a a i s.s. u = u......=....
u....,.. u i=..
.ai a iu.u s a.
.. e e a.....e.... na m.
..i.
. sa. c :.: m..u a m.. s.a.,i r.
u n.
.n.a.. u.u m.a,
- i..au.a
...m........t i.
in
...,saa.a.....,,.......a in......
... me..n m. w a.
.. me....a.
.a
. in....... r;.a... ii.u::
i l
ina i..,. s., a... u......;
.a.
- a.... u. u... u.....a. a i...
3C
l l.9.
RAM-90-009 pag 3 9 of 18 i M G.k.
C.
g gg N3 3000 - DES 10N Fig. NB.3W,ita 61 r
l l
> a -=
l.
l L
I I
hp
- i ---- a 2'
s v
_Y/.,
/
s'->
/
N tu jf T,
f Am1 h/
~
/
At2 i
f1 g
N<
/
s a
-a M 'A Y I
~~1 e
ini m
r r,.-
rg Ln e
+
t A
]
/u.A 7'
...a.....
v
(
cononion.
N'NY i
i
- L, 4 *-
h tci
- FIG. NB-3545.1(a).1 PRESSURE AREA METHOD 101
(
RAM-90-009 p g3 10 of 18
- 4' a
s Fic=uma. 5 4'
i g
)
L s
oA.,
25;.
~..ue 4
T g 4.
.. 95' -
- 5
- i c
w.1.sc L.
.,,I
........,vg_,4,
- 9' ei +-?
.S.*
i 4
s
..e, -
.m c.<,--
_3 l
L e
Y'6 f
E.
o T::<-
l l:.
r.
AL E l
I l
l l
l /
~.
.u w,
.I l
l i
9 5
g l'
e
q
=
q RAM-90-009._p g3_11 of 18:
4 k.
1 b
mm E
- /d 0>.
r.
LD rank eE gjt um PaE?
Ts "i'
h
.NN 3
i 4
i 16 l
l IM F,
,i l.h M ". bald.
T%4 c.KeJL55
~
\\
_ _ V6 W L E.D.
d s.
4
$~
~
i m
kt e,
h j
-i 0
4D wuva 4
Tb,4 tc.E6J WmS$
f I
9l i
RAM-90-009. pag 3 12 of 18
'h,
.d
~ J
' PAGE 20F1 FIELD REV 4
.A C
'9" 4
P
, M Q"i;;
i A
- MACHININC DETAILS FOR, W EHR. VALVE S - 90 '
PNsE NO. }&7 A tra,cuveu r_ 2
\\
=
A
=
l (l
,Li f*
[
j
=
=
v MA N
I 7-r.
e s
9
,./ p; 1/t"j
= =, -8/t*
lTHICKNESSES TO BE TAKEN + FLOW AT THESE LOCATIONS "0"
TRICKNESS READIN65 0T f[hgfgg6 I PREUM (STFP 9.5.B1INTER ($TkT 9.5.5)FINAL (STEPS.S.if C
i utan eusntn,upmm Icuenen uP!mtM CN9MH OM/M EN(alMEER TD O' lico " l 2.sr N/A i /. 9 / '
/. 4 -
@ETERMINE ACCEmblLITW 90' 3. w 2.2,"
N/m
- f. t "
/. vp
/. 33 0F FINAL *5' A 'C' O(MEN 610N6.
tar y eo-2.,e'-
y/a 4.c5"
/. o A s.2 Wtt.eu" 2. se
All A \\ *?.d I t. o 1.12 DIMEN5 IONS DIMEN610R DE6thN ACTUAL TAKEN SW/9 ATEINSTR. ND.
CAL VCE OuG M T 9s
- g f f f,,,,,,
d g g / p%/4 A
9t/t MIN.
e d/A,M d/@ d/d D
l'It' (E)
/h" 7//[-a.r.,o C.
Zw' ($) 'j $
ffg f-u.,e td/AD d/A@ d/@
L. L wtt y[
/_Z 29'ti 3-gg.,,
4 #de n/gp a/tig#
1
RAM-90-009 pags 13 of 18 Sutt? NO.
6ENER AL $ ELEC7RIC wAu TmCnNess rRoma ener een.we Projoet SYSTEM #d8 WELD NO o, 8,.pouw auom l
N#
UT Eneminetten Date Sheet No.
eN ese
\\
- Weld Edge h
Record Thicknots Measurements As Wold 7
pontorlig Indiested, including Wold Width,
- 1.5,,
> t.5,,
Edge-To Edge At O'.
is 3
i
.n p Positlen O'
90* 18 0* 170' p@
.L
/.3a t..% u.a /.td I 'id8 $1de 28 $1de i I.)
/w.
1.vs /.r.s n.e N.E.S
}.dB 1Rh lau
- 1. hh h
/
}
- 1. /J
/. /t
/h
/.Jef FLOW E
u.a see 1.nL M4 CROWN HEIGHT:
DI AMETER:
N" CROWN WIDTH:
- 1. 3 M "
WELD LENGTH:-
W
)
r......
. _... _ _._1 -..-
m
.. J
-r_
[. y....
. S.,
.. J. u.
g j
1 1
............ ~ _. _ _..
1 1
j
.. =......
I EXAMINED eY:
REVIEWED SY; C REVIEWED DAreaoveo
- C2A DATE 1 J t".
9e DATE DATE a
PAGE OF
q s
RAM-90-009 pag 3 14 of is st v tv: E::e: : :.t:
- -n.io : n:ct
.;;st sp.ussw::4 stis;.
4 ggyggen, g ij r a N r r o o. m e m.'
n
.D A _
_ A S,,,_:,_:,_,
,J
,m
.J mo nt nito m
+
MACHININCs DETAILS FOR'B' RHK VALVES 110' PAfsE NO.
E PA i
c.
AdacAmer 5 l
t
=
A
=
i 1
_d1
.[
=
=
{
=
w -
u l
T f
4 c=
1/t*
1/t*/
./
I l
I TEKNE55ES TO BE TAKEN
& FLOW AT TW.ESE IDCATl0N6 NOTE 7H.lcXNESS READIN65 IrEEUM (5TEP5.3.5)!!NTER ($iF9.S.6)FINAL (5TEP9. Sill
}kE N
OT t
- ursiv. I ewer. l uM3m Icwan upmn cMmtM OM/M EMSINEER TD 0'Ia rw' I2 u"i N/A I.u" A44'
/e'_
@ETERMINE ACCEFTIBILITd i
i-90'I s e" 1 2. sc~ l w/A i i, u"
/. 4v'
/. y 0F FINAL 'B' A 'C' ClHEHil0NS.
l.
Lh%.c e "
1.c o
- I MA l i., r "
- i. u*
i.tr# _
L'% w" 12. c.1" i N/A l i.n "
/. u'
- i. n "
i OlHENSIONS L
DIMEW10R CE616N ACTUAL TAKEN BW/9 ATE INSTE.NO.
QAL VK!1E DilETA l
k 9 tit" HtN.
/c "
[/ f l $0CA
$#aA h b
1'It' (N N I / h ~
Wf//d* &*d A
&!4A
$# dA C
241' (!W
.2 k "
f f f % s g 4-
{%^*ya fi$ y; I
LL M* 11 ?ff?f)
, )+, _
_ h Jg
,;4
- 4. 2 29*tt 3c*
f//fgpS**b f
jb
g..
RAM-90-009 pag 3 15 of 18 entti no.
3 SENERAL $ ELECTRIC WAR THICMtSS PMFRE $NF.ET TNoject
$YSTEM 8 M WELO NO I f,gked 2 f -
m on,oene Pouw 6 m
$!'es' aw!sse UT Esemination Date Sheet No.
- Weld Edge
)
u Record Thiekmees Wesouremente As
,,ig Inele644,incluttng Wold Width, Centerline I S,,
2.8,'
4 tage*To *Rege At O'.
4 vA*
m eition o* I err isos a70=
'ei h
r A m
h D
std r a su se M ais.
E side i se ia
,n
,n 1'
j y
.n ra su" 1n oss r. n y n, j
J re
,u i ne 2
t CROWN HEltHT:
r1ocu DIAMETER:
Ik" 5
- 1. I "
WELD LENGTH: 7I CROWN WIDTH:
l f
\\ih hk )I#
P
)
i 1 t 8
GV N
N 4t6 s
1 I
l Ve part /-11 9 d Datt SATE past or_
1
RAM-90-009 paga 16 of 18 i~
~
l I
W
.s x
e m
1
/-- 1_
=.,
)
~
\\
m 1
t s
\\
\\h
~
w T
t ti ij
- h l
gN I
E 1
Y
' e-.
- c. t n
~
i i.
L t
l' L
RECEtVED JAN :: 01990
Il,
!li11l e
gt$$
2' n :: *-
e jI 8i +
ss !.
je &'
S" s1>l
,i y i > !
eo 0r.
- e. l ts N, JJ
.e,
- I 5
ee
" E JJrj p
Rb!
3 i
. 4s;Y
,i' e g-i, k Aa:h at, s1QAj.Ar e.
4 r I
" e g K ]" p <l j 6 -}
E y$.
is ot,k, i
f1 L {.
eeQej
)
he1u hi 1s{-
r-gs l n k v p' d g g.g.
ao,i 4
4 f. ea8
^f l
gs e,
,te 1l'3.
d14
- sf O bl 4 e[ i e
ivi $q
,, J!
.i e}*g1p g$g 4 p
<a;
'E-v'
,s 4 t f,,g c t [ 2o 1
dy 7,
i
'. if 3ol of6$.
f b4 e
2.on 324. g[f flil' k
>5 J a;. nj3 ig 1e ee sd$ ~
s i3 t
i 03teti
"_ o
,-l l
ll flll11 l
7-RAM-90-009 paga 18 of is L.-
i t-i; MWuidt. "I"* :AT twt A4- %)iLT R m M-TW a. 6Axs Tur.:oe. Deu.ais,te:L A.s y a e, As-ma.tyez := P'e n s T4er. smap.i= =
Diwt cus WtLL Wau the6 e cm n(
^ ' " ' ' ' It.) TMicas.AJeett, o m.t T.Jit.A. 7Wer.
- c.. m. = L(. M(. - (2.[tA6S-1.\\1.)
- e..st-THe. MhJM MenkbJ64cD WW L. *iWr w.csAb 15anck 4.1 1.
N a. A % - Ib a l b y M ic ig y g h MD SQ ML6.JN Aag, T 4 N 'J.ada Susai4 - M t> 4M
- 4 Q.mpdq,
8 T,-4: gen.t a oA t-k *>Gr=l A m W T> 9e m l!>y 14:e36&auM AS - NJiL.T A2.esth. ** I c an / S o = \\. Q l'..
Wkg=.% m. 3,26, TWh. 55,C.Tema MotA3W% hra a.
i D e * ~2M, Mtr. kkkW4AA N&I" <Tianis*
L G2An. p x TMch A5. - Rai u.7 s-(w.ac Teste. 4 C :
I 6.P.*(c:2. G 1 I/J 4 4.c 8.4.1
- cm. 6 4 l
s.. u. v i s v u s e.
is e r m t.
, me A s mL att y (rad 6 f.,sa.Anw ts Am h*=.O J'4aK d $'i%t.l&5.'s
$ % D PawdT".
+
e a,p. red by R. A. Am t si / +o i
Checked by 0C OCt4R M u i.$1s46 g
Fde No d-I\\*C N "d et Page 7.-
of "E
p
N,.', A!M= -, -
I'.
ff(,., " -.
- -j. ' t.k. '
i 4.- _
4,
~
. q-m,.
t, t s
m?9 4
i
's 7,, [
- ~
- M _, L. a;
^*
1
[.
, ew q p _,,
- g ww.c a-x,
8, ec8m g. a.:1!, "'
. ENCLOSURE'4-
.e, m
<n v a K9 l
's_'
h'~
t
} 'l n.
e e
m; i
. BRUNSWICK STEAN ELECTRIC PLANTi UNIT 2-L.~., H s
1 F
3
'6..
NRC DOCKET'50-324
- g.
M
-R
' OPERATING LICENSE DPR-62'
.,..u v
.c c
H
.,r..
IGSCC INSPECTION RESULTS - REFUELING OUTAGE 8-
+m,.
p
) h, k'.-.
p
-'i-AFFIDAVIT - SMC O'DONNELL & ASSOCIATES,:INC.
a, k~
t
s
+
3.
i i 4
- {.
r
' f. '
.,,u..
1 0 '-
r
.t^
i
+
,q ;
+
)(
+
~
a j C r
.(.$ t i
s_..
1
=_n_
q ;w+
51 p
k.,'.,
i.
I k
)
- tQ.hiI
{
~
/.
+
k k
..'i
,; V:.
t.
.= ;
.)
4 2
.R;-
.)
..'Mj
~ N ', @ '.
t s
es 1..
M E
S 5
'_;(y i
r k'-
I k.,.
e w
}'
,r..
(. '..
.,4 e,
s u,s 5 ' 5 '
!. [;..,
,e
()%
t u
- ,. g;v v
ge m W.-
e
lD.
~
[ 'c -
I i
i>
i
/
COMMONWEALTH OF PENNSYLVANIA )
COUNTY OF ALLEGHENY
)
S.S.
j r
Before me, a Notary Public in and for said Commonwealth, appeared Manohar
~'
L. Badlani, to me known, who, being by me duly sworn according to law, deposed i
as follows:
4 S
1.
I am the Vice President, Engineering, of SMC O'Donnell Inc.
(O'Donnell"), a design and analysis firm doing business at 241 Curry Hollow Road, Pittsburgh, Pennsylvania 15236.
I am authorized to apply for the withholding from public disclosure of the information discussed in this Affidavit.
2.
This Affidavit is made in support of the application of 0'Donnell to have the materials, documents and information described in paragraph 3 (hereinafter referred to as " proprietary information") withheld from public disclosure and treated and protected by the Nuclear Regulatory Commission as trade secrets or confidential and privileged commercial information.
This Affidavitismadeinconformancewiththeprovisionsof10CFRf2.790ofthe Commission's regulations.
3.
The specific matter which O'Donnell wishes withheld from disclosure is identified in Analytical Verification of the Mechanical Stress Improvement Process for 12" Recirculation Inlet Nozzle, 2058-412 001-01; Training Program s k
2 i
Mechanical Stress Improvement Process at Brunswick Steam Electric Plant, 2058-200-001-00; Field Service Procedure Mechanical Stress Improvement Process at Brunswick Steam Electric Plant, 2058-200 002-00; Engineering Procedure Mechanical Stress Improvement Process at Brunswick Steam Electric Plant, 2058-200-003-00; all prepared for Carolina Power & Light Company, Southport, NC 28461-0429 and dated November, 1989, which are intended to be used in the application of O'Donnell's mechanical stress improvement process ("MSIP") used at both units #1 and #2. The proprietary information has great value and potential for use in the nuclear power industry and in the power industry in i
general. O'Donnell has expended much time and money in the development, analysis and testing of its mechanical stress improvement process.
The cost of development exceeds $4,000,000.00.
4.
The proprietary information is of a type customarily held in j
confidence by O'Donnell and not customarily disclosed to the public.
O'Donnell has a rational basis, described in this Affidavit, for treating the proprietary information as confidential. The information in the reports identified above have been treated and protected as confidential proprietary matter. All drawings, pictures and correspondence have been clearly marked Proprietary.
Contracts with clients and suppliers have provided for this protection and signed confidentiality agreements were obtained from these parties.
5.
The proprietary information represents the professional engineering product of 0'00nne11 and is entitled to protection from public disclosure under trade secret laws and Commission regulations.
6.
The proprietary information in the subject reports are labeled Proprietary and are being transmitted to Carolina Power & Light Company so
3 6
that they may elect to transmit them to the Nuclear Regulatory Commission in confidence;andunder10CFRf2.790,thesedocumentsaretobereceivedin j
confidence by the Commission.
7.
The proprietary information is a product of the engineering experience and judgement of O'Donnell and its staff and constitutes valuable commercial assets of O'Donnell's employees. The proprietary information is not known to any O'Donnell competitor and is not available in any public 4
source to the best of my knowledge and belief.
8.
O'Donnell has invested hundreds of man-months of engineering effort and has spent or committed in excess of $4,000,000.00 in the development of MSIP.
This is a very significant investment for a fira whose annual sales are of the order of $8,500,000.
Confidential possession of the proprietary information is an asset of O'Donnell and gives us a commercial advantage in selling the MSIP applications described in the above identified reports.
I Public discicture of this information would substantially harm O'Donnell's competitive position since O'Donnell's unique background of theoretical and practical experience in the nuclear design analysis and testing field and in MSIP technology have made the development of the MSIP service business possible.
If this information were publicly disclosed, it would enhance the ability of 0'Donnell's competitors to design, analyze, verify, sell and install the aforementioned technology without commensurate expense.
- Moreover, the proprietary information may contain patentable ideas for which patent protection may be desirable. Any such patentable ideas are entitled to protection against public disclosure.
9.
O'Donnell's competitors could only acquire or duplicate the proprietary information with difficulty and at significant expense by J
p u
Io 4
performing the same type of development effort including the full scale test program as has been expended by O'Donnell and by investing similar sums of money.
If the proprietary information sought to be protected was publicly disclosed. O'Donnell's competitors would have the use of that information g
without having made any payment to O'Donnell for the right of such use and could undersell O'Donnell in offering similar services to potential customers.
10.
For all the reasons discussed in the paragraphs of this Affidavit, O'Donnell would be harmed by any public disclosure of the O'Donnell proprietary inforuation.
Any further deponent sayeth not.
AM4W[%
u Manohar L. Badlani, Vice President, Engineering Sworn to and subscribed before me this 12 day of February, 1990 44L W
~
Q[/
Notary Public D
NoUra, sell
~
Line M Ti*y,Nowy Putic Pleasant Kk bo@,/Jerenycounty My Commes on Er;ces JJy 27,1992 Merriber,Pennsylms AssocabonolN:tcies
~
'