ML18100B156
| ML18100B156 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/20/1994 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NLR-N94114, NUDOCS 9406280152 | |
| Download: ML18100B156 (13) | |
Text
, 1
- ' j Public Service
... ~.* \\
1 Electric and Gas
!__ Company Stanley LaBruna Public Service Electric and Ga/company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering JUN 2 0 1994 NLR-N94114 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
GENERIC LETTER 92-01 SUPPLEMENTAL RESPONSE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In its letter to Public Service Electric and Gas (PSE&G) dated April 21, 1994, the NRC identified two information requests relative to the Salem Unit 1 and 2 Reactor Vessel Structural Integrity program.
Specifically, the NRC requested that PSE&G provide a schedule for the submittal of data to either confirm that the upper shelf energy (USE) at end-of-life (EOL) is greater than 50 ft-lb or to provide appropriate analyses if the projected USE at EOL is less than 50 ft-lb., and that PSE&G review the accuracy of the Salem Unit 1 and 2 data compiled by the NRC in its summary data file.
With respect to the first request, this issue was addressed by PSE&G in its December 1, 1993 response to an NRC request for additional information.
In this response, we described the methodology used for establishing generic initial unirradiated USE values to be used for certain Salem Unit 2 vessel welds.
At that time the acceptability of using generic USE values was under discussion between the NRC and Industry, and PSE&G committed to monitor the resolution of this issue as those discussions proceeded.
At the present time, PSE&G plans to participate in the utility funded Combustion Engineering Owners Group (CEOG) program for developing initial USE values for CE vessel weld metals.
The planned effort is to include technical justification for.th_e _USE _values__ that_ are dev.e_lope_d_. __ Based _on __ the c_urrent _
schedule for completion of the program, PSE&G expects to be able to supply the requested information by December 1995.
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Document Control Desk
- NLR-N94114 2
JUN 2 0 1994 Relative to the second request, PSE&G has reviewed the information in the reactor pressure vessel summary data files for*
Salem Units 1 and 2 which were provided in your letter of April 21, 1994.
We are in agreement with a majority of the information.
However, some information is inconsistent with the information we have, as discussed in the following paragraphs.
The Salem 1 Summary File for Pressurized Thermal Shock reports the copper content for intermediate shell B2402-2 as 0.34 w/o.
However, the value should be 0.237 w/o (or rounded off to 0.24),
as reported in our letter of August 4, 1993.
The Salem Units 1 and 2 summary Files for Pressurized Thermal Shock include chemistry factor values.
We are in agreement with all but two of these values.
For Salem Unit 2 intermediate shell B4712-2 you have listed a calculated value of 97.677.
our calculated value is 118.15.
This value was calculated using the fluences and ARTNDT values from the three surveillance capsules that have been removed from Salem Unit 2.
The fluence and corresponding ARTNDT values used were 2. 75E18 and 70 ° F, 5. 50E18 and 95°F, and 1.07E19 and 125°F.
Additionally, for Salem Unit 2 axial welds 2-442 you have listed a calculated chemistry factor value of 194.89 and indicated that it was calculated from surveil*lance data via procedures described in RG 1. 99, Revision
- 2.
It should be noted that the weld metal in the Salem 2 surveillance capsules is not the same heat numbers as welds 2-442.
By using Table 1 for weld metal in Regulatory Guide 1.99, Rev. 2, we calculate a chemistry factor value of 191.1.
The Salem 1 and 2 Summary Files for Pressurized Thermal Shock include IRTNDT values.
We are in accord with the five weld values listed as being -56°F.
We are also in accord with the value of 12°F for Salem 2 intermediate shell plate B4712-2 and with the value of -40°F for axial welds 2-442.
However, for the remaining eleven materials you have listed different values than those supplied in our submittals dated December 30, 1992 and September 29, 1993.
Representatives from PSE&G and NRC discussed this issue in telephone calls on June 14 and 15, 1994.
At that time, it was identified that PSE&G should recalculate the IRTNDT values and provide that information to the NRC along with the relevant assumptions and methodology used for the calculations.
In order to complete that effort additional time will be
-required.
PSE&G-will--provide the- *requested* -i-nformat-ion--by-July-20, 1994.
Document Control Desk
'NLR-N94114 3
JUN 2 0 1994 The Salem 2 Summary File for Upper Shelf Energy lists values of unirradiated USE for plates B4712-1, B4712-2, B4712-3, B4713-1, B4713-2 and B4713-3.
The listed USE values were reported to you in our December 30, 1992 submittal and were derived by multiplying the longitudinal values by 65%.
However, in that same letter we also reported transverse Charpy test data for the six plates identified above.
This transverse data represents direct material property measurements using transverse Charpy specimens and should be used in lieu of the longitudinal data for USE determination.
Also note that the six relevant descriptions in the "Method of Determin. Unirrad. USE" column should be changed from 11 65%" to "Direct". has been annotated to reflect these changes.
We have recently updated Salem Units 1 and 2 ID and 1/4T neutron fluence values for EOL.
These revised values are provided in to this letter.
The 1/4 T values were obtained using Equation 3 in Reg. Guide 1.99, Rev. 2.
The updated fluences were used to recalculate the EOL USE values.
For Salem Unit 1, the recalculated USE values are close to those reported in the summary data file, with one exception.
The revised EOL USE value for plate B2402-3 is 88 *ft-lbs.
For Salem Unit 2, the recalculated EOL USE values also vary from those reported in the summary data file for a number of materials.
The revised EOL USE values for welds 2-442 and 3-442 are 63 and 78 ft-lbs respectively, compared with 60 and 75 ft-lbs reported in the Table.
It should be noted that the revised values for the six plates vary significantly from the Table values.
These variances are attributed to the changes in the fluence values and the use of initial USE values based on transverse data as previously discussed.
The recalculated EOL USE values for the six plates are annotated in Attachment 2.
A reference for unirradiated USE values for welds is given in the list of references for the Summary File for Upper Shelf Energy for both Salem 1 and Salem 2.
It is a letter from s. LaBruna to USNRC Document Control Desk, and the date you have listed is December 4, 1993.
The file copy at PSE&G is dated December 1, 1993.
- Document Control Desk
'NLR-N94114 4
JUN 2 0 1994 to this letter is a hand corrected set of the four summary data files you sent to us in the April 21, 1994 letter.
They have been marked up to reflect the changes discussed above.
If there are any questions relative to the information provided herein, please feel free to contact us.
Document Control Desk
'NLR-N94114 5
C Mr. T. T. Martin, Administrator - Region I
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 JUN 2 0 1994 Mr. J. C. Stone, Licensing Project Manager -
Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
'J REF: NLR-N94114 STATE OF NEW JERSEY SS.
COUNTY OF SALEM
- s. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
1994 SHERRY L C.~GLE NOTARY PUBL~C OF NEW JERSEY My Commission expires on -~fY-1.11.....
y P.iCe~lfl~lfliw.is:;;;*&-i\\J.i'ciH-'i ~*-~o.+:'l'cu.'rr.,.,*s._,,M...
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[
SALEM 1 I
I 1/4T
---8ELTLINE ID NEUT.
EXPONENT NEUTRON IDENT.
FLUENCE AT VALUE FLUENCE AT EOL/EFPY (see note)
EOL/EFPY (as of 10/2/931 82402-1
- 1.42E+ 19 0.596 8.5E+18 82402-2 1.42E+ 19 0.596 8.5E+18 82402-3 1.42E+ 19 0.596 8.5E+ 18 NOTE: 1 /4T values are obtained using equation (3) 82403-1 1.37E+ 19 0.596 8.2E+18 given in Reg. guide 1.99 Rev. 2:
82403-2 1.37E+ 19 0.596 8.2E+18 82403-3 1.37E+ 19 0.596 8.2E+18 1-----
2-042 1.13E+ 19 0.596 6.7E+18 f = fsurf (e-0.24x) 9-042 1.39E+ 19 0.596 8.3E+ 18 where x is the vessel wall thickness (8.625 in) 3-042 1.37E+ 19 0.596 8.2E+18 (FLUENCE VALUES FROM
- ---1 052.6-0006)
SALEM 2 I
1/4T 8ELTLINE ID NEUT.
EXPONENT NEUTRON IDENT.
FLUENCE AT VALUE FLUENCE AT EOL/EFPY (see note)
EOL/EFPY (as of 3/16/93) 84712-1 1.52E+ 19 0.596 9.1E+18
!"\\.
84712-2 1.52E+ 19 0.596 9.1E+ 18 84712-3 1.52£+ 19 0.596 9.1E+ 18 84713-1 1.44E+ 19 0.596 8.6E+ 18 84713-2 1.44E+ 19 0.596 8.6E+18 84713-3 1.44E+19 0.596 8.6E+ 18 2-442 1.17E+ 19 0.596 7.0E+18 3-442 1.18E+ 19 0.596 7.0E+ 18 9-442 1.44E+ 19 0.596 8.6E+ 18
Summary File for Pressurized Thermal Shock Plant 8eltline Heat No.
ID Neut.
IRT *.,.
Method of Chemistry Method of XCu
%Ni Name I dent.
I dent.
Fluence at Determin.
Factor Determin.
/
EOL/EFPY IRT.-
CF Salem 1 Int. shell C-1354-1
+.38EIV q 50°F 8
Plant 157.82 Calculated 0.24 0.53 82402-1 loa.f">..S I Scecific EOL:
Int. shell C-1354-2 1.3se1r 30°F 8
Plant 154.37 Calculated 0.53 8/13/2016 82402-2 l*'i 'Z.E It)
Soecific
~"3?
Int. Shell C-1397*2
+.381!19 q 18°F 8
Plant 115.53 Calculated 0.22 0.51 82402-3 1.1.f"Z. EI s~ific Lower C-1356-1
-'1.35E19-23°F 9
MTE8 5-2 128.8 Table 0.19 0.48 Shell f, 3"Jlflq 82403-1 Lower C-1356-2
~.351!19' 30°F 9
MTEB 5-2 129.9 Table 0.19 0.49 Shell 1.3;e;1q 82403-2 Lower C-1356-3
+.ase*9' 38°F 9
MTEB 5-2 128.8 Table 0.19 0.48 Shell f,3'11? 19 82403-3 Int. Shell 398196 &
~
-56°F Generic 214 Table 0.18 1.00 Axial 348009 Welds (T) 1.13£ 1q 2-042 Int. to 13253
_l...25£19"'
-56°F Generic 195.8 Table 0.25 0.72 Lower
,. "39f-J9 Shell Circ. Weld 9-042 Lower 348009
~
-56°F Generic 220 Table 0.19 1.00 Shell f.3'1EICJ Axial Welds 3-042 References for Salem 1 Material type and data other than that noted below was provided in the June 30, 1992 letter from S.E. Miltenberger (PSE&G) to USNRC Docunent Control Desk, 11Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f), Salem Generating Station Unit Nos. 1 and 2.
Chemistries for the intermediate shell course plates were provided in the August 4, 1993 letter S. LaBruna to USNRC Docunen.t Control Desk, 11Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.5054(f) Request for Additional Information, Salem Generating Station Unit Nos. 1 and 2.
Initial RTr<<>T and llJSE values for the beltline plates were provided in the September 29, 1993 letter from s. LaBruna to USNRC Docunent Control Desk, 11Supplemental Response to Generic 92-01, Revision 1 Reactor Vessel. Structural Integrity, 10CFR50.54(f) Request for Additional Information, Salem Generating Station Unit No. 1.
Fluence reported in a December 15, 1992 letter from S. La8rWIB (PSE&G) to USNRC.
8Staff determination of IRTNDT from transverse CVN data.
9Staff determination of IRTN T from longitudinal CVN data by converting longitudinal data to transverse ~ata using the 65% correction factor, in accordance with MTEB 5-2.
8
9 Plant Name Beltline Ident.
Reference for Salem 1 Summary File for Upper Shelf Energy Heat No.
Material Type 1/4T USE at EOL/EFPY 1/4T Unirrad.
Neutron USE Fluence at EOL/EFPY Method of Determin.
Unirrad.
USE Material type and data other than that noted below was provided in the June 30, 1992 letter S.E. Miltenberger CPSE&G) to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54Cf), Salem Generating Station Unit Nos. 1 and 2.
Chemistries for the intermediate shell course plates were provided in the August 4, 1993 letter from s. LaBruna to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f) Request for Additional Information, Salem Generating Station Unit Nos. 1 and 2.
Initial RT~r and UUSE values for the beltline plates were provided in the September 29, 1993 letter from S. LaBruna to USNRC Docunent Control Desk, "Supplemental Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54Cf) Request for Additional Information, Salem Generating Station Unit No. 1.
UUSE values for the beltline welds except int. shell axial welds 2-042, were provided in the December:K1993 letter from S. LaBruna to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f) Request for Additional Information, Salem Generating Station Unit Nos. 1 and 2.
UUSE value for int. shell axial welds 2-042 is a generic value for welds fabricated by Con*lustion Engineering using Linde 1092, 0091, 123 and Arcos B-5 fluxes (Ref. Letter from s.
Bloom (USNRC) to T. L. Patterson (OPPO) dated December 3, 1993.
Fluence based on data provided in a December 15, 1992 letter from S. LaBruna CPSE&G) to USNRC.
Summary File for Pressurized Thermal Shock Plant Bel tl ine Heat No.
ID Neut.
IRT-Method of Chemistry Method of xcu
%Hi Name Ident.
!dent.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRTndt CF Salem 2 Int. Shell C-4173-1
+:.38E 19 q 9
MTEB 5-2 89.8 Table 0.13 0.56 5°F 84712-1 1*5"2.EI EOL:
Int. Shell C-4186-2 12°F Plant
.$1-.6-:P -
Calculated 0.12
+.:!8El9 '1 0 *. 62 4/18/2020 84712-2 1.s.2.GI Scecific 118. JS:
Int. Shell C-4194-2 1.38E19 50°F 9
MTEB 5-2 73.7 Table 0.11 0.57 84712-3
- 1. s-::i e 19 Lower C-4182-1
~ 33°F 9
MTEB 5-2 83 Table 0.12 0.60 Shell i.'ii.t E 1q 84713-1 Lower C-4182-2
-L4~E1'9" 22°F 9
MTEB 5'-2 82.4 Table 0.12 0.57 Shell 1.'if.4E"l9 84713-2 Lower 8-8343-1
~ 20°F 9
MTE8 5-2 82.6 Table 0.12 0.58 Shell 1t'if>i E19 84713-3 Int. Shell 13253 &
~.05E19"
-40°f Plant
~:. ~ed 0.23 0.73 Axial 20291 en 1.1'1 E' It)
Specific 1q1.. 1-,'
To.loJe.
Welds 2-442 Lower 21935 &
~.91E~9
-56°F Generic 202.7 Table 0.20 0.86 Shell 12008 en l. ISE 1q Axial Welds 3-442 Int. to 90099
~
.:581:19
-56°F Generic 95 Table 0.18 0.20 Lower Shell 1.'-tt\\E1q Circ. Weld 9-442
/
References for Salem 2 Material type, initial RT,.,T and data other than that noted below was provided in the June 30, 1992 letter S.E.
Miltenberger ePSE&G) to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54ef>, Salem Generating Station Units Nos. 1 and 2.
The chemistry for plate 84712-2 was provided in the August 4, 1993 letter from s. La8r1618 to USNRC Docunent Control Oesk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54ef> Request for Additional Information, Salem Generating Station Unit Nos. 1 and 2.
Fluence reported in a Deceld>er 15, 1992 letter from S. La8runa (PSE&G) to USNRC.
9Staff determination of IRTN T from longitudinal CVN data by converting longitudinal data to transverse ~ata using the 65% correction factor, in accordance with MTEB 5-2.
9
ENCLOSURE 2 Summary File for Upper Shelf Energy Plant Name 8eltline Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of
!dent.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirrad.
EOL/EFPY USE Salem 1 Int. shell C-1354-1 A5338*1 70 r**'
1t:ttt8 91 Direct 82402-1
'r'. 1 81.S'EIS EOL:
Int. shell C-1354-2 A5338-1 83
-8.2E18-B 98 Direct 8/13/2016 82402-2 g.5E'I Int. Shell C-1397-2 A533B*1
_)II" 8
-&:2Et8 s 104 Direct 82402-3
~ B,
9.s-er Lower C-1356-1 A533B-1 68 ft --*-
93 65X Shell g;z. C2 I B 82403-1 Lower C-1356-2 A5338-1 61 e.ae-tS"'
83 65X Shell.
- 8. "Z. EIS 82403-2 Lower C-1356-3 A5338-1 62
~
85 65X Shell
- '. ~ ' *'
82403-3 s.2E1e Int. Shell 398196 &
Linde 53
-6.6E18 75 NRC Axial 348009 (T) 1092, SAlil Generic lilelds 6 *..,E18 2-042 Int. to 13253 Linde 69
..a:ft18 111 Surv.
Lower 1092, SAlil lileld Shell B. 3E IB Circ. lileld 9-042 Lower 348009 Linde 75 PB.9E18*
112 Sister Shell 1092, SAlil Plant Axial
- 8. 2E19 Welds 3-042
- IO Summary File for Upper Shelf Energy Plant Name Bel tl ine Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of I dent.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirrad.
EOL/EFPY USE Salem 2 Int. Shell C-4173-1 A 533B-1
- " 8'-/
~s.?',ob
~i""ec.t B4712-1 q.1 GI EOL:
Int. Shell C-4186-2 A 533B-1 j6.9~./r.'lrn5 8 JY q'7
...65%'"
4Y1'B/2020 B4712-2 q.f El Di"'ec.t-Int. Shell C-4194-2 A 533B-1
"'28 bl
-&:-iE11t D.JY, 07
~
B4712-3
- q. J EI o p;"'"ec t Lower C-4182-1 A 533B-1
~'1Si 8.4E18 P' qg
~
Shell fJ,6Et8 D&v-e t. t-B4713-1
~SZl.
Lower C-4182-2 A 5338-1
..8...4e.t.I
~
Shell 8.6E 18 ro 3 Oi..-e,t-84713-2 Lower B-8343-1 A 533B-1 1' q'""]
~
~~I
.65%-
Shell 8.6 E*8 o,*,,..ed:
84713-3 Int.* Shell 13253 &
Linde "16 ldE+8 96 8
Generic Axial 20291 (T) i092, SAW Welds I *3 7,0Ef8 2-442 Lower 21935 &
Linde
-6.4E1S-114 Sister Shell 12008 (T) 1092, SAW
'I c Plant Axial
'781
'1.o El S Welds 3-442 Int. to 90099 Linde 52
-8.Z!E18 75 NRC Lower 0091, SAW Generic Shell 8.GE r8 Circ. Weld 9-442 6Licensee utilized a generic UUSE value; additional information required to confirm the value.
\\)AGE lo o Ft.a 11 ' -
Summary File for Upper Shelf Energy Plant Name Beltline I dent.
Heat No.
, Material Type 1/4T USE at EOL/EFPY 1/4T Neutron Fluence at EOL/EFPY Unirrad.
USE Method of Determin.
Unirrad.
USE Reference for Salem 2 Material type, Initial RT~, and data other than that noted below was provided in the June 30, 1992 letter S.E. Miltenberger (PSE&G) to USNRC Docunent Control Desk, "Response to Generic Letter 92*01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f), Salem Generating Station Unit Nos. 1 and 2.
The chemistry for plate 84712*2 was provided in the August 4, 1993 letter from s. LaBruna to USNRC Docunent Control Desk, "Response to Generic Letter 92*01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f) Request for Additional Information, Salem Generating
>(
Station Unit Nos. 1 and 2.
t 1q 11o ~
.... ec em'i'f\\f :)
7 UUSE value for the beltline welds except for 9*442 were provided in the ~eneer 4, 1993 letter from S. LaBruna to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structure Integrity, 10CFR50.54(f) Request for Additional Information, Salem Generating Station Uriit Nos. 1 and 2.
UUSE values for weld 9-442 is a generic value for welds fabricated by Conilustion Engineering using Linde 1092, 0091, 123 and Arcos B-5 fluxes (Ref. letter from S. Bloom (USNRC) to T.L.
Patterson (OPPD) dated Decenber 3, 1993.
Fluence based on data provided in a Decenber 15, 1992 lette from S. LaBruna CPSE&G) to USNRC.