ML18096B186: Difference between revisions

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{{#Wiki_filter:i I Public Service Electric and Gas Company Stanley LaBruna Public Service 1Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DEC 3 O 1992 NLR-N92150 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
* Public Service Electric and Gas Company Stanley LaBruna                                           Public Service 1Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DEC 3 O 1992 NLR-N92150 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL RESPONSE TO GENERIC LETTER 92-01,_REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY, 10CFR~0.54(f)
SUPPLEMENTAL RESPONSE TO GENERIC LETTER 92-01,_REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY, 10CFR~0.54(f)
SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Generic Letter 92-01, Revision 1 requested PSE&G to submit information to enable the NRC to assess compliance with 10CFR50.60 and 10CFR50.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Boundary set forth in .10CFR50, Appendices G and H.
SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Generic Letter 92-01, Revision 1 requested PSE&G to submit information to enable the NRC to assess compliance with 10CFR50.60 and 10CFR50.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Boundary set forth in.10CFR50, Appendices G and H.
The Salem Units 1 and 2 responses to Generic Letter 92-01, Revision 1 were submitted to the NRC in Letter NLR-N92081 dated June 30, 1992. This submittal included longitudinal Charpy V-notch impact data for the six (6) pressure vessel beltline plates originally generated by Combustion Engineering in 1968 and 1969.             It also included transverse Charpy V;notch impact data generated by Westinghouse in June, 1973 for plate B4712-2 which is included in the surveillance capsule monitoring program.
The Salem Units 1 and 2 responses to Generic Letter 92-01, Revision 1 were submitted to the NRC in Letter NLR-N92081 dated June 30, 1992.
Since the date of this submittal, Salem Unit 2 pressure vessel material transverse Charpy V-notch impact data was located by Westinghouse for the remaining five (5) beltline plates used in the fabrication of the pressure vessel. The data that Westinghouse recently found is for Charpy V-notch tests that Westinghouse conducted in June, 1973 while conducting the tests for plate B4712-2. ~he Salem Unit 2 response to the Generic Letter has therefore been revised to include this new Charpy V-notch data and is enclosed as Attachment 2.
This submittal included longitudinal Charpy V-notch impact data for the six (6) pressure vessel beltline plates originally generated by Combustion Engineering in 1968 and 1969.
At PSE&G's request, Westinghouse completed a search of their files and has determined that similar additional data does not exist for Salem Unit 1.
It also included transverse Charpy V;notch impact data generated by Westinghouse in June, 1973 for plate B4712-2 which is included in the surveillance capsule monitoring program.
            /----- -      -----*...:.:..ho .m.. _.:- ____ ~_   ---- --- - - - - - - - - - - -
Since the date of this submittal, Salem Unit 2 pressure vessel material transverse Charpy V-notch impact data was located by Westinghouse for the remaining five (5) beltline plates used in the fabrication of the pressure vessel.
          .'      9301070112 921230 PDR ADOCK 05000311 P                                               PDR
The data that Westinghouse recently found is for Charpy V-notch tests that Westinghouse conducted in June, 1973 while conducting the tests for plate B4712-2.  
~he Salem Unit 2 response to the Generic Letter has therefore been revised to include this new Charpy V-notch data and is enclosed as Attachment 2.
At PSE&G's request, Westinghouse completed a search of their files and has determined that similar additional data does not exist for Salem Unit 1.  
/-----
-----*...:.:..ho.m.. _.:-____ ~_
9301070112 921230 PDR ADOCK 05000311 P
PDR  


.~.
~.
Document Control Desk           2                     DEC 3 O 1992 NLR-N92150 Please do not hesitate to contact us if there are any questions regarding this submittal.
Document Control Desk NLR-N92150 2
Sincerely, Attachment Affidavit C     Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager U. s. Nuclear Regulatory Commission One White Flint North MC 14 E-21 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
DEC 3 O 1992 Please do not hesitate to contact us if there are any questions regarding this submittal.
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection
Attachment Affidavit Sincerely, C
          , Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager U. s. Nuclear Regulatory Commission One White Flint North MC 14 E-21 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection  
, Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625  


REF: NLR-N92150 STATE OF NEW JERSEY         )
REF: NLR-N92150 STATE OF NEW JERSEY COUNTY OF SALEM
                                ) SS.
)  
COUNTY OF SALEM            )
)
SS.  
)
S. LaBruna, being duly sworn according to law deposes and says:
S. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations 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 No. 2, are true to the best of my knowledge, information and belief.
I am Vice President - Nuclear Operations 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 No. 2, are true to the best of my knowledge, information and belief.
7#~
7#~
I 1992           ELIZABETH J. KIDD Notaiy Public of New Jersey My* Commission Expires April 25, 1995 My Commission expires
I 1992 My Commission expires ELIZABETH J. KIDD Notaiy Public of New Jersey My* Commission Expires April 25, 1995  


NLR-N92150 ATTACHMENT 2 SALEM UNIT 2 RESPONSE TO GENERIC LETTER 92-01, REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY NOVEMBER 05, 1992 REVISION 1
NLR-N92150
* ATTACHMENT 2 SALEM UNIT 2 RESPONSE TO GENERIC LETTER 92-01, REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY NOVEMBER 05, 1992 REVISION 1  


NLR-N92150 PSE&G has prepared the following information in response to the requests in Generic Letter 92-01, Revision 1 titled "REACTOR VESSEL STRUCTURAL INTEGRITY". In the following text, the individual requests for information are stated in boldface type as written in GL 92-01, and each request is followed by the PSE&G response in regular (non-boldface) type.
NLR-N92150 PSE&G has prepared the following information in response to the requests in Generic Letter 92-01, Revision 1 titled "REACTOR VESSEL STRUCTURAL INTEGRITY".
: 1. Certain addressees are requested to provide the following information regarding Appendix H to CFR Part so:
In the following text, the individual requests for information are stated in boldface type as written in GL 92-01, and each request is followed by the PSE&G response in regular (non-boldface) type.
: 1.
Certain addressees are requested to provide the following information regarding Appendix H to CFR Part so:
Addressees who do not have a surveillance program meeting ASTM E 18S-73, -79, or -82 and who do not have an integrated surveillance program approved by the NRC (see Enclosure 2),
Addressees who do not have a surveillance program meeting ASTM E 18S-73, -79, or -82 and who do not have an integrated surveillance program approved by the NRC (see Enclosure 2),
are requested to describe actions taken or to be taken to ensure compliance with Appendix H to 10 CFR Part so.
are requested to describe actions taken or to be taken to ensure compliance with Appendix H to 10 CFR Part so.
Addressees who plan to revise the surveillance program to meet Appendix II to 10 CFR Part so are requested to indicate when the revised program will be submitted to the NRC staff for review. If the surveillance program is not to be revised to meet Appendix H to 10 CFR Part so, addressees are requested to indicate when they plan to request an exemption from Appendix H to 10 CFR Part so under 10 CFR S0.60(b).
Addressees who plan to revise the surveillance program to meet Appendix II to 10 CFR Part so are requested to indicate when the revised program will be submitted to the NRC staff for review.
If the surveillance program is not to be revised to meet Appendix H to 10 CFR Part so, addressees are requested to indicate when they plan to request an exemption from Appendix H to 10 CFR Part so under 10 CFR S0.60(b).  


===Response===
===Response===
ASTM E-185-73 was the standard in place at the time the surveillance program was designed. The Salem Unit 2 surveillance program complies with ASTM E-185-73. Testing of surveillance capsules after July 26, 1983 has been performed in accordance with ASTM standard version E-185-82. Furthermore, since the surveillance program design was approved during the FSAR licensing process, the capsule testing program has been approved as part of the plant Technical Specifications. Therefore, it is determined that the surveillance program for Salem Unit 2 meets the requirements of Appendix H to 10 CFR Part 50 and that an exemption request is not considered necessary.
ASTM E-185-73 was the standard in place at the time the surveillance program was designed.
: 2. Certain addressees are requested to provide the following information regarding Appendix G to 10 CFR Part so:
The Salem Unit 2 surveillance program complies with ASTM E-185-73.
: a. Addressees of plants for which the Charpy upper shelf energy is predicted to be less than so foot-pounds at the end of their licenses using the guidance in Paragraphs c.1.2 or c.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or v.c of Appendix G to 10 CFR Part so.
Testing of surveillance capsules after July 26, 1983 has been performed in accordance with ASTM standard version E-185-82.
1 Revision 1
Furthermore, since the surveillance program design was approved during the FSAR licensing process, the capsule testing program has been approved as part of the plant Technical Specifications.
Therefore, it is determined that the surveillance program for Salem Unit 2 meets the requirements of Appendix H to 10 CFR Part 50 and that an exemption request is not considered necessary.
: 2.
Certain addressees are requested to provide the following information regarding Appendix G to 10 CFR Part so:
: a.
Addressees of plants for which the Charpy upper shelf energy is predicted to be less than so foot-pounds at the end of their licenses using the guidance in Paragraphs c.1.2 or c.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or v.c of Appendix G to 10 CFR Part so.
1 Revision 1  


NLR-N92150
NLR-N92150  


===Response===
===Response===
Table 1 contains the unirradiated, December 16, 1991 and EOL (April 18, 2020) Charpy upper shelf energy for Salem Unit 2 beltline materials. The December 16, 1991 and EOL values were calculated using Figure 2 of Regulatory Guide 1.99, Revision 2.
Table 1 contains the unirradiated, December 16, 1991 and EOL (April 18, 2020) Charpy upper shelf energy for Salem Unit 2 beltline materials.
The December 16, 1991 and EOL values were calculated using Figure 2 of Regulatory Guide 1.99, Revision 2.
The calculated EOL Charpy upper shelf energy for all the beltline materials which have known unirradiated USE values are predicted to be above the 50 ft-lb criteria.
The calculated EOL Charpy upper shelf energy for all the beltline materials which have known unirradiated USE values are predicted to be above the 50 ft-lb criteria.
: b. Addressees whose reactor vessels were constructed to an ASME Code earlier than the summer 1972 Addenda of the 1971 Edition are requested to describe the consideration given to the following material properties in their evaluations performed pursuant to 10 CFR 50.61 and Paragraph II.A of 10 CFR Part so, Appendix G:
: b.
(1)  The results from all Charpy and drop weight tests for all unirradiated beltline materials, the unirradiated reference temperature for each beltline material, and the method of determining the unirradiated reference temperature from the Charpy and drop weight test; (2)  The heat treatment received by all beltline and surveillance materials; (3)  The heat number for each beltline plate or forging and the heat number of wire and flux lot number used to fabricate each beltline weld; (4)  The heat number for each surveillance plate or forging and the heat number of wire and flux lot number used to fabricate the surveillance weld; (5)  The chemical composition, in particular the weight in percent of copper, nickel, phosphorous, and sulfur for each beltline and surveillance material; and (6)  The heat number of the wire used for determining the weld metal chemical composition if different than Item (3) above.
Addressees whose reactor vessels were constructed to an ASME Code earlier than the summer 1972 Addenda of the 1971 Edition are requested to describe the consideration given to the following material properties in their evaluations performed pursuant to 10 CFR 50.61 and Paragraph II.A of 10 CFR Part so, Appendix G:  


===Response===
===Response===
The Salem Unit 2 reactor vessel was constructed to the 1965 Edition, through Winter 1966 Addenda to Section III of the ASME Code. Thus, the Salem Unit 2 reactor vessel was constructed to an ASME Code earlier than the Summer 1972 Addenda of the 1971 Edition. Tables 2 through 19 *document the unirradiated data (Charpy and drop weight test results, reference temperature, upper shelf energy, heat treatment, heat number, flux lot number 2
(1)
Revision 1
The results from all Charpy and drop weight tests for all unirradiated beltline materials, the unirradiated reference temperature for each beltline material, and the method of determining the unirradiated reference temperature from the Charpy and drop weight test; (2)
The heat treatment received by all beltline and surveillance materials; (3)
The heat number for each beltline plate or forging and the heat number of wire and flux lot number used to fabricate each beltline weld; (4)
The heat number for each surveillance plate or forging and the heat number of wire and flux lot number used to fabricate the surveillance weld; (5)
The chemical composition, in particular the weight in percent of copper, nickel, phosphorous, and sulfur for each beltline and surveillance material; and (6)
The heat number of the wire used for determining the weld metal chemical composition if different than Item (3) above.
The Salem Unit 2 reactor vessel was constructed to the 1965 Edition, through Winter 1966 Addenda to Section III of the ASME Code.
Thus, the Salem Unit 2 reactor vessel was constructed to an ASME Code earlier than the Summer 1972 Addenda of the 1971 Edition.
Tables 2 through 19 *document the unirradiated data (Charpy and drop weight test results, reference temperature, upper shelf energy, heat treatment, heat number, flux lot number 2
Revision 1  


NLR-N92150 and chemical composition) for all beltline region and surveillance materials. These values were developed using the material test requirements and acceptance standards that were current at the time of the reactor pressure vessel construction.
NLR-N92150
* and chemical composition) for all beltline region and surveillance materials.
These values were developed using the material test requirements and acceptance standards that were current at the time of the reactor pressure vessel construction.
(Note that the chemical composition of the welds was determined from the weld wire heat numbers of the actual welds, except for weld 9-442, in which the nickel content was estimated to be the upper limit of type MIL B-4 wire heats).
(Note that the chemical composition of the welds was determined from the weld wire heat numbers of the actual welds, except for weld 9-442, in which the nickel content was estimated to be the upper limit of type MIL B-4 wire heats).
The nil-ductility transition temperature (NDTT) is defined as the maximum temperature at which a standard drop weight specimen breaks when tested* according to the provisions specified in ASTM E-208, "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic steels". The NDTT was determined for each beltline region material by drop weight tests (ASTM E-208) performed by Combustion Engineering except for welds 3-442A, 3-442B, 3-443C and 9-442.
The nil-ductility transition temperature (NDTT) is defined as the maximum temperature at which a standard drop weight specimen breaks when tested* according to the provisions specified in ASTM E-208, "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic steels".
The unirradiated reference temperature (RTNDT) of the beltline region materials was established from the drop weight NDTT tests and the Charpy V-notch tests, using the guidance provided in NUREG-0800, Branch Technical Position, MTEB 5-2, "Fracture Toughness Requirements", and the ASME Boiler and Pressure Vessel Code, Section III. The following three paragraphs summarize pertinent information from these two references, and the fourth following paragraph summarizes information from 10CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock."
The NDTT was determined for each beltline region material by drop weight tests (ASTM E-208) performed by Combustion Engineering except for welds 3-442A, 3-442B, 3-443C and 9-442.
The unirradiated reference temperature (RTNDT) of the beltline region materials was established from the drop weight NDTT tests and the Charpy V-notch tests, using the guidance provided in NUREG-0800, Branch Technical Position, MTEB 5-2, "Fracture Toughness Requirements", and the ASME Boiler and Pressure Vessel Code, Section III.
The following three paragraphs summarize pertinent information from these two references, and the fourth following paragraph summarizes information from 10CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock."
The NDTT temperature, as determined by drop weight tests (ASTM E-208) is the RTNDT if, at 60°F above the NDTT, at least 50 ft-lb of energy and 35 mils lateral expansion are obtained in Charpy V-notch tests on transverse specimens.
The NDTT temperature, as determined by drop weight tests (ASTM E-208) is the RTNDT if, at 60°F above the NDTT, at least 50 ft-lb of energy and 35 mils lateral expansion are obtained in Charpy V-notch tests on transverse specimens.
Otherwise, the RTNDT is the temperature at which 50 ft-lb and 35 mils lateral expansion are obtained on transverse Charpy specimens, minus 60°F.
Otherwise, the RTNDT is the temperature at which 50 ft-lb and 35 mils lateral expansion are obtained on transverse Charpy specimens, minus 60°F.
If drop weight tests were not performed, but full Charpy V-notch curves were obtained, the NDTT for SA-533 Grade B, Class 1 plate and weld material may be assumed to be the higher of the 30 ft-lb temperature, or 0°F.
If drop weight tests were not performed, but full Charpy V-notch curves were obtained, the NDTT for SA-533 Grade B, Class 1 plate and weld material may be assumed to be the higher of the 30 ft-lb temperature, or 0°F.
If transverse Charpy V-notch specimens were not tested, the temperature at which 50 ft-lb and 35 mils lateral expansion would have been obtained on transverse specimens may be estimated by using'65% of the values from longitudinal specimens, or increasing the 50 ft-lb and 35 mil lateral expansion temperatures for longitudinal specimens by 20°F.
If transverse Charpy V-notch specimens were not tested, the temperature at which 50 ft-lb and 35 mils lateral expansion would have been obtained on transverse specimens may be estimated by using'65% of the values from longitudinal specimens, or increasing the 50 ft-lb and 35 mil lateral expansion temperatures for longitudinal specimens by 20°F.
3 Revision 1
3 Revision 1  


NLR-N92150 If measured values of RTNDT are not available, the generic mean values must be used: 0°F for welds made with Linde 80 flux, and -56°F for welds made with Linde 0091, 1092 and 124, and ARCOS B-5 weld fluxes, as per 10 CFR50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
NLR-N92150
The Charpy V-notch data for each of the beltline region plates tested by Combustion Engineering at the time of fabrication were taken in the longitudinal direction. Westinghouse tested transverse Charpy V-notch specimens for each of the beltline region plates prior to developing the Salem 2 surveillance capsule testing program. This transverse Charpy data was used in determining the initial RTNDT and initial USE values for the plates. The RTNDT for each of these materials were determined to be the higher of (1) the value obtained by reducing the temperature at which 50 ft-lb and 35 mil lateral expansion was obtained by 60°F or (2) the NDTT. The RTNDT for the intermediate shell longitudinal weld seams, 2-442A, B & C and the surv~illance weld HAZ was determined to be equal to the NDTT. Full Charpy curves were not generated for lower shell longitudinal welds and the intermediate shell to lower shell circumferential weld seams; therefore, the generic mean value of -56°F is assumed.
* If measured values of RTNDT are not available, the generic mean values must be used:
0°F for welds made with Linde 80 flux, and -56°F for welds made with Linde 0091, 1092 and 124, and ARCOS B-5 weld fluxes, as per 10 CFR50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
The Charpy V-notch data for each of the beltline region plates tested by Combustion Engineering at the time of fabrication were taken in the longitudinal direction.
Westinghouse tested transverse Charpy V-notch specimens for each of the beltline region plates prior to developing the Salem 2 surveillance capsule testing program.
This transverse Charpy data was used in determining the initial RTNDT and initial USE values for the plates.
The RTNDT for each of these materials were determined to be the higher of (1) the value obtained by reducing the temperature at which 50 ft-lb and 35 mil lateral expansion was obtained by 60°F or (2) the NDTT.
The RTNDT for the intermediate shell longitudinal weld seams, 2-442A, B & C and the surv~illance weld HAZ was determined to be equal to the NDTT.
Full Charpy curves were not generated for lower shell longitudinal welds and the intermediate shell to lower shell circumferential weld seams; therefore, the generic mean value of -56°F is assumed.
The unirradiated upper shelf energy may be determined from Charpy V-notch tests using transverse specimen data (or using longitudinal data multiplied by 65% to estimate transverse data).
The unirradiated upper shelf energy may be determined from Charpy V-notch tests using transverse specimen data (or using longitudinal data multiplied by 65% to estimate transverse data).
The upper shelf energy is the average of the transverse Charpy energy values for specimens exhibiting fully ductile behavior (i.e. 100% shear), at a given test temperature. Typically, specimens are tested in sets of three at each test temperature.
The upper shelf energy is the average of the transverse Charpy energy values for specimens exhibiting fully ductile behavior (i.e. 100% shear), at a given test temperature.
The set having the highest average may be regarded as defining the upper shelf energy, as per ASTM E-185-82. The upper shelf energy values for the beltline region plates were calculated by multiplying the average of the 100% shear longitudinal Charpy V-notch data by 65% for Combustion Engineering tests. The upper shelf energy values for the beltine region surveillance test plates were determined by taking the average of the three 100%
Typically, specimens are tested in sets of three at each test temperature.
The set having the highest average may be regarded as defining the upper shelf energy, as per ASTM E-185-82.
The upper shelf energy values for the beltline region plates were calculated by multiplying the average of the 100% shear longitudinal Charpy V-notch data by 65% for Combustion Engineering tests.
The upper shelf energy values for the beltine region surveillance test plates were determined by taking the average of the three 100%
shear energy values for the transverse data obtained in tests conducted by Westinghouse Electric Corporation.
shear energy values for the transverse data obtained in tests conducted by Westinghouse Electric Corporation.
The upper shelf energy values for the intermediate shell longitudinal weld and surveillance weld materials were determined by the average of the three 100% shear energy values. Upper shelf energy values were not calculated for the lower shell longitudinal welds and intermediate to lower shell circumferential welds because full Charpy V-notch curves were not generated for these materials.
The upper shelf energy values for the intermediate shell longitudinal weld and surveillance weld materials were determined by the average of the three 100% shear energy values.
Upper shelf energy values were not calculated for the lower shell longitudinal welds and intermediate to lower shell circumferential welds because full Charpy V-notch curves were not generated for these materials.
The surveillance material Charpy and tensile specimens received heat treatments, including stress relieving operations, equivalent to those given to the actual reactor vessel materials as required by Section III of the ASME Boiler and Pressure Vessel 4
The surveillance material Charpy and tensile specimens received heat treatments, including stress relieving operations, equivalent to those given to the actual reactor vessel materials as required by Section III of the ASME Boiler and Pressure Vessel 4
Revision 1
Revision 1  


NLR-N92150 Code. Combustion Engineering supplied Westinghouse Electric Corporation with sections of A533 Grade B, Class 1 plate used in the core region of the Salem Unit 2 reactor pressure vessel for use in the Reactor Vessel Radiation Surveillance Program. The sections of material were removed from the 9 5/8-inch intermediate shell plate B4712-2 of the pressure vessel.
NLR-N92150 Code.
Combustion Engineering, Inc., also supplied a weldment made from sections of the intermediate shell plate B4712-2 ~nd adjoining intermediate shell plate B4712-1 using weld wire representative of that used in the original fabrication. The heat treatment histories of the pressure vessel beltline region material and
Combustion Engineering supplied Westinghouse Electric Corporation with sections of A533 Grade B, Class 1 plate used in the core region of the Salem Unit 2 reactor pressure vessel for use in the Reactor Vessel Radiation Surveillance Program.
The sections of material were removed from the 9 5/8-inch intermediate shell plate B4712-2 of the pressure vessel.
Combustion Engineering, Inc., also supplied a weldment made from sections of the intermediate shell plate B4712-2 ~nd adjoining intermediate shell plate B4712-1 using weld wire representative of that used in the original fabrication.
The heat treatment histories of the pressure vessel beltline region material and  
'surveillance materials are given in Tables 2 through 19.
'surveillance materials are given in Tables 2 through 19.
: 3. Addressees are requested to provide the following information regarding commitments made to respond to GL 88-11:
: 3.
: a. How the embrittlement effects of operating at an irradiation temperature (cold leg or recirculation suction temperature) below 525°F were considered.
Addressees are requested to provide the following information regarding commitments made to respond to GL 88-11:  
 
===Response===
: a.
How the embrittlement effects of operating at an irradiation temperature (cold leg or recirculation suction temperature) below 525°F were considered.
In particular licensees are requested to describe consideration given to determining the effect of.
In particular licensees are requested to describe consideration given to determining the effect of.
lower irradiation temperature on the reference temperature and on the Charpy upper shelf energy.
lower irradiation temperature on the reference temperature and on the Charpy upper shelf energy.
===Response===
The PSE&G Operations Department performed a review of its policies and procedures to determine if the stated scenario, i.e., cold leg temperature below 525°F while at power, has occurred for more than 24 hours total.
The PSE&G Operations Department performed a review of its policies and procedures to determine if the stated scenario, i.e., cold leg temperature below 525°F while at power, has occurred for more than 24 hours total.
This review included Integrated Operating Procedure-3 "Hot standby to Minimum Load", which states that Tave must be verified greater than 541°F within 15 minutes of achieving criticality.
This review included Integrated Operating Procedure-3 "Hot standby to Minimum Load", which states that Tave must be verified greater than 541°F within 15 minutes of achieving criticality.
In addition, Technical Specification 3.1.1.4 requires that while in Mode 1 and 2, Tave must be greater than 541°F. This LCO requires the temperature to be restored within 15 minutes or be in Hot Standby within an additional 15 minutes.
In addition, Technical Specification 3.1.1.4 requires that while in Mode 1 and 2, Tave must be greater than 541°F.
Based on department procedural requirements, it can be concluded that the outlined scenario has not occurred in the past and will not occur in the future at Salem. While historically there have been instances during plant transient, where RCS temperature may have gone below 525°F, the cumulative excursion time has been much less than 24 hours.
This LCO requires the temperature to be restored within 15 minutes or be in Hot Standby within an additional 15 minutes.
Based on department procedural requirements, it can be concluded that the outlined scenario has not occurred in the past and will not occur in the future at Salem.
While historically there have been instances during plant transient, where RCS temperature may have gone below 525°F, the cumulative excursion time has been much less than 24 hours.
Therefore, the effect of lower irradiation temperature on the reference temperature and Charpy upper shelf energy is negligible.
Therefore, the effect of lower irradiation temperature on the reference temperature and Charpy upper shelf energy is negligible.
: b. How their surveillance results on the predicted amount of embrittlement were considered.
: b.
5 Revision 1
How their surveillance results on the predicted amount of embrittlement were considered.
5 Revision 1  


NLR-N92150
NLR-N92150 *


===Response===
===Response===
As explained in the PSE&G response to Generic Letter 88-11, the surveillance capsule analyses were conducted using the methods described in Regulatory Guide 1.99 Revision 2 to predict the effects of neutron radiation on the reactor vessel materials.
As explained in the PSE&G response to Generic Letter 88-11, the surveillance capsule analyses were conducted using the methods described in Regulatory Guide 1.99 Revision 2 to predict the effects of neutron radiation on the reactor vessel materials.
PSE&G has complied with its commitment to submit a License Change Request to include new heatup and cooldown curves. Approval for the revised curves was received in January 1990 through Amendment 86 for the Salem Unit 2 Technical Specifications.
PSE&G has complied with its commitment to submit a License Change Request to include new heatup and cooldown curves.
: c. If a measured increase in reference temperature exceeds the mean-plus-two standard deviations predicted by Regulatory Guide 1.99, Revision 2, or if a measured decrease in Charpy upper shelf energy exceeds the value predicted using the guidance in Paragraph C.1.2 in Regulatory Guide 1.99, Revision 2, the licensee is requested to report the information and describe the effect of the surveillance results on the adjusted reference temperature and Charpy upper shelf energy for each beltline material as predicted for December 16, 1991, and for the end of its current license.
Approval for the revised curves was received in January 1990 through Amendment 86 for the Salem Unit 2 Technical Specifications.
: c.
If a measured increase in reference temperature exceeds the mean-plus-two standard deviations predicted by Regulatory Guide 1.99, Revision 2, or if a measured decrease in Charpy upper shelf energy exceeds the value predicted using the guidance in Paragraph C.1.2 in Regulatory Guide 1.99, Revision 2, the licensee is requested to report the information and describe the effect of the surveillance results on the adjusted reference temperature and Charpy upper shelf energy for each beltline material as predicted for December 16, 1991, and for the end of its current license.  


===Response===
===Response===
The measured increase in reference temperature does not exceed the mean-plus-two standard deviation predicted by Regulatory Guide 1.99 Revision 2 for any of the surveillance capsule materials as indicated in Table 20. The measured decrease in Charpy upper shelf energy exceeds the value predicted using methodology specified in Regulatory Guide 1.99 Revision 2 for the weld metal as indicated in Table 20. Therefore, the adjusted reference temperature and Charpy upper shelf energy of each I
The measured increase in reference temperature does not exceed the mean-plus-two standard deviation predicted by Regulatory Guide 1.99 Revision 2 for any of the surveillance capsule materials as indicated in Table 20.
beltline material as predicted by surveillance results for December 16, 1991 and end of current license are provided in Tables 21 and 22 as requested in Request 3c.
The measured decrease in Charpy upper shelf energy exceeds the value predicted using methodology specified in Regulatory Guide 1.99 Revision 2 for weld metal as indicated in Table 20.
6 Revision 1
Therefore, the adjusted reference temperature and Charpy upper shelf energy of each beltline material as predicted by surveillance results for December 16, 1991 and end of current license are provided in Tables 21 and 22 as requested in Request 3c.
6 Revision 1 the I


NLR-N92150
NLR-N92150 *
                    *                  - TABLE 1 SALEM UNIT 2 Unirradiated and Calculated Upper Shelf Energy (USE) Values USE, ft-lbs           USE, ft-lbs(l)   EOL USE ft-lbs (Z)
- TABLE 1 SALEM UNIT 2 Unirradiated and Calculated Upper Shelf Energy (USE) Values USE, ft-lbs USE, ft-lbs(l)
Material Description     Unirradiated           December 16i 1991 April 18i 2020 Intermediate Shell           106( 3 )                   90.1           83.7 Plate B4712-1 Intermediate Shell           97 (3 )                   81.5           75.7 Plate B4712-2 Intermediate Shell           107( 3 )                   92.0         86.7 Plate B4712-3 Intermediate Shell Long. 111                         86.6         76.6 Weld 2-442A Intermediate Shell Long. 111                         83.3         73.3 Weld 2-442B Intermediate Shell Long. 111                         83.3         73.3 Weld 2-442C Lower Shell Plate             98( 3 )                   83.0         78.4 B4713-1 Lower Shell Plate           103( 3 )                   87.6         82.4 B4713-2 Lower Shell Plate           121( 3 )                 102.8           96.8 B4713-3 Lower Shell Long.           NA                         NA           NA Weld 3-442A Lower Shell Long.           NA                       NA             NA Weld 3-442B Lower Shell Long.           NA                         NA           NA Weld 3-422C Intermediate to Lower         NA                         NA           NA Shell Girth Weld 9-442 NA - Unirradiated upper shelf energy not available because tests were not performed. In these cases, the December 16, 1991 and EOL USE values were not calculated.
EOL USE ft-lbs (Z)
(1) December 16, 1991 USE values calculated at ~T location, based on fluences in PSE&G letter SCI-92-0357, 6/11/92, J. Perrin to J. Chicots.
Material Description Unirradiated December 16i 1991 April 18i 2020 Intermediate Shell 106( 3 )
(2) EOL USE values calculated at l/4T location, based on fluences from PSE&G letter SCI-92-0319, 5/14/92, J. Perrin to J. Chicots.
90.1 83.7 Plate B4712-1 Intermediate Shell 97 (3 )
(3)   Unirradiated USE values determined from transverse data. -
81.5 75.7 Plate B4712-2 Intermediate Shell 107( 3 )
7 Revision 1
92.0 86.7 Plate B4712-3 Intermediate Shell Long.
111 86.6 76.6 Weld 2-442A Intermediate Shell Long.
111 83.3 73.3 Weld 2-442B Intermediate Shell Long.
111 83.3 73.3 Weld 2-442C Lower Shell Plate 98( 3) 83.0 78.4 B4713-1 Lower Shell Plate 103( 3) 87.6 82.4 B4713-2 Lower Shell Plate 121( 3 )
102.8 96.8 B4713-3 Lower Shell Long.
NA NA NA Weld 3-442A Lower Shell Long.
NA NA NA Weld 3-442B Lower Shell Long.
NA NA NA Weld 3-422C Intermediate to Lower NA NA NA Shell Girth Weld 9-442 NA - Unirradiated upper shelf energy not available because tests were not performed.
In these cases, the December 16, 1991 and EOL USE values were not calculated.
(1) December 16, 1991 USE values calculated at ~T location, based on fluences in PSE&G letter SCI-92-0357, 6/11/92, J. Perrin to J. Chicots.
(2)
EOL USE values calculated at l/4T location, based on fluences from PSE&G letter SCI-92-0319, 5/14/92, J. Perrin to J. Chicots.
(3)
Unirradiated USE values determined from transverse data. -
7 Revision 1  


NLR-N92150 TABLE 2 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on November 12, 1968.       (Corrected copy dated April 23, 1970).
NLR-N92150 TABLE 2 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on November 12, 1968.
Component:   Intermediate Shell Plate 84712-1                 Heat No.:     C-4173-1 Mill Chemical Analysis c         Mn         p         s         Si         Ni       Mo           Cu
(Corrected copy dated April 23, 1970).
  .21       1.33       .012     .016       .22         .56     .54         .13*
Component:
Intermediate Shell Plate 84712-1 Heat No.:
C-4173-1 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.21 1.33  
.012  
.016  
.22  
.56  
.54  
.13*  
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.
Longitudinal Charpy Impact and Fracture Tests Temp., op         Enerqy, ft-lbs           % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., op Enerqy, ft-lbs  
        -80                   8                   0                    4
-80 8  
        -80                   6                   0                    2
-80 6  
        -40                 20                   10                    16
-40 20  
        -40                 22                   10                    18
-40 22  
        -40                 21                   10                    17
-40 21  
        +10                 51                   25                    38
+10 51  
        +10                 52                   25                    39
+10 52  
        +10                 57                   25                    43
+10 57  
        +40                 69                   35                    51
+40 69  
        +40                 79                   35                    59
+40 79  
        +40                 75                   35                    56
+40 75  
        +110                 105                   85                    74
+110 105  
        +110                 111                   85                    82
+110 111  
        +160                 140                   100                  88
+160 140  
        +160                 136                   100                  90 Temp. OF       Drop Weights         NDT             RTNDT              USE
+160 136 Temp. OF Drop Weights NDT  
      +10             2NF             0°F               00F          90 ft-lbs 0             lF Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
+10 2NF 0°F 0
lF Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 0
8 Revision 1
0 10 10 10 25 25 25 35 35 35 85 85 100 100 RTNDT 00F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
8 Revision 1 Mils Lateral Exp.
4 2
16 18 17 38 39 43 51 59 56 74 82 88 90 USE 90 ft-lbs


NLR-N92150 TABLE 3 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
NLR-N92150 TABLE 3 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
Component:   Intermediate Shell Plate, B4712-1             Heat No.:   C-4173-1 Transverse Charpy Impact and Fracture Tests Temp., OF         Enerqy, ft-lbs         %  Shear      Mils Lateral Exp.
Component:
          -40                 12                   13                  6
Intermediate Shell Plate, B4712-1 Heat No.:
          -40                 23                 14                  16
C-4173-1 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
          -40                 26                   14                14
-40 12  
          +10                 39                   30                28
-40 23  
          +10                 31                 25                  26
-40 26  
          +10                 33                 25                  24
+10 39  
          +60                 52                 43                  41
+10 31  
          +60                 53                 42                  42
+10 33  
          +60                 51                   38                40
+60 52  
          +110                 81                   75                68
+60 53  
          +110                 93                   92                72
+60 51  
          +110                 76                   71                65
+110 81  
          +160                 97                   75                76
+110 93  
          +160                 101                 100                75
+110 76  
          +160                 101                 100                75
+160 97  
          +210                 103                 100                79
+160 101  
          +210                 111                 100                74
+160 101  
          +210                 105                 100                80 Temp., OF       Drop Weights         NDT             RTNDT              USE Performed by CE                 00F              00F           106 ft-lbs Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
+210 103  
+210 111  
+210 105 Temp., OF Drop Weights NDT Performed by CE 00F Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 13 14 14 30 25 25 43 42 38 75 92 71 75 100 100 100 100 100 1150°F +/- 25°F, 40 hours.
9 Revision 1
Furnace cooled to 600°F.
9 Revision 1 Mils Lateral Exp.
6 16 14 28 26 24 41 42 40 68 72 65 76 75 75 79 74 80 RTNDT USE 00F 106 ft-lbs


NLR-N92150 TABLE 4 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 3, 1968.           (Corrected copy dated April 23, 1970).
NLR-N92150 TABLE 4 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 3, 1968.
Components:   Intermediate Shell Plate B4712-2                 Heat No.:   C-4186-2 Mill Chemical Analysis c         Mn         p         s         Si         Ni       Mo         Cu
(Corrected copy dated April 23, 1970).
  .22       1.37
Components:
* 011     .OlS.       .24         .60     .SS         .14*
Intermediate Shell Plate B4712-2 Heat No.:
C-4186-2 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.22 1.37
* 011  
.OlS.  
.24  
.60  
.SS  
.14*  
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-S to PSE&G of October 10, 1977.
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-S to PSE&G of October 10, 1977.
Longitudinal Charpy Impact and Fracture Tests Temp., OF         Enerqy, ft-lbs             % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
          -40                   7                     0                  8
-40 7  
          -40                   12                     0                  9
-40 12  
          -40                   10                     0                  8
-40 10  
          +10                   21                   10                  20
+10 21  
          +10                 .37                     lS                  31
+10  
          +10                   30                     lS                  26
.37  
          +40                   62                   30                  46
+10 30  
          +40                   49                   2S                  39
+40 62  
          +40                   SS                     30                  42
+40 49  
        +110                   96                     70                  69
+40 SS  
        +110                   98                     80                  70
+110 96  
        +110                   90                     70                  67
+110 98  
        +160                 124                   100                  86
+110 90  
        +160                 134                   100                  92
+160 124  
        +160                 12S                   100                  88 Temp., OF       Drop Weights             NDT           RTNDT              USE 0               lNF
+160 134  
      -10             2NF               -20F             1°F        83 ft-lbs
+160 12S Temp., OF Drop Weights NDT 0
      -20               lF Heat Treatment lSSO - 16S0°F, 4 hours. Water quenched.
lNF  
-10 2NF  
-20F  
-20 lF Heat Treatment lSSO -
16S0°F, 4 hours.
Water quenched.
122S°F +/- 2S°F, 4 hours.
122S°F +/- 2S°F, 4 hours.
11S0°F +/- 2S°F, 40 hours. Furnace cooled to 600°F.
Shear 0
10 Revision 1
0 0
10 lS lS 30 2S 30 70 80 70 100 100 100 RTNDT 1°F 11S0°F +/- 2S°F, 40 hours.
Furnace cooled to 600°F.
10 Revision 1 Mils Lateral Exp.
8 9
8 20 31 26 46 39 42 69 70 67 86 92 88 USE 83 ft-lbs


NLR-N92150 TABLE 5 SALEM UNIT 2 Materials Certification Information The following information was taken from WCAP-8824, "PSE&G Co. Salem Unit No.
NLR-N92150 TABLE 5 SALEM UNIT 2 Materials Certification Information The following information was taken from WCAP-8824, "PSE&G Co. Salem Unit No.
2 Reactor Vessel Radiation Surveillance Program," January 1977 and the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
2 Reactor Vessel Radiation Surveillance Program," January 1977 and the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
Component:   Intermediate Shell Plate, 84712-2                   Heat No.:     C-4186-2 Chemical Analysis c     Mn     p     s     Si   Ni     Mo   Cu     Cr     Co   N?     Al     Sn
Component:
.23   1.34   .015   .010   .30   .61     .55   .10   .089   .015 .004   .030   .008 Transverse Charpy Impact and Fracture Tests Temp., OF           Enerqv, ft-lbs           % Shear          Mils Lateral Exp.
Intermediate Shell Plate, 84712-2 Heat No.:
        -40                     12                   10                      5
C-4186-2 Chemical Analysis c
        -40                     8                   15                      3
Mn p
        -40                     12                   10                      7 0                     34                   25                      26 0                     34                   25                      27 0                     24                   18                      18
s Si Ni Mo Cu Cr Co N?
        +40                     39                   35                      28
Al Sn  
        +40                     36                   34                      28
.23 1.34  
        +40                     43                   34                      34 RT                     58                   52                      46 RT                     58                   52                      47 RT                     61                   52                      49
.015  
        +110                   64                   62                    51
.010  
        +110                   74                   68                    61
.30  
        +110                   70                   68                    57
.61  
        +210                   100                  100                     80
.55  
        +210                   87                   100                    71
.10  
        +210                   104                   100                    75 Temp., OF       Drop Weights           NDT               RTNDT              USE Performed by CE                 -20°F              12°F          97 ft-lbs Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
.089  
1225°F +/- 25°F, 4 hours. Air cooled.
.015  
1150°F +/- 25°F, 40 hours. Furnace cooled.
.004  
11 Revision 1
.030  
.008 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs  
-40 12  
-40 8  
-40 12 0
34 0
34 0
24  
+40 39  
+40 36  
+40 43 RT 58 RT 58 RT 61  
+110 64  
+110 74  
+110 70  
+210 100  
+210 87  
+210 104 Temp., OF Drop Weights NDT Performed by CE 1550 -
1650°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours.  
-20°F Heat Treatment Water quenched.
Air cooled.
Furnace cooled.
11 Revision 1 Shear Mils Lateral Exp.
10 5
15 3
10 7
25 26 25 27 18 18 35 28 34 28 34 34 52 46 52 47 52 49 62 51 68 61 68 57 100 80 100 71 100 75 RTNDT USE 12°F 97 ft-lbs


NLR-N92150 TABLE 6 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc., on October 4, 1968.       (Corrected copy dated April 23, 1970).
NLR-N92150 TABLE 6 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc., on October 4, 1968.
Component:   Intermediate Shell Plate B4712-3                 Heat No.:   C-4194-2 Mill Chemical Analysis c         Mn         p         s       Si         Ni       Mo           Cu
(Corrected copy dated April 23, 1970).
  .22       1.37       .010     .016       .26         .57     .52         .11*
Component:
Intermediate Shell Plate B4712-3 Heat No.:
C-4194-2 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.22 1.37  
.010  
.016  
.26  
.57  
.52  
.11*  
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.
*Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.
Longitudinal Charpy Impact and Fracture Tests Temp., OF           Enerqy, ft-lbs           % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
          -40                 12                     a                  10
-40 12  
          -40                 11                     a                  9
-40 11  
          -40                   9                     a                  7
-40 9  
        +10                   33                   20                  26
+10 33  
        +10                   34                   20                  24
+10 34  
        +10                   28                   20                 23
+10 28  
+40 49
+40 50
+40 38
+110 100
+110 91
+110 79
+160 116
+160 122
+160 110 Temp. OF Drop Weights NOT a
lNF
-20 lNF
-40 2NF
-so lF
-50°F
-60 lF Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
Shear a a a 20 20 20 30 30 25 85 80 75 100 100 100 RTNDT 22°F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
12 Revision 1 Mils Lateral Exp.
10 9
7 26 24 23
(
(
        +40                  49                   30                  49
49 49 32 75 68 60 82 84 80 USE 75 ft-lbs  
        +40                  50                    30                  49
        +40                  38                  25                  32
        +110                100                    85                  75
        +110                  91                    80                  68
        +110                  79                    75                  60
        +160                116                  100                  82
        +160                122                  100                  84
        +160                110                  100                  80 Temp. OF        Drop Weights          NOT            RTNDT              USE a              lNF
      -20              lNF
      -40              2NF
      -so              lF            -50°F            22°F        75 ft-lbs
      -60              lF Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
12 Revision 1


NLR-N92150 TABLE 7 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
NLR-N92150 TABLE 7 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
Component:   Intermediate Shell Plate, 84712-3             Heat No.:   C-4194-2 Transverse Charpy Impact and Fracture Tests Temp., OF         Enerqy, ft-lbs         %  Shear      Mils Lateral Exp.
Component:
        -40                 12                   14                  5
Intermediate Shell Plate, 84712-3 Heat No.:
        -40                 32                   13                  13
C-4194-2 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
        -40                   8                   9                  3
-40 12  
        +10                 32                   25                  26
-40 32  
        +10                 32                   29                  22
-40 8  
        +10                 30                   25                  19 RT                 55                 47                  44 RT                 53                 47                  41 RT                 58                 42                  45
+10 32  
      +110                 75                   64                  59
+10 32  
      +110                 69                   59                  56
+10 30 RT 55 RT 53 RT 58  
      +110                 78                   69                  60
+110 75  
      +160                 91                   92                  72
+110 69  
      +160                 98                   92                  76
+110 78  
      +160                 95                 100                  72
+160 91  
      +210                 103                 100                  79
+160 98  
      +210                 110                 100                  82
+160 95  
      +210                 107                 100                  83 Temp., OF       Drop Weights         NDT           RTNDT              USE Performed by CE               -50°F           10°F        107 ft-lbs Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
+210 103  
+210 110  
+210 107 Temp., OF Drop Weights NDT Performed by CE  
-50°F Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 14 13 9
13 Revision 1
25 29 25 47 47 42 64 59 69 92 92 100 100 100 100 RTNDT 10°F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
13 Revision 1 Mils Lateral Exp.
5 13 3
26 22 19 44 41 45 59 56 60 72 76 72 79 82 83 USE 107 ft-lbs


NLR-N92150 TABLE 8 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on March 15, 1971 and "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl. 5-020, November 1985.
NLR-N92150 TABLE 8 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on March 15, 1971 and "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl. 5-020, November 1985.
Component:   Welds 2-442A, 2-442B, and 2-442C           Heat No.: 13253 & 20291 (tandem)
Component:
Flux: Linde 1092, Lot No. 3833 Chemical Analysis c        Mn        p          s        Si      Ni        Mo       Cu       Cr
Welds 2-442A, 2-442B, and 2-442C Chemical Analysis c
  .12      1.29    .019        .012      .19      .73      .48     .23       .028 Charpy Impact and Fracture Tests Temp., OF           Enerqv, ft-lbs           %  Shear        Mils Lateral Exp.
Mn p
        -80                     19                   0                  16
s Si Ni
        -80                     26                   10                  21
.12 1.29
        -40                     54                   25                  40
.019
        -40                     39                   20                  31
.012
        +10                     83                   60                  65
.19
        +10                     94                   70                  72
.73 Heat No.: 13253 & 20291 (tandem)
        +10                     85                   60                  69
Flux:
        +40                     83                   70                  63
Linde 1092, Lot No. 3833 Mo Cu Cr  
        +40                     92                   80                  70
.48  
        +40                     97                   80                  76
.23  
        +110                   105                 100                  80
.028 Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs  
        +110                   108                 100                  84
-80 19  
        +110                   119                 100                  89
-80 26  
        +160                   113                 100                  87
-40 54  
        +160                   115                 100                  86 Temp., OF       Drop Weights             NDT             RTNDT            USE
-40 39  
      -40                 lF
+10 83  
      -30               2NF
+10 94  
      -20               lNF             -40°F           -40°F         111 ft-lbs 0                lNF Heat Treatment 1150°F for 12 hours.
+10 85  
14 Revision 1
+40 83  
+40 92  
+40 97  
+110 105  
+110 108  
+110 119  
+160 113  
+160 115 Temp., OF Drop Weights NDT  
-40 lF  
-30 2NF  
-20 lNF 0
lNF 1150°F for 12 hours.
-40°F Heat Treatment 14 Revision 1 Shear Mils Lateral Exp.
0 16 10 21 25 40 20 31 60 65 70 72 60 69 70 63 80 70 80 76 100 80 100 84 100 89 100 87 100 86 RTNDT USE
-40°F 111 ft-lbs  


NLR-N92150
NLR-N92150
* TABLE 9 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc. on August 19, 1969.
* TABLE 9 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc. on August 19, 1969.
Component:   Lower Shell Plate 84713-1                 Heat No.: C-4182-1 Mill Chemical Analysis c         Mn         p         s         Si         Ni       Mo           Cu
Component:
  .22       1.32       .010     .015       .22         .60     .54         .12*
Lower Shell Plate 84713-1 Heat No.:
C-4182-1 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.22 1.32  
.010  
.015  
.22  
.60  
.54  
.12*
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
Longitudinal Charpy Impact and Fracture Tests Temp., OF         Enerav, ft-lbs           % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerav, ft-lbs  
          -80                   9                   0                    6
-80 9  
          -80                 13                   0                  12
-80 13  
          -40                 25                   10                  21
-40 25  
          -40                 44                   20                  34
-40 44  
          -40                 16                     5                  12
-40 16  
          +10                 36                   10                  28
+10 36  
          +10                 65                   30                  46
+10 65  
          +10                 61                   30                  46
+10 61  
          +40                 60                   30                  47
+40 60  
          +40                 68                   40                  49
+40 68  
          +40                 64                   35                  48
+40 64  
        +110                 93                   80                  73
+110 93  
        +110                 108                   85                  75
+110 108  
        +160                 131                   100                  88
+160 131  
        +160                 123                   100                  88 Temp., OF       Drop Weights         NDT             RTNDT              USE 0               2NF
+160 123 Temp., OF Drop Weights NDT 0
      -10               lF             -10°F            -10°F       82.5 ft-lbs
2NF  
      -20               lF Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
-10 lF  
-10°F  
-20 lF Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 0
15 Revision 1
0 10 20 5
10 30 30 30 40 35 80 85 100 100 RTNDT
-10°F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
15 Revision 1 Mils Lateral Exp.
6 12 21 34 12 28 46 46 47 49 48 73 75 88 88 USE 82.5 ft-lbs


NLR-N92150 TABLE 10 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
NLR-N92150 TABLE 10 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
Component:   Lower Shell Plate, B4713-1             Heat No.: C-4182-1 Transverse Charpy Impact and Fracture Tests Temp., OF         Energy, ft-lbs         % Shear       Mils Lateral Exp.
Component:
        -40                 lS                   lS                10
Lower Shell Plate, B4713-1 Heat No.:
        -40                 20                 14                lS
C-4182-1 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs  
        -40                 16                 14                  8
% Shear  
        +10                 29                 2S                26
-40 lS  
        +10                 39                 2S                28
-40 20  
        +10                 29                 46                2S
-40 16  
        +SO                 44                 40                36
+10 29  
        +SO                 40                  40                 33
+10 39  
        +SO                 S7                 40                44
+10 29  
        +80                 S6                   S2                48
+SO 44  
        +80                 60                   S2                48
+SO 40  
        +80                 71                   S4                S6
+SO S7  
      +140                 91                 92                72
+80 S6  
      +140                 89                 92                70
+80 60  
      +140                 88                   90                73
+80 71  
      +210                 90                 100                72
+140 91  
      +210                 106                 100                80
+140 89  
      +210                 99                 100                78 Temp., OF     Drop Weights         NOT           RTNDT            USE Performed by CE               -10°F           8°F        98 ft-lbs Heat Treatment lSSO - 16S0°F, 4 hours. Water quenched.
+140 88  
+210 90  
+210 106  
+210 99 Temp., OF Drop Weights NOT Performed by CE  
-10°F Heat Treatment lSSO -
16S0°F, 4 hours.
Water quenched.
122S°F +/- 2S°F, 4 hours.
122S°F +/- 2S°F, 4 hours.
11S0°F +/- 2S°F, 40 hours. Furnace cooled to 600 °F.
lS 14 14 2S 2S 46 40 40 40 S2 S2 S4 92 92 90 100 100 100 11S0°F +/- 2S°F, 40 hours.
16 Revision 1
Furnace cooled to 600 °F.
16 Revision 1 RTNDT 8°F Mils Lateral Exp.
10 lS 8
26 28 2S 36 33 44 48 48 S6 72 70 73 72 80 78 USE 98 ft-lbs


NLR-N92150 TABLE 11 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 28, 1969.
NLR-N92150 TABLE 11 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 28, 1969.
Component:   Lower Shell Plate B4713-2                 Heat No.: C-4182-2 Mill Chemical Analysis c         Mn         p         s         Si         Ni       Mo         Cu
Component:
  .22       1.28       .010     .015       .24         .57     .53         .12*
Lower Shell Plate B4713-2 Heat No.:
C-4182-2 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.22 1.28  
.010  
.015  
.24  
.57  
.53  
.12*
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
Longitudinal Charpy Impact and Fracture Tests Temp., OF         Energy, ft-lbs           % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs  
          -80                   6                     0                  3
-80 6  
          -so                 13                     0                  7
-so 13  
          -40                 43                   20                31
-40 43  
          -40                 13                     5                12
-40 13  
          -40                 22                   10                16
-40 22  
          +10                 56                   25                  38
+10 56  
          +10                 42                   20                  31
+10 42  
          +10                 58                   25                  40
+10 58  
          +40                 79                   35                58
+40 79  
          +40                 72                   30                52
+40 72  
          +40                 89                   40                63
+40 89  
        +110                 101                   70                70
+110 101  
        +110                 112                   80                  78
+110 112  
        +160                 136                   100                74
+160 136  
        +160                 135                   100                76 Temp., OF       Drop Weights         NDT             RTNDT            USE
+160 135 Temp., OF Drop Weights NDT  
      -20               lF
-20 lF  
      -10             2NF 0               lNF             -20°F           -20°F        88 ft-lbs Heat Treatment 1550°F - 1650°F, 4 hours. Water quenched.
-10 2NF 0
lNF  
-20°F Heat Treatment 1550°F -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 0
17 Revision 1
0 20 5
10 25 20 25 35 30 40 70 80 100 100 RTNDT
-20°F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
17 Revision 1 Mils Lateral Exp.
3 7
31 12 16 38 31 40 58 52 63 70 78 74 76 USE 88 ft-lbs


  .NLR-N92150
. NLR-N92150
* TABLE 12 SALEM UNIT 2 Materials certification Information The following information was taken*from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
* TABLE 12 SALEM UNIT 2 Materials certification Information The following information was taken*from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.
Component:   Lower Shell Plate, B4713-2             Heat No.: C-4182-2 Transverse Charpy Impact and Fracture Tests Temp., OF         Energy, ft-lbs         % Shear       Mils Lateral Exp.
Component:
            -40                 12                 10                6
Lower Shell Plate, B4713-2 Heat No.:
            -40                 13                 10                9
C-4182-2 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs  
            -40                 20                   5              11 0                   35                 10              25 0                   27                 20              22 0                   32                 10              24
% Shear  
            +40                 38                 15              33
-40 12  
            +40                 51                 20              48
-40 13  
            +40                 34                 20              29
-40 20 0
            +80                 62                 47              49
35 0
            +80                 59                 55              50
27 0
            +80                 70                 61              57
32  
          +110                 80                 70              62
+40 38  
          +110                 84                 80              61
+40 51  
          +110                 85                 80                63
+40 34  
          +210                 106                 100              81
+80 62  
          +210                 107                 100              77
+80 59  
          +210                 96                 100              78 Temp., OF     Drop Weights         NDT           RTNDT            USE Performed by CE             -20°F           8°F        103 ft-lbs Heat Treatment 1550°F - 1650°F, 4 hours. Water quenched.
+80 70  
+110 80  
+110 84  
+110 85  
+210 106  
+210 107  
+210 96 Temp., OF Drop Weights NDT Performed by CE  
-20°F Heat Treatment 1550°F -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
10 10 5
18 Revision 1
10 20 10 15 20 20 47 55 61 70 80 80 100 100 100 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
18 Revision 1 RTNDT 8°F Mils Lateral Exp.
6 9
11 25 22 24 33 48 29 49 50 57 62 61 63 81 77 78 USE 103 ft-lbs


  'NLR-N92150 TABLE 13 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on August 8, 1969.
'NLR-N92150 TABLE 13 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on August 8, 1969.
Component:   Lower Shell Plate, B4713-3                       Heat No:   B-8343-1 Mill Chemical Analysis c         Mn           p         s         Si         Ni       Mo         Cu
Component:
      .25       1. 34       .012     .014       .28         .58     .53         .12*
Lower Shell Plate, B4713-3 Heat No:
B-8343-1 Mill Chemical Analysis c
Mn p
s Si Ni Mo Cu  
.25
: 1. 34  
.012  
.014  
.28  
.58  
.53  
.12*
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
* Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.
Longitudinal Charpy Impact and Fracture Tests Temp., OF         Enerqy, ft-lbs           % Shear      Mils Lateral Exp.
Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
            -40                   19                     0                  10
-40 19  
            -40                   14                     0                  12
-40 14  
            -40                   12                     0                  10
-40 12  
            +10                   36                   25                  27
+10 36  
            +10                   52                   30                    37
+10 52  
            +10                   40                   25                  30
+10 40  
            +40                   63                   35                    46
+40 63  
            +40                   74                   40                  53
+40 74  
            +40                   50                   30                    38
+40 50  
            +110                 104                   85                    80
+110 104  
            +110                 108                   90                  82
+110 108  
            +110                 103                   80                  77
+110 103  
            +160                 135                   100                  85
+160 135  
            +160                 135                   100                  88
+160 135  
            +160                 136                   100                  91 Temp., OF       Drop Weights         NDT             RTNDT              USE
+160 136 Temp., OF Drop Weights NDT  
          -20               lF
-20 lF  
          -10               lF 0               2NF             -10°F             00F          88 ft-lbs Heat Treatment 1550 - 1650°F, 4 hours. Water quenched.
-10 lF 0
2NF  
-10°F Heat Treatment 1550 -
1650°F, 4 hours.
Water quenched.
1225°F +/- 25°F, 4 hours.
1225°F +/- 25°F, 4 hours.
1150°F +/- 25°F, 40 hours. Furnace cooled to 600°F.
Shear 0
19 Revision 1
0 0
25 30 25 35 40 30 85 90 80 100 100 100 RTNDT 00F 1150°F +/- 25°F, 40 hours.
Furnace cooled to 600°F.
19 Revision 1 Mils Lateral Exp.
10 12 10 27 37 30 46 53 38 80 82 77 85 88 91 USE 88 ft-lbs


        .NLR-N92150 TABLE 14 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared.by Westinghouse Electric Corporation on June 6, 1973.
. NLR-N92150 TABLE 14 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared.by Westinghouse Electric Corporation on June 6, 1973.
Component:   Lower Shell Plate, B4713-3                     Heat No.:   B-8343-1 Transverse Charpy Impact and Fracture Tests Temp., OF         Energy, ft-lbs         %  Shear      Mils Lateral Exp.
Component:
                  -40                 19                     9                11.S
Lower Shell Plate, B4713-3 Heat No.:
                  -40                   8                     9                  s
B-8343-1 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs  
                  -40                 11                     9                  8
-40 19  
                  +10                 27                   23                . 14
-40 8  
                  +10                 37                   29                30.S
-40 11  
                  +10                 27                   29                  22
+10 27  
                  +SO                 46                   38                  38
+10 37  
                  +SO                 68                   40                  Sl
+10 27  
                  +so                 S6                   38                  41
+SO 46  
                +90                   82                   61                  64
+SO 68  
                +90                   70                   S6                  SS
+so S6  
                +90                   61                   47                  Sl
+90 82  
                +lSO                 103                   8S                  73
+90 70  
                +lSO                 9S                   8S                  73
+90 61  
                +lSO                 108                   90                  81
+lSO 103  
                +210                 119 ..               100                  83
+lSO 9S  
                +210                 120                   100                  83
+lSO 108  
                +210                 12S                   100                  82 Temp.~ OF     Drop Weights           NOT           RTNDT              USE Performed by CE                 -10°F           10°F        121 ft-lbs Heat Treatment lSSO - 16S0°F, 4 hours. Water quenched.
+210 119..  
+210 120  
+210 12S Temp.~ OF Drop Weights NOT Performed by CE  
-10°F Heat Treatment lSSO -
16S0°F, 4 hours.
Water quenched.
122S°F +/- 2S°F, 4 hours.
122S°F +/- 2S°F, 4 hours.
11S0°F +/- 2S°F, 40 hours. Furnace cooled to 600°F.
Shear 9
20 Revision 1
9 9
23 29 29 38 40 38 61 S6 47 8S 8S 90 100 100 100 RTNDT 10°F 11S0°F +/- 2S°F, 40 hours.
Furnace cooled to 600°F.
20 Revision 1 Mils Lateral Exp.
11.S s
8
. 14 30.S 22 38 Sl 41 64 SS Sl 73 73 81 83 83 82 USE 121 ft-lbs


    .NLR-N92150 TABLE 15 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl.5-020, November 1985 and CE Welding Material Qualification, October 27, 1969.
.NLR-N92150 TABLE 15 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl.5-020, November 1985 and CE Welding Material Qualification, October 27, 1969.
Component:               Weld 3-442A, 3-442B, and 3-442C                       Heat No.:         21935 and 12008 (tandem)
Component:
Flux: Linde 1092, Lot No. 3889 Chemical Analysis c                 Mn             p             s           Si           Ni             Mo             Cu
Weld 3-442A, 3-442B, and 3-442C Heat No.:
  ._____.;.*~1..::..1 ____.____1_._3_8___,____._0_l_5___,____._o_1_1___._____
21935 and 12008 (tandem)
                                                                            .1_5____.____*_8_6_____..____._5_5____._____._2_0___,
Flux: Linde 1092, Lot No. 3889 Chemical Analysis c
Charpy Impact and Fracture Tests Temp., OF           Energy, ft-lbs 10                     97 10                     90 10                     83 Full Charpy curve not performed.
Mn p
Temp., °F                 Drop Weights                   NOT              RTNDT                      USE No drop wt. test performed.                                                     -56°F (generic value per 10CFR 50.61 Heat Treatment 1150°F for 8 hours.
s Si Ni Mo Cu  
21 Revision 1
._____.;.*~1..::..1 __ __._ ___
1_._3_8 __ _,_ ___
._0_l_5 __ _,__ __._o_1_1 __ _._ ____
.1_5 ____.__ __ *_8_6 __ ___.. ____._5_5 __ __._ ____
._2_0 __ _,
Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs 10 97 10 90 10 83 Full Charpy curve not performed.
Temp., °F Drop Weights No drop wt. test performed.
1150°F for 8 hours.
NOT Heat Treatment 21 Revision 1 RTNDT
-56°F (generic value per 10CFR 50.61 USE


0 NLR-N92150 TABLE 16 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data", CE Inc. Design Input File TOl.S-020, November 1985 and CE Welding Material Qualification Report, October 7, 1970.
0NLR-N92150 TABLE 16 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data", CE Inc. Design Input File TOl.S-020, November 1985 and CE Welding Material Qualification Report, October 7, 1970.
Component: Weld 9-442                           Heat No.:   90099 Flux: Linde 0091, Lot No. 3977 Chemical Analysis c       Mn         p         s         Si         Ni         Mo      Cu
Component:
    .14     1.20     .021       .013       .22       .20*       .so    .175
Weld 9-442 Heat No.:
  *Estimated value.
90099 Flux:
Charpy Impact and Fracture Tests Temp., OF       Enerqv, ft-lbs 10                 56 10                 30 10                 52 Full Charpy-curve not performed.
Linde 0091, Lot No. 3977 Chemical Analysis c
Temp., OF     Drop Weights         NDT             RTNDT           USE No drop wt. test performed.           ---              -56°F           ---
Mn p
(generic value per 10CFR 50.61)
s Si Ni  
Heat Treatment 1150°F for 10.5 hrs.
.14 1.20  
22 Revision 1
.021  
.013  
.22  
.20*  
*Estimated value.
Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs 10 56 10 30 10 52 Full Charpy-curve not performed.
Temp., OF Drop Weights NDT RTNDT No drop wt. test performed.
1150°F for 10.5 hrs.
Heat Treatment 22 Revision 1
-56°F (generic value per 10CFR 50.61)
Mo Cu
.so
.175 USE


)l "}*
)l  
0 NLR-N92150 TABLE 17 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data" CE Inc., Design Input File TOl.S-020, November 198S, and WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program,"
"}*
0NLR-N92150 TABLE 17 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data" CE Inc., Design Input File TOl.S-020, November 198S, and WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program,"
January 1977.
January 1977.
Component:   Weld Surveillance Material          Heat No.:       132S3 Weldment made from intermediate shell plates B4712-l and             Flux: Linde 1092, Lot No. 3833 B4712-2                                  and Linde 1092, Lot No. 3774 Chemical Analysis c         Mn         p         s       Si       Ni       Mo         Cu        Cr
Component:
          .10       1.27     .017     .011       .29
Heat No.:
* 71       .4S       .23        .OlS Charpy Impact and Fracture Tests Temp., °F           Enerqv, ft-lbs         %   Shear         Mils Lateral Exp.
132S3 Weld Surveillance Material Weldment made from intermediate shell plates B4712-l and B4712-2 Flux: Linde 1092, Lot No. 3833 and Linde 1092, Lot No. 3774 Chemical Analysis c
                -100                     4.S                    2                    1
Mn p
                -100                     11                      6                    2.S
s Si Ni Mo  
                -100                     6                    lS                    1
.10 1.27  
                -so                     11                    18                    7.S
.017  
                -so                     4                     20                    11
.011  
                -so                    3S.S                   29                    27 0                    48.S                   S2                    42 0                    72                     S2                    36 0                    63.S                   62                    so 40                    71                     S9                    S6 40                    so.s                   SS                    44 40                    80.S                   79                    62 100                    86                   100                    81 100                    96.S                   90                    74.S 100                    106.S                 100                    80 210                    112                     98                    82 210                    111. s                 100                    86 210                    111. s                 100                    8S.S Temp., °F     Drop Weights           NOT              RTNDT              USE Performed by CE                   -40°F             -20°F         111 ft-lbs Heat Treatment 11S0°F for 40 hours 23 Revision 1
.29
* 71  
.4S Charpy Impact and Fracture Tests Temp., °F Enerqv, ft-lbs  
% Shear  
-100  
-100  
-100  
-so  
-so  
-so 0
0 0
40 40 40 100 100 100 210 210 210 4.S 11 6
11 4
3S.S 48.S 72 63.S 71 so.s 80.S 86 96.S 106.S 112 111. s 111. s Temp., °F Drop Weights Performed by CE 11S0°F for 40 hours NOT
-40°F Heat Treatment 23 Revision 1 2
6 lS 18 20 29 S2 S2 62 S9 SS 79 100 90 100 98 100 100 RTNDT
-20°F Cu Cr
.23  
.OlS Mils Lateral Exp.
1 2.S 1
7.S 11 27 42 36 so S6 44 62 81 74.S 80 82 86 8S.S USE 111 ft-lbs


NLR-N92150
NLR-N92150
* TABLE 18 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. March lS, 1971.
* TABLE 18 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. March lS, 1971.
Component:     Weld Heat Affected Zone (Seam No. 2-442)
Component:
Weld Heat Affected Zone (Seam No. 2-442)
Chemical Analysis Information not available (analyses were not performed)
Chemical Analysis Information not available (analyses were not performed)
Charpy Impact and Fracture Tests Temo., OF             Energy, ft-lbs          %  Shear      Mils Lateral Exp.
Temo., OF  
      -110                       lS                  0                12
-110  
      -i10                       26                  10                19
-i10  
        ..:90                     41                  20                31
..:90  
        -80                       46                  20                36
-80  
        -40.                     4S                  30                38
-40.  
        ...;40                   SS                  40                46
...;40  
        -40                       47                  30                39
-40  
        +10                       68                  70                60
+10  
        +10                       87                80                  76
+10  
        +10                       83                80                  71
+10  
        +40                     lOS                9S                  86
+40  
        +40                     100                90                  83
+40  
        +40                     104                9S                  80
+40  
      +110                       8S                100                84
+110  
      +110                     104                100                98 Temp., OF         Drop Weights          NDT
+110 Temp., OF 0  
* RTNDT          USE 0                   lF
+10 11S0°F +/- 2S°F, Charpy Impact and Fracture Tests Energy, ft-lbs lS 26 41 46 4S SS 47 68 87 83 lOS 100 104 8S 104 Drop Weights lF 2NF 40 hours.
    +10                 2NF              00F              00F      94.S ft-lbs Heat Treatment 11S0°F +/- 2S°F, 40 hours.
NDT 00F Heat Treatment 24 Revision 1 Shear 0
24 Revision 1
10 20 20 30 40 30 70 80 80 9S 90 9S 100 100
* RTNDT 00F Mils Lateral Exp.
12 19 31 36 38 46 39 60 76 71 86 83 80 84 98 USE 94.S ft-lbs


NLR-N92150 TABLE 19 SALEM UNIT 2 Materials Certification Information The following information was taken from the WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program January 1977."
NLR-N92150 TABLE 19 SALEM UNIT 2 Materials Certification Information The following information was taken from the WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program January 1977."
Component:   Weld Heat Affected Zone Surveillance Material (HAZ material obtained from 84712-2 of Weldment made from intermediate shell plate 84712-1 and 84712-2)
Component:
Weld Heat Affected Zone Surveillance Material (HAZ material obtained from 84712-2 of Weldment made from intermediate shell plate 84712-1 and 84712-2)
Chemical Analysis Information not available (analyses were not performed on HAZ).
Chemical Analysis Information not available (analyses were not performed on HAZ).
Charpy Impact and Fracture Tests Temp., OF         Enerqy, ft-lbs         %  Shear      Mils Lateral Exp.
Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs  
      -125                 51                   33              24.5
-125 51  
      -125                 23                   6              15
-125 23  
      -125                 28                 12                10. 5
-125 28  
        -75                 122                 100              63
-75 122  
        -75                 36                   17              17
-75 36  
        -75                 66.5                 42              34
-75 66.5  
        -25                 79                   66              48
-25 79  
        -25                 93.5                 48              47
-25 93.5  
        -25                 76                   51              37 25                 131                 96                69 25                 111                 88                72 25                 74                   60              45 100                 101                 100              66.5 100                 114                 100               70 100                179                 100              78.5 210                 118.5                100              79.5 210                 115                 100              72.5 210                 106.5               100              75 Temp., OF       Drop Weights         NDT            RTNDT          USE Performed by CE                 00F            0°F      113 ft-lbs Heat Treatment 1150°F for 40 hours.
-25 76 25 131 25 111 25 74 100 101 100 114 100 179 210 118.5 210 115 210 106.5 Temp., OF Drop Weights Performed by CE 1150°F for 40 hours.
25 Revision 1
NDT 00F Heat Treatment 25 Revision 1 Shear 33 6
 
12 100 17 42 66 48 51 96 88 60 100 100 100 100 100 100 RTNDT 0°F Mils Lateral Exp.
      *NLR-N92150 TABLE 20 SALEM UNIT 2 Measured Versus Predicted 30 ft-lb Temperature Increases And Upper Shelf Energy Decreases ARTNDT ( oF) ( 1, 2) Upper Shelf Energy (1)
24.5 15
Decrease (%)
: 10. 5 63 17 34 48 47 37 69 72 45 66.5 70 78.5 79.5 72.5 75 USE 113 ft-lbs
Material     Capsule     Fluence     Measured   Predicted   Measured     Predicted no 19 n/cm2) 84712-2 (long.)       T           0.276         so           99         6           14 84712-2 (long.)       u           0.57           70         118         8           17 84712-2 (long.)       x           1.16           80         138         1           20 84712-2               T           0.276         70           99         8           14 (transverse) 84712-2               u           0.57           95         118       13           17 (transverse) 84712-2               x           1.16         125         138         8           20 (transverse)
* NLR-N92150 TABLE 20 SALEM UNIT 2 Measured Versus Predicted 30 ft-lb Temperature Increases And Upper Shelf Energy Decreases ARTNDT ( oF) ( 1, 2)
Weld Metal             T           0.276         155         180       29( 3 )       27.S Weld Metal             u           0.57         190         217       33( 3 )       32 Weld Metal             x           1.16         195         255         22           38 (1) Predicted values based on Regulatory Guide 1.99, Revision 2 Methodology.
Upper Shelf Energy Decrease (%)
(2) Predicted ARTNDT includes 2crA as defined in Regulatory Guide 1.99, Revision 2.
(1)
(3) Exceeds predicted value.
Material Capsule Fluence Measured Predicted Measured Predicted no19 n/cm2) 84712-2 (long.)
26 Revision 1
T 0.276 so 99 6
14 84712-2 (long.)
u 0.57 70 118 8
17 84712-2 (long.)
x 1.16 80 138 1
20 84712-2 T
0.276 70 99 8
14 (transverse) 84712-2 u
0.57 95 118 13 17 (transverse) 84712-2 x
1.16 125 138 8
20 (transverse)
Weld Metal T
0.276 155 180 29( 3 )
27.S Weld Metal u
0.57 190 217 33( 3 )
32 Weld Metal x
1.16 195 255 22 38 (1) Predicted values based on Regulatory Guide 1.99, Revision 2 Methodology.
(2) Predicted ARTNDT includes 2crA as defined in Regulatory Guide 1.99, Revision 2.
(3) Exceeds predicted value.
26 Revision 1  


NLR-N92150 TABLE 21 SALEM UNIT 2 Adjusted Reference Temperatures (ART) As Predicted By Surveillance Data ART (oF)             ART (OF)       Screening Material Description   December 16, 1991       April 18, 2020   Criterion B4712-l           96.3 (96.3)**         131.9 ( 131. 9)     270 B4712-2*           85.4 (96.4)           123.8 (134.8)       270 B4712-3           107.1 (95.1)           136.3 (124.3)       270 2-442A*                 105.7               190.9           270 2-442B*                 132.5               215.4           270 2-442C*                 132.5               215.4           270 Weld Surveillance Material                 152.5               235.4           270 B4713-1             81. 7 (99.7)         115.3 (133.3)       270 B4713-2             71.3 (99.3)         104.6 (132.6)       270 B4713-3           91.4 ( 101. 4)       124.9 (134.9)       270 3-442A                 134.5               216.8           270 3-442B                 108.5               190.0           270 3-442C                 134.5               216.8           270 9-442                   75.8               113.6           300
NLR-N92150 TABLE 21 SALEM UNIT 2 Adjusted Reference Temperatures (ART) As Predicted By Surveillance Data ART (oF)
* RTNDT based on surveillance capsule chemistry factor.
ART (OF)
      **  The numbers in () for B4712-l, B4712-2, B4712-3, B4713-1, B4713-2 and B4713-3 are calculated using the initial RTNDT values determined by Westinghouse from transverse Charpy test data. The corresponding numbers not in () are calculated using the initial RTNDT values determined from the original fabrication records with longitudinal Charpy test data.
Screening Material Description December 16, 1991 April 18, 2020 Criterion B4712-l 96.3 (96.3)**
27 Revision 1
131.9 ( 131. 9) 270 B4712-2*
85.4 (96.4) 123.8 (134.8) 270 B4712-3 107.1 (95.1) 136.3 (124.3) 270 2-442A*
105.7 190.9 270 2-442B*
132.5 215.4 270 2-442C*
132.5 215.4 270 Weld Surveillance Material 152.5 235.4 270 B4713-1
: 81. 7 (99.7) 115.3 (133.3) 270 B4713-2 71.3 (99.3) 104.6 (132.6) 270 B4713-3 91.4 ( 101. 4) 124.9 (134.9) 270 3-442A 134.5 216.8 270 3-442B 108.5 190.0 270 3-442C 134.5 216.8 270 9-442 75.8 113.6 300 RTNDT based on surveillance capsule chemistry factor.
The numbers in () for B4712-l, B4712-2, B4712-3, B4713-1, B4713-2 and B4713-3 are calculated using the initial RTNDT values determined by Westinghouse from transverse Charpy test data.
The corresponding numbers not in () are calculated using the initial RTNDT values determined from the original fabrication records with longitudinal Charpy test data.
27 Revision 1  


. NLR-N92150 TABLE 22 SALEM UNIT 2 Upper Shelf Energy (USE) As Predicted By Surveillance Data USE (ft-lbs)       USE (ft-lbs)   EOL USE (ft-lbs)
. NLR-N92150 TABLE 22 SALEM UNIT 2 Upper Shelf Energy (USE) As Predicted By Surveillance Data USE (ft-lbs)
Material Description     Unirradiated     December 16, 1991 April 18, 2020 B4712-l                       106               90.1       83.7 B4712-2 (long.)*               122               114. 7       111.0 B4712-2 (trans.)*               97               87.3       83.4 B4712-3                       107               92.0       86.7 2-442A*                       111               86.6       76.6 2-442B*                       111               83.3       72.2 2-442C*                       111               83.3       72 .2 Weld Surveillance             111               83.3       72 .2 Material*
USE (ft-lbs)
B4713-1                       98                 83.3       78.4 B4713-2                       103               87.6       82. 4 -
EOL USE (ft-lbs)
B4713-3                       121               102.8       96.8 3-442A                       NA**                 NA         NA 3-442B                       NA                   NA         NA 3-422C                       NA                   NA         NA 9-442                         NA                   NA         NA Weld HAZ*                     113                 87.0       75.7
Material Description Unirradiated December 16, 1991 April 18, 2020 B4712-l 106 90.1 83.7 B4712-2 (long.)*
* USE based on surveillance data trending on Figure 2 of Reg. Guide 1.99 Revision 2. All other USE predictions based on Cu content, using Figure 2 of Reg. Guide 1.99 Revision 2.
122 114. 7 111.0 B4712-2 (trans.)*
  **    NA - Unirradiated upper shelf energy not available because tests were not done in the upper shelf region.
97 87.3 83.4 B4712-3 107 92.0 86.7 2-442A*
111 86.6 76.6 2-442B*
111 83.3 72.2 2-442C*
111 83.3 72.2 Weld Surveillance 111 83.3 72.2 Material*
B4713-1 98 83.3 78.4 B4713-2 103 87.6
: 82. 4 -
B4713-3 121 102.8 96.8 3-442A NA**
NA NA 3-442B NA NA NA 3-422C NA NA NA 9-442 NA NA NA Weld HAZ*
113 87.0 75.7 USE based on surveillance data trending on Figure 2 of Reg. Guide 1.99 Revision 2.
All other USE predictions based on Cu content, using Figure 2 of Reg. Guide 1.99 Revision 2.
NA - Unirradiated upper shelf energy not available because tests were not done in the upper shelf region.
28 Revision 1}}
28 Revision 1}}

Latest revision as of 02:15, 6 January 2025

Forwards Rev 1 Response to GL 92-01 Re Reactor Vessel Structural Integrity
ML18096B186
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/30/1992
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NLR-N92150, NUDOCS 9301070112
Download: ML18096B186 (32)
v • d • e


Text

i I Public Service Electric and Gas Company Stanley LaBruna Public Service 1Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DEC 3 O 1992 NLR-N92150 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SUPPLEMENTAL RESPONSE TO GENERIC LETTER 92-01,_REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY, 10CFR~0.54(f)

SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Generic Letter 92-01, Revision 1 requested PSE&G to submit information to enable the NRC to assess compliance with 10CFR50.60 and 10CFR50.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Boundary set forth in.10CFR50, Appendices G and H.

The Salem Units 1 and 2 responses to Generic Letter 92-01, Revision 1 were submitted to the NRC in Letter NLR-N92081 dated June 30, 1992.

This submittal included longitudinal Charpy V-notch impact data for the six (6) pressure vessel beltline plates originally generated by Combustion Engineering in 1968 and 1969.

It also included transverse Charpy V;notch impact data generated by Westinghouse in June, 1973 for plate B4712-2 which is included in the surveillance capsule monitoring program.

Since the date of this submittal, Salem Unit 2 pressure vessel material transverse Charpy V-notch impact data was located by Westinghouse for the remaining five (5) beltline plates used in the fabrication of the pressure vessel.

The data that Westinghouse recently found is for Charpy V-notch tests that Westinghouse conducted in June, 1973 while conducting the tests for plate B4712-2.

~he Salem Unit 2 response to the Generic Letter has therefore been revised to include this new Charpy V-notch data and is enclosed as Attachment 2.

At PSE&G's request, Westinghouse completed a search of their files and has determined that similar additional data does not exist for Salem Unit 1.

/-----

*...:.:..ho.m.. _.:-____ ~_

9301070112 921230 PDR ADOCK 05000311 P

PDR

~.

Document Control Desk NLR-N92150 2

DEC 3 O 1992 Please do not hesitate to contact us if there are any questions regarding this submittal.

Attachment Affidavit Sincerely, C

Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager U. s. Nuclear Regulatory Commission One White Flint North MC 14 E-21 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection

, Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

REF: NLR-N92150 STATE OF NEW JERSEY COUNTY OF SALEM

)

)

SS.

)

S. LaBruna, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations 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 No. 2, are true to the best of my knowledge, information and belief.

7#~

I 1992 My Commission expires ELIZABETH J. KIDD Notaiy Public of New Jersey My* Commission Expires April 25, 1995

NLR-N92150

  • ATTACHMENT 2 SALEM UNIT 2 RESPONSE TO GENERIC LETTER 92-01, REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY NOVEMBER 05, 1992 REVISION 1

NLR-N92150 PSE&G has prepared the following information in response to the requests in Generic Letter 92-01, Revision 1 titled "REACTOR VESSEL STRUCTURAL INTEGRITY".

In the following text, the individual requests for information are stated in boldface type as written in GL 92-01, and each request is followed by the PSE&G response in regular (non-boldface) type.

1.

Certain addressees are requested to provide the following information regarding Appendix H to CFR Part so:

Addressees who do not have a surveillance program meeting ASTM E 18S-73, -79, or -82 and who do not have an integrated surveillance program approved by the NRC (see Enclosure 2),

are requested to describe actions taken or to be taken to ensure compliance with Appendix H to 10 CFR Part so.

Addressees who plan to revise the surveillance program to meet Appendix II to 10 CFR Part so are requested to indicate when the revised program will be submitted to the NRC staff for review.

If the surveillance program is not to be revised to meet Appendix H to 10 CFR Part so, addressees are requested to indicate when they plan to request an exemption from Appendix H to 10 CFR Part so under 10 CFR S0.60(b).

Response

ASTM E-185-73 was the standard in place at the time the surveillance program was designed.

The Salem Unit 2 surveillance program complies with ASTM E-185-73.

Testing of surveillance capsules after July 26, 1983 has been performed in accordance with ASTM standard version E-185-82.

Furthermore, since the surveillance program design was approved during the FSAR licensing process, the capsule testing program has been approved as part of the plant Technical Specifications.

Therefore, it is determined that the surveillance program for Salem Unit 2 meets the requirements of Appendix H to 10 CFR Part 50 and that an exemption request is not considered necessary.

2.

Certain addressees are requested to provide the following information regarding Appendix G to 10 CFR Part so:

a.

Addressees of plants for which the Charpy upper shelf energy is predicted to be less than so foot-pounds at the end of their licenses using the guidance in Paragraphs c.1.2 or c.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or v.c of Appendix G to 10 CFR Part so.

1 Revision 1

NLR-N92150

Response

Table 1 contains the unirradiated, December 16, 1991 and EOL (April 18, 2020) Charpy upper shelf energy for Salem Unit 2 beltline materials.

The December 16, 1991 and EOL values were calculated using Figure 2 of Regulatory Guide 1.99, Revision 2.

The calculated EOL Charpy upper shelf energy for all the beltline materials which have known unirradiated USE values are predicted to be above the 50 ft-lb criteria.

b.

Addressees whose reactor vessels were constructed to an ASME Code earlier than the summer 1972 Addenda of the 1971 Edition are requested to describe the consideration given to the following material properties in their evaluations performed pursuant to 10 CFR 50.61 and Paragraph II.A of 10 CFR Part so, Appendix G:

Response

(1)

The results from all Charpy and drop weight tests for all unirradiated beltline materials, the unirradiated reference temperature for each beltline material, and the method of determining the unirradiated reference temperature from the Charpy and drop weight test; (2)

The heat treatment received by all beltline and surveillance materials; (3)

The heat number for each beltline plate or forging and the heat number of wire and flux lot number used to fabricate each beltline weld; (4)

The heat number for each surveillance plate or forging and the heat number of wire and flux lot number used to fabricate the surveillance weld; (5)

The chemical composition, in particular the weight in percent of copper, nickel, phosphorous, and sulfur for each beltline and surveillance material; and (6)

The heat number of the wire used for determining the weld metal chemical composition if different than Item (3) above.

The Salem Unit 2 reactor vessel was constructed to the 1965 Edition, through Winter 1966 Addenda to Section III of the ASME Code.

Thus, the Salem Unit 2 reactor vessel was constructed to an ASME Code earlier than the Summer 1972 Addenda of the 1971 Edition.

Tables 2 through 19 *document the unirradiated data (Charpy and drop weight test results, reference temperature, upper shelf energy, heat treatment, heat number, flux lot number 2

Revision 1

NLR-N92150

  • and chemical composition) for all beltline region and surveillance materials.

These values were developed using the material test requirements and acceptance standards that were current at the time of the reactor pressure vessel construction.

(Note that the chemical composition of the welds was determined from the weld wire heat numbers of the actual welds, except for weld 9-442, in which the nickel content was estimated to be the upper limit of type MIL B-4 wire heats).

The nil-ductility transition temperature (NDTT) is defined as the maximum temperature at which a standard drop weight specimen breaks when tested* according to the provisions specified in ASTM E-208, "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic steels".

The NDTT was determined for each beltline region material by drop weight tests (ASTM E-208) performed by Combustion Engineering except for welds 3-442A, 3-442B, 3-443C and 9-442.

The unirradiated reference temperature (RTNDT) of the beltline region materials was established from the drop weight NDTT tests and the Charpy V-notch tests, using the guidance provided in NUREG-0800, Branch Technical Position, MTEB 5-2, "Fracture Toughness Requirements", and the ASME Boiler and Pressure Vessel Code,Section III.

The following three paragraphs summarize pertinent information from these two references, and the fourth following paragraph summarizes information from 10CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock."

The NDTT temperature, as determined by drop weight tests (ASTM E-208) is the RTNDT if, at 60°F above the NDTT, at least 50 ft-lb of energy and 35 mils lateral expansion are obtained in Charpy V-notch tests on transverse specimens.

Otherwise, the RTNDT is the temperature at which 50 ft-lb and 35 mils lateral expansion are obtained on transverse Charpy specimens, minus 60°F.

If drop weight tests were not performed, but full Charpy V-notch curves were obtained, the NDTT for SA-533 Grade B, Class 1 plate and weld material may be assumed to be the higher of the 30 ft-lb temperature, or 0°F.

If transverse Charpy V-notch specimens were not tested, the temperature at which 50 ft-lb and 35 mils lateral expansion would have been obtained on transverse specimens may be estimated by using'65% of the values from longitudinal specimens, or increasing the 50 ft-lb and 35 mil lateral expansion temperatures for longitudinal specimens by 20°F.

3 Revision 1

NLR-N92150

  • If measured values of RTNDT are not available, the generic mean values must be used:

0°F for welds made with Linde 80 flux, and -56°F for welds made with Linde 0091, 1092 and 124, and ARCOS B-5 weld fluxes, as per 10 CFR50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."

The Charpy V-notch data for each of the beltline region plates tested by Combustion Engineering at the time of fabrication were taken in the longitudinal direction.

Westinghouse tested transverse Charpy V-notch specimens for each of the beltline region plates prior to developing the Salem 2 surveillance capsule testing program.

This transverse Charpy data was used in determining the initial RTNDT and initial USE values for the plates.

The RTNDT for each of these materials were determined to be the higher of (1) the value obtained by reducing the temperature at which 50 ft-lb and 35 mil lateral expansion was obtained by 60°F or (2) the NDTT.

The RTNDT for the intermediate shell longitudinal weld seams, 2-442A, B & C and the surv~illance weld HAZ was determined to be equal to the NDTT.

Full Charpy curves were not generated for lower shell longitudinal welds and the intermediate shell to lower shell circumferential weld seams; therefore, the generic mean value of -56°F is assumed.

The unirradiated upper shelf energy may be determined from Charpy V-notch tests using transverse specimen data (or using longitudinal data multiplied by 65% to estimate transverse data).

The upper shelf energy is the average of the transverse Charpy energy values for specimens exhibiting fully ductile behavior (i.e. 100% shear), at a given test temperature.

Typically, specimens are tested in sets of three at each test temperature.

The set having the highest average may be regarded as defining the upper shelf energy, as per ASTM E-185-82.

The upper shelf energy values for the beltline region plates were calculated by multiplying the average of the 100% shear longitudinal Charpy V-notch data by 65% for Combustion Engineering tests.

The upper shelf energy values for the beltine region surveillance test plates were determined by taking the average of the three 100%

shear energy values for the transverse data obtained in tests conducted by Westinghouse Electric Corporation.

The upper shelf energy values for the intermediate shell longitudinal weld and surveillance weld materials were determined by the average of the three 100% shear energy values.

Upper shelf energy values were not calculated for the lower shell longitudinal welds and intermediate to lower shell circumferential welds because full Charpy V-notch curves were not generated for these materials.

The surveillance material Charpy and tensile specimens received heat treatments, including stress relieving operations, equivalent to those given to the actual reactor vessel materials as required by Section III of the ASME Boiler and Pressure Vessel 4

Revision 1

NLR-N92150 Code.

Combustion Engineering supplied Westinghouse Electric Corporation with sections of A533 Grade B, Class 1 plate used in the core region of the Salem Unit 2 reactor pressure vessel for use in the Reactor Vessel Radiation Surveillance Program.

The sections of material were removed from the 9 5/8-inch intermediate shell plate B4712-2 of the pressure vessel.

Combustion Engineering, Inc., also supplied a weldment made from sections of the intermediate shell plate B4712-2 ~nd adjoining intermediate shell plate B4712-1 using weld wire representative of that used in the original fabrication.

The heat treatment histories of the pressure vessel beltline region material and

'surveillance materials are given in Tables 2 through 19.

3.

Addressees are requested to provide the following information regarding commitments made to respond to GL 88-11:

Response

a.

How the embrittlement effects of operating at an irradiation temperature (cold leg or recirculation suction temperature) below 525°F were considered.

In particular licensees are requested to describe consideration given to determining the effect of.

lower irradiation temperature on the reference temperature and on the Charpy upper shelf energy.

The PSE&G Operations Department performed a review of its policies and procedures to determine if the stated scenario, i.e., cold leg temperature below 525°F while at power, has occurred for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total.

This review included Integrated Operating Procedure-3 "Hot standby to Minimum Load", which states that Tave must be verified greater than 541°F within 15 minutes of achieving criticality.

In addition, Technical Specification 3.1.1.4 requires that while in Mode 1 and 2, Tave must be greater than 541°F.

This LCO requires the temperature to be restored within 15 minutes or be in Hot Standby within an additional 15 minutes.

Based on department procedural requirements, it can be concluded that the outlined scenario has not occurred in the past and will not occur in the future at Salem.

While historically there have been instances during plant transient, where RCS temperature may have gone below 525°F, the cumulative excursion time has been much less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Therefore, the effect of lower irradiation temperature on the reference temperature and Charpy upper shelf energy is negligible.

b.

How their surveillance results on the predicted amount of embrittlement were considered.

5 Revision 1

NLR-N92150 *

Response

As explained in the PSE&G response to Generic Letter 88-11, the surveillance capsule analyses were conducted using the methods described in Regulatory Guide 1.99 Revision 2 to predict the effects of neutron radiation on the reactor vessel materials.

PSE&G has complied with its commitment to submit a License Change Request to include new heatup and cooldown curves.

Approval for the revised curves was received in January 1990 through Amendment 86 for the Salem Unit 2 Technical Specifications.

c.

If a measured increase in reference temperature exceeds the mean-plus-two standard deviations predicted by Regulatory Guide 1.99, Revision 2, or if a measured decrease in Charpy upper shelf energy exceeds the value predicted using the guidance in Paragraph C.1.2 in Regulatory Guide 1.99, Revision 2, the licensee is requested to report the information and describe the effect of the surveillance results on the adjusted reference temperature and Charpy upper shelf energy for each beltline material as predicted for December 16, 1991, and for the end of its current license.

Response

The measured increase in reference temperature does not exceed the mean-plus-two standard deviation predicted by Regulatory Guide 1.99 Revision 2 for any of the surveillance capsule materials as indicated in Table 20.

The measured decrease in Charpy upper shelf energy exceeds the value predicted using methodology specified in Regulatory Guide 1.99 Revision 2 for weld metal as indicated in Table 20.

Therefore, the adjusted reference temperature and Charpy upper shelf energy of each beltline material as predicted by surveillance results for December 16, 1991 and end of current license are provided in Tables 21 and 22 as requested in Request 3c.

6 Revision 1 the I

NLR-N92150 *

- TABLE 1 SALEM UNIT 2 Unirradiated and Calculated Upper Shelf Energy (USE) Values USE, ft-lbs USE, ft-lbs(l)

EOL USE ft-lbs (Z)

Material Description Unirradiated December 16i 1991 April 18i 2020 Intermediate Shell 106( 3 )

90.1 83.7 Plate B4712-1 Intermediate Shell 97 (3 )

81.5 75.7 Plate B4712-2 Intermediate Shell 107( 3 )

92.0 86.7 Plate B4712-3 Intermediate Shell Long.

111 86.6 76.6 Weld 2-442A Intermediate Shell Long.

111 83.3 73.3 Weld 2-442B Intermediate Shell Long.

111 83.3 73.3 Weld 2-442C Lower Shell Plate 98( 3) 83.0 78.4 B4713-1 Lower Shell Plate 103( 3) 87.6 82.4 B4713-2 Lower Shell Plate 121( 3 )

102.8 96.8 B4713-3 Lower Shell Long.

NA NA NA Weld 3-442A Lower Shell Long.

NA NA NA Weld 3-442B Lower Shell Long.

NA NA NA Weld 3-422C Intermediate to Lower NA NA NA Shell Girth Weld 9-442 NA - Unirradiated upper shelf energy not available because tests were not performed.

In these cases, the December 16, 1991 and EOL USE values were not calculated.

(1) December 16, 1991 USE values calculated at ~T location, based on fluences in PSE&G letter SCI-92-0357, 6/11/92, J. Perrin to J. Chicots.

(2)

EOL USE values calculated at l/4T location, based on fluences from PSE&G letter SCI-92-0319, 5/14/92, J. Perrin to J. Chicots.

(3)

Unirradiated USE values determined from transverse data. -

7 Revision 1

NLR-N92150 TABLE 2 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on November 12, 1968.

(Corrected copy dated April 23, 1970).

Component:

Intermediate Shell Plate 84712-1 Heat No.:

C-4173-1 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.21 1.33

.012

.016

.22

.56

.54

.13*

  • Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.

Longitudinal Charpy Impact and Fracture Tests Temp., op Enerqy, ft-lbs

-80 8

-80 6

-40 20

-40 22

-40 21

+10 51

+10 52

+10 57

+40 69

+40 79

+40 75

+110 105

+110 111

+160 140

+160 136 Temp. OF Drop Weights NDT

+10 2NF 0°F 0

lF Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 0

0 10 10 10 25 25 25 35 35 35 85 85 100 100 RTNDT 00F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

8 Revision 1 Mils Lateral Exp.

4 2

16 18 17 38 39 43 51 59 56 74 82 88 90 USE 90 ft-lbs

NLR-N92150 TABLE 3 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.

Component:

Intermediate Shell Plate, B4712-1 Heat No.:

C-4173-1 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-40 12

-40 23

-40 26

+10 39

+10 31

+10 33

+60 52

+60 53

+60 51

+110 81

+110 93

+110 76

+160 97

+160 101

+160 101

+210 103

+210 111

+210 105 Temp., OF Drop Weights NDT Performed by CE 00F Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 13 14 14 30 25 25 43 42 38 75 92 71 75 100 100 100 100 100 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

9 Revision 1 Mils Lateral Exp.

6 16 14 28 26 24 41 42 40 68 72 65 76 75 75 79 74 80 RTNDT USE 00F 106 ft-lbs

NLR-N92150 TABLE 4 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 3, 1968.

(Corrected copy dated April 23, 1970).

Components:

Intermediate Shell Plate B4712-2 Heat No.:

C-4186-2 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.22 1.37

  • 011

.OlS.

.24

.60

.SS

.14*

  • Per Salem 2 Table 6 of Westinghouse letter PSE-77-S to PSE&G of October 10, 1977.

Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-40 7

-40 12

-40 10

+10 21

+10

.37

+10 30

+40 62

+40 49

+40 SS

+110 96

+110 98

+110 90

+160 124

+160 134

+160 12S Temp., OF Drop Weights NDT 0

lNF

-10 2NF

-20F

-20 lF Heat Treatment lSSO -

16S0°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

122S°F +/- 2S°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 0

0 0

10 lS lS 30 2S 30 70 80 70 100 100 100 RTNDT 1°F 11S0°F +/- 2S°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

10 Revision 1 Mils Lateral Exp.

8 9

8 20 31 26 46 39 42 69 70 67 86 92 88 USE 83 ft-lbs

NLR-N92150 TABLE 5 SALEM UNIT 2 Materials Certification Information The following information was taken from WCAP-8824, "PSE&G Co. Salem Unit No.

2 Reactor Vessel Radiation Surveillance Program," January 1977 and the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.

Component:

Intermediate Shell Plate, 84712-2 Heat No.:

C-4186-2 Chemical Analysis c

Mn p

s Si Ni Mo Cu Cr Co N?

Al Sn

.23 1.34

.015

.010

.30

.61

.55

.10

.089

.015

.004

.030

.008 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs

-40 12

-40 8

-40 12 0

34 0

34 0

24

+40 39

+40 36

+40 43 RT 58 RT 58 RT 61

+110 64

+110 74

+110 70

+210 100

+210 87

+210 104 Temp., OF Drop Weights NDT Performed by CE 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

-20°F Heat Treatment Water quenched.

Air cooled.

Furnace cooled.

11 Revision 1 Shear Mils Lateral Exp.

10 5

15 3

10 7

25 26 25 27 18 18 35 28 34 28 34 34 52 46 52 47 52 49 62 51 68 61 68 57 100 80 100 71 100 75 RTNDT USE 12°F 97 ft-lbs

NLR-N92150 TABLE 6 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc., on October 4, 1968.

(Corrected copy dated April 23, 1970).

Component:

Intermediate Shell Plate B4712-3 Heat No.:

C-4194-2 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.22 1.37

.010

.016

.26

.57

.52

.11*

  • Per Salem 2 Table 6 of Westinghouse letter PSE-77-5 to PSE&G of October 10, 1977.

Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-40 12

-40 11

-40 9

+10 33

+10 34

+10 28

+40 49

+40 50

+40 38

+110 100

+110 91

+110 79

+160 116

+160 122

+160 110 Temp. OF Drop Weights NOT a

lNF

-20 lNF

-40 2NF

-so lF

-50°F

-60 lF Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear a a a 20 20 20 30 30 25 85 80 75 100 100 100 RTNDT 22°F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

12 Revision 1 Mils Lateral Exp.

10 9

7 26 24 23

(

49 49 32 75 68 60 82 84 80 USE 75 ft-lbs

NLR-N92150 TABLE 7 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.

Component:

Intermediate Shell Plate, 84712-3 Heat No.:

C-4194-2 Transverse Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-40 12

-40 32

-40 8

+10 32

+10 32

+10 30 RT 55 RT 53 RT 58

+110 75

+110 69

+110 78

+160 91

+160 98

+160 95

+210 103

+210 110

+210 107 Temp., OF Drop Weights NDT Performed by CE

-50°F Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 14 13 9

25 29 25 47 47 42 64 59 69 92 92 100 100 100 100 RTNDT 10°F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

13 Revision 1 Mils Lateral Exp.

5 13 3

26 22 19 44 41 45 59 56 60 72 76 72 79 82 83 USE 107 ft-lbs

NLR-N92150 TABLE 8 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on March 15, 1971 and "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl. 5-020, November 1985.

Component:

Welds 2-442A, 2-442B, and 2-442C Chemical Analysis c

Mn p

s Si Ni

.12 1.29

.019

.012

.19

.73 Heat No.: 13253 & 20291 (tandem)

Flux:

Linde 1092, Lot No. 3833 Mo Cu Cr

.48

.23

.028 Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs

-80 19

-80 26

-40 54

-40 39

+10 83

+10 94

+10 85

+40 83

+40 92

+40 97

+110 105

+110 108

+110 119

+160 113

+160 115 Temp., OF Drop Weights NDT

-40 lF

-30 2NF

-20 lNF 0

lNF 1150°F for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

-40°F Heat Treatment 14 Revision 1 Shear Mils Lateral Exp.

0 16 10 21 25 40 20 31 60 65 70 72 60 69 70 63 80 70 80 76 100 80 100 84 100 89 100 87 100 86 RTNDT USE

-40°F 111 ft-lbs

NLR-N92150

  • TABLE 9 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering. Inc. on August 19, 1969.

Component:

Lower Shell Plate 84713-1 Heat No.:

C-4182-1 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.22 1.32

.010

.015

.22

.60

.54

.12*

  • Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.

Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerav, ft-lbs

-80 9

-80 13

-40 25

-40 44

-40 16

+10 36

+10 65

+10 61

+40 60

+40 68

+40 64

+110 93

+110 108

+160 131

+160 123 Temp., OF Drop Weights NDT 0

2NF

-10 lF

-10°F

-20 lF Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 0

0 10 20 5

10 30 30 30 40 35 80 85 100 100 RTNDT

-10°F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

15 Revision 1 Mils Lateral Exp.

6 12 21 34 12 28 46 46 47 49 48 73 75 88 88 USE 82.5 ft-lbs

NLR-N92150 TABLE 10 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.

Component:

Lower Shell Plate, B4713-1 Heat No.:

C-4182-1 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs

% Shear

-40 lS

-40 20

-40 16

+10 29

+10 39

+10 29

+SO 44

+SO 40

+SO S7

+80 S6

+80 60

+80 71

+140 91

+140 89

+140 88

+210 90

+210 106

+210 99 Temp., OF Drop Weights NOT Performed by CE

-10°F Heat Treatment lSSO -

16S0°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

122S°F +/- 2S°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

lS 14 14 2S 2S 46 40 40 40 S2 S2 S4 92 92 90 100 100 100 11S0°F +/- 2S°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600 °F.

16 Revision 1 RTNDT 8°F Mils Lateral Exp.

10 lS 8

26 28 2S 36 33 44 48 48 S6 72 70 73 72 80 78 USE 98 ft-lbs

NLR-N92150 TABLE 11 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on October 28, 1969.

Component:

Lower Shell Plate B4713-2 Heat No.:

C-4182-2 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.22 1.28

.010

.015

.24

.57

.53

.12*

  • Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.

Longitudinal Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs

-80 6

-so 13

-40 43

-40 13

-40 22

+10 56

+10 42

+10 58

+40 79

+40 72

+40 89

+110 101

+110 112

+160 136

+160 135 Temp., OF Drop Weights NDT

-20 lF

-10 2NF 0

lNF

-20°F Heat Treatment 1550°F -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 0

0 20 5

10 25 20 25 35 30 40 70 80 100 100 RTNDT

-20°F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

17 Revision 1 Mils Lateral Exp.

3 7

31 12 16 38 31 40 58 52 63 70 78 74 76 USE 88 ft-lbs

. NLR-N92150

  • TABLE 12 SALEM UNIT 2 Materials certification Information The following information was taken*from the Materials Test Report prepared by Westinghouse Electric Corporation on June 6, 1973.

Component:

Lower Shell Plate, B4713-2 Heat No.:

C-4182-2 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs

% Shear

-40 12

-40 13

-40 20 0

35 0

27 0

32

+40 38

+40 51

+40 34

+80 62

+80 59

+80 70

+110 80

+110 84

+110 85

+210 106

+210 107

+210 96 Temp., OF Drop Weights NDT Performed by CE

-20°F Heat Treatment 1550°F -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

10 10 5

10 20 10 15 20 20 47 55 61 70 80 80 100 100 100 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

18 Revision 1 RTNDT 8°F Mils Lateral Exp.

6 9

11 25 22 24 33 48 29 49 50 57 62 61 63 81 77 78 USE 103 ft-lbs

'NLR-N92150 TABLE 13 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. on August 8, 1969.

Component:

Lower Shell Plate, B4713-3 Heat No:

B-8343-1 Mill Chemical Analysis c

Mn p

s Si Ni Mo Cu

.25

1. 34

.012

.014

.28

.58

.53

.12*

  • Per WCAP 10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program," March 1984.

Longitudinal Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-40 19

-40 14

-40 12

+10 36

+10 52

+10 40

+40 63

+40 74

+40 50

+110 104

+110 108

+110 103

+160 135

+160 135

+160 136 Temp., OF Drop Weights NDT

-20 lF

-10 lF 0

2NF

-10°F Heat Treatment 1550 -

1650°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

1225°F +/- 25°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 0

0 0

25 30 25 35 40 30 85 90 80 100 100 100 RTNDT 00F 1150°F +/- 25°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

19 Revision 1 Mils Lateral Exp.

10 12 10 27 37 30 46 53 38 80 82 77 85 88 91 USE 88 ft-lbs

. NLR-N92150 TABLE 14 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Test Report prepared.by Westinghouse Electric Corporation on June 6, 1973.

Component:

Lower Shell Plate, B4713-3 Heat No.:

B-8343-1 Transverse Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs

-40 19

-40 8

-40 11

+10 27

+10 37

+10 27

+SO 46

+SO 68

+so S6

+90 82

+90 70

+90 61

+lSO 103

+lSO 9S

+lSO 108

+210 119..

+210 120

+210 12S Temp.~ OF Drop Weights NOT Performed by CE

-10°F Heat Treatment lSSO -

16S0°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Water quenched.

122S°F +/- 2S°F, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Shear 9

9 9

23 29 29 38 40 38 61 S6 47 8S 8S 90 100 100 100 RTNDT 10°F 11S0°F +/- 2S°F, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Furnace cooled to 600°F.

20 Revision 1 Mils Lateral Exp.

11.S s

8

. 14 30.S 22 38 Sl 41 64 SS Sl 73 73 81 83 83 82 USE 121 ft-lbs

.NLR-N92150 TABLE 15 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data," CE Inc., Design Input File TOl.5-020, November 1985 and CE Welding Material Qualification, October 27, 1969.

Component:

Weld 3-442A, 3-442B, and 3-442C Heat No.:

21935 and 12008 (tandem)

Flux: Linde 1092, Lot No. 3889 Chemical Analysis c

Mn p

s Si Ni Mo Cu

._____.;.*~1..::..1 __ __._ ___

1_._3_8 __ _,_ ___

._0_l_5 __ _,__ __._o_1_1 __ _._ ____

.1_5 ____.__ __ *_8_6 __ ___.. ____._5_5 __ __._ ____

._2_0 __ _,

Charpy Impact and Fracture Tests Temp., OF Energy, ft-lbs 10 97 10 90 10 83 Full Charpy curve not performed.

Temp., °F Drop Weights No drop wt. test performed.

1150°F for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

NOT Heat Treatment 21 Revision 1 RTNDT

-56°F (generic value per 10CFR 50.61 USE

0NLR-N92150 TABLE 16 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data", CE Inc. Design Input File TOl.S-020, November 1985 and CE Welding Material Qualification Report, October 7, 1970.

Component:

Weld 9-442 Heat No.:

90099 Flux:

Linde 0091, Lot No. 3977 Chemical Analysis c

Mn p

s Si Ni

.14 1.20

.021

.013

.22

.20*

  • Estimated value.

Charpy Impact and Fracture Tests Temp., OF Enerqv, ft-lbs 10 56 10 30 10 52 Full Charpy-curve not performed.

Temp., OF Drop Weights NDT RTNDT No drop wt. test performed.

1150°F for 10.5 hrs.

Heat Treatment 22 Revision 1

-56°F (generic value per 10CFR 50.61)

Mo Cu

.so

.175 USE

)l

"}*

0NLR-N92150 TABLE 17 SALEM UNIT 2 Materials Certification Information The following information was taken from "Salem Units 1 and 2 Reactor Vessel Weld Data" CE Inc., Design Input File TOl.S-020, November 198S, and WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program,"

January 1977.

Component:

Heat No.:

132S3 Weld Surveillance Material Weldment made from intermediate shell plates B4712-l and B4712-2 Flux: Linde 1092, Lot No. 3833 and Linde 1092, Lot No. 3774 Chemical Analysis c

Mn p

s Si Ni Mo

.10 1.27

.017

.011

.29

  • 71

.4S Charpy Impact and Fracture Tests Temp., °F Enerqv, ft-lbs

% Shear

-100

-100

-100

-so

-so

-so 0

0 0

40 40 40 100 100 100 210 210 210 4.S 11 6

11 4

3S.S 48.S 72 63.S 71 so.s 80.S 86 96.S 106.S 112 111. s 111. s Temp., °F Drop Weights Performed by CE 11S0°F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> NOT

-40°F Heat Treatment 23 Revision 1 2

6 lS 18 20 29 S2 S2 62 S9 SS 79 100 90 100 98 100 100 RTNDT

-20°F Cu Cr

.23

.OlS Mils Lateral Exp.

1 2.S 1

7.S 11 27 42 36 so S6 44 62 81 74.S 80 82 86 8S.S USE 111 ft-lbs

NLR-N92150

  • TABLE 18 SALEM UNIT 2 Materials Certification Information The following information was taken from the Materials Certification Report prepared by Combustion Engineering, Inc. March lS, 1971.

Component:

Weld Heat Affected Zone (Seam No. 2-442)

Chemical Analysis Information not available (analyses were not performed)

Temo., OF

-110

-i10

..:90

-80

-40.

...;40

-40

+10

+10

+10

+40

+40

+40

+110

+110 Temp., OF 0

+10 11S0°F +/- 2S°F, Charpy Impact and Fracture Tests Energy, ft-lbs lS 26 41 46 4S SS 47 68 87 83 lOS 100 104 8S 104 Drop Weights lF 2NF 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

NDT 00F Heat Treatment 24 Revision 1 Shear 0

10 20 20 30 40 30 70 80 80 9S 90 9S 100 100

  • RTNDT 00F Mils Lateral Exp.

12 19 31 36 38 46 39 60 76 71 86 83 80 84 98 USE 94.S ft-lbs

NLR-N92150 TABLE 19 SALEM UNIT 2 Materials Certification Information The following information was taken from the WCAP-8824, "PSE&G Co. Salem Unit No. 2 Reactor Vessel Radiation Surveillance Program January 1977."

Component:

Weld Heat Affected Zone Surveillance Material (HAZ material obtained from 84712-2 of Weldment made from intermediate shell plate 84712-1 and 84712-2)

Chemical Analysis Information not available (analyses were not performed on HAZ).

Charpy Impact and Fracture Tests Temp., OF Enerqy, ft-lbs

-125 51

-125 23

-125 28

-75 122

-75 36

-75 66.5

-25 79

-25 93.5

-25 76 25 131 25 111 25 74 100 101 100 114 100 179 210 118.5 210 115 210 106.5 Temp., OF Drop Weights Performed by CE 1150°F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

NDT 00F Heat Treatment 25 Revision 1 Shear 33 6

12 100 17 42 66 48 51 96 88 60 100 100 100 100 100 100 RTNDT 0°F Mils Lateral Exp.

24.5 15

10. 5 63 17 34 48 47 37 69 72 45 66.5 70 78.5 79.5 72.5 75 USE 113 ft-lbs
  • NLR-N92150 TABLE 20 SALEM UNIT 2 Measured Versus Predicted 30 ft-lb Temperature Increases And Upper Shelf Energy Decreases ARTNDT ( oF) ( 1, 2)

Upper Shelf Energy Decrease (%)

(1)

Material Capsule Fluence Measured Predicted Measured Predicted no19 n/cm2) 84712-2 (long.)

T 0.276 so 99 6

14 84712-2 (long.)

u 0.57 70 118 8

17 84712-2 (long.)

x 1.16 80 138 1

20 84712-2 T

0.276 70 99 8

14 (transverse) 84712-2 u

0.57 95 118 13 17 (transverse) 84712-2 x

1.16 125 138 8

20 (transverse)

Weld Metal T

0.276 155 180 29( 3 )

27.S Weld Metal u

0.57 190 217 33( 3 )

32 Weld Metal x

1.16 195 255 22 38 (1) Predicted values based on Regulatory Guide 1.99, Revision 2 Methodology.

(2) Predicted ARTNDT includes 2crA as defined in Regulatory Guide 1.99, Revision 2.

(3) Exceeds predicted value.

26 Revision 1

NLR-N92150 TABLE 21 SALEM UNIT 2 Adjusted Reference Temperatures (ART) As Predicted By Surveillance Data ART (oF)

ART (OF)

Screening Material Description December 16, 1991 April 18, 2020 Criterion B4712-l 96.3 (96.3)**

131.9 ( 131. 9) 270 B4712-2*

85.4 (96.4) 123.8 (134.8) 270 B4712-3 107.1 (95.1) 136.3 (124.3) 270 2-442A*

105.7 190.9 270 2-442B*

132.5 215.4 270 2-442C*

132.5 215.4 270 Weld Surveillance Material 152.5 235.4 270 B4713-1

81. 7 (99.7) 115.3 (133.3) 270 B4713-2 71.3 (99.3) 104.6 (132.6) 270 B4713-3 91.4 ( 101. 4) 124.9 (134.9) 270 3-442A 134.5 216.8 270 3-442B 108.5 190.0 270 3-442C 134.5 216.8 270 9-442 75.8 113.6 300 RTNDT based on surveillance capsule chemistry factor.

The numbers in () for B4712-l, B4712-2, B4712-3, B4713-1, B4713-2 and B4713-3 are calculated using the initial RTNDT values determined by Westinghouse from transverse Charpy test data.

The corresponding numbers not in () are calculated using the initial RTNDT values determined from the original fabrication records with longitudinal Charpy test data.

27 Revision 1

. NLR-N92150 TABLE 22 SALEM UNIT 2 Upper Shelf Energy (USE) As Predicted By Surveillance Data USE (ft-lbs)

USE (ft-lbs)

EOL USE (ft-lbs)

Material Description Unirradiated December 16, 1991 April 18, 2020 B4712-l 106 90.1 83.7 B4712-2 (long.)*

122 114. 7 111.0 B4712-2 (trans.)*

97 87.3 83.4 B4712-3 107 92.0 86.7 2-442A*

111 86.6 76.6 2-442B*

111 83.3 72.2 2-442C*

111 83.3 72.2 Weld Surveillance 111 83.3 72.2 Material*

B4713-1 98 83.3 78.4 B4713-2 103 87.6

82. 4 -

B4713-3 121 102.8 96.8 3-442A NA**

NA NA 3-442B NA NA NA 3-422C NA NA NA 9-442 NA NA NA Weld HAZ*

113 87.0 75.7 USE based on surveillance data trending on Figure 2 of Reg. Guide 1.99 Revision 2.

All other USE predictions based on Cu content, using Figure 2 of Reg. Guide 1.99 Revision 2.

NA - Unirradiated upper shelf energy not available because tests were not done in the upper shelf region.

28 Revision 1

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