Text

Forwards Rev 1 Response to GL 92-01 Re Reactor Vessel Structural Integrity
	ML18096B186
Person / Time
Site:	Salem
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

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.

/-----

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9301070112 921230 PDR ADOCK 05000311 P

PDR

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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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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

+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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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

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

-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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

-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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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

+160 136 Temp., OF Drop Weights NDT

-20 lF

-10 lF 0

2NF

-10°F Heat Treatment 1550 -

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

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Water quenched.

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

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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

-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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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

+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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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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