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{{#Wiki_filter:Public Service Electric and Gas Company
{{#Wiki_filter:Public Service Electric and Gas
* Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President  
* Company Stanley LaBruna                     Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations July 31, 1989 NLR-N89139 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
-Nuclear Operations July 31, 1989 NLR-N89139 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION PRESSURE TEMPERATURE LIMITS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide PSE&G's responses to the questions forwarded in the request for additional information dated May 26, 1989. The attached responses were discussed with Mr. Tsao of the NRC staff on July 24, 1989. Figures 3.4-2 and 3.4-3 for Unit 1 were revised as a result of this conversation and are attached for incorporation into LCR 88-14.
REQUEST FOR ADDITIONAL INFORMATION PRESSURE TEMPERATURE LIMITS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide PSE&G's responses to the questions forwarded in the request for additional information dated May 26, 1989. The attached responses were discussed with Mr. Tsao of the NRC staff on July 24, 1989. Figures 3.4-2 and 3.4-3 for Unit 1 were revised as a result of this conversation and are attached for incorporation into LCR 88-14. Should you have any questions, please feel free to contact us. Attachment 89-oaoso2:30--89o731  
Should you have any questions, please feel free to contact us.
--.----. P PDR ADOCK 05000272 PNU Sincerely, I I
Sincerely, Attachment 89-oaoso2:30--89o731           --.----.
* *----*-' Document Control Desk NLR-N89139 C Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector 2 Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief
PDR         ADOCK 05000272 P                      PNU                                                                               I I
* New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 7-31-89 
 
*
                  *
* ATTACHMENT QUESTIONS  
              *----*-'
& RESPONSES  
Document Control Desk NLR-N89139 2
-PRESSURE/TEMPERATURE LIMITS (LCR 88-14) A. WCAP-11955 describes the test results of specimens in Capsule Z at Salem 1. The following questions relate to WCAP-11955 which provides the technical bases for the 12/28/88 submittal for Salem, Unit 1: 1. There was no discussion of weld metal in Section 4, Description of Program, in WCAP-11955.
* 7-31-89 C   Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
However, Table 4-1 discusses weld metal from Capsule Y. Table 4-2 and Table A-1 discusses a certain weld metal but we could not determine whether that weld metal was included in Capsule z. Was there a weld metal included in Capsule Z? Rl. Salem Unit 1 Capsule z did not contain any weld metal specimens.
* ATTACHMENT
Therefore, no discussion of weld metal results was included in WCAP-11955.
* QUESTIONS & RESPONSES - PRESSURE/TEMPERATURE LIMITS (LCR 88-14)
: 2. Assuming there was no weld metal in Capsule z, then how was RTNDT of the weld metal calculated as shown on Pages A-7 and A-8. It appears that Westinghouse took the weld metal in Capsule Y (WCAP-11554) to be used in the P/T curves in WCAP-11955.
A. WCAP-11955 describes the test results of specimens in Capsule Z at Salem 1. The following questions relate to WCAP-11955 which provides the technical bases for the 12/28/88 submittal for Salem, Unit 1:
Explain. 3. Table A-1 showed three weld metals. Which weld metal is the limiting one? That is, which weld metal was used in the calculations on Pages A-7 and A-8? R2 & R3. The lower shell longitudinal weld seam 2-042C located on a 45° azimuth was considered the limiting weld material as indicated on Page A-7 of WCAP-11955.
: 1. There was no discussion of weld metal in Section 4, Description of Program, in WCAP-11955. However, Table 4-1 discusses weld metal from Capsule Y. Table 4-2 and Table A-1 discusses a certain weld metal but we could not determine whether that weld metal was included in Capsule z. Was there a weld metal included in Capsule Z?
A chemical content of 0.35 cu and 1.00 Ni was used in developing (H/C) curves. A fluence of 7.68 X 10 n/cm at 15 EFPY for a weld located at a 45° azimuth from table 6-14 of WCAP 11955 was used for H/C curves. 4. It appears that the chemistry factor of 212°F as shown on Page A-7 was obtained by using the copper and nickel contents of the weld metal. However, we could not determine how the chemistry factor of 158.9°F for the based plate was obtained.
Rl. Salem Unit 1 Capsule z did not contain any weld metal specimens. Therefore, no discussion of weld metal results was included in WCAP-11955.
Regulatory Guide 1.99, Rev. 2, provides an alternative method (Section 2.1) to calculate the chemistry factor when two or more credible surveillance data sets become available.
: 2. Assuming there was no weld metal in Capsule z, then how was RTNDT of the weld metal calculated as shown on Pages A-7 and A-8. It appears that Westinghouse took the weld metal in Capsule Y (WCAP-11554) to be used in the P/T curves in WCAP-11955. Explain.
Explain how both chemistry factors (weld and base plate) were obtained.
: 3. Table A-1 showed three weld metals. Which weld metal is the limiting one? That is, which weld metal was used in the calculations on Pages A-7 and A-8?
*
R2 & R3. The lower shell longitudinal weld seam 2-042C located on a 45° azimuth was considered the limiting weld material as indicated on Page A-7 of WCAP-11955. A chemical content of 0.35 cu and 1.00 Ni was used in developing t~g hea~up/cooldown (H/C) curves. A fluence of 7.68 X 10 n/cm at 15 EFPY for a weld located at a 45° azimuth from table 6-14 of WCAP 11955 was used for H/C curves.
* R4. A chemistry factor of 272°F was obtained for weld metal from Table 1 of Regulatory Guide 1.99, Revision 2 for Cu 0.35 and 1.00 Ni. The base metal chemistry factor of 158.9°F was obtained from surveillance data for plate B2402-1 as follows: (OF) Capsule Flue2'ce n/cm RTNDT ff RTNDT x ff (OF) f f 2 T 0.24 x 1019 100 0.6138 61. 4 0.377 z 1. 33 x 1019 170 1.079 183.4 1.164 244.8 1.541 Chemistry factor = 244.8/1.541  
: 4. It appears that the chemistry factor of 212°F as shown on Page A-7 was obtained by using the copper and nickel contents of the weld metal. However, we could not determine how the chemistry factor of 158.9°F for the based plate was obtained. Regulatory Guide 1.99, Rev.
= 158.9 ff -fluence factor 5. Figure A-2 in WCAP-11955 (corresponding to Figure 3.4-2 in the 12/28/88 submittal).
2, provides an alternative method (Section 2.1) to calculate the chemistry factor when two or more credible surveillance data sets become available.
R5. Provide detailed/hand calculations to show that when RTNDT of 162°F is used in calculating P/T heatup curve it is more conservative than if RTNDT of 222.5°F is used. Following RTNDT values were calculated for 15EFPY (Page A-8 of WCAP-ll955) . Component EFPY Location ART Plate B2402-1 15 1/4T 204°F Plate B2402-l 15 3/4T 162°F Weld 15 1/4T 222.5°F Weld 15 3/4T 151. 5°F From the above table it is seen that for the 1/4T location, the limiting material is the weld and for the 3/4T location, the limiting material is the plate. Instead of generating two sets of heatup and cooldown curves, a conservative approach is taken by using 0 0 222.5 F RTNDT at the 1/4T and 162 F RTNDT at the 3/4T. This approacfi will envelop both the (B2402-1) and the weld. The Unit 1 Technical Specification heatup and cooldown curves submitted in LCR 88-14 have been revised to indicate both the 1/4T and 3/4T RTNDT values and are submitted herein. 6. Table 4-1 and Table A-1 show inconsistent copper and nickel contents for the base plate B2402-1 and weld metal. Explain. What are the exact percentages of copper and nickel contents used in the calculation of RTNDT of the B2402-1 plate and weld metal.
Explain how both chemistry factors (weld and base plate) were obtained.
*
 
* R6. Table 4-1 reports the copper and nickel values obtained for the Salem surveillance materials.
R4.
Table A-1 identifies the original chemistry reported for the plates and forgings used in the vessel. In this weld metal a chemical composition of 0.35 Cu and 1.00 Ni was used. In the base metal see the response identified in A-4. B. Other Questions
              *
* A chemistry factor of 272°F was obtained for weld metal from Table 1 of Regulatory Guide 1.99, Revision 2 for Cu 0.35 and 1.00 Ni.
The base metal chemistry factor of 158.9°F was obtained from surveillance data for plate B2402-1 as follows:
Flue2'ce    RTNDT (OF)                               2 Capsule   n/cm                     ff   RTNDT x ff (OF)     ff T   0.24 x 1019       100     0.6138         61. 4     0.377 z   1. 33 x 1019     170     1.079         183.4       1.164 244.8       1.541 Chemistry factor   = 244.8/1.541   = 158.9 ff - fluence factor
: 5. Figure A-2 in WCAP-11955 (corresponding to Figure 3.4-2 in the 12/28/88 submittal).
Provide detailed/hand calculations to show that when RTNDT of 162°F is used in calculating P/T heatup curve
      ~ha~ it is more conservative than if RTNDT of 222.5°F is used.
R5. Following RTNDT values were calculated for 15EFPY (Page A-8 of WCAP-ll955) .
Component         EFPY       Location       ART Plate B2402-1       15           1/4T       204°F Plate B2402-l       15           3/4T       162°F Weld               15           1/4T       222.5°F Weld               15           3/4T       151. 5°F From the above table it is seen that for the 1/4T location, the limiting material is the weld and for the 3/4T location, the limiting material is the plate.
Instead of generating two sets of heatup and cooldown curves, a conservative approach is taken by using 0                             0 222.5 F RTNDT at the 1/4T and 162 F RTNDT at the 3/4T.
This approacfi will envelop both the pla~e (B2402-1) and the weld. The Unit 1 Technical Specification heatup and cooldown curves submitted in LCR 88-14 have been revised to indicate both the 1/4T and 3/4T RTNDT values and are submitted herein.
: 6. Table 4-1 and Table A-1 show inconsistent copper and nickel contents for the base plate B2402-1 and weld metal. Explain. What are the exact percentages of copper and nickel contents used in the calculation of RTNDT of the B2402-1 plate and weld metal.
 
R6.
                *
* Table 4-1 reports the copper and nickel values obtained for the Salem surveillance materials. Table A-1 identifies the original chemistry reported for the plates and forgings used in the vessel. In this weld metal a chemical composition of 0.35 Cu and 1.00 Ni was used. In the base metal see the response identified in A-4.
B. Other Questions
: 1. 10 CFR 50, Appendix G, Section IV.2 specifies pressure and temperature requirements for the vessel closure flange region. Discuss whether Salem 1 and 2 P/T limits satisfy the requirements.
: 1. 10 CFR 50, Appendix G, Section IV.2 specifies pressure and temperature requirements for the vessel closure flange region. Discuss whether Salem 1 and 2 P/T limits satisfy the requirements.
R1. Salem Unit 1 and 2 P/T limits satisfy the requirements of 10CFR50 Appendix G, Section IV.2 as noted on page A-5 of WCAP-11955 for Unit 1 and page A-6 of WCAP-11554 for Unit 2. 2. The the and was for Salem Unit 2 P/T curves (Figure 3.4-2 and 3.4-3) in 12/28/88 submittal show two RTNDT values at 1/4T 3/4T locations.
R1. Salem Unit 1 and 2 P/T limits satisfy the requirements of 10CFR50 Appendix G, Section IV.2 as noted on page A-5 of WCAP-11955 for Unit 1 and page A-6 of WCAP-11554 for Unit 2.
We could not aeeerrnine which RTNDT used for the heatup curve and which RTNDT was usea the cooldown curve. Discuss. R2. The following RTNDT values were used to develop the heatup and cooldown curves for Unit 2. Component Long. Weld Long. Weld 10 10 Location 1/4T 3/4T ART 178.6°F 116.1°F RTN of 178.6°F at 1/4T location is used to develop coo£down curves and RTNDT of 178.6°F (at 1/4T), 116.1°F (at 3/4T) are used to aevelop heatup curves. 3. Table B 3/4.4-1 of the Salem Unit 2 Technical Specification revision in the 12/28/88 submittal:
: 2. The Salem Unit 2 P/T curves (Figure 3.4-2 and 3.4-3) in the  12/28/88 submittal show two RTNDT values at 1/4T and  3/4T locations. We could not aeeerrnine which RTNDT was  used for the heatup curve and which RTNDT was usea for  the cooldown curve. Discuss.
The limiting longitudinal weld in Figure 3.4-2 and 3.4-3 of the Salem Unit 2 Technical Specification revision show the copper content of 0.35% and nickel content 1.00%. This chemical composition is inconsistent with the weld metals in table B 3/4.4-1.
R2. The following RTNDT values were used to develop the heatup and cooldown curves for Unit 2.
* R3. Although the chemical composition for Salem Unit 2 weld metal identified in Table B 3/4.4-1 of the Technical Specification is inconsistent with Figures 3.4-2 and 3.4-3, a more conservative chemical content (0.35% Cu and 1.00% Ni) was used for the H/C curves.
Component                   Location      ART Long. Weld         10         1/4T       178.6°F Long. Weld        10          3/4T        116.1°F RTN   of 178.6°F at 1/4T location is used to develop coo£down curves and RTNDT of 178.6°F (at 1/4T), 116.1°F (at 3/4T) are used to aevelop heatup curves.
..... <.> -Cll Q. -w a: Cll Cll w a: Q. Q w -u -Q z -Material Pr.rty Initial RTNDT' -56 F
: 3. Table B 3/4.4-1 of the Salem Unit 2 Technical Specification revision in the 12/28/88 submittal: The limiting longitudinal weld in Figure 3.4-2 and 3.4-3 of the Salem Unit 2 Technical Specification revision show the copper content of 0.35% and nickel content 1.00%.
* RTNDT After 15 EFPY: 2500 2250 2000 1750 1500 1250 1000 i-. CooldCMI 750
This chemical composition is inconsistent with the weld metals in table B 3/4.4-1.
* Rates .. *F/Hr .. .. o-.. 500 250 .. .. .. 6 j-"""" .. 50 100 l/4T = 222.5&deg;F 3/4T = 162&deg;F URiCClt)tible Operation
* R3. Although the chemical composition for Salem Unit 2 weld metal identified in Table B 3/4.4-1 of the Technical Specification is inconsistent with Figures 3.4-2 and 3.4-3, a more conservative chemical content (0.35% Cu and 1.00% Ni) was used for the H/C curves.
,,,, . .... .... , _.__ -,., ,,,. '-"'" '-... ... _..__ ,,. ..,.. i--150 200 I I . ' , .. ... '/' V.1 'fT I"/'/, "'/OIJ' ,,,-/ AccepUble Operation 250 300 I I j I I 350 INDICATED TEMPERATURE (DEG.F) CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS I 7 I I Figure 3.4-3 Salem Unit 1 Reactor Coolant System Cooldown Limitations Applicable for Cooldown Rates up to 100&deg;F/HR for the Service Period up to 15 EFPY SALEM -UNIT 1 3/4 4-27 500 _________________
 
_
Material Pr.rty B:sis*--
' .
Initial RTNDT' RTNDT After 15 EFPY:
* Initial RT NOT: 45 &deg; F RT NOT After lSEFPY: 2500 2250 2000 1750 3/4T, 162&deg;F l/4T, 222.5&deg;F r r I I I I I ! I I f I I I r I I r ! Leak Test I Limit I I Heetup
                                          -56 F l/4T 3/4T
-I 1500 111 a. .._ 1250 111 111 lo.I f 1000 Q lo.I ... c u 750 Q z 500 250 00 50 100 Up To I 61 l *F /Hr" I I ) I Unacceptable
                                                        =
/ Operation f/ f_; D I/ -.... Acceptible Operation 150 200 250 300 I I I I I I I I I 7 I I I 7 I . 1orft1calit)
                                                        =
L 1111ft Bu--* Jn lnservfcu Hydrostitfc Test Tenp. (JJ;*F) fo;-the Servic. Period Up
                                                                --~-~--'
* 15 EFPY I I I I I I I I 350 400 INOICATED TEMPERATURE (DEG.r) CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS 450 Fiqure 3.4-2
222.5&deg;F 162&deg;F
* Salem Unit 1 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 60&deg;F/HR for the Service Period up to 15 EFPY SALEM -UNIT l 3/4 4-26 I I 500}}
* 2500 I
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I 1750                                                                                              j I
          ..... 1500                                                                                            I
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                                                                                                          .
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            -         ...
CooldCMI Rates
                              *F/Hr             _.__
                                                                .... ....
                                                                        ~  .
                                                                            ~
                                                                          ,,,.
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                                                '-"'"   ~          ~
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                                                          ..,..                           AccepUble 250 .
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                                  ~
50        100    150             200             250               300       350           500 INDICATED TEMPERATURE (DEG.F)
CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure 3.4-3         Salem Unit 1 Reactor Coolant System Cooldown Limitations Applicable for Cooldown Rates up to 100&deg;F/HR for the Service Period up to 15 EFPY SALEM - UNIT 1                                         3/4 4-27
~: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
 
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Initial RT NOT: 45 &deg;F -~----------==------=-=-=--=-=--~-
RT NOT After lSEFPY: 3/4T, 162&deg;F
* l/4T, 222.5&deg;F 2500                                      r r I           I   I   I I ! I        I                                          I I f I I         I   r   I I r   !   I                                            I I
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                                                                                    - I                     I Heetup ~ates
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    ~      1250                                                               I
    ~
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111 lo.I f       1000                                                       I Q
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u        750                                            f_;
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500
                                              .... -                                                    1orft1calit)
L1111ft Bu--*
                                        ~
Jn lnservfcu Acceptible                                        Hydrostitfc Operation                                        Test Tenp.
250                                                                                        (JJ;*F) fo;-
the Servic.
Period Up
* 15 EFPY I     I     I   I I   I     I I 00      50      100    150        200          250          300              350                   400           450 500 INOICATED TEMPERATURE (DEG.r)
CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Fiqure 3.4-2
* Salem Unit 1 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 60&deg;F/HR for the Service Period up to 15 EFPY SALEM - UNIT l                                     3/4 4-26}}

Revision as of 11:12, 21 October 2019

Forwards Addl Info Re Pressure Temp Limits,Per NRC 890526 Request & Discussion W/Tsao of NRC on 890724.Capsule Z Did Not Contain Any Weld Metal Specimens.Therefore,Discussion of Specimens Not Included in WCAP-11955
ML18094A595
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/31/1989
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N89139, NUDOCS 8908080230
Download: ML18094A595 (7)
v • d • e


Text

Public Service Electric and Gas

  • Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations July 31, 1989 NLR-N89139 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR ADDITIONAL INFORMATION PRESSURE TEMPERATURE LIMITS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide PSE&G's responses to the questions forwarded in the request for additional information dated May 26, 1989. The attached responses were discussed with Mr. Tsao of the NRC staff on July 24, 1989. Figures 3.4-2 and 3.4-3 for Unit 1 were revised as a result of this conversation and are attached for incorporation into LCR 88-14.

Should you have any questions, please feel free to contact us.

Sincerely, Attachment 89-oaoso2:30--89o731 --.----.

PDR ADOCK 05000272 P PNU I I

  • ----*-'

Document Control Desk NLR-N89139 2

  • 7-31-89 C Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
  • ATTACHMENT
  • QUESTIONS & RESPONSES - PRESSURE/TEMPERATURE LIMITS (LCR 88-14)

A. WCAP-11955 describes the test results of specimens in Capsule Z at Salem 1. The following questions relate to WCAP-11955 which provides the technical bases for the 12/28/88 submittal for Salem, Unit 1:

1. There was no discussion of weld metal in Section 4, Description of Program, in WCAP-11955. However, Table 4-1 discusses weld metal from Capsule Y. Table 4-2 and Table A-1 discusses a certain weld metal but we could not determine whether that weld metal was included in Capsule z. Was there a weld metal included in Capsule Z?

Rl. Salem Unit 1 Capsule z did not contain any weld metal specimens. Therefore, no discussion of weld metal results was included in WCAP-11955.

2. Assuming there was no weld metal in Capsule z, then how was RTNDT of the weld metal calculated as shown on Pages A-7 and A-8. It appears that Westinghouse took the weld metal in Capsule Y (WCAP-11554) to be used in the P/T curves in WCAP-11955. Explain.
3. Table A-1 showed three weld metals. Which weld metal is the limiting one? That is, which weld metal was used in the calculations on Pages A-7 and A-8?

R2 & R3. The lower shell longitudinal weld seam 2-042C located on a 45° azimuth was considered the limiting weld material as indicated on Page A-7 of WCAP-11955. A chemical content of 0.35 cu and 1.00 Ni was used in developing t~g hea~up/cooldown (H/C) curves. A fluence of 7.68 X 10 n/cm at 15 EFPY for a weld located at a 45° azimuth from table 6-14 of WCAP 11955 was used for H/C curves.

4. It appears that the chemistry factor of 212°F as shown on Page A-7 was obtained by using the copper and nickel contents of the weld metal. However, we could not determine how the chemistry factor of 158.9°F for the based plate was obtained. Regulatory Guide 1.99, Rev.

2, provides an alternative method (Section 2.1) to calculate the chemistry factor when two or more credible surveillance data sets become available.

Explain how both chemistry factors (weld and base plate) were obtained.

R4.

  • A chemistry factor of 272°F was obtained for weld metal from Table 1 of Regulatory Guide 1.99, Revision 2 for Cu 0.35 and 1.00 Ni.

The base metal chemistry factor of 158.9°F was obtained from surveillance data for plate B2402-1 as follows:

Flue2'ce RTNDT (OF) 2 Capsule n/cm ff RTNDT x ff (OF) ff T 0.24 x 1019 100 0.6138 61. 4 0.377 z 1. 33 x 1019 170 1.079 183.4 1.164 244.8 1.541 Chemistry factor = 244.8/1.541 = 158.9 ff - fluence factor

5. Figure A-2 in WCAP-11955 (corresponding to Figure 3.4-2 in the 12/28/88 submittal).

Provide detailed/hand calculations to show that when RTNDT of 162°F is used in calculating P/T heatup curve

~ha~ it is more conservative than if RTNDT of 222.5°F is used.

R5. Following RTNDT values were calculated for 15EFPY (Page A-8 of WCAP-ll955) .

Component EFPY Location ART Plate B2402-1 15 1/4T 204°F Plate B2402-l 15 3/4T 162°F Weld 15 1/4T 222.5°F Weld 15 3/4T 151. 5°F From the above table it is seen that for the 1/4T location, the limiting material is the weld and for the 3/4T location, the limiting material is the plate.

Instead of generating two sets of heatup and cooldown curves, a conservative approach is taken by using 0 0 222.5 F RTNDT at the 1/4T and 162 F RTNDT at the 3/4T.

This approacfi will envelop both the pla~e (B2402-1) and the weld. The Unit 1 Technical Specification heatup and cooldown curves submitted in LCR 88-14 have been revised to indicate both the 1/4T and 3/4T RTNDT values and are submitted herein.

6. Table 4-1 and Table A-1 show inconsistent copper and nickel contents for the base plate B2402-1 and weld metal. Explain. What are the exact percentages of copper and nickel contents used in the calculation of RTNDT of the B2402-1 plate and weld metal.

R6.

  • Table 4-1 reports the copper and nickel values obtained for the Salem surveillance materials. Table A-1 identifies the original chemistry reported for the plates and forgings used in the vessel. In this weld metal a chemical composition of 0.35 Cu and 1.00 Ni was used. In the base metal see the response identified in A-4.

B. Other Questions

1. 10 CFR 50, Appendix G, Section IV.2 specifies pressure and temperature requirements for the vessel closure flange region. Discuss whether Salem 1 and 2 P/T limits satisfy the requirements.

R1. Salem Unit 1 and 2 P/T limits satisfy the requirements of 10CFR50 Appendix G, Section IV.2 as noted on page A-5 of WCAP-11955 for Unit 1 and page A-6 of WCAP-11554 for Unit 2.

2. The Salem Unit 2 P/T curves (Figure 3.4-2 and 3.4-3) in the 12/28/88 submittal show two RTNDT values at 1/4T and 3/4T locations. We could not aeeerrnine which RTNDT was used for the heatup curve and which RTNDT was usea for the cooldown curve. Discuss.

R2. The following RTNDT values were used to develop the heatup and cooldown curves for Unit 2.

Component Location ART Long. Weld 10 1/4T 178.6°F Long. Weld 10 3/4T 116.1°F RTN of 178.6°F at 1/4T location is used to develop coo£down curves and RTNDT of 178.6°F (at 1/4T), 116.1°F (at 3/4T) are used to aevelop heatup curves.

3. Table B 3/4.4-1 of the Salem Unit 2 Technical Specification revision in the 12/28/88 submittal: The limiting longitudinal weld in Figure 3.4-2 and 3.4-3 of the Salem Unit 2 Technical Specification revision show the copper content of 0.35% and nickel content 1.00%.

This chemical composition is inconsistent with the weld metals in table B 3/4.4-1.

  • R3. Although the chemical composition for Salem Unit 2 weld metal identified in Table B 3/4.4-1 of the Technical Specification is inconsistent with Figures 3.4-2 and 3.4-3, a more conservative chemical content (0.35% Cu and 1.00% Ni) was used for the H/C curves.

Material Pr.rty B:sis*--

Initial RTNDT' RTNDT After 15 EFPY:

-56 F l/4T 3/4T

=

=

--~-~--'

222.5°F 162°F

  • 2500 I

7 2250 I

I 2000 I

I 1750 j I

..... 1500 I

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w a:

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Cll Cll 1250

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750 .*

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CooldCMI Rates

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Operation

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50 100 150 200 250 300 350 500 INDICATED TEMPERATURE (DEG.F)

CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure 3.4-3 Salem Unit 1 Reactor Coolant System Cooldown Limitations Applicable for Cooldown Rates up to 100°F/HR for the Service Period up to 15 EFPY SALEM - UNIT 1 3/4 4-27

~: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

'. ~

Initial RT NOT: 45 °F -~----------==------=-=-=--=-=--~-

RT NOT After lSEFPY: 3/4T, 162°F

  • l/4T, 222.5°F 2500 r r I I I I I ! I I I I f I I I r I I r  ! I I I

Leak Test I I Limit I I 2250 I I I I 7 I

2000 I

I 1750 I 7

- I I Heetup ~ates

~ 1500 Up To 61 l *F/Hr" I .

111 a.

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~ 1250 I

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111 )

111 lo.I f 1000 I Q

Unacceptable /

...c lo.I Operation f/

u 750 f_;

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500

.... - 1orft1calit)

L1111ft Bu--*

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Jn lnservfcu Acceptible Hydrostitfc Operation Test Tenp.

250 (JJ;*F) fo;-

the Servic.

Period Up

  • 15 EFPY I I I I I I I I 00 50 100 150 200 250 300 350 400 450 500 INOICATED TEMPERATURE (DEG.r)

CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Fiqure 3.4-2

  • Salem Unit 1 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 60°F/HR for the Service Period up to 15 EFPY SALEM - UNIT l 3/4 4-26
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