ML18094B128

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Amends 890731 Response to NRC Request for Addl Info Re License Change Request 88-14 Concerning Pressure Temp Limits.Revised Questions & Answers & Revised Tech Spec Table B 3/4.4-1 Encl
ML18094B128
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/18/1989
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18094B129 List:
References
NLR-N89207, NUDOCS 8910240144
Download: ML18094B128 (8)
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Text

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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer OCT 1 8 1989 NLR-N89207 U.S. 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 amend PSE&G's letter dated July 31, 1989, which responded to a NRC request for information with regard to License Change Request (LCR) 88-14.

As discussed with Mr. Tsao of the NRC staff on September 29, 1989, the reactor vessel lower shell longitudinal weld seam on the 45° azimuth is 3-042C, not 2-042C as indicated in WCAP 11955.

The questions and responses originally attached to PSE&G's July 31, 1989 letter have been.revised and are provided in Attachment 1 to this letter.

Attachment 2 contains Technical Specification table B 3/4.4-1, which has been revised since its submittal via letter dated December 28, 1988 to include a better description of the reactor vessel welds. No changes to the Salem Generating Station heatup and cooldown curves, nor to their supporting calculational methodology or inputs are proposed herein.

  • Therefore, the original determination of No Significant Hazards Consideration, in PSE&G's letter of December 28, 1988, remains valid.

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Document Control Desk

  • Der 1 s 1989 NLR-N89207 If there are any additional questions, please do not hesitate to contact us.

Sincerely, Attachment 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 1 NLR-N89207 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*?

R1. 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 ana 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 3-042C 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° 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 base 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 212°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:

Flue2ce RTNDT (OF)

Capsule n/cm ff RTND'f x ff (OF) ff2 19 100 T 0.24 x 1019 0.6138 61.4 0.377 z 1.33 x 10 170 1. 079 183.4 1.164 244.8 1.541 Chemistry factor = 244.8/1.541 = 15809 ff - fluence factor

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

Provide deta~led/hand calculations to show that when RTNDT of 162 F is used in calculating P/T heatup cu~e

~heft. it is more conserv~ive than if RTNDT of 222. 5 F is used. . * .

RS. Following RT¥£g values were calculated for lSEFPY (Page A-8 of WCAP- 55).

Component EFPY Location ART Plate B2402-1 15 l/4T 204°F Plate B2402-1 15 3/4T 162°F Weld 15 1/4T 222.5°F*

Weld 15* 3/4T 151. s°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 curveB, a conservative approach iB taken by using 222.5 F RT at the 1/4T and 162 F RT at the 3/4T.

This appro!iBft will envelop both the plliE~ (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 l/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.

Rl. 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 I: .. and page A-6 of WCAP-115~4 for Unit 2. * * ... ,.

2. The Salem Unit 2 *P/T cµrves (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 ae~ermine which RTNDT was used for the heatup curve and which RTNDT was usea-for the cooldown curve. Discuss.

~... ~

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 RTNDT of 178.6°F at 1/4T location bs used to develop cooiaowncurves and RT of 178.6 F (at l/4T), 116.1°F (at 3/4T) are used to tfR~elop heatup curves.

3. Taple 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%.

Thi~ 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 P19:rty Basis Initial RTNOT: -56°F RT NOT After 15 EFPY: l/4T s 222. S°F 3/4T = 162°F 250.0 j

2250 I

2000 T

1750

- 1500

-w . 1250

!Ill I

Ill

! 1000 Ur11ccepUJtle OperaCfOft ......

Q w m w,_

~

c 750 .. ,

,,,,, *~

Q z --D CooldCMI Rates

,_ J 500 -- *FJHr

---~

~

.- o- --

-.. ~ Acc1t1t.Uls 250 - --

6,....... ~

Operat10ft 50 100 150 200 250 . 300 350 ,00 500 INOICUED TC-ERATUIC (DEG~F)

CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure 3.4-3 Sala Unit 1 Reactor Coolant Syst* Cooldown Limitations Applicable for Cooldown Rates up to ioo*F/HR for the Service Period up to 15 EFPY SALBM - ONI'l' 1 3/4 4-27

  • ~ Material Pr~ty Initial RTNOT: 45°F RTNOT After lSEFPY: 3/4T, 162°F l/4T, 222.5°F 2500 I TI I I I I I I I ! I

' I 111 I I I I I I r 11 I I

Luk-THC I I L1*1t I 2250 I I

. I I

I I

2000 j . I I I 1750 I I I I Heaiup A1t11

~ 1500 Up To Ill a.

Ill 12"1

~**'/Hr I

I Ill

~

a. 1000 UNCcepUlt1e I

Q

&.I Opent1on c .-

u 750 .!*

., I./

i j

i.rtt1c11 t) 500

- Acceptable

_Lf*1t S.s-*

..n lnservtc.

HydroltHt~

Opent1on Tut Temp.

250 (llM) fo-the Servic.

Period Up

  • I 15 Em I I I I I I I 50 100 150 300 350. 400 INOICATED TEMPERATUIWC (DCG.r) 1.

CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS.

Fiqur* 3.4-2

  • Saliili Unit 1 Reactor Coolant Syst.. Haatup Limitations Applicable for He1tup Rates up ta &o*F/HR for the S.rvic1 Period up to 15 EFPY SALBM - UNI'l' 1 3/4 4-26

ATTACHMENT 2

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