ML18094B128

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
Issue date:	10/18/1989
From:	MILTENBERGER S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18094B129	List: ML18094B128 ML18094B130
References
NLR-N89207, NUDOCS 8910240144
Download: ML18094B128 (8)

Text

• • _. ' *' 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. :::9 :L 0240 i 44 F'DR ADOCt< F' :39101::: 05000272 PDC f>rCPI . *\1

. ,_ .. Document Control Desk NLR-N89207

• Der 1 s 1989 If there are any additional questions, please do not hesitate to contact us. Attachment C Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Sincerely, 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. R1. 2. 3. R2 & R3. 4. 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*? Salem Unit 1 Capsule Z did not contain any weld metal specimens.

Therefore, no discussion of weld metal results was included in WCAP-11955.

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. 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? 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 (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. 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: (OF) Capsule Flue2ce n/cm RTNDT ff RTND'f x ff (OF) f f 2 T 0.24 19 100 0.6138 61.4 0.377 x 1019 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).

RS. Provide calculations to show that when RTNDT of 162 F is used in calculating P/T heatup it is more than if RTNDT of 222. 5 F is used. . * . .*:*.-. 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 (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 A-5 of WCAP-11955 for Unit I: .. and page A-6 of

2. for Unit 2. * * ... ,. The the and was for Salem Unit 2 *P/T cµrves (Figure 3.4-2 and 3.4-3) in 12/28/88 submittal show two RTNDT values at 1/4T 3/4T locations.

We could not which RTNDT used for the heatup curve and which RTNDT was the cooldown curve. Discuss. ... . . . 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 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 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%.

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 2250 2000 1750 ; 1500 --w. 1250 ! Ill Ill ! 1000 Q w -c 750 Ur11ccepUJtle OperaCfOft

.. , D Q z CooldCMI Rates ,,,,, --*FJHr -" --250 ,,. -o-----. -----,, --6,.......

.. --500 ... ... m w,_ ,., ,_ J Acc1t1t.Uls Operat10ft 50 100 150 200 250 . 300 T I 350 INOICUED TC-ERATUIC CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS j ,-I ,00 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 -.. 500 Material Initial RTNOT: 45°F RTNOT After lSEFPY: 3/4T, 162°F l/4T, 222.5°F 2500 2250 2000 1750 1500 Ill a. -! 12"1 Ill Ill a. 1000 I T I I I I I I I I ! I ' 111 I I I I I I r 11 Luk-THC I L1*1t I . I I Heaiup A1t11 I Up To . I I I I I I I I I j . I I I I I ' . Q &.I UNCcepUlt1e Opent1on I -c u 750 .!* I./ ., i j i.rtt1c11 t) 500 -_Lf*1t S.s-* .. n lnservtc.

Acceptable Opent1on Tut Temp. 250 (llM) fo-the Servic. Period Up

• 15 Em I 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 I I .-

ATTACHMENT 2