ML17284A881

Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS

ML17284A881
Person / Time
Site:	Columbia
Issue date:	09/09/1999
From:	Coleman D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-99-169, NUDOCS 9909170206
Download: ML17284A881 (8)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9909170206 DOC.DATE: 99/09/09 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397

.AUTH . iVAME AUTHOR AFFILIATION COLEMAN,D.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards response to NRC 990623 RAI to support review of pending request for amend to reactor pressure-temp limit curve TS.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD4-2 LA 1 1 CUSHING,J 1 1 SC 1 1 INTERNAL: ACRS 1 1 LE CENTER 01 ~ 1 1 NRR/DSSA/SPLB 1 1 .R-/DS SA./SRXB~ 1 1 NUDOCS-ABSTRACT 1 1 OGC/RP 1 0 4

EXTERNAL: NOAC NRC PDR D

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'E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT DISTRIBUTION LISTS THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF. COPIES REQUIRED: LTTR 11 ENCL 10

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NORTH lllfEST PO. Box 968 a Richland, Washington 99352-0968 September 9, 1999 G02-99-169 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TECHNICALSPECIFICATION 3.4.11 (ADDITIONALINFORMATION)

Reference:

Letter, dated June 23, 1999, Jack Cushing (NRC) to JV Parrish (SS), "Request, for Additional Information (RAI) for the Washington Public Power Supply System Nuclear Project No. 2 (TAC No. MA5307)"

In the reference, the staff requested that additional information be provided to support review of our pending request for an amendment to the reactor pressure-temperature limit curve Technical Specification.

The additional information is included as an attachment. Should you have any questions or desire additional information regarding this matter, please call me or PJ Inserra at (509) 377-4147.

Respectfully, 3R DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachment cc: EW Merschoff - NRC RIV DL Williams - BPA/1399 p ~O)

JS Cushing - NRR TC Poindexter - Winston & Strawn NRC Sr. Resident Inspector - 927N 9909i70206 990909 PDR'DQCK 05000397 P PDR

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REQUEST FOR AMENDMENT, TECHNICALSPECIFICATION 3.4.11 (ADDITIONALINFORMATION) TAC NO. MA5307 Attachment

'age1of3 II ~

e Question 1: Pressure Stress Intensity Calculation. Please provide the equation for the pressure stress intensity calculation. In addition, please provide an example using the 150', 158 psig point from Figure 3.4.11-3 of your submittal. Provide all parameters that appear in the pressure stress intensity equation.

~Res anne The pressure stress intensity was calculated using ASME Code (Section XI, 1989 Edition) Figure G-2214-1 and ASME equation Ki= M

• cr The allowable pressure was calculated using a combination of ASME equation K,= M " cr and standard reactor pressure vessel hoop stress equation P = a t /R [where P = pressure (psig), cr = allowable applied stress, t = 9.625 inches (thicker shell section) and R = the mean radius of the vessel at the thicker shell section (130.3 inches)]. The following parameters were calculated using an Energy Northwest verified computer program.

K= 39.47 ksivin K= 27.09 ksi ~in Ki = 6.19 ksi ~in M = 2.89 P = 158psig Using the computer parameters and associated equations, the calculations for allowable pressure are as follows:

6.19 ksi Jin = 2.89 "o cz = 2.142 ksi Therefore: P = (2. 142 ksi ":

9.625 in )/ 130.3 in = 158 psig

I REQUEST FOR AMENDMENT, TECHNICALSPECIFICATION 3.4.11 (ADDITIONALINFORMATION) TAC NO. MA5307 Attachment Page 2 of 3 I

sI The above calculation uses the limiting values of 110'F (150'F minus 40'F) and 158 psig from proposed Technical Specification Figure 3.4.11-2, "Non-Nuclear Heating and Cooldown Curve." Proposed Technical Specification Figure 3.4.11-3, "Nuclear Heating and Cooldown Curve,"

has an additional conservatism in that the 110'F value was increased by 40'F, as required by 10 CFR 50 (Appendix G), which increased the allowable temperature at pressure to 150'F. Appendix G to 10 CFR 50 requires that the pressure-temperature relationship provide at least a 40'F margin over that required for non-nuclear heatup and cooldown.

A reactor pressure vessel fluid temperature of 110'F is used because there are no thermocouples in the beltline region to measure vessel metal temperature. The fluid temperature is then adjusted to the 1/4t thickness

.using ASME Code (Section XI, 1989 Edition) Figure G-2214-3. The minimum temperature used at the 1/4t thickness is conservatively set at 80'F for a corresponding 110'F fluid temperature. The 80'F represents the minimum temperature for bolt-up.

Question 2: Thermal Stress Intensity Calculation. If ASME Code Figure G-2214-2 was used for the thermal stress calculation, please provide the detailed information needed to use the ftgure. If an equation was used instead, please provide the equation and Young's Modulus, the coeQcient of thermal expansion, and Poisson's ratio. For either approach, use the 150', 158 psig point Pom Figure 3.4.11-3 of your submittal as an example, and provide values for the thermal diffusivity, heatup or cooldown rate, and wall thickness.

R~es ense The ASME Code,Section XI (1989 Edition), Figure 6-2214-2 was used for the thermal stress calculation. The following parameters were used in the thermal calculation for 110'F (150'P minus the 40'F conservative margin required by 10 CPR 50, Appendix 6).

Thermal Diffusivity at 110'F = 0.427 ft.sq./hr Heatup/Cooldown Rate = 100'P/hr Wall (Vessel Shell) Thickness = 9.625 inches

REQUEST FOR AMENDMENT, TECHNICALSPECIFICATION 3.4.11 ~ ~

(ADDITIONALINFORMATION) TAC NO. MA5307 Attachment Page 3 of 3 Where d,T = t2 2+P

• 100'F/ hour d,T = 75.255' hT = differential temperature through wall t = vessel thickness P = thermal diffusivity at temperature The Kvalue was determined using ASME Code (Section XI, 1989 Edition) Figure G-2214-2, where K= M,

• hT(M, was determined to be 0.36 for a 9.625 inch thick vessel wall). The M, value was then multiplied by 75.255'F to obtain a Kvalue of 27.091 ksi ~in .

Question 3 Fracture Toughness Equation. Identify the fracture toughness equation used in your calculation.

R~en on e The ASME Code,Section XI (1989 Edition), Figure G-2210-1 was used for the fracture toughness calculation. The equation is as follows:

K-26.78 = 1.233 exp. [0.0145 (T RT>>T + 160)]

Where Kwas calculated conservatively using 80'F as the minimum ~/4t metal temperature (associated with the 110'F and 158 psig points). The RT>>T value used is 79.2'F.

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