ML20050C712

Forwards Bounding Analysis Impact Study of NUREG-0630, in Response to Open Item Re NUREG-0630,cladding Swelling & Rupture Models for LOCA Analysis

ML20050C712
Person / Time
Site:	Midland
Issue date:	04/02/1982
From:	Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20050C713	List: ML20050C712 ML20050C714
References
RTR-NUREG-0630, RTR-NUREG-630 NUDOCS 8204090280
Download: ML20050C712 (3)

Text

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f Consumers v Power

i Pr sid - Projects, Engineering and Construction General offices

1945 West Parnell Road, Jackson, MI 49201 * (517) 78!F0453 April 2, 1982 k h 6' g p,GC3. : d0 Harold R Denton, Director Office of Nuclear Reactor Regulation

[- "g O g )ggy g Division of Licensing It"g' %'g" Y US Nuclear Regulatory Commission 7 T.06 @'

Washington, DC 20555 /

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?!IDLAND PROJECT "

tilDLAND DOCKET NO 50-329, 50-330 NUREG-0630 CLADDING SWELLING AND RUPTURE ff0DELS FOR LOCA ANALYSIS FILE: 0505.804 SERIAL: 16593

Reference:

tieeting between CP Co and NRC/CPB on Pfarch 16, 1982 Enclosures (1) B&W Report " Bounding Analysis Impact Study NUREG-0630",

B&W IJocument No 12-1132424, Rev 0 During a meeting on December 14, 1981, Consumers Power Company discussed with the CPB Staff their position regarding NUREG-0630. Subsequent to this meeting, Consumers Power enaaged B&W to perform a supplemental ECCS analysis to determine the impact of NUREG-0630 on flidland. This analysis was discussed with your staff in a second meeting at Bethesda on riarch 16, 1982. The attachment is a report of the analysis.

This analysis is a conservative bounding impact study which was performed on the 177 FA lowered loop NSS, but the results are consi kred to be generally applicable to all B&W NSS. The impact on the most limiting large break (8.55 ft' at the PD, C was saluated at t h 2 foot core elsation, since D

previous experience has demonstrated this core elevation to be the most sensitive with respect to the cladding swelling and rupture model phenomena.

Other core elevations would experience less impact.

The NUREG-0630 models used i:aciuded the O C/S curve from Figure 3 of NUREG-0630 and the combination of the more limiting of the fast or slow ramp correlations f rom Appendix B of NUREG-0630. No code modifications were performed prior to the above analysis. The envelope of the fast and slow ramp Flow Blockage curves from Appendix B was used in the CRAFT 2 code since flow retardation is the dominant effect of rupture on core hydraulic predictions. g ol The Circumferential Strain ?!odel of Appendix B was incorporated into the 3 TilETAl-B hot pin analysis.

8204090280 820402 /f PDR ADOCK 05000329 A PDR oc0382-0822a131

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) We propose to establish a technical specification LOCA limit of 14.0 kW/ft at the 2 foot elevation. This translates into a 0.5 kW/ft penalty from

, NUREG-0630. Higher elevations in the core will have less (or zero) impact as explained in the attachment.'

i With the information included in the attachment, it should be possible for the Commission to close the open item regarding the impact of NUREG-0630 on the Midland ECCS analysis.

1 JWC/TEll/ fms

. CC RJCook, Midland Resident Inspector Rifernan, US NRC CBerlinger, US NRC/CPB 4

DBMiller, Midland Construction (3)

RWII2ston, Washington l

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CONSUMERS POWER COMPANY Midland Units 1 and 2 Docket No 50-329, 50-330 Letter Serial 16593 Dated April 2, 1982

At the request of the Commission and pursuant to the Atomic Energy Act of 1954, and the Energy Reorganization Act of 1974, as amended and the Commission's Rules and Regulations thereunder, Consumers Power Company submits this letter concerning hTREG-0630 Cladding Swelling and Rupture Models for LOCA Analysis.

CONSUMERS POWER COMPANY By h Cook, Vice President Proj ts, Engineering and Construction j Sworn and subscribed before me this 6 day of April 19J) kW= en %

Notary Public- )

Jackson County, Michigan My Commission Expires September 8, 1984 L

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