ML20081J201

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Provides Supplemental Info in Support of NRC Independent Confirmatory Piping Analysis.Info Identifies Bases for Decoupling Core Flood Lines from RCS in Analyses Evaluating Sys Response Due to Asymmetric LOCA Loadings
ML20081J201
Person / Time
Site: Midland
Issue date: 11/04/1983
From: Reynolds J
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Harold Denton
Office of Nuclear Reactor Regulation
References
26463, NUDOCS 8311080353
Download: ML20081J201 (2)


Text

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Consumers Power 0@any a w a.vooia.

Executive Vice President General offices: 1945 West Parnall Road, Jacksorg MI 49201 + (517) 788-1920 November 4, 1983 Harold R Denton, Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 MIDLAND ENERGY CENTER MIDLAND DOCKET NOS 50-329, 50-330 INDEPENDENT CONFIRMATORY PIPING ANALYSIS TRANSMITTAL OF SUPPLEMENTAL INFORMATION FILE: 0485.11, Bl.7, B6.3 SERIAL:

26463

REFERENCE:

(1)

MAMILLER (NRC) TO APPLICANT (CPCO) DATED OCTOBER 17, 1983 (2)

NRC LE* ITER FROM J F STOLZ TO H B TUCKER CF DUKE POWER C0 DATED MAY 20, 1983 ON DOCKET NOS 50-269, 50-270, 50-287 This letter forwards supplemental information in support of the NRC Staff's independent confirmatory piping analysis for the Midland Plant. This information was requested during a telephone conversation between the NRC and Consumers Power Company (CPCo) on October 13, 1983. Specifically, this letter identifies the bases for decoupling the core flood lines from the Reactor Coolant System (RCS) in the analyses which evaluates system response due to asymmetric LOCA loadings.

In NUREG-0800 Rev 1, July 1981, Section 3.7.2.II.3.b, the Staff cited conditions and criteria for when decoupling of piping systems is considered appropriate. The procedure for analyzing the effects of asymmetrical cavity pressures on the NSSS following a postulcted LOCA event has been documented by B&W in their Task Action Plan A-2 report BAW-1621 entitled, " Effects of Asymmetric LOCA Loadings - Phase II Analysis." The decoupling of the RCS and the core flood lines is specifically addressed in Section 5.1.8 of BAW-1621.

In summary, since the mass and stiffness of the core flood lines are very small when compared to those of the reactor vessel, decoupling the core flood lines would have only a negligible effect on the response of the reactor vessel during dynamic excitation. Therefore, the core flood lines are not included in the NSSS analyses performed by B&W. As noted in Reference (2),

BAW-1621 has been previously submitted and accepted by the NRC.

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JWR/MFC/bjw CC RJCook, Midland Resident Inspector JGKeppler, Administrator, NRC Region III MAMiller, USNRC, Licensing Branch 4 8311080353 831104 PDR ADOCK 05000329 IE oc1083-0651a100 A

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1 CONSUMERS POWER COMPANY Midland Units 1 and 2 Docket No 50-329, 50-330 Letter Serial 26463 Dated November 4, 1983 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 additional information concerning the Staff's Independent Confirmatory Piping Analysis.

CONSUMERS POWER COMPANY By L J W ReynbTds, Executive Vice President Energy Supply Sworn and subscribed before me this 4th day of November,19E}3.

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