ML20062C960

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Forwards Revised Response to Containment Sys Branch 820301 Request for Addl Info.Comparsion for Worst Case LOCA of Containment Pressure & Temp Response Using Mass & Energy Release Data Provided
ML20062C960
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 08/03/1982
From: Devincentis J
PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO.
To: Miraglia F
Office of Nuclear Reactor Regulation
References
SBN-303, NUDOCS 8208050408
Download: ML20062C960 (4)


Text

- ______

PUBLIC SERVICE s u a su m Engineering Office-.

Companyof New H-@

1671 Worcester Road Framinoham, Mossochusetts 01701 (617) - 872 - 8100 August 3, 1982 SEN-303 T. F. B 7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Mr. Frank J. Miraglia, Chief Licensing Branch No. 3 Division of Licensing

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docl<et Nos. 50-443 and 50-444 (b) USNFC Letter, dated March 1,1982, " Request for Additional Infonnation" F. J. Miraglia to W. C. Tallman (c)

PShH Letter, dated April 2,19E2, "Fesponse to 480 Series RAIs; (Containment Systems Branch)" J. DeVincentis to F. J. Miraglia

Subject:

Revised Response to RAI 480.9; (Containment Systems Eranch)

Dear Sir:

We have enclosed a revised response to the subject RAI which you forwarded in Reference (b).

The initial response to RAI 480.9 was included in Reference (c).

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY hp d.

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J. DeVincentfs O

Project Manager 8208050408 820803 PDR ADOCK 05000443 PDR A

__.____J

s RAI 480.9 The mass and energy release analysis for postula ted LOCAs in FSAR Section 6.2.1.3 is based on a Westinghouse report, NS-TMA-2075, " Westinghouse LOCA Fbss and Energy Release Model for Containment Dec1gn." This report is current-ly under staff review and has not been accepted.

Provide a comparison for the worst case LOCA of containment pressure and temper-ature response using the mass and energy release data based on NS-TMA-2075 and on the previously accepted methodology of WCAP-8312A.

RESPONSE

The containment pressure-temperature transient responses have been analyzed using mass and energy release rates calculated by using the method given in WCAP-8312A for a double-ended guillotine break in the pump suction line with maximum safety injection, which is identified in FSAR as the most severe LOCA.

Figures 480.9-1 and 480.9-2 show the calculated pressure and temperature responses, respectively. Also shown in Figures 480.9-1 and 480.9-2 are the results of the analysis performed in the FSAR for comparison. The maximum containment pressure using WCAP-8312A blowdown is calculated to be 46.3 psig compared to 46.1 psig as reported in the FSAR.

The maximum containment temperature of 297 F cal-culated herein, however, is significantly higher than 2700F obtained in the FSAR analysis because of the relatively higher enthalpy steam blowdown during the early reflood period given in WCAP-8312A.

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