ML20091P205

Forwards Request for Addl Info Re Radiological Consequences Following Postulated Steam Generator Tube Rupture Accident, for Transmittal to Applicant

ML20091P205
Person / Time
Site:	Midland
Issue date:	07/06/1983
From:	Muller D Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML17198A223	List: IR 05000329/1983008 ML20090A052 ML20090A064 ML20090A067 ML20090A071 ML20090A076 ML20090A080 ML20090A090 ML20090A103 ML20090A106 ML20090A110 ML20090A367 ML20090A377 ML20090A397 ML20090A403 ML20090A447 ML20090A451 ML20090A456 ML20090A465 ML20090A481 ML20090A487 ML20090A491 ML20090A500 ML20090A504 ML20090A514 ML20090A517 ML20090A543 ML20090A547 ML20090A559 ML20090A590 ML20090A594 ML20090A600 ML20090A613 ML20090A614 ML20090A623 ML20090A626 ML20090A631 ML20090A637 ML20090A642 ML20090A656 ML20090A658 ML20090A673 ML20090A698 ML20090A703 ML20090A733 ML20090A741 ML20090A748 ML20090A751 ML20090A758 ML20090A762 ... further results
References
CON-BOX-08, CON-BOX-8, FOIA-84-96 NUDOCS 8406120624
Download: ML20091P205 (2)

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JUI. 0 6 1983

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bucket tios.: 50-329, 33c

!!Q1 ORA!! Dull FOR: Thomas II. Novah, Assistant Director for Licensinr Division of Licensine i

FR0il:

Daniel R. Iluller, Assistant Director fo'r Radiation Protectior:

Division of Systems Integration

SUBJECT:

lilDLAND UNITS 1 & 2 STEni GENERATOR TUSE RUPTURE ANALYSIS (SGTR)

The current Ilidland Safety Evaluation Report cuncludes that the radiological consequences following a SGTR arc within the acceptance criteria of Standard Review Plan (SRP) Section 15.G.3.

Ilowever, in FSAR t

Anencuent 47 (December 1982) the applicant presented an accident scenario which included steanino the aficcted steam oenerator until the

/, unit was able to switch to the. decay heat removal system. This is the

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first plant of any reactor type to present an accitient scenario which includes steaming of the affected stcam generator as a means of nitigating the SGTR accident. Because the assumed plant respcnse is a significant departure fron the previous applicant assumptions of isolating the affected stean generator as rapidly as possible, we conclude that we need r.; ore ininrrution abcut the systen response in order to evaluate the potential offsite radiological consequences.

i Therefore, please forward the rLinuest for additional infornation j

contained in the enclosure to the applicant.

I In a memo dated June 29,1983 from R. W. Ilouston tn T. II. tlovak, P.SB also 4

requested additional infomation about the 111diand SGTR. - In this memo, R5G also requested that the applicant provice a duse analysis of the SGTR with a loss of offsite power and any additional single failure. ~ lt should be noted that the sir.gle active failure assumption was not rigorously enforced on past application reviews due.to the lack of a detailed systems review coincident with the ridiological review.

ilhile the single failure assumption in conjunction with the use of the 10 CFR 1

Part 100 dose guideline values is an extension of the current SRP revieu prc.cedures, it is entirely consistent with current and past staff revieu l

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practices for all events categorized as postulated design basis.

accidents. As part of the evaluation of such events, it will be nccessary for AEG to evaluate the offsite radiological consequences.

Therefore, the enclosure also includes a rdquest for additional information concerning inportant radiological parancters.

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ENCLOSURE

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REQUEST FOR ADDITIONAL INFOR!!ATION CONCERNING THE RADIOLOGIC CONSEQUENCES FOLLOWING A POSTULATED STEAM GENERATOR TUBE RUPTi

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ACCIDENT AT MIDLAND UNITS 1 & 2 t

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For a postulated design basis steam generator tube rupture accident 1.

j (SGTR) as prescirbed in Standard Review Plan Section 15.6.3 provide the following information until such time as releases from the affected steam generator terminate:

A description of the sequence of events which includes an a.

identification of all operator actions and when these actions are expected to occur. Also include descriptions of the automatic i

initiations and actuations as they occur chronologically.

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The following paran.aters as a function of time:

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1) the primary system pressure;

2) the tube rupture flow rate and integrated tube rupture flow; s

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3) the secondary liquid water mass and level in both steam t

generators;

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4) the primary system liquid mass;

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5) the secondary system pressure in both steam generators;

6) the integrated mass released out of the atmospheric relief valves or safety valves for both the affected and unaffected 1

steam generators; mem.

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