ML20117P773

Advises That Based on Review of CEN-348(B)-P, Extended Statistical Combination of Uncertainties, Many Items Classified as Proprietary Per 10CFR2.790 Should Be Unclassified.Requests Findings Be Forwarded to Licensee

ML20117P773
Person / Time
Site:	Calvert Cliffs
Issue date:	07/22/1987
From:	Hodges M Office of Nuclear Reactor Regulation
To:	Capra R Office of Nuclear Reactor Regulation
Shared Package
ML20116D885	List: ML20116D909 ML20116D938 ML20116D955 ML20116D996 ML20116E022 ML20116E030 ML20116E054 ML20116E116 ML20116E188 ML20116E217 ML20116E250 ML20116E468 ML20116E482 ML20116E510 ML20116E531 ML20116E556 ML20116E581 ML20116E602 ML20116E630 ML20116E658 ML20116E700 ML20116E718 ML20116E733 ML20116E793 ML20116E819 ML20116E870 ML20116F010 ML20116F242 ML20116F258 ML20117P719 ML20117P732 ML20117P766 ML20117P770 ML20117P773 ML20117P775 ML20117P777 ML20117P784 ML20117P786 ML20117P789 ML20117P802 ML20117P803 ML20117P820 ML20117P823 ML20117P824 ML20117P828 ML20117P831 ML20117P854 ML20117P857 ML20117P860 ML20117P861 ... further results
References
FOIA-96-237 NUDOCS 8707310265
Download: ML20117P773 (1)

Text

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i MEMORANDLM FOR:

Robert A..Capra, Project Director i

Project Directorate I-1 Division of Reactor Projects - I/II

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FROM:

M. W. Hodges, Chief l

Reactor Systems Branch l

Division of Engineering & Systems Technology SU8 JECT:

10 CFR 2.790 REVIEW 0F TOPICAL REPORT CEN-348(B).P i.

l In reviewing topical report CEN.348(B).P. " Extended Statistical Combination of j

Uncertainties," the Reactor Systems Branch has found that many of the items describin; the currently approved statistical combination of uncertainties l

(SCU) metelology which have been designated as proprietary in the report have been previously mentioned in CEN.124(B).P Parts 1, 2, and 3 as j

non-proprietary. The staff, therefore, feels that these items should also be j

non-proprietary in the current report. Similar items classified as j

proprietary for the proposed extended SCU concept should also be treated as non. proprietary since they(are of a type that are not customarily held in confidence by their owner CE). This includes all the items in the Abstract i

and Chapters 1 through 3, except for the numerical values of the uncertainty i

penalties, component system parameter uncertainties and allowances, and the j

figures detailing the SCU procedures. The minimum DNBR limit, of course.

should not be proprietary since it is a Tech Spec value upon which many of the i

safety analyses are based.

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Please forward our findings to the licensee (Baltimore Gas & Electric) concluding that much of the infomation sought to be withheld from publie disclosure does not meet the requirements of 10 CFR 2.790 and advise them to l

revise CEN-348(B).P accordingly.

i stWest dgand by MW M. W. Hodges, Chief Reactor Systems Branch Division of Engineering & Systems Technology cc:

A. Thadani DISTRIBUTION i: l';,

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M. W. Hodges 7, b (B70731036 b 70722 6 $ / / f, T. Collins-0 N-8-2EDE*RP CE CF h

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L. Kopp, SRXB, x24204

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.C DATE :7/24/87

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7/$-/87 OFFICIAL RECORD COPY