ML20117Q046

Forwards Safety Evaluation Supporting Fast Neutron Fluence to Reactor Pressure Vessel.Salp Input Encl

ML20117Q046
Person / Time
Site:	Calvert Cliffs
Issue date:	06/22/1990
From:	Rosalyn Jones 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 TAC-76130, NUDOCS 9006280101
Download: ML20117Q046 (1)

Text

i June 22, 1990 j

MEMORANDUM FOR: Robert A. Capra, Project Director (14B-2)

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

FROM:

Robert C. Jones, Chief Reactor Systems Branch i

Division of Systems Technology

SUBJECT:

CALVERT CLIFFS UNIT 1, PRESSURE VESSEL NEUTRON FLUENCE ESTIMATE FOR PRESSURE-TEMPERATURE LIMITS i

Plant Name:

Calvert Cliffs, Unit 1 I

Utility:

Baltimore Gas and Electric Company TACNo(s).:

76130 DocketNo(s).:

50-317 Operating License:

DPR-53 Project Directorate:

Project Directorate I-1 Project Manager:

D. Mcdonald i

Review Branch:

SRXB/ DST Review Status:

Complete The Reactor Systems Branch (SRXB), reviewed the " Pressure-Temperature Limits for Calvert Cliffs Nuclear Power Plant Unit 1" report prepared by the Southwest Research Institute on behalf of the Baltimore Gas and Electric Company (BG&E) the licensee for the Calvert Cliffs Unit I plant. This review was requested by the Materials Engineering Branch who has the primary responsibility for the approval of Technical Specification changes regarding the low temperature operating limits.

The SRXB review covers only the neutron fluence estimates of the report, i.e.,

Section 4 and Appendices A, B, and C.

Our evaluation is attached as Enclosure 1.

Evaluation of the licensee's performance (SALP) is provided in Enclosure 2.

This completes SRXB's requirements for TAC No. 76130.

Ile Robert C. Jones, Chief 8

Reactor Systems Branch

qo Division of Systems Technology

Enclosures:

DISTRIBUTION

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As stated Ubeket File 2

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