ML20117Q050

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Forwards Safety Evaluation Accepting Util 900813 Proposed Changes to Tech Specs Re Low Temp Overpressure Protection. Proposed Changes Acceptable.Salp Evaluation Provided
ML20117Q050
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 08/28/1990
From: Rosalyn Jones
Office of Nuclear Reactor Regulation
To: Capra R
Office of Nuclear Reactor Regulation
Shared Package
ML20116D885 List: ... further results
References
FOIA-96-237 TAC-77292, NUDOCS 9008310137
Download: ML20117Q050 (2)


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August 28, 1990 MEMORANDUM FOR:

R. A. Capra, Project Director (148-2)

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

Robert C. Jones Chief Reactor Systems Branch Division of Systems Technology

SUBJECT:

SAFETY EVALUATION FOR CALVERT CLIFFS UNIT 1 TECHNICAL SPECIFICATION CHANGES FOR LOW TEMPERATURE OVERPRESSURE PROTECTION Plant Name:

Calvert Cliffs Unit 1 Utility:

Baltimore Gas and Electric Company TACNo(s).:

77292 DocketNo(s).:

50-317 Operating License:

DPR-53 Project Directorate:

Project Directorate I-I Project Manager:

D. Mcdonald Review Branch:

SRXB/ DST Review Status:

Complete By letter dated August 13, 1990, The Baltimore Gas and Electric Company (BG&E) proposed Technical Specification changes relating to low temperature overpressure protection (LTOP) for Calvert Cliffs Unit 1.

The Reactor Systems Branch (SRXB) has reviewed the licensee's submittal in those areas involving the adjustment of LTOP controls required to ensure the Appendix G Pressure-Temperature (P/T) limits applicable to 12 effective full power years are not exceeded. The most recent review of the Calvert Cliffs LTOP system was performed to allow a continuation of the Unit 1 outage while analyses were completed for long term reactor coolant pump (RCP) start controls. This temporary approval was effective onl,y for the period prior to the plant entering operational Mode 2 (Startup) and was granted in License Amendment No.

145 to the Calvert Cliffs Unit 1 Facility Operating License. The current request reflects an updated analysis of the limiting energy addition transient assuming higher decay heat loads that exist shortly after a reactor shutdown.

The basis for the new P/T curves is the final Revision 2 to Regulatory Guide 1.99; this part of the proposal is being reviewed elsewhere. SRXB has prepared the enclosed safety evaluation (Enclosure 1). We find the proposed 4

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R. A. Capra Technical Specification changes acceptable. Our SALP evaluation is provided in Enclosure 2.

This completes the SRXB effort for TAC No. 77292.

Originalsigned by Robert C. Jones Robert C. Jones, Chief Reactor Systems Branch Division of Systers Technology

Enclosures:

As stated cc w/ enclosures:

A. Thadani D. Mcdonald (148-2 PEB/SALP(10A-19))

SRXB Members DISTRIBUTION Dockdt File SRXB R/F RJones TCollins MMcCoy MMcCoy R/F Calvert Cliffs P/F

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Document Name: CAPRA, CALVERT CLIFFS /77292 l