ML20138E182

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Forwards SE Accepting Licensee 901220,911206,920511 & 1009 Responses to GL 90-06, Power Operated Relief Valves & Block Valves Relievability & Addl Low Temp Overpressure Protection for Light Water Reactors
ML20138E182
Person / Time
Site: Saint Lucie  
Issue date: 08/09/1993
From: Rosalyn Jones
Office of Nuclear Reactor Regulation
To: Berkow H
Office of Nuclear Reactor Regulation
Shared Package
ML20136C539 List: ... further results
References
FOIA-96-485 GL-90-06, GL-90-6, TAC-M77382, TAC-M77383, TAC-M77457, TAC-M77458, NUDOCS 9308260110
Download: ML20138E182 (1)


Text

MEMORANDUM FOR: Herbert N. Berkow, Director Project Directorate, PD-II-2 Division of Reactor Projects, 1/II FROM:

Robert C. Jones, Chief Reactor Systems Branch Division of Systems Safety & Analysis

SUBJECT:

ST. LUCIE UNITS 1 AND 2; RESPONSE TO GENERIC LETTER 90-06 (TAC NOS M77382/3, M77457/8)

Plant (s):

St. Lucie, Units 1 and 2 Utility:

Florida Power & Light TAC No(s):

M77382, M77383, M77457, M77458 Docket No(s):

50-335, 50-389 License No(s):

DPR-067, NPF-016 Project Directorate: PD, 11-2 Project Manager:

J. Norris Review Branch:

SRXB Review Status:

Complete By letters dated December 20, 1990, December 6, 1991, May 11, 1992, and October 9, 1992, Florida Power and Light Company, the licensee for the St.

Lucie Units 1 and 2, responded to Generic Letter 90-06 " Power Operated Relief Valves and Block Valve reliability and Additional Low Temperature Overpressure Protection for Light Water Reactors".

The Reactor Systems Branch (SRXB) reviewed the submitted information and we find the response acceptable.

For GI-70, acceptability is based on the fact that both St. Lucie Units are equipped with safety grade auxiliary spray and charging pumps; systems equivalent to those used to perform the PORV function by plants licensed without PORVs.

For GI-94, acceptability is based on a licensee commitment to adopt the GL 90-06 technical specifications for Unit 1 and the finding that Unit 2 has technical specifications which fulfill the

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intent of GL 90-06.

The SRXB evaluation is in Enclosure 1, the SALP evaluation is in Enclosure 2.

This completes the SRXB review requirements for TAC Nos M77382/3 and M77457/8.

R. C. Jones, Chief Reactor Systems Branch Division of Systems Safety & Analysis

Enclosures:

As stated

Contact:

L. Lois, SRXB/DSSA, 504-3233

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