ML20138E316
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k UNITED STATES
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NUCLEAR REGULATORY COMMISSION j[
WASHINGTON, D.C. 20555-0001 March 24 1994 g 4 yg Docket Nos. 50 %
MEMORANDUM FOR: Herbert N. Berkow, Project Director Project Directorate II-2 Division of Reactor Projects - I/II FROM:
Jared S. Wermiel, Chief Instrumentation and Controls Branch Division of Reactor Controls and Human Factors
SUBJECT:
ST. LUCIE UNITS, 1 AND 2 - RESPONSE TO GENERIC LETTER 89-19 (A-47), STEAM GENERATOR OVERFILL PROTECTION (TAC NOS. M75002 AND M75003)
Plant Name:
St. Lucie, Units 1 and 2 Utility:
Florida Power & Light Company TAC No.
M75002 and M75003 Docket No.:
50-313 Project Directorate:
11-2 Project Manager:
J. Norris Review Branch:
HICB/DRCH l
Review Status:
Complete As a result of the technical resolution of USI A-47, " Safety Implications of Control Systems in LWR Nuclear Power Plants," the NRC concluded that protection should be provided for certain control system failures, and, for certain plants, that selected emergency procedures should be modified to assure that plant transients resulting from control system failures do not compromise public safety.
Generic Letter (GL) 89-19 provided recommendations for control system design and procedural modifications for resolution of USI A-47. Specifically, i
GL 89-19 recommended that all Combustion Engineering plant designs provide automatic steam generator overfill protection, with associated technical specifications for periodically verifying its operability, to mitigate main feedwater overfeed events during normal operation. Additionally, it was recommended that all utilities that have plants designed with high pressure injection pump discharge pressures less than or equal to 1275 psi reassess their emergency procedures and operator training programs and modify
Contact:
Sang Rhow (HICB/DRCH)
L.4-2826 4\\o\\
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2b0028 i
NE HLE CENTER COPY I4 (c; 3 2_ 9 e> c> 7 2 M M..?
v' H. N. Berkow.
them, as needed, to ensure that the operators can handle the full spectrum of l
possible small-break loss of coolant accident scenarios which may occur from control system failures and a resulting steam generator overfill. By "L-90-106, Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants, Per [[CFR" contains a listed "[" character as part of the property label and has therefore been classified as invalid.)|letter dated March 19, 1990]], the licensee provided a response to the recommendations in GL 89-19 for St. Lucie Units 1 and 2.
The Instrumentation and Controls Branch has reviewed the licensee's response to GL 89-19 and prepared the enclosed safety evaluation. Based on our evaluation, we conclude that St. Lucie Units 1 and 2 provide acceptable automatic steam generator overfill protection systems. Also, we conclude that the plant operating procedures and operator training program are adequate to ensure that operators can handle the full spectrum of possible small-break loss-of-coolant-accident (SBLOCA) scenarios.
SALP input is provided as Enclosure 2.
Original signed by:
Jared S. Wermiel, Chief Instrumentation and Controls Branch Division of Reactor Controls and Human factors i
Enclosures:
As stated i
cc:
J. Norris K. Jabbour 1
Distribution 1 i
etsubpWWWMNpmW HICB R/F (2)
DRIL/RPEB (SALP) 10A19 S. Rhow J. Wermiel J. Mauck C. Thomas /B. Boger 0FFICE HICB SC:HICB
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BC:H5f B:DR_CH n
NAME S.Rhow)lb J. Mauck J.Wehl u
DATE 3/2 ;/93 3/ss/93 3/23/93 h
NO NO YES C Y OFFICIAL RECORD COPY Document Name: STLA47 i
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