ML20059N827

Proposed Tech Specs Re Eagle 21 Mod & Functional Upgrades to Plant Reactor Protection Sys

ML20059N827
Person / Time
Site:	Sequoyah
Issue date:	10/02/1990
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20059N826	List: ML20059N825 ML20059N827
References
NUDOCS 9010180009
Download: ML20059N827 (10)

Text

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TABLE 2.2-1 (Continued).

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8: REACTOR TRIP SYSTEM IN'STRUMENTATION TRIP SETPOINTS FUNCTIONAL' UNIT' v:- ~ TRIP!SETPOINT // /m y n - ALLOWABLE VA' LUES' ~ . E '13.~ Steam Generator Water s I M 4f.narr = rege instruent ' ' r" ef narr=ftrg: %:tr :nt 3,,.L A " - Q F level--Low-Low-4 -Tpen-eech ster generate-Ip:n-esch;ste r g n reter R7. to De(M F

14. -Steam /Eeedwater r!=

-Mismatch-and-tee Ster - ' it" of fe!' L ;te= ' f!= ct ' 12.5% ef fe!' :ter '! = st -Generator-Water Level --RATED THERMAL-POWER coincid:.t NATED THER".".L "'rR : incident xith ste= generater unter' 1 v:!' with ete r ;;;; rater -125% f naq6e r=ge in:tre-1 2if cf narr= rang- = ter levell 's %:tre-~ cat span-eech ste r generater r nt sp r-each :te r g rer:ter i.

15. Undervoltage-Reactor 1 5022 volts each bus R76 Coolant Pumps 1.4739 volts each bus i

16. Underfrequency-Reactor 1 56 Hz each bus

'? Coolant Pumps-1 55.9 Hz each bus m .17. Turbine Trip A. Low Trip System 1 45 psig Pressure 1 43 psig B. Turbine Stop Valve 1 1% open Closure > 1% open 1

18. Safety Injection Input Not Applicable from ESF Not Applicable

19. Intermediate Range Neutron

> 1 x-10 28 amps Flux, P-6, Enable Block 1 6 x 10 11 amps-y, r G; g Source Range Reactor Trip .,.Eg c: Pr g

20. Powt." Range Neutron Flux

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,'r '0 'a ' i; ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 2 DOCKET NO. 50-328 (TVA-SQN-TS-89-27) ' DESCRIPTION AND' JUSTIFICATION FOR REVISION TO TS 89-27 7 4 { - k s,_ 4 ' !j

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e -l o SNCLOSURE 2 j -1 Description of Change. The steam generator water level trip setpoints (Table 2.2-1, Reactor Trip = System Instrumentation Trip Setpoints, Items 13.a and b, and Table 3.3-4, ~' Engineered Safety Feature Actuation System Trip Setpoints, Item 6.c), are revised to account for the installation of modified International Telephone and Telegraph Corporation (ITT) Barton Model 764 steam generator level transmitt:rs-for Unit 2 only. Reason for Change The revised trip setpoints and allowable values reflect the improved accuracy of the modifief. Barton steam generator. level transmitters being installed in Usih z during the Unit 2 Cycle 4 refueling outage. AvailaM*1ty of the modified Barton transmitters was not verified until early Septe.ober 1990, just prior to this refueling outage. The modification to these transmitters was performed by the manufacturer and eliminated errors associated with thermal nonrepeatability (environmental heatup and subsequent cooling) of the transmitter. The previously revised TS 89-27 submittal provided corresponding steam generator setpoints for unmodifled Barton transmitters. Unit 1 presently has unmodified Barton transmitters and will retain the steam generator trip setpoints previously submitted until modified Barton transmitters are installed. 'i Justification for Change i The original setpoints.In the Westinghouse Electric Corporation Setpoint Methodology, WCAP-11239 (transmitted to NRC by letter dated April 23, 1990 "Sequoyah Nuclear Plant (SQN] - Eagle 21 Setpoint Methodology - Westinghouse Electric Corporation WCAPs 11239 and 11626"), provided values j. for both unmodified and modified Barton level transmitters to accommodate the installed steam generator level transmitters and to provide values for l the modified Barton transmitters TVA planned to install when available. l As documented in a Westinghouse Electric Corporation Letter, TVA-90-792 dated May 13, 1990, adjustments to steam generator level setpoints (adverse) for reference leg heatup were issued for unmodified Barton transmitters. TVA's letter to Westinghouse, Letter No. N8212, dated-June 27, 1990, documented the applicability of this correction to the modified Barton Model 764 steam generator transmitters, and because of the increased accuracy over Barton 764 unmodified level transmitters, supports the lower setpoints for environmental allowance modifier (EAM) and adverse steam generator lo-lo level. This installation is being performed for = Unit' 2 during the Cycle 4 refueling outage and will be implemented for l ' Unit.1 during a future outage. With the modified Barton level transmitters, the revised setpoints in this revision will meet the requirements assumed in the SQN safety analysis. The lower setpoints will also provide additional margin for steam generator lo-lo level trips, within.the safety analysis, to decrease the occurrences of challenging SQN safety systems during startup and normal operation feedwater transients.

n The steam generator lo-lo-level setpoints are changed using the Eagle 21 man machine interface (MMI) cart parameter update function for the-affected racks. Eagle 21 setpoints do not reside within the electrically programmable read only memory components that have undergone verification and validation as summarized.in the Eagle 21 Verification and Validation Final Report WCAP-12588 (transmitted to NRC by letter dated May 8, 1990, "Sequoyah Nuclear Plant (SQN] - Eagle 21 Verification and Validation - Final Report"), thus there is no impact on verified and validated Eagle 21 software. Like all Eagle 21 setpoints and tuning constants, the new setpoint is to be proven via printout from the applicable racks. Thus, this setpoint change _will have no impact on site acceptance test procedures that have been previously completed. Additionally, the ' conclusions of Safety Evaluation SECL-89-863 (transmitted to NRC by letter dated April 11, 1990, "Sequoyah Nuclear Plant (SQN] - Eagle 21 Unreviewed Safety Question (USQ]") that addresses the resistance temperature detector bypass elimination, Eagle 21 reactor protection system upgrade, new steamline break, median signal selector, environmental allowance modifier, and time trip delay modification continue to apply without change, i-}}