ML20101F002

Responds to NRC Re Violations Noted in Insp Rept 50-327/95-26 & 50-328/95-26.C/As:converted to Standardized TS for Each Unit,Clarifying Intent of Trip Setpoints Provided by TSs & Fidelity Between TSs & Plant Procedures

ML20101F002
Person / Time
Site:	Sequoyah
Issue date:	03/18/1996
From:	Adney R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9603250302
Download: ML20101F002 (2)

Text

F e

s.. .

Tennessee Valley Authority. Post Office Box 2000, Soddy-Daisy, Tennessee 37379-2000 R.J. Adney Site Vice President Sequoyah Nuclear Plant March 18,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - NRC INSPECTION REPORT NOS. 50-327, 328/95 INSTRUMENT SETPOINTS FOR ENGINEERED S AFETY FEATURE ACTUATION SYSTEM (ESFAS)

This letter is TVA's reply to Mark S. Lesser's letter to O. D. Kingsley, Jr., dated February 1,1996, which requested schedule information relative to resolution ofinstrument trip setpoints for ESFAS instrumentation channels contained in technical specifications (TSs) versus those contained in plant procedures. ,

i SQN plans to resolve the subject condition in conjunction with the conversion to a i standardized TS for each of Sequoyah's units. These standard TSs will clarify the intent of the trip setpoints provided by the TSs and provide fidelity between the TSs and plant procedures.

We currently plan to submit the standard TS conversion in approximately one year. Please ,

note that there is an ongoing effort between NRC and the Westinghouse Owner's Group to l resolve this issue as it relates to NUREG-1431 (Westinghouse standard TSs). It is anticipated that this issue will be resolved in time to support SQN's conversion to standard TSs.

I 1

l 9603250302 960318 PDR ADOCK 05000327 G PDR l

~ _ _ _

. . .a is .

U.S. Nuclear Regulatory Commission Page 2 March 18, 1996 In addition, a clarification is needed in regard to the subject condition and the safety evaluation report (SER) from NRC dated May 16,1990. Specifically, this SER provided NRC's approval of TS Change 89-27 (TAC 75843) for Unit 1 (similar approval was provided for Unit 2). TS 89-27 revised specifications to reflect reactor protection system upgrades and enhancements that were implemented during the Unit 1 Cycle 4 refueling outage. This SER explicitly  ;

approved the Westinghouse setpoint methodology (WCAP-11239, Revision 4, " Westinghouse Setpoint Methodology for Protection Systems - Sequoyah Units 1 and 2 - Eagle-21 Version.").

This methodology states that the " trip setpoint" is a " nominal" value. Based on the above information, it is not clear to TVA how NRC views the SER relative to implementation of l TS 89-27. Therefore, TVA is requesting a clarification of the application of this SER in light  ;

of the noncited violation received in the subject inspection report.

If you have any questions conceming this submittal, please telephone R. H. Shell at (423) 843-7170.

I Sincerely, 1 IO uJ /

h. J. Adney cc: Mr. D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 1

!