2CAN079001, Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip

Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip

ML20055E014
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/05/1990
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN079001, 2CAN79001, NUDOCS 9007100271
Download: ML20055E014 (2)

Text

. p. y. l L~ lent

~' Entergy Operauens. Inc.

Opgr g to wm ssi j me no m 7m3 July 5, 1990  !

2CAN079001 U.. S. Nuclear Regulatory Commission

Document Control Desk.  ;

Mail Station P1-137 .  !

4 Washington, DC 20555 l

Subject:

Arkansas Nuclear One - Unit 2  !

4 Docket No. 50-368 License No,' NPF-6 Further Information Related to Technical Specificas. ion  :

Change Request for Reactor Coolant System Safety Valves and Plant System Turbine Cycle Safety Valves  ;

Gentlemen:  :

On August 22, 1989, Entergy Operations submitted a Technical Specification Change Request for Reactor Coolant System Safety Valves (RCSVs) and Plant

- System Turbine Cycle Safety Valves (PSTCSVs) by letter 2CAN088903.. On February 20, 1990, the staff verbally requested that Entergy Operations submit a statement that the ANO-2 safety analyses would not be affected by  ;

the safety valves lifting at a -3% of setpoint. The Technical Specification '

Change Request (TSCR) involves allowing an '.'as-found" setpoint tolerance of  ;

I

-3%, +1% of the lif t setting of the RCSVs and PSTCSVs. However, the TSCR requires that the setting be reset to within 11%.

l l

A review has been performed of the ANO-2 analysis and determined the  ;

following:

(1) In the case of the RCSVs, the -3% tolerance in combination with the '

current High Pressurizer Pressure Trip setpoint ensures that the RCSVs will not open prior to reactor trip. Therefore, the current' safety '

analysis' assumptions with regard to system response are preserved such that there will'be no impact on the consequences of the safety analysis events that open the RCSVs.

(2). Decreasing the set pressures, and consequently the blowdown pressures, ,

of the PSTCSVs by 3% would not cause any of the results of the safety analysis events to exceed acceptance criteria. The PSTCSVs open during .

six events only. In all but one of these, there would be essentially i no. change in the consequences of the event. For one event, the Steam Generator Tube Rupture with Loss of AC Power, the offsite dose could increase by as much as 10%, but the result would remain well within-10CFR 100 limits and below the offsite doses calculated for a Loss of Coolant Accident (bounding case). The increased dose reflects the ,

< increased release of steam through the PSTCSVs associated with the +

affected steam generator-prior to its isolation. Following isolation ,

only steam from the intact steam generator is released and this steam 't  :

fy<pn- has a lower assumed concentration of radioactive material. p g >

9007100271 900705 S .4  ;

PDR: ADOCK 05000368 ( i V F PDC l a u.

W e.

f e

O. S. NRC Page 2 July 2, 1990 Entergy Operations would like to emphasize that the TSCR does not seek .

permission to operate ANO-2 at -3% of setpoint. Since we are not requesting approval tn operate at -3% of setpoint, our design basis will remain at t1% .

of setpoint and no changes to the Safety Analysis Report required. The approach of not requiring an analysis to be performed is consistent with the Staff's approval of a similar change to the Beaver Valley, Units One and Two Technical Specifications.

This has been discussed with Mr. Chester Posiusny of your staff.

.Very truly yours, w dix.en (mes J. Fisicaro Ma0ager, Licensing JJF: ,'w ,

cc: Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV i fill Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector '-

Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission  :

NRR Mail Stop 11-B-19 One White Flint North  :

11555 Rockville Pike Rockville, Maryland 20852  !

Mr. Chester Poslusny NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-B-19 One White Flint North ,

11555 Rockville Pike Rockville, Maryland 20852 l

Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72201