ML18033B099

Provides Description of Facility Phase 1 SPDS Which Will Be Functional by Restart of Unit & Provide Partial Implementation of NUREG-0737,Suppl 1,Item I.D.2.Features of SPDS Will Include color-graphic CRT Displays

ML18033B099
Person / Time
Site:	Browns Ferry
Issue date:	12/19/1989
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-0800, RTR-NUREG-1342, RTR-NUREG-737, RTR-NUREG-800, TASK-1.D.2, TASK-TM NUDOCS 9001020317
Download: ML18033B099 (10)

Text

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ACCESSION NBR:9001020317 DOC.DATE: 89/12/19 NOTARIZED: NO DOCKET N FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH. NAME AUTHOR AFFILIATION

• Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) 4

SUBJECT:

Provides description of facility Phase 1 safety parameter display sys per MJ Ray 890919 ltr.

DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR I ENCL L TITLE: .OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)

SIZE: L D

NOTES:1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw, 05000260 R.Pierson,B.Wilson S RECIPIENT COPIES RECIPIENT COPIES ID CODE/NEGATE LTTR ENCL ID CODE/NAME LTTR ENCL LA 1 1 PD .7 7 GEARSEG 1 1 INTERNAL: NRR/DLPQ/LHFB11 1 1 NUDOCS~(BS CT 1 OC/LFMB 1 0 G FIL.E 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTES: 5 5 R

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 t

5N 157B Lookout Place DEC 19%89 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-260 Tennessee Val 1ey Authori ty )

BROWNS FERRY NUCLEAR PLANT (BFN) PHASE 1 SAFETY PARAMETER DISPLAY SYSTEM (ISPDS)

Reference:

M. J. Ray to NRC letter dated September 19, 1988 "Browns Ferry Nuclear Plant (BFN) Response to Request for Additional Information Safety Parameter Display System (ISPDS)"

The purpose of this letter is to provide NRC with a description of BFN's Phase 1'afety Parameter Display System (PSPDS) which TVA will have functional by restart of Unit 2. This will provide partial implementation of NUREG-0737, Supplement 1, Item I.D.2. The PSPDS will assist operations personnel in the monitoring of plant safety status and in the mitigation of design basis accidents. The PSPDS will also aide Technical Support Center personnel in operations support and emergency response. Implementation of PSPDS does not supercede the previous TVA commitment to complete the SPDS during the first refueling outage after restart and to declare it operational during the subsequent operating cycle (Reference).

The PSPDS will provide indication under all plant conditions to operations and TSC personnel of the status of the parameters listed in Enclosure 1 via color-graphic cathode ray tube (CRT) displays. The PSPDS instrument inputs will be isolated from plant safety systems and operations personnel will be trained in PSPDS use before Unit 2 restart. The PSPDS will include a documented human factors review and verification and validation (V&V) programs, designed to satisfy the intent of Appendix A of NUREG-0800, Section 18.2 and the Nuclear Safety Analysis Center NSAC-39 document, respectively.

However, due to the controlled scope of the PSPDS, TVA anticipates that there will be some open V5V issues which will be resolved by implementation of SPDS.

The PSPDS user will be able to continuously monitor the status of the five critical s'afety functions by monitoring the entry conditions for Emergency Operating Instructions (EOIs) associated with Reactor Control, Primary Containment Control, and Radioactive Release Control. Ore exception is that PSPDS will not monitor "conditions requiring MSIV closure" (an entry condition to EOI-l), since it is expected that this entry condition will be deleted in the next major EOI revision. Additionally, this entry condition is not related to one of the five critical safety functions and therefore need not be directly monitored.

9001020317 89121'9 I An Equal OPPortunlty Employer PDR ADacg 050002g0 P PNU

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U.S. Nuclear Regulatory Commission DEC 19 988 This display format will be maintained and supplemented with additional EOI parameter information in the final SPDS. Table 3 and Section III.F.2 of NUREG-1342, Status Report Regarding Industry Implementation of Safety Parameter Display System, lists acceptable SPDS parameters for BNRs. Of those parameters listed the source range monitors, off-gas monitors, containment radiation monitor, containment isolation status and drywell oxygen concentration will not be included in the PSPDS. Each of these parameters are readily available to operations personnel on the Unit 2 control room panels and reference to each is made, as appropriate, in the EOIs. Operations personnel will have indication and will be trained in the use of all of the recommended SPDS parameters in the control room before restart of Unit 2 ~

Summary statements of commitments contained in this submittal are provided in .

Please refer any questions concerning this submittal to Patrick P. Carier, BFN Site Licensing, (205) 729-3570.

Very truly yours, TENNESSEE VALLEY AUTHORITY Manager, Nuc e Licensing and Regulatory Affairs Enclosures cc (Enclosures)

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One Hhite Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Ni lson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NN, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000

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Enclosure 1 INTERIM SAFETY PARAMETER DISPLAY SYSTEM PARAMETERS Average Power Range Monitors Reactor Water Level Drywell Temperature Reactor Pressure Vessel Pressure Drywell Pressure Torus Water Temperature Torus Water Level Drywell Hydrogen Concentration Stack Radioactivity Release Rate Torus Hydrogen Concentration Reactor Protection System Scram Signal 0347k/3

0 Enclosure 2

SUMMARY

LIST OF COMMITMENTS

l. BFN will have a functional PSPDS by restart of unit 2. The PSPDS will have the following features:

Color-graphic CRT displays in the main control room and technical support center.

Documented human factors review and verification and validation programs.

Capability to provide the status of the five critical safety functions by monitoring the entry conditions of the EOIs associated with Reactor Control, Primary Containment Control, and Radioactive Release Control.

One exception is that PSPDS will not monitor "conditions requiring MSIV closure" (an entry condition to EOI-l), since it is expected that this entry condition will be deleted in the next major EOI revision.

2. Operations personnel will be trained in the use of PSPDS before unit 2 restart.

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