ML19323F750

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Forwards Proposed Plans for Upgrading Facility Technical Support Ctr.Implementation of Improvement Should Be Completed by 810101
ML19323F750
Person / Time
Site: Browns Ferry  
Issue date: 05/22/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Ippolito T
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578 NUDOCS 8005290430
Download: ML19323F750 (7)


Text

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o TENNESSEE VALLEY AUTHORITY CH ATTA NCOG A, TENNESS EE 37401 400 Chestnut Street Tower 11 May 22, 1980 Director of Nuclear Reactor Regulation Attention:

Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Ippolito:

In the Matter of the

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 Enclosed are TVA's proposed plans for upgrading the Browns Ferry Nuclear Plant Technical Support Center (Enclosure 1).

These plans were developed using NUREG-0578 and " Discussion of Lessons Learned Short Term Require--

ments" as guides and calls for implementation of the improvements by January 1, 1981. The proposed long-range plans for improvements in the Browns Ferry TSC are also provided (Enclosure 2).

Implementation of these plans calls for significant expenditures of money and manpower, and we, therefore, request that you inform us of any comments you may have by August 1, 1980.

If we do not receive any comments from you by this date, we will assume that you concur with our plans and TVA will proceed on that basis.

Your expeditious cooperation in this matter will be greatly' appreciated.

Very truly yours, TENNESSEE VALLEY AUTHORITY

, Yi, filha & ill L. M. Mills, Manager Nuclear Regulation and Safety Enclosures 4

hDhi 8005290 Y An Ecual Occortunity Emmover

l6.**

e ENCLOSURE 1 PLAN FOR UPGRADING OF THE TECHNICAL SUPPORT CENTER BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, -260, -296)

TVA will have the following additional systems in place at the Browns Ferry Nuclear Plant by January 1, 1981:

1.

Process Computer Link A data link between the GF/ PAC 4020 and a PRIME 400 will be installed.

The PRIME computer is a powerful interactive machine with virtual memory. It is located in the unit 3 computer room at Browns Ferry.

The process computer data will be scanned, stored, and made available for color graphic display by the PRIME.

Depending on the type of data, scan rates as fast as 5 seconds will be used. Several hours of historical data for important analog points will ina available for trending. The historical and current LPRM readings and process computer calculated power distributions can be displayed. Copies of the color CRT displays can be made on the color copier in the TSC.

A scanning program on the PRIME will print process computer alarms on a printer in the TSC.

Information currently available on the process computer:

Analoc Points 1.

Neutron flux - from the average poker range monitors 2.

All local power range monitor readiz:gs 3.

Main steam line flow 4.

Main steam line temperature 5.

Pressure drop through the reactor 6.

Control rod positions 7.

Control rod drive flow 8.

Recirculation flow 9.

Recirculation flow temperature 10.

Total core flow 11.

Feedwater flow i

12.

Feedwater temperature 13.

Reactor coolant system pressure 14.

Normal range vessel water level Dioital Indications 1.

Reactor water low 2.

Initiate RCIC - low water level 3.

Low-low water level - initiate ESS l

4.

Water level at 2/3 core height 5.

Main steam line. high radiation 6.

Main steam line leak detection 7

Reactor high pressure 8.

Containment high pressure 6

1

The results of the process computer on demand programs are available also.

i Large amounts of other data are on the process computer.

It is not directly applicable to the TSC function.

2.

Radiation Release Rate Monitoring System (RRRMS)

The RRRMS computer will be linked to the Environmental Data Station's Nova 1200 computer. Meteorological data will be sent to the RRRMS computer at 15-minute and 1-hour intervals.

Thus both meteorological and radiological data will be available on the RRRMS. A CRT and a printer will be available in the ISC to monitor either radiation releases or meteorological data.

Information currently available on the Radiation Release Rate Monitoring System (RRRMS):

Readings from halogen, particulate, and noble gas monitors at the following locations are on the RRRMS.

Exhaust gas flow rates from the same locations are also monitored.

Reactor Building Turbine Building Turbine Building Roof Radwaste Building In addition, the stack flow rate and radiation in counts per second are monitored.

The following information will be available through a data link to the environmental computcr.

Wind Speed Wind Direction j

Air Temperature Vertical Temperature Differen'ce (10-40 meters)

Precipitation Rate

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r ADDITIONAL POINTS TO BE MONITORED ON THE GE/ PAC 4020 OR RRP24S IN THE BFNP TECHNICAL SUPPORT CENTER BY JANUARY 1, 1981 POINT DESCRIPTION 4020 or RRRMS COMMENTS 1.

Coolant level 4020 From the bottom of the in Reactor fuel to the top of t't.e vessel 2.

Primary system 4020 safety & relief valve positions 3.

Reactor water 4020 conductivity before domineralizers Drywell Pressure 4020 2 indications 5.

Torus water level 4020 6.

Torus water temperature 4020 7.

High range containment 4020 area radiation 8.

Torus Pressure 4020 9.

Condensate storage 4020 tank level 10.

Containment spray 4020 flow 11.

Steam flow to RCIC 4020

12. -RCIC flow 4020 13.

HPCI flow 4020 14.

LPCI flow 4020 15.

Core spray flow 4020

16. HPCI pressure 4020 Water Pressure 17.

RCIC pressure 4020 Water Pressure i

. POINT DESCRIPTION 020 or RRRMS COMMENTS 13.

LPCI pressure 4020 Water pressure 19.

Core spray pressure 4020 Water pressure 20.

SBGTS flow RRRMS 21.

SECTS WP RRRMS 22.

Reactor Sc'.lding 4020 Pressure 23.

MSL Radiation 4020 24.

Radwaste Liquid 4020 discharra radiation monitor 23.

Radiatiin levels RRRMS 5 locations i

at sitt boundary i

i I

I

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ADDITIONAL EQUIPMENT FOR BFNP TECHNICAL SUPPORT CENTER Iquipment 2un From the RRRMS Computer Equipment Run From the PRIME 400 Printer For Process Computer CRT Alarms Color CRT -

For Process Computer D

Display Or Print Radiological D

ay ac< Meteorciogical Data Color CRT -

For Process l

Computer Data Printer Display Color CRT PSSD or Process Computer Data Color Copier

ENCLOSURE 2 LONG RANGE PLANS FOR BRO W FERRY NUCLEAR PLANT TSC IMPROVEMENTS TVA has been planning to replace the CE/ PAC 4020 process computers of Browns Ferry Nuclear Plant.

Smart front end equipment will be used to interface analog and digital data to a large modern computer with more than sufficient capacity for computing needs now envisioned. The large computer will have duplicate processors to provid.e single failure, proof comouting power. Some of the new hardware should be available in late 1981 and the changeouts should start in 1983.

As the computers replacing the old process computers become availabic, the TSC functions will be moved to the upgraded process computers.

Bvoassed and Inoperable Status Indication (BISI)

The BISI will be run on the new process computer equipment before the chan;eout.

It will remain on the new process c iputer after the changeout.

Plant Safety Status Displav (PSSD)

This system is not yet well defined. TVA's tentative current plan is to define a first cut of a PSSD and run it from the PRIME until the upgraded process computer becomes available. The PRIME is not single failure proof, but the new process computer will be.

The final upgraded PSSD will be run from the new process computer.

Additional Points Additional points vill be added to the upgraded process computer for display in the TSC as time permits and as experience shows their usefulness.

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