ML18024B050

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Evaluation of Environ Effects on Nonsafety-Related Sys Resulting from Postulated High Energy Pipe Failures Inside & Outside Primary Containment
ML18024B050
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/05/1979
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024B049 List:
References
NUDOCS 7910120148
Download: ML18024B050 (12)


Text

EVALUATION OF ENVIRONMENTAL EFFECTS ON NONSAFETY RELATED SYSTEMS RESULTING FROM POSTULATED HIGH-ENERGY PIPE FAILURES INSIDE AND OUTSIDE PRIMARY CONTAINMENT FOR BROWNS FERRY NUCLEAR PLAIT UNITS 1, 2, AND 3 OCTOBER 5, 1979

INTRODUCTION'VA has performed a systematic evaluation of the environmental effects on nonsafety-related systems resulting from postulated high-energy pipe failures inside and outside containment.

Halfunctions were then evaluated for a potential effect on safety systems.

Those systems relied upon to mitigate the consequences of a high-energy pipe break and those required to obtain and maintain the plant in a cold shutdown following. such a postulated event were examined and whgre applicable previous pipe break studies formed the basis for the evaluations in this report.

ANALYSIS METHOD In analyzing the potential effects of a high-energy line break on nonsafety-related

systems, the following general approach was used:

(1)

The location of the system was determined.

Particular attention was given as to whether or not a system had portions inside or penetrating the primary containment or inside secondary containment.

(2)

The system was examined to det'ermine if it had physical or electrical interfaces with components in a safety-related system.

(3) If the system:

(a) was.inside or penetrated primary containment; or, (b) was inside secondary containment; or, (c) interfaces with a component in a safety-related

system, then the system was examined to determine what control functions were in the zone of influence of a high-energy line break.

(4) If the system was determined to have control functions in the zone of influence of a high-energy line break, then the potential effects of a malfunction of that control function were examined, especially with regard to affectittg safety-related systems.

(5) If a malfunction was determined to have a potentially adverse effect on a safety-related

system, the environmental qualifications of the components postulated to fail were examined.

The worst case environment was assumed to exist.

ANALYSIS CONTINUED In determining if a nonsafety-related system had components within the zone of influence of a high-energy line break, specific break sizes and locations were not used.

Instead, bounding assumptions were used as a conservative approach.

A component in the zone of influence of a break was assumed to fail for analysis purposes.. If failure led to a potentially adverse effect on plant safety, the specific conditions were used to determine if the component was qualified.

Worst case conditions were assumed for qualification purposes even though a

small break or critical crack could result in an adverse malfunction that would not occur with a large break.

Although the adverse environment due to' small break or critical crack may not be as severe as that for a large break, in this study, it was assumed to be for conservative purposes.

In several

cases, nonsafety-related system components could malfunction, giving spurious annunciations and indications in the main control room.

No cases were found where these spurious signals affected safety-related equipment.

The plant operators are instructed to rely on the safety-related indications and annunciators.

We do not consider spurious indications for nonsafety systems to be a plant safety hazard.

CONCLUSION In our evaluation we found no cases where a nonsafety-related system could malfunction so as to have an adverse effect on plant safety.

The conclusions and summary of TVA's evaluation are presented in Table I which follows.

Y>> YES N ~ NO TABLE I HATRIX FOR POTENTIAL CONTROL INTERACTIONS BETWEEN SAFETY AND NON-SAFETY SYSTEHS S stem Hain Steam Extraction Steam Portions Inside Primary Portions Inside Secondary Interfaces with Safety Containment Containment Related S stem N

(Steam Tunnel)

N System Experiences Malfunction That Ma Ad ersel Comments Effects on safety system previously analyzed Outside zone of influence Reactor Feedwater Condensate N

N (Steam Tunnel)

N Results of mal-function bounded by t)e galyses of FSAR Outside zone of influence Heater Drains & Vents N

N Outside zone of influence Turbine Drains N

N Outsade zone of influence Off-Gas System Reactor Water Clean Up N

N N

Malfunction results in loss of vacuum-analyzed in FSAR...

14.5 - Outside zone quahBek isolation valves Auxiliary Boiler Lubrication Oil System Can be manually con-nected to HPCI 6 RCIC (Separated by manuaQy~

closed valves and needs spoolpicco installation Outside zone of influence Nuclear Boiler (RPV Head Vent)

Control system is qualified for adverse environment

S stem Condensate Storage Portions Inside Primary Portions Inside Secondary Interfaces with Safety System Experiences Malfunction that Containment.

Containment Related S stem Ha Adverselv Affect Plant afe v Comments Has qualified isolation from safety systems Chemical Cleaning Reactor Building Closed Cooling Water Breathing Air N

N N

N N

Y (Fuel Pool Cooling)

N N

Used preopcrational only Qualified isolation Outside zone of influence Radwaste Condenser Circulating Y

(Conaects to drywell equipment drain sump)

Y'Connects to drains and sumps)

N (RHR)

Qualified isolation

& manual normally closed valves Outside zone of influence Fuel Pool Demineralizer Condensate Demineralizer Makeup to Water Treatment N

. N N

Y N

N N

N N

N Valves & controls are outside break zone of influence Outside zone of influence Outside zoae of influence Potable Water Raw Water Yard N

N N

See RSW & Fire Prot:

See RSW & Fire Prot.

No interface with a safety system, mal-function will not affect safety related systems Outside zone of influence S stem Portions Inside Primary Portions Inside Secondary Interfaces with Safety Containment Containment Related S stem System Experiences Malfunction That V

Comments Cleanup Filter Demineralizer N

N N

Outside zone of influence Rav Water Chlorination N

N N

Outside zone of influence Fuel Oil Gland Seal Water N

N N

Y (D.G. 7-day supply)

N N

0+side zone of influence No interfaces Mith safety related equipment - malfunc-tion cannot affect safety related equipment Insulating Oil N

N N

Outside zone of refluence CO2 Storage, Fire Prot., Purging N

N N

N Outside zone of influence Raw Cooling Water N

Y (EECW)

N Qualified isolation valves and check valves separate systems - no RCW failure can affect EECW operation Compressed Air (Station Service)

Y (SLC)

Manually isolated from SLC vith locked Compressed Air for Condensate Demin.

Rackvash N

'N N

Malfunction cannot afflict safety system

- No interfaces exist S stem Portions Inside Primary Portions Inside Secondary Containment Containment uter aces t

a ety System Experiences Halfunction That Related S stem Adve se fe Connects Control Air includes Orywell Control Air Vacuum Priming Hydrogen for Cen. Cooling N

N Y

(ADS or HSIV's, but have accumulators)

Y (EECM)

N N

Loss of air is iso-lated from ADS 6 HSIV accumulators by check valves in series Isolatxon valve not affected by adverse environment Outside zone of influence Fire Protcctin and Raw Service Mater N

N N

Previously evaluated spurious spray-requires operator action within I hour due to flooding Station Drains Reactor Bldg.

Y Y

(Primary Containmcnt Isolation)

Qualified isolation valves Secondary Chem.

Feed N

N N

Outside zone of influence Demineralized Mater Distribution Y

(SLC)

N Hanual isolation valves that are normally closed Condenser Tube Cleaning N

N N

Outside zone of influence Containment Inerting HVAC Y

(Drywall HVAC)

Y N

Y (Containmcnt Isolation)

System isolated by qualified valve Qualified isolation valves for Secondary Containment Isolation

S stem Portions Inside Primary Portions Inside Secondary Containment Containment er ac s

a Related S stem System Experienkes Malfunction That Ma Adverselv Affect Plant Sefet Comments Building Heating (cxcept Control Bay HVAC)

Lighting Communications Process Sampling Safety/Relief Valves (non-ADS)

Fuel Handling Equipment N

Y (Containment Isolation)

Y (Containment Isolation)

Qualified isolation valves for Secondary Containment isolation

'lectrically isolated by qualified means from safety-related equipment Electrically isolated, by qualified means from safety related equipment Isolated by normally closed manually operated valves Qualified for adverse environment Outside xone of influence Process Radiation Monitoring (Honsafety-related portions)

Area Radiation Monitoring N

Normal A-C Auxiliary Power Y

Auxiliary D-C Power Suppression Pool Temperature Monitoring Turbine Control N N Electrically isolated by qualified means from safety-related equipment Electrically isolated by qualified means from safety-related equipment Electrically isolated by qualified means from safety-related equipment Electrically isolated by qualified means from safety-related equipment Qualified for adverse environment Failures previously analyzed in FSAR

S stem Portions Insi e Primary Port ons Insi e econ ary Containmcnt Containment nter aces w t a ety System Experiences Malfunction Ihat mments Related S stem Reactor Manual Control Does not interface with safety-related equipmcnt Neutron Monitoring (Nonsafety portions)

N Does not interface with safety-related equipment Process Computer Recirculation Plow Control System Reactor Core Isolation Cooling N

N N

Electrically isolated by qualified means from safety-related equipment Failures previously analyted in FShR Qualified isolated valves J7 S~

ll)

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