ML17339A664

Forwards Addl Documentation Requested During NRC Jan 1980 Short Term TMI-2 Lessons Learned Task Force Implementation Review.Info Re Emergency Power Supply,Direct Indication of Valve Position & Plant Shielding Review Included

ML17339A664
Person / Time
Site:	Turkey Point
Issue date:	03/10/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 L-80-79, NUDOCS 8003170268
Download: ML17339A664 (44)

Text

REGULATOR NFORMATION DISTRIBUTION S'M (RIDS)

ACCESSION NBR: 8003170268 DOC ~ DATE: 80/03/10 NOTARIZED:

NO FACIL:50 250 Turkey Point Pl anti Unj t 3i Florida Power and Light C

50 251, Turkey Point Planti Unit Qi Florida Power and Light C

AUTH'4MK AUTHOR AFFILIATION UHRIGt R,E ~

Florida Power L Light Co ~

RECIP ~ NAME RECIPIENT'" AFFILIATION SCHl'lENCKRi A ~

Operating Reactors Branch 1

DOCKET 05000250 05000251

SUBJECT:

Forwards addi documentation requested during NRC Jan 1980 Short Term Lessons Learned Task Force implementation review.

Info pe emergency power supplyqdirect indication of-valve position L plant shielding review included.

DISTRIBUTION CODE:

A039S COPIES RECEIVED:LTR J 'NCL SIZE:,W3 TITLE: Resp to Lesson Learn Task Force

~ Hestinghouse ACTIONs RECIPIENT COPIES ID CODE/NAME L'TTR ENCL 10 BC g~~~~

7 7

RKCIP IKN I'~

COPIES ID CODE/NAME LTTR ENCL'NTERNAL; 1

N PDR 21 ENG BR 23 PLANT SYS BR 25 EFLT TRT SYS NSIC 6

J KERRIGAN 8

C NILLIS N

ANDERSON OELD EXTERNAL: 26 ACRS 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

0 16 16 17 I 8

E 20 CORE PKRF BR 22 REAC SFTY BR 24 KEB 3

LPDR 5

J OLSHINSKI 7 J BUR DION FIELDS',

0'RE ILLYg P ~

TELFORDrJ AT ~

2 2

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 2

2 MAg 18 1980 TOTAL NUMBER OF COPIES REQUIRED'TTR 45 ENCL

j I

O. BOX S29100, MIAMI,F L 33152

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FLORIOA POWER 8 LIGHTCOMPANY tlarch 10, 1980 L-80-79 Office of Nuclear Reactor Regulation Attention:

i1r. A. Schwencer, ChieF Operating Reactors Branch Pl Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Nr. Schwencer:

Re:

Turkey Point Units 3

8. 4 Docket Nos.

50-250 8 50-251 Short Term Lessons Learned The purpose of this letter is to provide additional documentation requested during a Short Term Lessons Learned implementation review conducted by the NRC Staff at the Turkey Point Plant in January 1980.

The documentation is attach d and supplerIents our letter L-80-39 of January 31, 1980.

Very trul

yours, Robert E. Uhrig Vice President Advanced Systems 5 Technology REU/i~'lAS/RJA/ah Attachment cc:

J.

P. O'Reilly, Region II Harold F. Reis, Esquire y%

Bgos),vo ZQ PEOPLE... SERVING PEOPLE

ATTACHMEflT RE:

TURKEY POINT UNITS 3

& 4 Docket Nos.

50-250 5 50-251 SHORT TERM LESSONS LEARNED Additional documentation on the following NUREG-0578 sections is being sub-mitted as a result of an NRC implementation review conducted at the Turkey Point Plant site in Januarv 1980:

2.1.1

'.1.

3. a 2.1. 3.b 2.1. 4 2.1.6. a 2.1.6.b 2.1.7.b 2.1.8.b 8

c 2.1.9 2.2.1. a

2. 2.1. b 2.2.1. c 2.2.2.b Emergency Power Supply Direct Indication of Valve Position Instrumentation for Inadequate Core Cooling Containment Isolation Systems Intearity for High Radioactivitv Plant Shielding Review Auto Initiation of AFM Radiation Monitors 5 Iodine Monitoring RCS Vent Shift Suoervisor Responsiblities Shift Technical Advisor Shift Turnover Procedure On-Site Technical Su@port Center

2.1.1 EMERGENCY POllER SUPPLY Pressurizer Heaters Two similar Mestinqhouse PMR's are located at Turkey Point.

To maintain clarity the following discussion will address single unit operation.

Un-less otherwise stated, comments concerning one unit also appl.y to the second unit.

The Turkey Point Unit has three banks oF pressurizer heaters.

Control Group (400 kw), Backup Grouo A (450 kw). and Backup Group B (450 kw) have a combined capability of 1300 kw in the 1300 cubic foot oressuri zer.

During normal power operation the heaters are oowered from 480 volt load centers.

In the event of a loss of off-site power, these same load centers are fed from emergency diesel aenerators.

In the event of a loss of off-site power the three qroups of heaters are trioped.

The Control Group and Backup Grouo B receive a continous trip signal un-til power via the startup transformer is reinstated to the olant.

Un-less snecial.actions are performed, these heaters are lost to the operator until. off-site power is restored.

Backup Group A can be reins'tated after the A emergency diesel qenerator is running and the Backup Group A lockout relay in the electrical penetration room is reset.

Westinghouse Electric Corporation, Nuclear Service Division, has oer-formed a studv to determine the minimum heater caoacity necessary to maintain subcooling for the shutdown reactor and the maximum time available to restore heater operation in the event of a loss of off-site power to assure core subcoolinq.

r The results of this studv were transmitted to Florida Power 5 Liqht Co.

in a le ter dated September 26, 1979, numbered TNI-OG-83, to Mr. G.E.

Liebler from t1r.

B. L. King.

The study determined that the minimum heater capacitv for a pressurizer of our approximate size is one hundred twentyfive (125)

KM and the ability to supply emeraency pow-er to one group of heaters within four hours will prevent loss of subcooling in the primary system following a loss of off-site Dower.

Therefore, the required number of grouos of heaters for a unit is one.

In our plant, this is Backup Group A which is available for manual reinstatement from the Control Room after first resetting its lockout relay in the electrical penetration room.

2.

Procedural chanaes'ave been implemented which inform the operator when he must have Backup Group A energized and the method necessarv to accomplish energizing Backup Group A in the event of a loss of off-site power.

Emeraency load shedding is not necessarv to energize Backup Group A because the load added by:enerqizing Backup Group A on both units will be within the capability of Emergency Diesel A.

3.

Mestinghouse oredicts that subcooling would be lost within five to six hours unless the heaters are enerqized.

They recommend that heaters be available within sixtv minutes to assure subcooling.

The action necessary to restore power to Backun Group A (resetting of its lockout relay) can easi 1.v be accomplish~el within this time frame and the di rective to accomplish the reinitiation of Backup Group A heater operation within one hour is now included in the procedures.

4.

Pressurizer heater motif-Dower is supplied from a 480

.t load center.

The 480 volt load centers and the 4160 volt buses from which. they are fed are designated as Class I equipment as defined in Turkey Point's

FSAR, Sections 1.3.1 and 8.1.1.

Pressurizer heater control power is suoplied from the 125 volt station batteries via emergency D.C. buses which are designated as Class I

eauipment.

CLARIFICATION:

2.

3.

Backuo Group A i s fed from the "A" 480 volt 1 oad center whi ch i s fed from the "A" 4160 volt bus which is fed during loss of off-site power con-ditions from the "A" Emergency Diesel.

Its alternate is Backup Group B which is fed from the "D" 480 volt load center which is fed from the "B" 4160 volt bus which is fed durina loss of off-site power conditions from the "B" Emergencv, Diesel.

In the event of a fai lure of the Backup Group A heaters, procedures have been formulated giving the operator instructions how to nveride the trip signal to Backuo Group B to use the B group as an alternate.

Only one grouo of heaters is required to maintain natural circulation.

As stated

above, Backup Group A and Backup Group B each have access to seoarate emergency Dower'sources.

It is est':mated that even with the loads required for LOCA. the Emergencv Diesels h'ave adequate caoacity to also provide power to the required heaters on both units.

4.

5-6.

As stated previously. it is necessary to reset a lockout relay in the Electrical Penetration Room so that Backuo Group A will be available for operation from the console in the Control Room.

No FSF loads will be needed to be shed to load pressurizer heaters.

Reset of Safety Injection is addressed in the procedures in reaard to regaining use of pressurizer heaters.

Althouah is is not likely that the operator would overload the diesel, instrumention and criteria are outlined in the procedure.

The interfaces for main power and control power are protected by Class I circuit breakers.

7.

Pressurizer heaters are automatically shed from the emergency power sources upon the occurrence of a safety injection actuation signal.

Pressurizer Level and Relief Block Valves 2.

3.

4.

The Turkey Pnint Unit PORV '

are solenoid operated di aohram valves.

The motive component is normally supplied hy instrument air whose cnmpressors are fed from the vital side of motor contro1 centers.

The~e motor control centers will automatically be fed from emergency diesels in the event of a loss o

of<-site power.

In the event o+ a loss of off-site power con-current with safety injection the compressor's operation is blocked hut this block can be overridden locally by push button actuation.

Should instrument air be lost, a completely redundant nitrogen system suDplied from cylinders will automatically supply force to the PORV's.

The control power is supplied from the vital. D.C. b>>ses which ~re supplied

~rom statinn batteries regardless of whether nff-site power exists or not.

The motive and control components to the PORV block valves originate frnm the same source.

The so>>rce is the vital side of motor control centers which are fed from emergency diese~s in the event of a loss of off-site power.

Control power for PORV '

is fed from the emergency A.C. buses whirh are d~sinnated as Class I eauinment.

Nogive power for PORV's is supplied

+rom instrument air compressors which are connected to the vital side of motor control centers wl ich are designated as Class I equipment.

Con-trol and motive power to PORV block valves are supplied

<rom the vital side o< motor rontrol centers which are designated as Class I equipment.

The press>>rizer level indicating instrument channels

~re nowered from the vital A.C. instrument buses.

The vital A.C. instrument buses are fed from the station batteries which supply power whether off-site powe~ is avail able or not.

CLARIF ICATIOH:

2.

3.

Since the PORV.'s and PORY block valves are energized by emergencv diesels during a loss of off-site power, the design does retain the capability to open these valves.

The motive and control power for the block valves are fed from the vital side nf NCC "C" (NOV 536) and NCC "8" (NAV 535) whirh are powered hy the "A" diesel a~d "8" diesel respectively.

The PORV's control power is from the station battery as stated previously and the emotive power (instrument air compressor) is fed from the "A" diesel and "8" diesel

~especti vely

Again, if inStrument air iS 1OSt. barkun nitrOgen iS autOmatiCa1ly Supplied.

No manual changeover for either PORV's or blork valves is necessary as both emergency power supplies are the same as norm~1 power suoplies or the chanaeovers are automatic.

Instrumont air is used <or PORV operation.

The electrical supDly requirement (as discussed previouslyl is automatically connected to the emergency power sources and if instrument air supply is lost backup nitrogen is automatically supplied.

2.1.3.a DIRECT INDICATION OE VALVE POSITION Technology for Energy Corporation (TEC), supplier of Turkey Point Units 8 3 and 8 4.valve position indication, has conducted a design review of their equipment with respect to secsvni.c and envirawwrentaf qualifications.

TEC has concluded from their design review the't equipment they provided to Turkey Point can be qualifie) to meet RegulatoxyGuides 1.100 and. 1.89.

They are now proceeding to qualify their equipment by independent tests.

Testing should be completed before the end of this year.

Documention supporting seismic and environmental qualification pex'egulatory require-ments will be available by 1/1/81.

Off Normal Operating Procedure 1208.1 covers backup methods of determining valve position.

2.1.3.b INSTRUMENTATION for INADE UATE CORE COOLING By 1/1/81 FP8L will upgrade inputs to the existing subcooling monitor to provide:

a)

Redundant safety grade temperature input from each hot leg.

b>

Seismic qualification per Reg.

Guide 1.100.

c)

Environmental qualification per Peg Guide 1.89.

The above depends on material availibility and delivery schedules.

FPSL is now actively pursuing equipment to implement criteria before 1/1/81.

NOTE:

Per Oct. 30, 1979 NRC clarification letter the ENTIRE SYSTEM is. not required to be safety grade; only the inputs.

~Dis la INFORMATION REQUIRED OH THE SUBCOOLIllG NETER WV CC~

1~s~s "5gN~

(Om= uaVW C sg ma P'i, )

Information Displayed {T-Tsat, Tsat, Press, etc-.)

Oi spl ay Type (Anal og, Oi gital, CRT)

Continuous or on Oemand a CQ I< ~i 5'a..

F(as )

fr.

rr~u C.c)~INQD~~

Single or Redundant Oisplay Location of Display Alarms (include setpoints}

Overall. uncertainty

( F, PSI)

Range of Display qualifications {seismic, environmental, IEEE323)

QlMwl 5'~ D P lJO~~rnr s

OP4&~grJ 5

3+pm

~OQ>> ~Zo~

SK,tv'Y os ~r 5.r

. l Hxc, C4~~~ 1~ OOWAg 'bless Calculator Type (process

computer, dedicated digital or analog calc.)

>A'-"~==i >>=~~

C--

kf process computer is used specify availability. (" of time) k) a Single or redundant calculators Selection Logic {highe'st T., lowest press) qualifications

{seismic, environmental, IEEE323)

Calcul ationa'l Technique (Steam Tables, Functional I'4165~

~Mg u ~p~ ptas~

<M~ ~>f59 Lr~y p,gg,j~

Fit, ranges) W~-< ~em/i.vsAz,~

Temperature (RTO's or T/C's)

Temperature (number of sensors and locations)

. Range of temperature sensors

~

RY'Q

~4-l~

(A,B>c)

OOD P

Uncertainty" of temperature sensors

( F at 1

)

qualifications {seismic, environmental, IEEE323)

Pressure (specify instrument used)

Pressure (number of sensors and locations)

Range of Pressure sensors Unc rtainty~ of pressure sensors (PSl at 1

)

qualifications (seismic, environmental, IEEE323) w HZ'ax Backu Capability Availability of Tery 8 Press AvailabHity of Steam Tables etc.

Training of operators Procedures

~Uncertainties rrust address conditions of'orced flew and natural circulation

2.1.4 CONTADlMENT ISOLATION The concern regarding "ganged" valves on one switch has been

reviewed, by our Engineering Department.

They have concluded that there is sufficient separation at the switch-to maintain electrical independence between re-dundant valves and that the electrical circuits are designed consistant with the safety criteria as outlined in the Turkey Point PSAR.

2.1.6.a SYSTKIS XNTEGRXTY for HXGH RADXOACTXVXTY A new proceduxe has been written to inspect and reduce leakage to as-low-as-practical.levels from systems outside containment that would or could contain highly radioactive fluids during a serious transient ox accident.

The leak reduction program will be performed at a frequency not to exceed refueling cycle intervals.

The following systems are included in the program:

High Head Safety Xnjection.

Containment Spray.

Sampling.

Haste Gas.

CVCS; Letdown, and Yakeup.

Residual Heat Removal.

The program implementation includes step-by-step instructions to ensure the detection, measurement, xecoxding, and correction of any leakage found in the above mentioned systems.

1'urthermore, the appropiate maintenence depaxtment informs the PRO originator upon completion. of any requested work, fox reinspection of the particular system (portions and/or components worked on).

Iinal leak results of the reinspected portions,and/ox cnmpo>ento worked on are then compaired with as-found original leakage results to make sure that the leakage is reduced to as-low-as-practical levels.

Systems excluded from the leak reduction program are listed on the following 8 pages.

A brief justification is given next to the corresponding system.

Systems included in the program are marked "YES."

10GQ

, REACTOR AND REACTOR COOLANT SYSTEM 1100 1200

'1300 Reactor Coolant Pumps Pressurizer Pressurizer Relief Tank zAd.

lllslPEZD127.

Pl 50AL ~~4sIM7/DAJ zovsi LB udaea PP /os./-

1400 1500 Reactor Vessel Steam Generator including Steam Dump Ex 4D

~/lsd'!c

. - ~j ~,L, xi:srdc'I//jul Io~'City 8f 1560 Secondary Chemistry and Chemical Addition 1600 1700 Full Length Rod Control Cluster Assemblies Part Length Rod Control Cluster Assemblies Il/o7 ar:r-ec,e3 Jl/8iz-s &r(ovs vfcY~rts/u:z'- aA ACC/27mnl7 '

1800 Rod Position Indication fLecv/6/PAL.

1900 Fuel Zae=as 81 nels.

c Harass/'v rearJrrorziA6-.

2000 CHEi4lICAL AND APOLUNE CONTROL SYSTEM 2100 Charging and Letdown System 2110 Regenerative Heat Exchanger 2120 Non-regenerative Heat Exchanger fE s 2130 Volume Control Tank V <~.

2140 Charging Pump 'fE5.

2150 Deborating Demineral izer 2160 Cation Bed Demineralizer eau.- ~m uSV acreZP

~ SZI(a~

ACcl&HNT ~A ACclxrcBN..

2170 tlixed Bed Demineralizer gas.

2180 Resin Fill System Ex(~.par~< w D5g.

2190 RCP Seal )later System ggg.

2200 Hydrogen Supply System Zy.cm.-~lDr were.ere~.

2210 Nitrogen Purge and Supply System Nor aScu.

2400 2500 2600 Chemical tlix System >J~~r s~r~<<eu Heat Tracing System ~l~~ >

Boron Concentration Control System 2610 2620 2630 2640 Boric Acid Batching Tank Boric Acid Transfer Pumps Boric Acid Tanks Boric Acid Blender 'fB AD'r-AFedCrd D DalIGll& nrJ nCCtrrEd

~a MZnnlsr@=<sr.

2800 Boron'ecycle System 2810 Holdup Tank '/~5 2820 Holdup Tank Recirculation Pump 2830 Gas Stripper Feed Pumps 2840 Base and Cation Ion Exchangers d~r Afr=ee.c'c7

2850 Ion Exchanger Filters 2860 Gas Stipper Package 2870 Evaporator Package 2880 Concentrates Fi1 ters 2890 Concentrates Holding Tank 2900 Concentrates Holding Tank Transfer Pumps 2910 Evaporator Condensate Demi neral izers hlc I AFi rCr~P MZodC Ad Acc.l Vf.~f Ds~ 7Ã8dSIZA'l,

'2920 Condensate Filters 2930 tlonitor Tanks 2940 ttonitor Tank Pumps 3000 COOLING WATER SYSTEMS 3100 Component Cool ing s

3200 Residual Heat Removal VEs.

3300 Turbine Plant Cooling 3400 Intake Cooling 3500 Spent Fuel Pit Cooling 3600 Closed Canal System 4000 SAFEGVARDS

- Aler Al=rVdKMP 4100 4200 4300 Safety Injection Containment Spray Diesel Generator sior ~r=nearm 4400 4500 4600 4700 Refueling Water Storage Tank.

Accumulators XAsIad Cow

, Containment Pecircul ation Sump was>'D~ dn -,.

Emergency Filters and Coolers 5000 HASTE DISPOSAL 5100 Liquid Haste

5110 Reactor Coolant Drain Tank System-ZiJ'Sion Coi-'

5120 5130 Chemical Drain Tank System Laundry and Hot Shower Syst n/or A&CCrea mucid-iZ 8'c.cia ~r nx vZikWi~i

~

5140 5150 PZE Dlkiw'i A4 ACO'DHA i niZ fiZAAJ~JEi

~z'aste Evaporator Package Waste Holdup System Inc'luding Radioactive Sumps-5v>re is rior.

SSICR/Z Bbr,'p /acr 17M<

i-~'(1 ccUr.

5160 Waste Condensate S stem der AFFccTG). wuizi vc A sdi2iuLs Ac.c.i.ve~W ~ WiZhrdSir hfP.

'I 5300 Solid Waste 5310 Spent Resin System 5320 Solid Waste Baler 5330 Drumming Stations Including Ifandling Equipment 5500 Gaseous Waste 5510 Gas Analyzer fc~

5520 Gas Decay Tanks System Y~ ~

5530 ltaste Gas Compressor Package 6000 COI,DENSER At D AUXILIARIES 6100 Condenser

,6200 Circul ating Water System 6300 Lube Water System 6400 Intake Screens-6500 Chlorinator 6600 Air Ejectors 6700 Cathodic Protection (Intake) 6800 Cathodic Protection (Water Box) 6900 Intake Hoists 7000 COi'IDENSATE AND FEEDWATER AF'F'EMPT>

7100 Condensate Pumps 7200 Steam Generator Feed Pumps

7300 Auxiliary Feedwater Pumps 7400 Feedwater Heaters 7500 'ooter Drain Pump 7600 Condensate Recovery 8000 TURBINE GENERATOR 8100 Turbine 8110 Turbine Seals 8120 Turbine Valves 8200 8300 8400 8500 8600 8700 8800 Turbine Controls 8210 Governor 8220 Trips and Interlocks 8230 DACA Lubricating, Lift and Hydraulic Oil Turning Gear Lube Oil Purification and Storage Generator Generator Cooling (H2 and Seal Oil)

Exciter and Voltage Regulator 8900 Reheater 9000

'LECTR ICAL 9100 9200 9300 9400 9500 9550 9600 Hain Transformers Auxiliary Transformers Startup Transformer 4

KV Switchgear 480 KV Switchgear and tlCC Lighting DC System

9650 Batteries and Chargers.

9700 Instrument AC (inverter and constant voltage transformer) 9800 Communication Systems 9900 Iso Phase Bus pJcl A.CC<C7~

~g~p'/p/> Ild AH.inct.'s gg rgji/0>)En!T.

10000 VENTILATION SYSTEH 10100 Containment

~~w er~s ~uenle A seance naca.=-~i oa Mariu&ri-.

10200 Auxiliary Building Pwc-8wr v'a Pe~suize Svdrcra 10300 Control Building fvsr~v IsDLAvdD'/'cArA27iAJ/ad

~ Evi Ls.

5vsrd rw ae~IRGS tfS.c.f-

~

10600 New and Spent Fuel Areas-A!of. ~r/e2r~a I

11000 RAOIATION NONITORING AND PROTECTION

-P Aleiaa7te~u.!

11100 Process Honitoring slop A<zem~u zuP ~>a4A'~<

11200 Area Honitoring 11300 Environmental Honitoring 11400 Surveys 11500 Radiation Protection 11550 'ealth Physics Instructions 11600 Radio-Chemistry 12000 'UCLEAR INSTRUHENTATION 12100 Source 12200 Intermediate 12300 Power 12400 Incore 4or Apl=a'~-r+~>

12500 Refueling 12600 Incore Thermocouples 12700 Excore 13000 CONTAINHENT 13100 Leakage Surveillance

13200 Tendons

~13300 Isolation System

'3400 Penetrat.'ons 13410Piping 13420 Electrical 13500 Access Hatches 13510 Personnel 13520 Emergency 13530 Equipment 14000 PROCESS INSTRUt1EtiTATION 15000 MISCELLANEOUS Qa ~ AFFi c-~.27Ue'irma-wr.'mia'-

cu 7 iAn/ucn11.

Co u-,ca~ i&-O&r34ac.I

" dP /3d~g~-. X

. "aP)35J+ I 15100 15200 15300 15400 15500 15600 15700-15800 15900 Water Treatment Demineralizers Primary Water System Service Water System 15450 I'!on-Radioactive Sumps Fire Protection Systems 15510

'ire Fighting Equipment 15520 Fire Water System 15530 Smoke Detection System 15540 Transformer Deluge Systems Instrument Air Service Air Auxiliary Steam J l6 i AFeEcT'a.W.

15950

-Gonm-rnmen~E-l.eva4or 15960

-Am+7mry-Bui-4W-ag-Deva4or-

15970

-'Fu+bi-ne-GanC~Gr~e-16000 FUEL HANDLING 16100 16120 16200 16300 16400 Fuel Transfer Tube and Upending Devices Refueling Canal and Reactor Cavity t1anipul ator Crane Spent Fuel Pit Bridge Crane Hew Fuel Elevator 16500 New Fuel Bridge Crane 16600 Spent Fuel Casks 16700 Spent Fuel Cask Crane 16900 Fuel Handling Tools and Fixtures 17000 SAMPLING SYSTEM l~S-18000

-9K474LMTA-PROCES&MB-SVSTBH 20000 EMERGENCIES

-RQ NQ Emesgessy-P ~epkeaes~t4ea-

UNIT 3 LEAK REDUCTION PROGRAH RESULTS

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2.1.6.b PLANT SHIELDING REVIEW Elastomer or plastic insulation materials used in the aux'iary building on safety grade systems have a threshold for radiation damage of 106 rads or higher.

Me have concluded from our radiation assessment study that the maximum dose rates in high radiation areas at the auxiliary building would be less than one {1) percent of that found in containment during a postulated accident.

The estimated FSAR, Post-LOCA accident radiation dose for in containment equipment qualification is 108 rads.

Thus, the maximum dose in high ra-diation'areas of the, auxiliary building is 106 rads or less.

We believe all safety grade plastic or elastomer material used in the auxiliary building can be qualified to meet post-accident THX radiation levels.

He are continuing our investigation of equipment environmental quali-fication in conjuction with Bulletin 79-013 and intend to make all necessary modifications'required by. 1/1/81.

A general arrangement ground floor plan for Elevation 18'nclosed for.

information {Appendix A).

See FPL letter dated January 11, 1980 (L-80-16) to Hr. Eisenhut for a description of the zones.

2. 1.7. b AUTO INITIATION OF AFH The maximum inaccuracy of the AFM indication system is 2/.

This takes into account all variables that could affect the accuracy of the measured parameter.

2.1.8.5 &4 RADIATION MONITORS

& IODINE MONITORING 1.

NOBLE GAS EFFLUENTS a.

Sample Locations:

Plant Vent Auxiliary building, rad-waste building, units fi3 and 84 containment buildings, gas decay tanks, unit 84 spent: fuel pool, and laundry room.

All exhaust through the plant.

Uni,t 83 spent fuel pool Units II3 & fI4 'air ejectors S)owdomy, flash tagk Vest Secondary safety valves and atmospheric steam dumps b.

Monitors and',Sampling Techniques Plant Vent Sampling will be accomplished using the NMC monitor.

used for normal sampling and dilution techniques as described in procedure NC-56.'quipment necessary has been inst:alled and could be put in service in 2-3 minutes when needed.

NC-56 also includes calculationSwhich correct for the sample dilutiongonvert cpm to ci per. second release rate.

Unit Pr3 spent fuel pool-Sampling will be performed using the NMC monitor used for normal sampling.

Units II3 and kr'4 air ejectors-An NMC monitor with gas, iodine, and particulate monitors will be stored on the turbine deck.

Quick disconnects will allow the monitor to be placed in service within a few minutes on eit:her unit.

Procedure NC-71 has instructions for using the monitor.

Blowdown flash tank vent-Direct sampling of the vent is impractical.

Steam generator blowdotm water willbe sampled instead>

and using blowdown flow dat:a and NRC guidelines for partition factors, an est:imate of released isotope quantities can be made.

Procedure NV-73 has instructions.

~ Secondary safety valves and atmospheric steam dumps-Direct sampling is impractical.

Condensed main steam will be sampled,

and, along with estimated flow data, isotopic release quantities can be approximated.

4 c.

The plant vent monitor willread out in the contxol room while the other monitors will be read in-situ.

Their readings will be transferred baclc to the control room via telephone or portable radio.

d.

A procedure for the annual calibration of the RIC monitors is a-vailable and current calibration curves axe available for the plant vent and unit //3spent. fuel pit EPIC manitors.

e.

For all systems on normal AC power, backup power will be supplied by the emergency diesels.

f.

Health physics procedures and shielding materials are available for minimizing occupational exposures.

g.

Accident related information will be txansmitted to the control room.

2.

RADXODXNE AND PARTXCULATE EFFLUENTS a.

The NHC monitors described in l.b above will also collect the iodine and particulate samples.

Filters will be installed for short durations to minimize overloading them.

For the flash tank and atmospheric, steam dumps, iodine release quantities will be. determined using the blowdown and main steam liquid samples, and known or estimated flows data.

b.

Nonitor locations are listed in l.a.

c.

See l.f for methods to minimize occupational exposure.

d.

Filters will be either the silver zeolite or the activiated charcoal type and will be back~flushed with compresses air to help remove noble gases.

e.

See l.e for method to handle power interruption.

f.

Xnfoxmation will be disseminated as in l.g g.

The filters will be analyzed on a multichannel analyzer system which is calibrated annually.

2.2.1.6 SHIFT SUPERVISOR. RESPONSIBILITIES Plant procedures have been revised to incorporate wording to address concerns expressed by the NRC implementation review team during their site visit.

The concerns related to subsections 2.a and 2.b under section 2.2.l.a in the October 30, 1979 letter form Harold R. Denton to All Operating Nuclear Power Plants.

The revised procedures are available for further review at the plant site.

~l,l Item 2.2.l.b Shift Technic~~ Advisor The Shift Technical Adv'sor requirement for Turkey Point has been met in the following manner:

The responsibility to accomplish this requirement has been assigned to the plant Technical Department, which provides plant engineering support and special testing capability in support of operating and maintaining the nuclear plant.

Authorization to increase the Technical Department plant engineering staff by five engineers to a total of twelve has been approved.

This will assure that at least five engineers can be assigned to the STA position without reducing the capability to perform the normal duties of the Technical Department.

Three of the positions have been filled and active recruiting is continuing to fillthe remaining positions.

On January 1,

1980, four engineers were assigned to fulfilltha STA accident assess-ment requirement on a round-the-clock basis, with two engineers assigned as backup.

Initial training consisted of five weeks of accelerated training in nuclear physics, instrument and control, plant systems, plant response to off noxma1 conditions, and in accident and transient analysis.

Training was conducted by use of video tapes, by presentations by Technical Department and Training personnel, and by presentations by pexsonnel from oux General Office's Thermal Hydraulics and System Analysis Section, All of the initial six STAs have at least a four year degree in engineering from an accredited university or college.

The experience level xanges fxom ten years to one and a half years with various ranges of plant experience.

It is planned to fill the remaining positions with experienced, degreed engineers and train them for the STA function.

A training program has been started for a second group of STAs.

After initial training, they will be available to relieve the first group of STAs so they can be given additional training.

Further training will be provided in transient response and accident analysis, including training at an off-site "imulator.

Limited assessment of operating experience has been conducted on a routine basis by the plant Technical Department as a result of having the responsibility for the following items:

1.

Investigating abnormal occurrences, pxeparing LERs, and for assuring that adequate corrective action is taken; 2.

review of the technical aspects of all plant changes and modifications, and for coordinating plant'nputs to the engineering department responsible for design; 3.

coordinating all requests for engineering assistance and for all budget items requiring engineering assistance; 4.

assuring that initial and follow-up action is taken on all I & E Bulletins, Circulars, and Infor'mation Notices; 5.

and implementing the pump and valve testing programs required by our Inservice Inspection Program.

This assessment will be continued on an expanded basis utilizing both off shift pex-sonnel and the on shift STAs in an attempt to improve the safety oE, plant operations.

2. 2. I. c SHIFT TURNOVER PROCEDURES The practice of periodic independent verification of the effectiveness of shift turnover procedures by the Quality Control Department has been establ"shed.

V The following information is submitted to update our letter L-80-39 dated January 31, 1980:

The TSC has been equipped with conference table, chairs, desks, filing

cabinets, storage

cabinet, and supplies.

The TSC has been equipped with the following instruments for monitoring airborne and direct radiation:

20 0-500 mrem dosimeters 2 chargers for dosimeters 1 /3-a survey instrument 1 1K-14 with 210 (P-h')

and 44-6 (oC) probes 1 high volume air sampler The TSC has been stocked with the drawings, documents, and technical data listed below:

Operating Procedures Emergency Plan Technical Specifications rSAR Precautions, Limitation, and Setpoints Document Circuit Breaker List Plant Curve Book Plant Data Book Training Department Lesson Plans Training Department P

& ID's (5610-T-E series)

Valve Inde'fiscellaneous Trainiwg Information The remaining information listed in our 1/31/80 letter will be placed in the TSC as soon as practical.

Also, the in-plant paging system is being ex-tended to the TSC.