ML17341A339

Notice of Issuance & Availability of Amend 62 to License DPR-41

ML17341A339
Person / Time
Site:	Turkey Point
Issue date:	07/06/1981
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17341A335	List: ML17341A334 ML17341A339
References
NUDOCS 8107210085
Download: ML17341A339 (78)

Text

7590-01 UNITED "STATES 'NUCLEAR 'REGULATORY CONIISSION DOCKET NO; '50-'251 FLORIDA'POWER AND LIGHT COMPANY NOTICE 'OF 'ISSUANCE,'.OF AtlENI}CLIENT'TO.'FACILI~TY.

PE IN 'L NSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.

62 to Facility Operating License No.

DPR-41 issued to Florida Power and Light Company (the licensee),

.which revised Technical Soecifications for operation of the Turkey Point Plant, Unit No.

4 (the facility) located i n Dade County, Florida.

The amendment is effecti ve as of the date of issuance.

The amendment extends the Unit 4 operating interval from six to eight effective full power months from January

'i3, 1981.

The application for the amendment complies with the standards and requirments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regula.ations.

Th Comnission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.

Prior public notice of this amendment was not required Since this amendment does not involve a significant hazards consideration.

8f072i0085 Bi0706

~l PDR ADOCK 0500025i l

PDR

0 7590-01 The Comnission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR

$51':5(d)(4) an environmental impact statement or negative dehlaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.

For furtherIdetails with respect to this action, see (l),the application for amendment dated i<lay 27, 1981, (2) Amendment No.

to License No. DPR-41, and (3) the Commission's related Safety Evaluation.

A'll of these items are available for public inspection at the Commission's Public Document Room 1717 H Street, N.W., Washington, D.C. and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199.

A copy of items (2) and (3):.may be obtained upon request addressed to the U.

S. Nuclear Regulatory Commission, Washington, D.C.

20555, Attention:

Director, Division of Licensing.

Dated at Bethesda, Maryland, this 6th day of July, 1981.

FOR THE NUCLEAf'REGULATORY COiSISS ION even A. gangahief, Operating Reactors Bran h

>1 Division of Licensing

V

oe,a Docket Nos. 50-250 a

0-251 Dr. Pobert E. Uhrig, Vice President Advanced Systems and Technology Florida Power arid Light Company Post Office Box 529100 Miami, Florida 33152

Dear Dr. Uhrig:

DISTRIBUTION.

Docket Fil.es

Chairman, ASLAB."

. NRC P,OR..

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Local POR ORBo 1 File D. Eisenhut.

C. Parrish

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The Commission has issued the enclosed Amendment No.

70 to Facility Operating License No.

DPR-31 and Amendment Ho.

63 to Facility Operating License Ho.

OPP,-41 for the Turkey Point Plant Unit Nos.

3 and 4, respectively.

The amendments consist oF changes to the Technical Specifications in response to your application transmitted by lettersdated December 23, 1980 and March 10, 1 981.

These amendments incorporate certain of the lessons learned Category A require-ments into the Technical Specifications.

Copies of the Safety Evaluation and the tlotice of Issuance are also enclosed.

Sincerely, Wigiaal Signed,3y:

Steven A. Varga, Chief Operating Reac ors Branch No.

1 Division of'icensing

Enclosures:

l.

Amendment No. 70 to OPR-31

2. 'mendment No.

63 to DPR 41 3.

Safety Evaluation 4.

Notice of Issuance cc w/enclosures:

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..... /.t../Bi NRC FORM 31$ n0-8QI NRCM 0340 OFFlClAL RECORD COPY,....

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gl Robert E. Uhrig Florida Power and Light Company

. cc:

Mr. Pobert-Lowenstein, Esquire Lowenstein, Newman,. Reis and Axelrad 1025 Connecticut

Avenue, N.W.

Suite 1214 Washington, D-C.

20036 Environmental and Urban Affairs Library Fl ori da Inte mat iona 1 Uni vers ig',

'Miami, ~lorida 33199 r~,

L Mr. Norman A. Coll, Esquire

Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131 Mr. Henry Yaeger, Plant Manager Turkey'oint Plant Florida Power and Light Company P.

O.

Box 013100

Miami, F 1 ori da 33101 Honorable Dewey Knight County Manager of Me.ropolitan Dade County M i ami, F 1 ori da 33130 Bureau of Intergovernmen.al Relations 6"-0 Aoalachee Parkwav Tallahassee, Florida 32304 Resid nt Inspector Turkey Point Nuclear Generating Station U. S. Nuclear Regulatory Com...ission Post Office Box 971277 quail Heights Stati,on

!liami, F 1 ori da 33197 Director, Criteria and Standards'ivision Office of Radiation Progrars (ANR 460)

U. S. Environmental Protection Agency Washington, D.

C.

20460 U. S. Environmental Protection Agency Region IV Office ATTN:

EIS COORD INATOR 345 Courtland Street, N.M.

Atlanta, Georgia 30308 Hr. Jack Shreve Office'f the Public Counsel P oom, 4,.

Ho 1 1 a nd 8ui 1 ding Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY..'

~

~1 TURKEY POINT PLANT UNIT NO.

4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

63 License No.

DPR-41 1.

The A.

B.

Nuclear Regulatory Commission (the Commission) has found that:

The application for amendment by Florida Power and Light Company (the licensee) dated December 23, 1980, supplemented on March 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity wi<h the application, the provisions of the Act, and the rules and regulations of the Commission; C.

D.

There. is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the'ommission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

V.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of.Facility Operating License No.

DPR-41 is hereby amended'.to-read.-

as follows:

(b) Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 63, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is e'ffective as of the date of its issuance.

F THE NUCL REGULATORY COMMISSION even Operating eactors ranch No.

1 Division of Licen i g

Attachment:

Changes to the Technical Specifications Date of Issuance:

JUL 6 1981=

~ g

/

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

70 TO FACILITY OPERATINC'.LICENSE N~..

OPR-31 AMENDMENT NO.

63 TO FACILITY OPERATING LICENSE NO.

DPR-41 DOCKET NOS.

50-250 AND 50-251; Revise Appendix A as follows:

3.2-4 3.3-1 3.5-1 Table 3.5-2 Table 3.5-4 Table 4.1-1 Table 4.1-1 sheet 3

4.10-1 Table 6.2-1 6.5 6.30 Insert Pa es 3.l-la 3.2-4 3.3-1 3.5-1 Table 3.5-2 Table 3.5-4 Table 3.5-5, Table 4.1-1 Table 4.1-1 sheet 3

Table 4.1-1 sheet 4

4.10-1 Table 6.2-1 6.5 6.30

d..

Presssurizer The pressurizer shal.l be operable with a steam bubble, and with at least 125 KM of pressurizer heaters capable of being supplied by emergency

power, when the reactor coolant is heated above 350F.

e.

Relief Valves 1-A power operated relief valve (PORV) and its associated block valve shall be operable when the reactor coolant is heated above 35QF.

2.

If the average coolant temperature is greasier than 350F and the conditions of 3-1.l-e-l cannot be met because one or more PORY(s) is inope. able, within 1

, hour either restore the PORV(s) to operable status or close the associated block valve(s}

and remove power from the block valve(s), otherwise, be in a condition with Keff < 0.99 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

'and in cold shutdown within the followirg 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s-3.

If the average coolant temperature is greater than 350F and the conditions of 3.1.1.e-l cannot be met because one or more block valve(s} is inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block'valve(s) to operable status or close the block valve(s) and remove power frcm the b)ock valve(s); otherwise, be in a condition wiD Keff < 0.99 within the next 6

hours and in cold shutdown within the follcwirg 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s-

3. 1-1 a Amendment Nos.

70 4E 63

't

(

)

he measurement of total peaking ractor F~~

(I )

ed b

three percent to acco nt for q manufacturing o erances and further increased b

five y

ive percent to account F

shall b

(

) ')e measoreaent of the entha1jy:rise h t h

o c annel factor, H'

increased by four,.percent to account for measurement error.

I If the measured hot channel factor exc ed t I' ce s i s imit specified under I 0.99,

~ thermal power excluding decay heat

> 0, and an average coolant temperature Tav

> 200F', the following conditions shall be met:

The containment isolation valves for Phase "ontainment isolation, Phase B cohtainment isolation, and'Containment Ventilation Isolation shall be operable with the isolation times of each power operated or automatic valve within the limits established for testing in accordance with Section XI of AStlE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),

except where specific written relief has been granted by the Com-mission pursuant to 10 CFR 50.55a(g){6){i), or the valve is closed.

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3. 3-1 Amendment Nos.

70 5 63 Jag facIg Af'A CTT E(II(<l.

3.5 INSTRUMENTATION bill:

Apl'<< <<f df instrumentation systems.

Objective:

To delineate the conditions of the instrumentation and.

safety circuits necessary to ensure reactor safety.

2.

3.

Tables 3.5-1 through 3.5-5 state the minimum instru-mentation operation.conditions.

Specification 3.0.1 applies to Tables 3.5-1 through 3.5-3.

With the number of OPERABLE accident monitoring instr~mentation channel(s) less than the Total Number of Channels shown in Table 3.5':5, either restore the inoperable channel(s) to OPERABLE status within. 7 days, or be in a condition with K

<<0.99, 5 thermal power excluding decay heat efufl to zero, and an average coolant temperature T

<350'F within.the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

avg With the number of OPERABLE accident monitoring instrumentation channels less than the NINIt1UM CHANNELS OPERABLE requirements of Table 3.5-5, either 'restore the inoperable channel(s) to OPERABLE status. within '48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in a condition with K

+ <0.99, " thermal power excluding decay heat equal to zero, and an average coolant temperature T

<350'F within,the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

avg

3. 5-1 Amendment Nos.,70

& 63 Cor<ec.4hz

64. t-Jf& (

r,

TABLE 3.5-2 ENGINEERED SAFETY FEATURES ACTUATION 1

~ 5 Hi'gh Steam Flow in 2/3 Steam L>nes with Low Ta or Low Steam Lfn4 Pressure 2.

CONTAIINM NT SPRAY 2..1 High ContainNmient Pressure and High-High Containment Pressure (Coincident) 3.

AUXILIARYFE DMATER 3.1 Low-Low Steam Generator Level 3.2 Loss of Voltage (both 4KV busses)

NO FU>FACT IONAL UN IT 1.

SAFETY INJECTION 1.1 Manual 1.2 High Containment Prwssure 1.3 High 'Differential Pressure between any Steam Line and the Steam Line Header 1.4 Pressuri zer Low Pressure~

- M!N.

OPERABLE CHANNELS 1/1 inc in.,each Qf 2 1 ines 2 per set 2

MIN.

DEGREE OF REDUNDANCY 1/set 3

OPERATOR ACTION

!F CONDITIONS OF COLUMN 1 OR 2 CANNOT BE MET Cold Shutdown Cold Shutdown Cold Shutdown Cold Shutdown Cold Shutdown Cold Siiutdown Hot Shutdown Cold Shutdown 3.-3 Safety Injection 3.4 Trip of both Main Feedwater Pump Breakers

(-See I above- )

Cold Shutdown This signal may be manually bypassed, when the reactor is shut down and pressure is below 2000 psig.

Amendment Nos.

70

& $3

1 TABLE 3.5-4 ~

~ r NO-FUNCTIONAL UNIT 1.

High Containment.Presure Z.

High-High Containment Pressure 3.

Pressur izer Low Pressure

< 30 psig t

- Safety Injection

> 1715 psig ENGINEERED SAFETY FEATURE I'ET POINTS CHANNEL ACTION SET POINT Safety Ln'gection

< 6 psig Containment. Spray*

Styam Line Isolation*

Csntai nment Isolation~

See No-l.

4.

High 5"earn Lire Diffe. ential Pressure (2/3 '~~~een any header and any line) 5.

High eami Line F':ow (2/3 lines)

Safety Injection Safety Injection Steam Line Iso'ation

< 150 psi d/p for 3.84x106 lb/hr, 770 psig, 100>>

RP d/p for 0.64xl06 1b/hr.

1005 psig, 0>>

RP d/p linear with ls stg.

press-,

0-100>>

RP'.

Coincident with:

Low Steam Line Pressure, or Lo'w Tav g Low-Low Steam Generator Level Auxi1 iary Feedwater

> 600 psig

>531F

> 15" narrow range 7.

Loss of 'loltage (both 4

KV busses) 8.

Safety Injection 9.

Trip of both Hain-Feedwater Pump Breakers Auxil i ary Feedwa ter Auxiliary Feedwater Auxiliary Feedwater N.

A.

All SI setpoints N A.

High and High-High coincident Amendment los.

70 5 63

4

'NSTRUHENT TABI k, 3 5 5 ACC I l)l:NT HON I I OR I N(i I NSlRUHEN I ATIOH TOTAL NO.

OF CINNNELS HINIHUH CHANNELS OPERABLE 1.

Pressurizer Ilater Level 2-Auxiliary Feedwater Flow Rate 2

I I

2 lier generator 1

per generator 3.

Reactor Coolant System Subcooling Hargin Honitor 4.

PORV Position Indicator (Primary Detector}

5.

PORV Block Valve Position Indicator 1/val ve 1/va1 ve 1/valve 1/val ve

'(valve 1/valve 6.

Safety Valve Position Indicator (Primary Detector)

HOTE:

Hot effective until installed.

I

('or the purpose of this Specification, the pressure and tern erature I

System Subcooling Hargin Honitor are redundant.

empera ure nputs to the Reactor Coolant Or close the associated block valve and rack t it ou

.s c>rcuit breaker.

I Amendment Nos 70

& 63

lg

TABLE 4. l-l NINIIIUIIFRE(UENCIES FOR CIIECKS CAL IORATIONS ANO TEST OF INSTRUI)EHT CIIANNELS CIIAHNEL DESCRIPTION l.a. Nuclear Power Range (Check, Calibrate and Test only applicable above lOX of rated power.)

CIIECK S(1)

I<~(4)

CALIBRATE TEST D(2)

H(3)

Q*(4) b.

Power Distribution Map P(2) 3.

Nuclear Source Range S(1)

N.A.

P(2) 4.

Reactor Coolant Temperature St 5.

Reactor, Coolant Flow S~

R B/W(1)'I'2)~

2.

Hucl ear Intermediate Range S(1)t H.A.

REISRKS i

1) Load vs. flux curve

2) Thermal power calculation

3) Signal to aT; bistable action (permissive, rod stop, trips)

4) Upper 8 lower detectors for symmetric offset

(+5 to -5$).

/

1) Following'initial loading and prior to operatiog~above 75% power.

2) Once per effective full power month.

3) Confirm hot channel factor limits.

l) Once/shift'p to 50$

R~<P.

2) Log l.evel;bistable action (permissive, rod stop, trip) 1 Once/shift when in servjce.

2 Bistable action (alarm-, 'trip)

1) Overtemperature-A'

2) Overpower-aT 6.

Pressurizer Water Level 7.

Pressurizer Pressure SI 9-Analog Rod Position St 8.

4 kv Voltage 8 Frequency H.A.

R**

Reactor protection circui ts only With step counters.

Amendment Nos.

70 5 63

fg,

TABLE 4.1-1 SiiEET 3 Channel Descri tion Ciieck Calibrate Test Remarks 23.

Environnental Radiological Honito'rs H.A.

A(1)

H{1)

{1) Flow 24.

Logic Channels 25.

Bier. Portable Survey instruments 26.

Seismograph 27'uxiliary Feedwater Flow Rate 28.

RCS Subcooling Hargin Honitor N. A.

H.A.

H.A.

H.A.

N. A-H-A.

H.A.

Hake trace.

Test battery (change semi-annually) 29.

PORV Position Indicator (Priinary Detector) 30.

PORV Dlock Valve Position Ipdicator Ht N.A H.A I

Check consists of monitoring indicated position and verifying by observation 31.

Safety Yal ve Posi tion Indicator 32.

Loss of Voltage (both 4kv busses) 33.

Trip of botii Hain Feedwater Pump Dreakers Hi H.A.

N.A.

RLf

-g.A.

N.A.

N.A.

of related parameters For AFW actuation at power only R

For AFW actuation at po~er only Amendment Nos.

70

& 63

TABLE n.i-l SliEET O

Using moveable. in-core detector system.

Frequency only'**

Effluent monitors only.

Calibration shall be as specified in 3.9.

P S

.Each Shift D

Daily W

Weekly 0/W Every Two Weeks H

Honthly quarterly p

Prior to each startup if not done previous week A

Each liefueling Shutdown A

Annually N.A.

Not appliable N.A. during cold or refueling shutdowns.

iThe speci fied surveillance interva'1 prior to startup.

N.A-during cold or refueling shutdowns.

The specified surveillance interval prior to heatup above 200F.

tests, however, shall be performed

tests, however, shal,l be.pe'rforiaed within one within one Amendment Nos.

70 I5 63

4.10 AUXILIARY FEEDWATER SYSTEM

~0b ective:

Applies to periodic testing requirements-of-the-auxiliary feedwater system.+

To verify the operability of the auxiliary feedwater system and its ability to respond properly when required.

I.

Each turbine-dri'ven au'xiliary feedwater pump shall be started at intervals not greater than one month; run for 15 minutes and a

low rate of 600 gpm established to the steam generators.

2.

The auxil iary feedwater discharge val ves shall be tested by operator action during pump tests.

3.

Steam supply and turbine pressure val'ves shall be tested during pump tests.

4.

~ These tests shall be considered satisfactory if control panel indication and visual observation of equipment demonstrate that all ccmponents have operated properly.

5.

At least once per 18 months:

a.

Verify that each automatic valve in the =low path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.

b.

Verify that each auxiliary eedwater pump receives a start signal as designed automatically upon receipt of each auxiliary eedwater ac.uation test signal.

N.A. during cold or refueling shutdowns (oaly for the Unit at cold or refueling shutdown).

The specified tests,

however, shall be performed within one surveillance interval prior to starting. the turbine.

~

4. 10>>1 Amendment Nos. 70.5 63

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITIONO,.

LICENSE CATEGORY gUALIF ICATIONS One or Two Units Operati ngA All Units Shutdown SRO*

RO 3

Non-Licensed Auxiliary Operators Shift Technical Advisor None Required This position may be filled by one of the SRO's

above, provided the individual meets the quali,ication requirements of 6.3.1 Includes the licensed Senior Reactor Operator serving as Shift Supervisor.

Does not include the licensed Senior Reactor Operator or Senior Reac.or Operator Limi ed to.Fuel Handling, supervising the movement of any component within the reactor presssure vessel with the vessel head removed and fuel in the, vessel.

Operating is defined as Keff ) 0 99 lo thermal power excluding decay heat greater than or equal to zero, and an average coolant temperature Tavg

> 200'F.

4 I

Siiifi crew ccmposiiion may be one less ihan ihe minimum requirements ior a perizd of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate ac.ion is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

Amendment Nos.

70 E

63

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e-ALL CORE ALTERATIONS shal 1

be directly supervised by either a

licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent' responsibilities during this operation.

f.

At least three (3) persons shall be maintained on site at all times for Fire Emergency response-This excludes two (2) menbers of the shift crew.

6.3 FACILITY STAFF UALIFICATIONS

6. 3.1 Each member of She facility staff shall meet or exceed the minimum qualifications of ANSI N18. 1-1971 for comparable positions.

except for the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a-scientific or engineering discipline with specific

.training in plant design and in the response and analysis of the plant for transients and accidents.

6-3. 2 HEALTH PHYSICS SUPERVISOR QUALIFICATIONS 6.3.2.1.

The Health Physics Supervisor at the time of appointment to the position, shall, except as indicated below, meet the following:

1.

He shall have a bachelor's degree er equivalent in a science or engineer ing subject, including some 'formal training in radiation protec ion.

2.

He shall have five years of professional experience in applied radiation protection; where a master'.

degree in a related field is equivalent to one year experience and a doctor's degree in a related field is equivalent to two years of exoerience.

3. Of his five years of experience, three years shall be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered at Turkey Point Plant.

6.3.2.2 6.4 When the Health Physics Supervisor does not meet the above requirements, compensatory action shall be taken which the Plant Nuclear Safety Committee determines, and the NRC 0 ice of Nuclear reactor'egulation concurs that the action meets the intent of Specification 6.3.2.1.

TRAINING 6.4.1 A retaining and replacement program for the acility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and reccmmendations of Section 5.5, ANSI N18.1-1971 and Appendix A to 10 CFR Part 55.

6-5 Amendment Nos.

70 8

63

i

~

r 6.13 'iV/IRONMENTAL UALIFICATIONS 6 13.1 By no later than June 30, 1982 all safety-related

~ ectrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of= Operating Reactors "Guidelines for Evaluating Environmental Qualification of Class

'1E Electrical Equipment in Operating Reactors" (DOR Guideline's): or, NUREG&588 "Interim Staff Position on Environmental Qualifcation of Safety-Related Electrical Equipment,"

December 1979.

Copies of these documents are attached to the Orde~ of Modification of License Nos.

DPR-31" and DPR-41 dated October 2'4, 1980.

J 6.13.2 By no later than December JP 1980, complete and auditible rec'ords

'ust be available and maintained at a central location which describe the environmental qualifica'tion methods used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588.

Thereafter, such records should be updated and maintained current as equiprqent is

replaced, further" tested'or otherwise further qualified.

6.14 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the following:

1.

Provisions establishing preventaticie

. aintenance and periodic visual inspection requirements, and 6.15 2.

Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

IODINE MiONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1.

Training of personnel 2.

Procedures for monitoring, and 6.16 3.

Provisions for maintenance of sampling and analysis equipment.

BACKUP METHODS FOR DETERMINING SUBCOOLING MARGIN The licensee shall implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.

This program shall include the following:

1.

Training of personnel, and 2.

Proc'edures for monitoring.

6-30 Amendment Nos.

70 IE 63

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UNITED STATES NUCLEAR REGULATORY COMIVltSSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIOH RELATED TO AMENDMEHT HO.

70 TO FACILITY OPERATING LICENSE NO.

DPR-31 AND AMENDMENT NO.

63 TO FACILITY OPERATING LICENSE NO.

DPR-41 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT UNIT NOS.

3 AND 4 DOCKET NOS.

50-250 AND 50-251 I.

INTRODUCTION By letters dated December 23, 1980, and supplemented on March 10, 1981, Florida Power and Light Company (the licensee) proposed changes to the Technical Specifications (TSs) appended to Facility Operating License Nos.

DPR-31 and DPR-41 for the Turkey Point Plant Unit Nos.

3 and 4.

The changes involve the incorporation of certain of the TMI-2 Lessons Learned Category "A" requirements.

The licensee's request is in direct response to the HRC staff's letter dated July 2, 3 980"-.

~ w II.

BACKGROUND INFORMATION By our letter dated September 13, 1979, we issued to all operating nuclear power plants requirements established as a result of our review of the TMI-2 accident.'ertain of these requirements, designated Lessons Learned Category "A" requirements, were to have been completed by the licensee prior to any. operation subsequent to January 1, 1980.

Our evaluation of the licensee's compliance with these Category "A" items was attached to our letter dated April 7, 1980.

In order to.provide reasonable assurance that operating reactor facilities are maintained within the limits determined acceptable following the

'mplementation of the TMI-2 Lessons Learned Category "A" items, we requested that licensees amend their TS to incorporate additional Limiting Conditions of Operation and Surveillance Requirements, as appropriate.

This request was transmitted to all licensees on July 2, 1980.

Included therein were model specifications that we had determined to be acceptable.

The licensee's application is in direct response to our request.

Each of the issues identified by the NRC staff and the licensee's response is discussed in the Evaluation below.

III.

EVALUATION 2.1.1 Emer enc Power Su 1

Re uirements The pressurizer water level indicators, pressurizer relief and block valves, and pressurizer heaters are important in a post-accident situation.

Adequate emergency power supplies add assurance of post-accident functioning of these components..

The licensee has (has prov%ed) the requisite emergency power supplies.

.The licensee has proposed adequate TSs which provide for a 31-day channel'heck and 18-month channel calibration and actions in the event of component inoperability.

We haW reviewed 'these proposed TSs and find that the emergency power supplies are reasonably ensured for post-accident functionin'g of the subject components and, are thus acceptable.

2.1.3.a Direct Indication of (of Flow Valve Position The licensee has provided a direct indication. of power-operated relief valve (PORV) and safety valve position in the control room.

Thes'e indications are a diagnostic aid for the plant operator and provide no automatic action.

The licensee has provided TSs with a 31-day channel check and an 18-month channel calibration requirement;

thus, the TSs are acceptable and they meet our July 2, 1980 model TS criteria.

2.1.3.b Instrumentation for Inade uate Core Coolin The licensee has installed an instrument system-to detect the effects of low reactor coolant level and inadequate core cooling.

These instruments, sub-cooling meters, receive and process data from existing plant instrumentation.

We previously reviewed this system in our Safety Evaluation dated April 7, 1980.

The licensee submitted TSs with a 31-day channel check and an 18-month channel calibration requirement and actions to be taken in the event of component inoperability.

We conclude the TSs are acceptable as they meet our July 2, 1980 model TS criteria.

2.1.4 Diverse Containment Isolation The licensee has modified the containment isolation system so.that diverse parameters will be sensed to ensure automatic isolation of non-essential systems under postulated accident conditions.

These parameters are safety inspection or main steam isolation.

We have reviewed this system in our Lessons Learned Category "A" Safety Evaluation dated April 7-; 1980, The modification is such that it does not result in the automatic loss of containment isolation after the containment isolation signal is reset, Reopening of containment isolation would require deliberate operator action.

2.1.7a Auto Initiation of Auxiliar Feedwater S stems The plant has provision for the automatic initiation of auxiliary (emergency) feedwater flow on loss of normal feedwater flow.

The TSs "submitted by the licensee list the appropriate components, describe the tests and provide for proper test frequency.

The TSs contain appropriate actions in the event of component inoperability; therefore; we conclude that the TSs are acceptable.

2.1.7.b Auxiliar Emer enc Feedwater Flow Indication The licensee has installed auxiliary (emergency) feedwater flow indication that meets our testability and vital power requirements.

We reviewed this system in our Safety Evaluation dated April 7, 1980.

The licensee-has proposed a

TS with 31-day channel check and 18-month channel calibration requirements.

We find this TS acceptable as it meets the criteria of our July 2, 1980 model TS criteria'.

2.2.1.b.

Shift Technical Advisor STA)

Our request indicated that the TSs related to minimum shift manning should be revised to reflect the augmentation of an STA.

The licensee's application would add one STA to each shift to perform the function of accident assessment.

The individual performing this function will have at least a bachelor' degree or equivalent in a scientific or engineering discipline with special training in plant design, and response and analysis of the plant for transients and accidents.

Part of the STA duties are r'elated to operating experience review function.

Based on our review, we find the licensee's submittal to satisfy our requirements and is acceptable.

EVALUATION TO SUPPORT ADMINISTRATIVE CONOITIONS 2.1.4 Inte rit of S stems Outside Containment Our letter dated July 2, 1980, indicated that the license should be amended by.adding a license condition related to a Systems Integrity Measurements Program.

Such a condition would require the licensee to effect an appro-priate program to eliminate or prevent the release of significant amounts of radioactivity to the environment via leakage from engineered safety systems and auxiliary systems, which are located outside reactor containment.

By letter dated March 10, 1981, the licensee agreed to adopt such an administrative condi tion; accordingly we have included this condition in the TSs.

2.1.8.c.

Iodine Monitorin Our letter dated July 2, 1980, indicated that the license should be amended by adding a condition related to iodine monitoring.

Such a condition would require the licensee to effect a program which would ensure the capability to determine the airborne iodine concentration in areas requiring personnel access under accident conditons.

By letter dated March 10, 1981, the licensee agreed to adopt such an administrative condition; accordingly, we have included this condition in the TSs.

2.1.3.b Backu Method for Determinin Subxoolin Mar i...

'Our letter of July 2, 1980, indicated that the license should be amended by adding a condition related to the determination of subcooling margin; this is a precursor to warn of inadequate core cooling in the event of an accident; Such a condition would require the training of personnel and the generation of procedures to accurately monito'r',the reactor coolant system subcooling margin.

By letter dajed March*10, ~1981, the licensee agreed.to.adopt such an administrative'ondition; accordingly, we have included this condition in the TSs.

ENYIRONMENTAL CONS I DERATION We have determined that the amendments do'o't authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.

Having made this determination,, we have further concluded that the amendments involve an action which'is insig-nificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.

CONCLUSION We have concluded, based on the considerations discussed above, that:

(1) because the amendments do not involve a sigiiif&anf increase in the proba-bility or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not, involve a

significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS.

50-250 AND 50-251 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY.

OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.

70 to Facility Operating License No.

DPR-31, and Amendment

'I No.

63 to Facility Operating License No.

DPR-41 issued to Florida Power and Light Company (the licensee),

which revised Technical Specifications for operation of Turkey Point Plant, Unit Nos.

3 and 4 (the facilities) located in Dade County, Florida.

The amendments are effective as of the date of issuance.

The amendments incorporate certain of the 1'masons learned Category A

requirements into the Technical Specifications, The application for the amendments complies with the s.andards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.

The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.

S

7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact. and that pur'suant to 10 CFR 551.5(d)(4) an environmental impact statement',or negative V

declaration and environmental impact appraisal need not b'e prepared in

'V 1

connecti'on'with issuance of these amendments.

r For further 'details with respect to this action, see (1) the appli-cation for amendments dated December 23, 1980, as supplemented March 10,

1981, (2) Amendment Nos.'0 and 63 to License'Nos.

DPR-31 and DPR-41, and (3) the Commission's related Safety Evaluation.

All of these items are available for public inspection at the Commission's Public Document

Room, 1717 H Street, N. 1l., Llashington, D.

C.

and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199.

A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, llashington, D.

C.

20555, Attention:

Director, Division of Licensing.

E Dated at 8ethesda, Maryland, this 6thday of July, 1981.

8 THE N i LEAR REGULATORY COMMISSION

arga, C 'ef Operationg Rea rs Hranch No.

1 Division of Licensing

J

\\

4 >

IIIIV / A nooo 1ost'ooe P

Dr. Robert F. Uhrig, Vice President Advanced Systems

& Technology Florida Poplar

& Light Company Post Office Box 529100 Miami, Florida 33152

Dear Dr. Uhrig:

N Ml'J I 1K LOC.a r ur, ORB l File D. Ei senhut Parrien f)

Gro+enhooi 0 OELD OI&E (5) 6.

Deeaan

{8')

B. Schar, J.

Metmore.

ACRS (10)

OPA {Clare Miles)

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Diggs NSIC TERA

Chairman, ASLAB 8~&

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VVilMlle@

The Commission has issued the enclosed Amendment Ho. 69 to Facflity Operating License No.

DPR-31 and Amendment No.

61 to Facflfty Operatfng License No.

DPR-41 for the Turkey Point Nuclear-Generatfng Unft Nos.

3 and 4.

The amend-ments, consist of changes to the licenses fn response to your submittal dated Septenber 2", 1977, as supplemented on December 20, Parch 7, April 25, June 20, and August 4, 1978, January 26, 1979, and Harch 28, 1980, and incorporate the Final Order of the Atomic Safety and Licensing Board dated June 19, 1981.

These amendments approve the steam generator repair program for the Turkey.

Point Plant Unit Hos.

3 and 4 and provfde lfcense conditions related to the repair operation.

Copies of the Safety Evaluatfon (NUREG-0756) and the Final Environmental Statement (NUREG-0743) have been sent to you on December 18, 1980 and March 30, 1981, respectively.

The Notice of Issuance fs enclosed.

Sfncerely, original Slgaed Bgt

Enclosures:

l.

Amendment No.

69 to Lfcense DPR-31 2.

Amendment No.

61 to Lfcense DPR-41 3.

Notice of Issuance Steven A. Yarga, Chief Operatfng Reactors Branch Ho.

1 Dfvfsfon of Lfcensing cc M/enclosures:

See next page E PREVIOUS CONCURRENCES SUh.

S Q DATE ORB 1

CPar rish 6/

/81

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Florida Power"L '-ight Company '=

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Mr. Robert Lowenstein, Esquire Lowenstein;- Neman, Reis 5 Axelrad 1025 Cor nec.icut Avenue, NW S

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Washington, D.C.

20036 Environmental K. Urban Affairs Library Florida International University Miami, Florida 33199 Mr. Norman A. Coll, Esquire

Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131 Florida Power E Light Company ATTN:

Mr. Henry Yaeger Plant Manager Turkey Point Plant P. 0.

Box 013100 Miami, Florida 33101 Honorable Dewey Knight County Manager of Metropolitan Dade County Miami,- Flori da 331 30 Bureau of Intergovernmental Relations 660 Apalachee Parkway Tallahassee, Florida 32304 M>>

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F irst Bui 1 di ng One Soutneast Third Avenue M<ia. i,

. d'or',da 33)31 Burt Saunders, Asst.

County Attorney Courthouse, 16th Floor Miami, Florida 33131 Henry H.

Harn<age, squire Peninsula Fe" ral Building, 10.h Floor 200 S.

E. First Street.

'<.1 ami, Fl ori< da 33131 Ms-Cheryl I.; taxman 1023'olk Street Hol1ywood, Flori da 33019 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall 82 Arlington, Virginia 20460 U.S.

Environmental Protection Agency Region IV Office ATTN:

E IS COORDINATOR 345 Courtland Street, NW Atlanta, Georgia 30308

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UMITEO STATES NUCLEAR REGULATORY COMMISSION V/ASHINGTON,D: C. 20555 FLORIDA POWER AHD LIGHT COMPANY DOCYET HO.'50-251 TURKEY POINT NUCLEAR GENERATING UHIT NO 4

AI'EHDNENT TO FACILITY OPERATING LICENSE Amendment No.

61 License Ho.

DPR-41 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power and Light Company

=

'the licensee) dated September 20, 1977, as supplemented December 20,.

Narch 7, April 25,'June 20 and August 4, 1978, January 26, 1979 arid Harch 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (ttte Act) and'ihe Commission's rules and reaulations set forth in '10 CFR Chapter "I; B.

The facility will operate in conformity with the application, the provisions of the Atomic Eneroy Act, of 1954, as amended (the Act)..-

and the Commission's rules and regulations set forth in 10 CFR Chapter I; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted wi thout endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's reoulations; D.

The issuance of. this amendment will noi. be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, Facility Operating License No.

DPR-41 is hereby amended by adding a

new paragraph 3.H as follows:

3.H Steam Generator Re air Pro ram (1)

The Turkey Point Plant steam generator repair program, as described in the licensee's "Steam Generator Repair Report" dated Sep ember 20, 1977, as supplemented

.on December 20, tlarch 7, April 25, June 20 and August 4, 1978, January 26, 1979 and Harch 28, 1980, and the affidavit of A. J.

Gould dated June 12, 1981, for Unit Ho.

4 is approved pursuant to the Atomic Safety and Licensing Board Final OrdeI..dated June 19, 1981.,

e

(

't 2)

During tt e repair w I I i LJC iIIojr'vhCd~

pr oarar

".e

"'.1 "w'.n" em"orarv 1'i cense cordi + 1 ra c'%a)

Ai i fuei snaii be removed fr=.i, ~ne reactor pressure vessel of

~

the= unit under repair-and-szoreo-in the soent fuel pool.

(c)

""e "e-'

"hysics procra-... an" procedures which have been established for the steam generator reoail program snail be implemented.

C Prooress reoorts shall be provided ai 60-day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided v.ithin 60 davs after completion of the repair.

These reports will include:

(iii)

(iv)

A summary of the occupation exposure expended to date using the format and detail of Table 3.3-2 of the "Steam Generator Repair Report" as supplamentea.

I An evaluation of the effectiveness o

dose reouction techniques as specified i.n Section 3.3.5 of the "Steam Generator Repair Report" as supplemented in reducing occupational exposures.

An estimate of radioactivity released in beth liquid and gaseous effluents.

I An estima.e of the solid radioactive vaste oenerated during the repair effor. including volume and radioactive content.

(d)

Procedures shall be prepared to assure that pov.er can be restored by manual operator actions to the fuel pool oi

.he unit under-ooing repair within eight hours (3.2.2.2).

(e)

The remedy chosen by FPL to provide the availability of the diesel fuel supply v,hile the oil-retention dike is removed

,rom the main diesel safety tank shall be addressed and adequately demonstrated by FPL prior to initiating-.the cons ruction changes affecting the dike (3.2.2.2).

(f)

Sixty days prior to fuel loading, the program or preoperational testing and startup shall be submitted for HRC reviev (2.7).

(g)

Sixty days prior to fuel loading, FPL should submit for eval-uation by the HRC a steam generator secondary water chemistry control and monitoring program (3.2.4) which vill address the foll'owing:

• References in parentheses refer to the Safety Evaluation Report (NUREG-0756)

December 1980.

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normal operativn, hot

shutdown, cola wet.wayup; Y Aos+ <4 < a+a ss

<<4 + ha ~~~co)< ~~os eesed to po7 t s ~ ~ o +he values of tne critical parameters; (iii) 1dentification of process sampling points; (iv)

Procedure for the recording and management of data; (v)

Proceaures definina corrective actions* for o> -control point, chemistry conditions; and (vi)

A procedure identifying (a) the authority responsible for the interpre.ation of the data and (b) the seouence and timing of adminis'rative events required to initia-.~

corrective action.

FPL should verify that the steam oenerator secondary water chemistry control program incorporates technical recommendations o

the NSSS vendor.

Any significant deviations from KSSS vendor recommendations should be noted and justified iechnically.

(h)

Sixty davs prior to the decontanination of the channel

head, FPL should meet the followina conditions (3.2.5):

(i)

A system should be set up so tha he pressure in the inflatable plug seal in the RCS pipe nozzles should be monitored.

Upon loss of seal

pressure, injection of the orit slurry should be stopped immediately and the

.seal plug replaced.

(ii)

. Mri ten procedures should be provided o include accoun.-

ability controls of all tools, equipmen., materials, and supplies that are to be used in the channel heads to prevent inadvertent entry of such items into the reac.or primary coolant system.

These controls should be in effect whenever the inflatable plug seals and their associated cover plates are not in pl.ace in the nozzles o

the reactor coolant system piping.

(iii) Mritten procedures should be provided to restrict materials'o be used in the channel head area to prevent the presence of materials having potential adverse effects on the reactor coolan systen conponents

( or example, chloride-bearing materials).

t *Branch Technical Position YiTEB 5-3 describes the acceptable means for monitoring secondary side water chemistry in

."-iiR steam g nerators, includino correciive actions for o

-control point chenistry conditions.

However, the sta f is amenable.to.

alternatives, particularly to Branch Technical Position B.3.b(9) o, hTiB 5-3 (.5-hour time limit to repair or 'plug coniir<<mged condenser tube leaks).

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,incluoing ine nozz]es, bewnsoected ano confirm<ed to

'be free 'of']I-loose'materials, eouipment, and tools'rior to. removing the cover. plate from the inflatable p]ug sea].

(v)

Prior to closing up the reactor coo]ant system and starting the RCS pumps, any loose debris, including the abrasive grits, in the channel

head, RCS hot leg, and cold leg should be cleaned up.

(vi)

Prior to resumption of power operation, the licensee should submit for NRC review and acceptance a report which will include an analysis of the possible e,fects of any foreign material which has entered the primary coolant system and hah not been retrieved; The'report should include all wor k on the decontamination and steam generator repair-.-

(i)

S-x v days prior to the movement of the'sed steam generator lower assembl i es from the containment, the procedures for the move, associated gA requirements, and a description of'he equipment to be used shall be provided to the NRC (3.2.6).

(J)

Before storage or shipment. of Xhe used steam generator lower assemblies, the seal welds gust be coated with a heavy bodied varnish such as glyptel (3.2.6).

(k) If credit for the unplugged configuration of the repaired steam generators is to be taken, a

new ECCS analysis using the approved model will be required (3.3.1)..

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY CO<"<MISSION

'/

I Darrell G.

isenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance:

JUN 2 4 1981

ATTAI'VMS~'Ti~Pic M~PA f/)

AMENDHEHT NO.

61 TG ~CiLiT-i OPERATTNG LICENSE NO.

OPR-41 nnrvcT NG

~0 ygl Replace the followino paoes of FaciIit'y Operating'License Ho= DPR-41 a"-c>>ed -" e- "s inCicated.

The "" "..-e" area in the 1icense is ind by a marginal line.

J I WI 4II I IIC scat'ed Remove Pa es 7

8 9

10

'm

0 V'.

Steam Generator Re air Pro ram.

(1)

The Turkey Point Plant steam generator repair program as described in the licensee s "Steam Generator Repai~

Report" dated September 20, 1977, as supplemerited on.

"=

~ December 20, March 7, April 25, June 20 and August 4, 1978, January 26, 1979 and March 28, 1980, and the affidavit of A. J.

Gould dated June 12, 1981, for Unit No.

4 is approved pursuant to the Atomic Safety and Licensing Board Final Order dated June 19, 1981-(2)

During the repair program the following temporary license conditions*

will be imposed: ':.

(a)

(b)

All fuel shall be removed from the reactor pressure vessel of the unit under repair and stored in the spent fuel pool.

The health physics program and procedures which have been established for the steam generator repair program shall be implemented.

-'c)

Progress reports shall be provided at 60-day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair.

These reports will include:

(i)

A summary of the occupation exposure expended to date using the format and detail of Table 3.3-'

of the "Steam Generator Repair Report" as supplemented.

(ii)

An evaluation of'he effectiveness of dose reduction techniques as specified in Section 3.3.5 of the "Steam

Generator Repair Report" as supplemented'in reducing occupational exposures.

(iii)

An estimate of radioactivity released in both liquid and gaseous effluents..

(iv)

An estimate of the solid radioactive waste generated during the repair effort including volume and

'adioactive content...

(d)

Procedures shall be prepared to assure that power can be restored by manual 'operator actions to the fuel po'ol of the unit under-going repair within eight hours (3.2.2.2).

(e)

The remedy chosen by FPL to provide the availability of the diesel fuel supply while the oil-retention dike is removed from the main diesel safety tank shall be addressed and adequately demonstrated by FPL prior to initiating the construction changes affecting the dike (3.2.2.2).

• References in parentheses refer to the Safety Evaluation Report (NUREG-0756)

December 1980.

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Sixty days pr"'or o ~uo~

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(g) 'Sixty days prior to fuel-loading, FPL-should-submit" for eval-uation bv the NRC a steam aenerator secondary water chemistry control and monitoring program (3.2.~> which will address the following:

(i)

Identification of a'ampling schedule for the critical parameters and of control points for these parameters for each mode of operation:

normal operation hot

startup, cold startup, hot shutdown, cold wet layup; (ii)

Identification of the procedures used to measure the values of the critical.parameters; (iii) Identification of process sampling points; (iv)

Procedure for the recorkirig and maaagement of data:

(v)

(vi)

Procedures defining corrective actions* for off-control point chemistry conditions; and A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing o'f administrative events required to initiate corrective action.

FPL should verify that the steam generator secondary water chemistry control program incorporates technical recommendations of the NSSS vendor.

Any significant deviations from NSSS vendor recommendations should be noted and justified technically.

(h)

Sixty days prior to the decontamination of the channel

head, FPL should meet the following conditions (3.2.5):

(i)

A system should be set up so that the pressure in the inflatable plug seal in the RCS pipe nozzles should be monitored.

Upon loss of seal

pressure, injection of the grit slurry should be stopped immediately and the seal plug replaced.

"Branch Technica Position MTEB 5-3 describes the acceptable means for monitoring secondary side water chemistry in PWR steam generators, including corrective actions for off-control point chemistry conditions.

However, the staff is amenable to alternatives, particularly to Branch Technical Position B.3.b(9) of HTEB 5-3 (96-hour time limit to repair or plug confirmed condenser tube leaks).

ed., ee shoiul d he r ovided +n ins-ii>des account-t '

~onttrol s o s all oui s, equi p"...ent,.~t ".'. a. s, nd S..

- a v

d L.i ad isabel 4 vV~Ay 4ev suppr rA lvJ!c L cf & lo ide Uos Ls rss svslt vitsasssss

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~ ~ v used

~ v peaven~advertent.entry of. such items ir~ v ie reac or primar~ coolant system. 'hese controls'hould be in-ef+>>t whenever the inflatable plua seals and their associaieo cover plates are not in place sn

".,e noz-les of the. reactor coolant. system piping.

(iii)

Mri.:eo procedures should be provided to res:rict materials to be used in the channel head area to prevent the presence of materials having potential adverse effects on the reactor coolant system components (for example, chloride-bearing materials).

(iv)

Written procedures should be provided to include instruc ;o-s o require that the channel head area, including the nozzles,(be inspected and confirmed to be free of all loose materials, equipment, and tools prior to removing the cover plate Srom the inflatable plug seal.

(v) 'rior to closina up the reactor coolant system and starting the RCS pumps, any loose debris, including the abrasive grits, in the channel

head, RCS hot leg,

~

and cold leg should be cleaned up'.

(vi)

Prior to resumption of power operation, the licensee should submit for NRC review and acceptance a report which will include an analysis of the possible effects of any foreign material which has entered the primary coolant system and has not been retrieved.

The report should include all work on the decontamination and steam generator repair.

Sixty days.prior to the movement of the used steam generator lower assemblies from the containment, the procedures for the move, associated gA requirements, and a description of the equipment to be used shall be provided t'o the NRC (3.2.6).

(j)

Before storage or shipment of the used steam generator lower assemblies, the seal welds must be coated with a heavy bodied varnish such as glyptol (3.2.6).

(k) 'lf credit for the unplugged configuration of the repaired steam generators is to be taken, a

new ECCS analysis using the approved model will be required (3.3.1).

t 0

4.

This license-is effective as of the date of issuance,-and sriali expire at midnioht Aor i

> 27., 2007.

p~v &t a~sactw-racrnnV-l huMTC CThlJ (vs I 4lE Alvlwats)si aQa eve s ~ osvSI ver Orioinal Signed By-.-

A. Giambusso, 0 ""+v director for Reactor Prospects Directorate of Licensing Attachments:

Appendix A Technical Specifications Appendix B - Environmental, Technical Specifications Date of Issuance:

April 10, 1973

7cQQ F1 UNITED STATES NUCLEAR:-REGULATORY. CONHISSION DOCKET NOS. 50-25"

"".J0.50-251 FLORIDA POWER AND-LIGHT CONPANY.-

~ rA&V nV I Lit GF ISSUAi CE OF A 'NGso S

TQ FACI I e

~

OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment Nos.

69 and 61 to Facility Operating License Nos.

DPR-31 and DPR-41, respectively, issued to Florida Power an'd Light Company for operation of the Turkey Point Plant Unit Nos.

3 and 4, located in Dade County,'lorida.

The amendments are effective as of the date of ifsuance.

The amendments approve the steam generator repair program for the Turkey Point Plant Unit Nos.

3 and 4 and provide licen'se conditions related to the repair operation.

The amendments comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.

The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.

Notice of Proposed Issuance of Amendments to Facility Operating Licenses in Connection with this action was published in the FEDERAL REGISTER on December 13, 1977 (42 FR 62569).

On August 3, 1979, Hr. Nark P.

Oncavage was granted status as an intervenor.

0 7590-01 On May. 28, 1981, the Atomic Safety and Licensing Board (ASL B) issued a

Memorandum and Order gran ing summary disposi ion on all con.entions and cancelling the evidentiary hearing.

On June 19, 1981 the ASLB issued its Final Order which authorized the Director of Nuclear Reactor Regulation to issue appropriate license amendments to permit the proposed steam generator repair.

The Commission has issued a Final Environmental Statement on March 30, 1981, which was noticed in the Federal Register.nn April 3,. 1981 (46 FR 20340),

and has concluded that the action will not significantly affect the quality of.he human environment.

For further details with respect to this ac'tion see (1) the Report dated September 20, 1977, as supplemented on December 20, March 7, April 25, June 20, and August 4, 1978, January 26, 1979, and March 28, 1980; (2) Amendment Hos.

P 69 and 61 to License. Hos.

DPR-31 and DPR-41; (3) the Commission's related Safety Evaluation (NUREG-0756) dated December 1980; and (4) the Commission's related Final Environmental Statement (NUREG-0743) dated March 1981.

All of these items are available for public inspection at the Commission's Public Document

Room, 1717 H Street, H. M., Washington, D.

C.

and at the Environmental E Urban Affairs Library, Florida International University, Miami, Florida 33199.

A

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~

copy of i tens (p)

(3) ar,

~4~

ay e obtained.

pon request add.

d to the U. S.

Nuc1ear Regulatory Co;"ission, Washington, D.

C.

ZO"5o, Attention:

Director, Division of Licensing.

Dated at Bethesda, Maryland this 24th day of June 1981.

FO. THE NUCLEA R

ULATORY COMMISSION I

1 ga, Chi f Operating Reactors B

Division of Licensing ch No.

1

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