ML19351A192

Amends 71,68 & 43 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Incorporating TMI Lessons Learned Category a Requirements Into Tech Specs,Concerning Emergency Power Supply/Inadequate Core Cooling & Valve Position Indicator

ML19351A192
Person / Time
Site:	Browns Ferry
Issue date:	06/18/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML19351A193	List: ML19351A192 ML19351A194 ML19354C476
References
TASK-***, TASK-TM NUDOCS 8106260239
Download: ML19351A192 (42)

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-V UNITED STATES g-

. NUCLEAR REGULATORY COMMISSION g

'E WASHINGTON, D. C. 20555 k**..+,/

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-33

'l.

The Nuclear Regulatoiy Comission (the Comission) has found that:

A.

The application for amendments by Tennessee Valley Authority-(the licensee), dated September 9,1980, as supplemented by letter dated -

February 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Coanission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements l.

have been satisfied.

l 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:

l l

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR'THE NUCLEAR REGULATORY COMMISSION ~

s Thomas. Ippolito,: Chief

-Operating Reactors Branch #2 Division of Licensi.ng

Attachment:

Changes:to the Technical Specifications Date of Issuance': June 18, 1981' r

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i ATTACHMEhT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

1.

Remove' the following pages and replace with identically numbered pages:

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~ 181 TEE 359 3BT 2.

The underlined pages are those being changed; marginal lines on these pages indicate the area being revised. Overleaf pages are provided-for convenience.

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Remove the following page:

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Channel' shared by FPS.. d Primary Containment & Reactor vessel Isolation control System. A channel failure may be a channel -fai3ure in each system.

7.

A train is considered a trip system.

'8.

Two out of three SGTS trains required.

A failure of more than one will require action A and F.

9.

There is only one trip system with auto transfer to two power cources.

-l10.

Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups i

and their initiating signals.

61 l

Amendment No. 71 e

l

9 TABrz 3.2.F

&arve113ance Instruwntation 1

' Mintamn 8 of f

Operable Instrument Type Indication i

Channelt Instrument l Instrument and llange Notes

{

2 H M 37 Drywell H 0.1 - 20%

(1) 2 2

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Il M 39 Concentration 2

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PdI-64-137 Drywell to Suppression Indicator

'(1) (2) G)

PdI-64-138 Chamber Differential P to 2 paid pressure i

j 1/ Valve Relief Valve Tailpipe (5)

Thermocouple Temperature j

or Acoustic Monitor on l

Relief Valve Ta11 pipe a

Amendment Nos. g, $tI, 71 i

I e

No?TS FOR TABLE 3.2.F (1) From and af ter the date that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

(2) From and after the date that one of these parameters is not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

(3) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(e) These surveillance instruments are considered to be. redundant to each other.

(5) From and af ter the date that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, continued operation is permissible during the succeeding thirty daya, unless one of the two monitoring ch'annels is sooner made operable. If both the primary and secondary indication on any SRV tail pipe is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which might be indicative of an open SRV.

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Amendment No. ff, 71 i

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2 TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRU!!SNTATION i

l Instrument Channel Calioration Frequency

. Instrument Check 17 Relief valve Tailpipe

-NA Once/ month (24)

Thermocouple Temperature 18 Acoustic Monitor on once/ cycle (25) l Relief Valve Tailpipe

-Once/ month-(26) i

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Amendment No. 71 9

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NOTES'FOR TABLES h.2.A THROUGH L.2.H 21.; Functional. tests shall be performed once-per month, s

2. - Functional-tests shall be performed before each startup with a-required frequency not to. exceed once per veek.

'3.

' This -instrumentatien is excepted from the functional test. definition.

-The functional test. vill consist of injecting a simulated electrical

. signal'into the measurement l channel.

h. ' Tested during logic. system functional tests.

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. 5.

Refer to Table 4.1.B.~.

6.

The logic system functional tests shall inclu' e a calibration once d

. per-operating cycle of time delay relays and timers necessary for proper:

functioning.of the trip systems.

c 7.. ' The' functional test will consist of verifying continunity across the 4

Linhibit.vith a volt-ohmmeter.-

8.

Instrument checks ' stall be performed in accordance with the definition

~ of Instrument Check (see Section 1.0, Definitions). An instrument

. check is not' applicable to-a particular setpoint, such as Upscale, but is a qualitative check that the instrument is behaving and/or indicating in an acceptable manner for the particular plant condition. Instrument check is included in this table for convenience and to indicate that an Instrument Check will be performed on the instrument. Instrument checks

,are-not required when these instruments are not required to be operable

~or are tripped.

9. -calibration frequency shall be ence/ year.

10.'

Tested during logic system functienal test of SGTS.

11.

Portion of the logic is functionally tested during outage only.

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' 12.

The' detector vill be inserted during each operating cycle and the proper amount of travel into the core verified.

13. Functional test vill censist of applying simulated inputs (see note 3).

r Local alarm lights representing upscale and downscale trips vill be verified, but no rod block vill be produced at this time. The inopera-tive trip will be initiated to produce a rod block (SRM and IRM inoperative also bypassed with the mode switch in RUN). The functions that cannot be verified to produce a rod block directly vill be verified during the operating cycle.

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i NOTtS FOR TABLES 4.2.A THROUCll 4.2.H (Continued) 14 Upscale trip is functionally tested during functional test time as j

required by section 4.7.B.1.a and 4.7.C.1.c.

15. The flow bias comparator will be tested by putting one flow unit t

" Test" (producing 1/2 scram) and adjusting the test input to obt.sn comparator rod block. The flow bias upscale vill be vetified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.

16. Performed during operating cycle. Fortions of the logic is checked more frequently during functional tests of the functions that produce a rod block.

17. This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.

Functional test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3.7.C.3.

19.

Functional test is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.1.c.

20.

Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flow bias signal to the APRM and RBM and scramming the reactor. This calibration can only be performed during an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

22.

One channot of either the reactor zone ur refueling zone Reactor Building Ventilation Radiation Monitoring System may be administrative 1y bypassed for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.

23.

The Reactor Cleanup System Space Temperature monitors are RTD's that feed a temperature switch in the control room. The temperature switch may be tested monthly by using a sinulated signal. The RTD itself is a highly reliable instrument and less frequent testing is necessary.

24 This instrument check consists of comparing the thermocouple readings I

for all valves for consistence and for nominal expected values (not required during refueling outages).

25.

During each refueling outage, all acoustic monitoring channels shall be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the set.sor.

l 26.

This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not l

required during refueling outages).

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110 Amendment No. 71 l

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s LIMITING CONDITIONS FOR OPERATION SURVEILI.ANCE REQUIREMENTS 3.6.C Coolant t.c a k s ef 4.6.C Coolant Leakage 3.

If the condition in 1 or 2 above csanot be met, an orderly shutdown shall be initiated and the t'eactor shall be shut-D. Relief Valves down in the Cold Condition within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.

1.

At least one safety valve and approximately one-half of all n.

Relief Valves relief volves shall be bench-checked or replaced with a

3. When more than one relief bench-checked valve each opera-valve or one or more safety ting cycle. All 13 valves (2 valves are known to be safety and 11 relief) vill have failed, an orderly shutdown

.been checked or replaced upon shall be initiated and the the cosolecion of every second reactor depressurired to 8781**

1ess than 105 peig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Once during each operating cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors dounstream of the valve indicate steam is flowing from the valve.

3.

The integrity of the relieff safety valve bellows shall be continuoasly monitored.

4.

At least one relief valve shall be disassembled and inspected each operating cycle.

E.

Jet Pumps E.

Jet Pumps 1.

Whenever the reactor is in the 1.

Whenever there is recirculation startup or run modes, all jet flow with the reactor in the pumps shall be operable. If startup or run modes with both it is determined that a jet recirculation pumps ru.ning, pump la inoperable, or if two jet pump operability shall be or more jet purap flow instrv-checked' daily by verifying that ment failures occur and aa9-the following conditions do not not be corrected witain 12 occur slaultaneously hours, an orderly shutdown shall be initiated and the a.

The two recirculatior. loops reactor shall be shutdown in have a flow imbalance of the Cold Candition within 26 15 or more when the punps hours.

are operated at the same speed.

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The indicated value of core 3 6.T Jet P a 71ov Mis.atch flow rate ve' ries f rwe the walue derived frou loop flow messarements by more than 10%.

c. The dif fuser to lo4er plenum dif f erential pressure read-tag on an todividual jet pump varies from the mesa el all ',et pump dif f eren-tisl pressures by snore than Sot.

l 2.

Sfhenever thers is recirculation flev vith the reactor in the

1. The reactor shall not be Startup er Run Mode and one re-operated with one re".ffculation "ifCdl*ti'a Pump ti operatins loop out of service for more erith the equaliser valve closed, than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor the diffuser to lower plenus operating, if one recirculation differential ytessore shall bs loop is out of service, the checked daily and she differen.

plant shall be placed in a hot tial Wressure of an individual shutdown condition within jet pump in a loop shall not 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is vary from the mean of all jet sooner returned to service, pump dif f erential pressures in that loop by more than 10.

2, ToMoving one puq epa.rstion, the discharge valve of the low F.

Jet Fums Flow Mies.steh speed pu:::p may ret be opened unless the speed of the faster Recircul,etion pump speeds shall L

pu=p is less than $(e of its be checked and logged ct least rated speed.

este per day.

3. Steady state operation with both recirculation pumps out of ser-vice for up to 12 hrs is per-

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aitted. During such interval l

restart of the recirculation l

pumps is permitted. provided the loop discharge temperature is Mithin 750F of the saturation temperature of the reactor vessel water as determined by dome pressure.

C.

Struerural Intecrity 1.

Tat le 4.6. A together with sup-C.

Structural Intecritv_

plementary noces, specifies the The s tructural integrity of 1.

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6.0 ADMt!!IrPATIVE CONTROLS 6.8 Mi $1 mum Fl an t staffina-The. mini =um plant staffing for monitoring and conduct of

' operations is as fcllows.

1 1.

A. licensed senior operator shall' be present at' the site

.I at all times when there is fuel in the reactor.

A licensed operater shall be in the SoNrol room 2.

whenever there is fuel in the reactor.,_,

3.

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A licensed senior operator shall be in direct charge of o

a reactor refueling. operation; 1.e., able to devote full' -

time to the refueling operation.

4

. A health physics technician shall be present at the

-f acility at all times there is -fuel in the reactor.

i 5.

Two li, censed operators shall be-in the 'centrol. room during any cold startups,. while shutting' down the reactor, and during recovery from unit trip.

6.

Either the. plant superintendent or the assistant plant superintendent shall have acquired the experience an(

training normally required for examination by the !GC for a senior Reactor Opera, tor's-License, whether or not

.the. examination is taken.

In addition, either the operations supervisc: or t.he, assistant operations supervisor snall have an SRG-license.

i 7.

A Shif t Technical Advisor shall be present at the site at all ti=es.

6.9 Environmental Qualification A.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines j fer Evaluating Environmental Qualification of Class IE Electrical p'

Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588

" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," Dece=ber 1979. Copies of these documents are attached to Order for Modification of License DPR-33 dated October 24, 1980.

t B.

By no later than December 1,1980, ce=plete and auditible records 1

must be available and maintained at a central location which L

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describe the environmental qualification method used for all safety-related electrical equip =ent in sufficient detail to docu-

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ment the degree of co=pliance with the DOR Guidelines or NUREG-i 0588. Thereaf ter, such records should be updated and maintained /

current as equipment is replaced, further tested, or otherwise further qualified.

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6.10 Intecrity of Svstess_outsid2 Conceinmsnt_

A program shall be implemented to reduce -leakage from systems outside that would or could contain highly radioactive fluids

. containment during a serious transient or. accident to as low as practical levels.

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This program. shill include the following:

=1); Provisions establishing preventive maintenance and.' periodic visual inspection requirements at a frequency not to exceed refueling cycle intervals. Systems subject to this program are (1) residual heat -

removal, (2) core spray, (3) reactor water cleanup,.(4) EPCI, and (5) RCIC.

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2) - System leak test require =ents, to the extent permitted by system design and radiological conditions, for each system at'a frequency in accordance with ASME code section II.~

The systems subject to this testing are (1)- residual heat removal, (2) core spray, (3) HPCI, and (4) RCIC.

6.11 Iodine Monitoring A program shall be implemented which will ensure the ca'pability to accurately determine the airhorne iodine concentration in vital areas

• under' accident conditions. This program shall include the following:

1) Training of personnel,-

2) Procedures for monitoring, and

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31-Provisions for =aintenance of sampling and analysis equipment.-

• Areas requiring personnel access forestah11shing hot shutdown condition.

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. 6.0 A7j!NISTRATIVE CONTROI,5

- Table 6.8.A

-*41nimum Shift Crew Reccirements Units in Operation Sh t te Position 1

2 1

Tvoe of I,icense

' Shift Engineers (SE)

,1 1

1

- SRO Assistant Shift Engineers (AS E) 0 1

2 SRO Licensed Reactor.Operatori 1

1

~1 RO

- Unit Operators (UC) 1 2

3 RO.

Assistant Unit Operators (AUO) 4 4

6 Kone 2

Shift Technical Advisor 1

1 1

None

!!ealth Physics Technician 1

1 1

None Minirum Shift Crew 9

11 15 Notes:

SRO - Senior Reactor Operator RO - Reacto,r Operator Nota for Table 6.8.A

- 1 Thic accision is nor:r. ally filled by an assistant shift enotneer,- but as a minimum it may be filled by a licensed r 2 actor opierator.

When the incumbent is not a senior reactor ope ra to r, he sna11 not be assigned duties requiring him to

<lirect licensed activities of reactor operaters.

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The Shift Technical Advisor shalt have a bachelor's degree or equivalent l

in a scientific or engineering discipline with specific training in plant l

design and transient and accident response and analysis.

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DIVISION OF

- POWElf PHODUCTION

• Overall Restoration Coordinator E

NUCLEAR CENERATION BRMCH i

HUCLEAR PLANTS This is a teeporary position which BRowH5 F ER A ' HUCL E AR PL ANT will only continue until all FINAL $AF E TY. N ALY511 REPOR T restoration co=itments have been completed.

TVA Cffice of Power Crganteatior for Opera:1cn of Nuclear Plants.

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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION 3

E WADilN'3 TON, D. C. 20555

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TENNESSEE VALLEY /.UTHORITY DOCKET NO.30-260 1

B,ROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR 52 1.

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

A.

The application for amendments by Tennessee Valley Authority (the licensee), dated September 9,1980, as supplemented by letter dated February 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; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activit..s 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to tne 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, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment, and L

paragraph 2.C(2) of Facility License No. DPR-52 is hereby amended to read as follows:

(2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY' COMMISSION fl g

Thomas Ippolito,~ Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

t Changes-to the Technical Specifications

- Date of. Issuance:

Jur,e 18,1981 i.

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4 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 68 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260

' Revise Appendix A as follows:

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1.

Remove the-following pages and replace with.dentically numbered pages:

fil 79/80 T697T10 '

181/ M 357/358 359/,W 2.

The underlined pages are those being changed; marginal lines on these pages indicate.the' area being revised.. 0verleaf pages are provided for

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- convenience.

3.

Add the following.new page:

105a 4.- Remove the following page:

359a r

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Channel shared by RPS and Primary Containment & Reactor Vessel Isolation Control: System.

A channel. failure may be a channel failure in each system.

7.

A train is. considered a trip system.

8.

.Two out of three SGTS trains required.

A failure of more than one will require action A and F.

9.

There is only one trip system with auto transfer to two. power sources.

i j10.- Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups i

and their initiating. signals.

4 4

61 Amendment No. 68

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TABIE 3.2.F i

j aarveillance Instrumentation,

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i Minimum # of 4

Operable Instnunent Type Indication Channels Instrument I Instnament and Range Notes i

2 ittt 94 Drywell and Torus 0.1 - 20$ '

(1) 2 ilydrogen j

ll M 104 Concentration 2

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2 PdI-64-137 Dryve11 to Suppression Indicator (1) (2) Q)

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1 1/ Valve Relief Valve Tailpipe (5)

Thermocouple Temperature i

or 4

Acoustic Monitor on i

Relief Valve Tailpipe i

l Amendment No. M. M. T. 68 1

a

NOTES FOR TABLE 3.2.F

-(1) From and afte; the date that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

(2) From and after the date that one of these parameters is not

~

indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

(3) 'If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in (6) hours, an orderly shutdown shal', be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4) These surveillance instruments are considered to be. redundant to'each other.

(5)-From and after the date that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, continued operation is permissible during the succeeding thirty days, unless one of the two monitoring channels is sooner made operable. If both the primary and secondary indication on any SRV tail pipe is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which.

might be indicative of an open SRV.

l 80.

d Amendment No. f, 68

s i

. TABLE 4. 2.F -

l MINIMUM TEST AND CALIBRATION FREQUENCY.FOR SURVEILLANCE INSTRUMENTATION' Instrument Channel Calibration Frequency Instrument Check-1 l

17 Relief valve Tailpipe NA Once/ month (24)

Thermocouple Temperature i

18 Acoustic Monitor on Once/ cycle (25)

Once/ month'(26)

I Relief Valve Tailpipe i

l i

8 I

i i

i E

I s

i e

Amendment No. 68 I

e

3

. 7, 1-U9T'r? F 11 TAELYO h.2. A THROUCH h.2.H -

.1 Fur'etimal tests chall be performed once per month.

Functional'tes'ts shall be performed before each startup with a required

' 2.

- frequency not to exceed once per week.

~

.3 This instrumentation is excepted from the functional test definition.

~ The functional test. will consist of in,jecting a. simulated electrical cignal into the rieasurement channel.

.l..~ LTested during logic system functional tests.~-

s

~

25.~ Refer to Table.h.l.B.

'6.

'"he logic systes functional tests shall include a calibration or.ec

- per operating cycle of time delay relays and timers necessary for prcper functioning of the trip systems.

- 7.

The functional test will consist of verifying continunity acrose the inhibit with a volt-ohmmeter.

8. ' Instrument' checks 'shall be performed in accordance with the definitioh of Instrument Check ~(see Section.1.0, Definitions). An instrument check is'not' applicable to a particular setpoint, such as Upscale, but is n' qualitative. check.that the instruraent is behaving and/or indicating in an acceptable manner for the particular plant condition. Instrument

~ check is included in this table for convenience and to indicate that an

~ Instrument Check will be performed on the instrument. Instrument checks are not required when these instruments are'not required to be operable or are tripped.

9.

Calibration frequency'shall be once/ year.

o.

~

~ Tested during logic' system functional test of SGTS.

10.

11.. Portion of the logic is functionally tested during outace only.

I

14. The detector vill be inserted during each operating cycle and the proper

- amount of travel into the core verified.

4

~

'13 Functional test will consist of applying simulated inputs (see note 3).

, Local alarm lights representing upscale and downscale trips will be

- verified, but no rod block vill be produced at this time. The inopera-tive trip vill be initiated to produce a rod block'(SRM and IRM inoperative i

als; bypassed with the mode switch in RUU). The functions that cannot be verified to produce a rod block directly will be verified during the operating cycle.

109 4

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'l NOTES FOR TABLES 4.2.A THROUC!I 4.2.H (Continued) 14 Upscale trip 14 functionally tested during functional test time as required by section 4.7.5.1.a and 4.7.C.1.c.

l

15. The flow bias comparator vill be tested by putting one flow unit in

" Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod block. The flow bias upscale vill be verified by observing a local upscale trip light during operation and verified that_it will produce a rod block during the operating cycle.

16. Performed during operating cycle. Portions of the logic is checked more frequently during functional tests of the functions that produce a rod block.

17. This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.. Functional test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3.7.C.3.

19.

Functional test is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.1.c.

20.

Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flow bias signal to the APRM and RBM a id scramming the reactor. This calibration can only be performed durt.ig an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

22.

One channel of either the reactor zone ur refueling zone Reactor Building Ventilation Radiation Monitoring System may be administrative 1y bypassed for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.

23.

The. Reactor Cleanup System Space Temperature monitors are R7D's that feed a temperature switch in the control room. The temperature evitch may be tested monthly by using a simulated signal. The RTD itself is a highly reliable' instrument and less frequent testing is necessary.

24.

This inetrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not l

required during refueline outages).

l 25.

During each refueling outage, all acoustic nonitoring channels shall i

be calibrated. This calibration includes verification of accelerometer I

response due to mechanical excitation in the vicinity of the sensor.

26.

This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).

i 110 Amendment No. 68 l

~

LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REQUIREMENTS 3.6.C Coolant Leakar*

4.6.C Coolant teshame 3.

If the condition in 1 or 2 above cannot be set, an orderly shutdown shall be initiated and the r'eactor shall be shut.

D. Relief Valves down in the Cold Condition within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.

1.

At least one safety valve and approximately one-half of all D.

Relief Valves relief va?ves shall be bench-checked or replaced with a 1

When more than one relief bench-checked valve each opera-valve or one or more safety ting cycle. All 13 valves (2 valves are knovo to be safety and'11 relief) vill have failed, an orderly shutdown been cheeked or replaced upon shall be initiated and the the conolettos of every second reactor depressurized to cycle.

less than 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Once during each operating cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors downstrean of the valve indicate steam is flowing from the valve.

3.

The integrity of ths relief /

safety valve bellt a sha be continuously monitsred.

4.

At least one relief valve shall be disassembled and inspected each operating cycle.

E.

Jet' Pumps Jet Pumps 1.

Whenever the reactor is in the 1.

Whenever there is recireviation startup or run modes, all jet flow with the reactor in the pumps shall be operable. If startup or run modes with both it is determined that a jet recirculation punps ru.ning, pump ta inoperable, or if ;vo jet pump operability shall be or more jet ovmp flow instrv-checked' daily by verifying that ment failures occur end can-the following conditicas do not not be corrected within 12 occur simultaneously:

hours, an orderly shutdown shall be initiated and the a.

The two recirculation loeps reactor shall be shutdown in have a flow it. balance of the Cold Condition within 26 15" or nere when the ;usps t.ou r s.

are operated at the same speed.

181 AmendmentNo.}6,k,68

[

l.1 M i T If., ej'#8f* l I i 88% Pon oPtRATIcas Sun W t II.t.,n'ec t a vi}ule.g r.HT 8.6.E l,g,t,,h',,f *,

4.6.2 Jet Piemr e 3 6.T Jt t lary T3ec Mice.atch b.

The indicated value uf care flow rate varies fro, the valae derived f rni loop flow tireturaments by, corn than 101.

c.

The dif fuser to lower pl.nws dif f erential pre saur' re..d-ing c,n an individuta jet pump varies f rite tha sicate of all jet purs; dif ferce.-

tial pressures by c, ore char.

10Z.

2.

Whenever there is recirculation flow with the reactor in the 1.

The reactor shall not ba.

Startup or Run Mode and ene e.

operated with one retirculation cited 1= tion giunp is opera:!nt loop out 'of service for more with the equaliser velve c3r,ed.

than 2!4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. With the reactor the dif fusar to 1crese plenu-operating, if one recirculation differential press. ire shall 3 loop is out of servies, the checked.f.117 and the dif f er:n-tial pressure of an indivicu,1 plant shall be pisced in a hot shutdo o conditix. within jet pusp in a loep shall not

TY ff'" th' *can of all jet 2ls hours unless the loop is pump a1fferential pressures in

-sooner returned to service.

that loop by este than IG%.

2.

Tol.loung one pucp operation, F.

Jet "un r1% h e the discharge valve of.the low speed psep n:ay not be opened 1.

Retirculation pump speeds ahtil unicas the speed of the faster d 1 sg d at lease pus:p is less thaa 80f.ofits da rated cpeed.

3.

Steady state operation with both recirculation pur:ps out of ser-vice for up to 12 hrs is per-mitted. Durihg such interval restart of the recirculation purnos is permitted, provided the loop discharge typerature is within 75 F of the saturation 0

temperature of the reactor vessel water as determined by doine pressure. The total elapsed time in natural circula-tion and one pump creration must C.

Structurat Inte,rtty be no greater than 24 hrs.

C.

S t riietural I nt. trity

~

1.

Table 4.6.A together vich sun-1.

1he 6ttucturut inter.rity of the primary system shall be Piezenta ry not es. specifies the 162 Amendment No. 54

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6.0 ADMINISTDAT IVE COUTROLS FOOTNOTES 1.

A single submittal may be made for a multiple unit station.

- The submittal should combine those sections that are common to all units at the statien.

2.

The term aforced reduction in power is normally defined in a

the electric power industry as the occurrence of a component f ailure or other condition which requires that the load on the unit he reduced for corrective action immediately or up to -and -including the very next weekend.

Note that routine preventive. maintenance, surveillance, and calibration activities requiring power reductions are not covered by this section.

3.

The term aforced outage" is nermally defined in the electric

~

power industry as the occurrenre of a component failure or other condition which requires that the unit be removed from service f or corrective action immediately or up to and including the very next weekend.

4 This tabulatien supplements the requirements of $ 20.407 of 10 CFR Part 20.

.5.

Each integrated. leak rate test of the secondary containment shall be the subject of a summary technical report.

This report ~ should include data on the wind speed, wind direction, outside and inside temperatures during.the test, concurrent reactor building pressure, and emergency ventilation ficw rate.

The report shall also include analyses and interpretations of those data which demcastrate compliance with the-specified leak rate limits.

L 4

l f-1 i

357 l

l l-1

=..

6.0 bbMti!IT PATIVE CONTPOL3 6.8 Minimum Plant Staffine The minimum plant staffing for monitoring and conduct of operations is as follows.

1.

A -licensed senior operator shall' be present.at the site at all times when there is fuel in the reactor.

2.

A licensed operator shall be in the. control room whenever there is fuel in the reactor.

3.

A licensed _ senior operator shall' he in. direct charge, cf.

a reactor refueling operation; i.e., able to devote full time to the refueling operation..

I 4.

A health physics technician shall be present at the facility at all times there'is fuel in the reactor.

5.

Two licensed ' operators.shall-be in the control room-during any cold startups, while shutting dcwn the reactor, and. during recovery from unit trip.

6.

Either the plant superintendent or the assistant plant superintendent sna11 have acquired the experience and training normally required for ~ examination by the bAC for a Senior Reactor Operator's License, whether or not the examination is taken.

In addition, either the operations supervisor or the assistant operations supervisor snall' have an SRO license.

7.

A Shif t Tachsical Advisor shall be present at the site at all j

ti=es.

I i

6.9 Environmental Qualification l

l A.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of C1sss IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588

" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to Order for Modification of License DPR-52 l

dated October 24, 1980.

l l

R.

By no later than December 1, 1980, co=plete and auditible records j'

must be available and maintained at a central location which l

describe the environmental qualification method used for all l

safety-related electrical equipment in sufficient detail to docu-l ment the degree of compliance with the DOR Guidelines or NUREG-l 0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise l

furd w qualified.

-9ekr datcd Oc tc kr 22, ' 030 l

Amendment No. 68 i.-.,~._.___-_..._..__...___.__._.__._._____,..._.___.._._____

a6.10 Jytoerity of systees outsid, contniem~nt A program shall be inplenented to reduce leakage from systems outside

. containment' that would or could co.ntain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program 'shk11 include the following:

Provisions establishing preventive maintenance and ~ periodic visual '

~

1) inspection requirenents at a frequency not to exceed refueling cycle intervals.

Systems subject to this program are (1) residual heat removal,- (2) core spray, (3) reactor water cleanup, (4) EPCI, and (5).RCIC.

~

2) -System leak test requirements, to the extent permitted by system -

design and radiological conditions, for each system at a frequency in accordance with ASNZ code section T.I.

The systems subject to this testing are (1) residual heat removal, (2) core spray, (3) HPCI, and (4) RCIC.

6.11 Iodine Penitoring A program shall be imple=ented which will ensure the ca'pability to accurately deter =ine the airborne iodine concentration in vital areas

• under accident conditions.

This program shall include the following:

1) Training of perse'nnel,

2) Procedures for monitoring, and 31 Provisions for maintenance of s'ampling and analysis equipment.

• Areas requiring personnel access fo!~ establishing hot _ shutdown condition.

J r

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Amendment No. 68 359 l

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, l 6.0.

Aptt!sIfiTRATIVE CONTROLS

-~

l, Table 6.8.A

• 41nimum.<hi f t Crew Recuirements -

Units in Operation

, f:

Shirt Position 1.

2 i

TYDe of License Shif t. Engineers (SE) 1 1

- -- 1 SRO Assistant Shift Eng'ineers,'

,4 (AS E) 0 1

2 SRO' Licensed Reactor Operatort 1

1 1

RO Unit O'perators (U0) 1 2

3.'

RC 4

Assistant Unit Operators (AUQ).

4 4

6 None Shift Technical Advisor 1

l' 1

be2

!!ealth Physics Technician 1

~1 1

None Minimum Shift crew 9

11 13 Notes:

SRO - Sen3 9r Reactor Ope *rator Ro - Reacter operator Note f or Table 6. 8.A 1.

Thte no:itien is normally filled by an assistant shift

.enctneer, but as a minimum it may be filled by a licensed reactor operator.

When the incumbent is not a senior reactor operator, he shall not be assigned duties requiri.ng him to direct licensed activities of reactor operatcrs.

.1-2.

Ths Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline vitli' specific training in plant derian and transient and accident rergonse and analysis.

E 4

f

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360

- - - - - - - ~ ~ -

Amendment,No. '68 J

~... _. _. _. _. _... -. _ _ _ _ _ _ _.,... _. _ _ _ _ _. -. _ _ _ _

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k UNITED STATES

-f, NUCLEAR REGULATORY COMMISSION o-I y

wAsHWGTON, D. C. 20656 TENNESSEE. VALLEY AUTHORITY DOCKET NO. 50-296 s.

BROWNS FERRY NUCL' EAR PLANT, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No.: DPR-68:

1.. The_ Nuclear Regulatcry Comission '(the Comission)' has found that:'

A..The application for amendments by Tennessee Valley Authority (::he licensee), dated September 9,1980, ~as supplemented by letter dated February 10, 1981, complies with the standards and requirements of the Atomic Energy Act of _1954, as_ amended (the Act), and the Comission's rules and regulations set forth in,10 CFR Chapter ~ I; B. - The-facility wi11 operate in conformity with the application, the provisions of. the.*ct, and the rules and regulations of the

' Comission; C.

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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon

. 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 Comission's regulations and all applicable requirements have been satisfied.

2. - Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph -2.C(2) of Facility License No. DPR-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. O, are hereby incorporated in the L

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

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13. -This license amendmen't is effective 'as of the date'of its issuance.

FORTHENUCLEARREGULATORICOMMISSION A

& v gJA-Thomas A. Inpolito, Chief-Operating Reactors Branch #2 Divis-ion of Licensing _

Attachment:

Changes to the Technical ~

Specifications ;

Date of Issuance: June 18, 1981 l

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 43 FACILITY Ol'ERATI;Mi LICENSE NO. DPR-68

~ DOCKET NO. 50-296

,. Revise Appendix-A as follows:-

7 1.

Remove the following pages ind. replace with ider.tically number d pages:

63-82 -

83' 107 192-

-388 389-

- 390 2.

Marginal lines on the above pages indicate revised area.

3. -Add the following new page:

-102a-4.

Remove the following page:

389a b

f e

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3.

There are four channels per steam line of which two must'be operable.

Only' required in Run Mode (interlocked with Mode Switch).

4

5.. Not required in Run Mode (bypassed by mode switch).

6.

Channel shared.by RPS and Primary Containment 5 Reactor

- Vessel Isolation Control System. A channel failure may be,a channel failure 'in each system.

7.. A train is considered a trip' system.

8. _ Two out. of three SGTS trains required. - A failure of more than one will require action A and F.

There 'is only one trip system with auto transfer to two power 9..

sources.

.10.

Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups and their initiating. signals.

63 Amendment No. 43 e

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l TABIE 3 2.F

' 32rve111ance Instrumentation i

Minimun 0 of Operable Instrument Type Indication Channels Instnarr.ent #

Instnament

~

and Range-

-Notes.

2 H H 94 Drywell' and Torus

0,1 _ 20%

(1) 2 ilydrogen H H 104 Ccncentration 2

}

1 4

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4

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f 2

PdI-64-137 Drywell to Suppression-Indicator.

(1) (2). (3)

PdI-64-138 Cbcaber Differential O to 2 paid pressure i

j 1/ Valve Relfef. Valve' Tailpipe

. (5).

~

Thermocouple. Temperature or Acoustic Monitor on j

Relief Valve Tailpipe 1

i i

Amendment No. }(, Jg SI 43

e NOTES FOR TABLE 3.2.F (1) From and af ter the date that one of these parameters is -

reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

(2) From and after the date that one of these parameters is not indicated in the control room, centinued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

(3) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in (6) hours, an orderly shutdown shall be initiated and the reactor shell be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4) These surveillance instruments are considered to be redundant to each other.

(5) From and af ter the date that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, continued operation is permissible during the succeeding thirty days, unless one of the two monitoring channels is sooner made available. If both the primary and secondary indication on any SRV tailpipe is inoperable, the torus temperature will be moni-tored at least once per shif t to observe any unexplafned temperature increase which might be indicative of an open SRV.

l l

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83 Amendment No. K, 43

~.

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i TABLE 4.2.Fr MIllIMUM TEST AND CALIBRATION FREQUEllCY FOR SURVEILLANCE INSTRUMENTATION fo I

f Instrument Channel Calibration Frequency'

- Instrument Check D

17 Relief valve Tailpipe NA '

Once/ month.(24)'-

Thermocouple Temperature

~

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18 Acoustic Monitor on

-Once/ cycle-(25)

Once/ month'(26).

i Relief Valve Tailpipe

?

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4 1

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NOTES FoR TABLES 4.2.A THROUCll 4.2.H (Continued)

14. Upscale trip 1+ functionally tested during functional test time as required by section 4.7.5.1.s and 4.7.C.l.c.

15. The flow bias comparator will be tested.by putting one flow unit in

" Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod block. The flow bias upscale vill be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.

16. Performed during operating cycle. Portions of the logic is checked more frequently during functional tests of the functions that produce

.a rod block.

17..-This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18..Tunctional test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3.7.C.3.

19.

Functional tent is limited to the time where the SCTS is required to meet :he requirements of section 4.7 C.1.c.

L

20. _ Calibration of the comparator requires the inputs from.both recirculation loops to be interrupted. thereby removing the flow bias signal to the APRM and RBM and scramming the reactor. This calibration can only be performed duriag an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

22.

One channel of either the reactor zone or refueling zone Reactor Building I_

Ventilation Radiation Monitoring System may be administrative 1y bypassed I

for a period not to_ exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.

l

23. The Reactor Cleanup System Space Temperature monitors are RTD's that feed a temperature switch in the control room. The temperature evitch may be tested monthly by using a simulated signal. The RTD itself is a highly reliable instrument and less frequent testing is necessary.

24.

This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).

25.

During each refueling outage, all acoustic monitoring channels shall be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.

I 26.

This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not l

required during refueling outages).

107 l

Amendment No. 43 1

- ~

~-

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

1. 's PJ4 T M AT4 Y SYSTEM BCUtDARY

4. 6 PRIMARY SYSTEM BOUNDARY D.

Re hef Vahes D.

Relief Valves 1.

At least one safety 1.

When one or more valve and-valves. saf ety or approximately one-relief, is known to half of all relief-be failed, an orderly.

valves shall be shutdown shall be bench-checked or initiated and the replaced with a reactor depressurized bench-checked valve-to less than 105 psig each operating cycle.

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

All 13 valves (2 safety and 11 relief)-

will have been checked or replaced upon the completion of every second cycle.

2.

Once durine, each operating cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors downstream of the valve indicate steam is flowing from the valve.

3.

The integrity of the relief / safety valve bellows shall be continuously menitored.

u.

At least one relief valve shall be disassembled and inspected each operating cycle.

4 192 AmendmentNo.[,42

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4.0 AbMit3 F.*PATIVE CONTROLS f

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. % ti. Minimum Plant Staffino l

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The minimum plant staffing for monitoring and conduct of p

- operations is as follows.

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-1.. 'A licen:ed senior operator shall be present at the site

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at'all times when there is fuel in the reactor.

I; 2.-

A licensed operator shall be in the control room i

whenever there.is fuel in the-reactor.

H 3.

'A' licensed senior operator'shall'he'in direct. charge of a reactor refueling. operation; i.e.,-- able to devote full time to the refueling operation.

4 A-health physics technician shall be present at the f aciliry at ' all times there is fuel in the reactor.

I 5;

Two licensed operators shall be in the control room-during any cold startups, whila shutting down the reactor, and during recovery from unit trip.

6.

Either the plant superintendent or-the assistant plant c ~

superintendent shall have acquired the experience and t

training.normally required for examination by the bAC

' for a Senior Reactor Operator's ' License, whether or not the examination is taken.

In addition, either tha operations supervisor or the, assistant operations supervisor snall have an SRO license.

L 7.

A Shif t Technical Advisor shall be present at the site at all times.

6.9 Environmental Qualification l

A.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division o'f Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical t:p-Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 i

"Interin Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documente are attached to Order for Modification of License DPR 68 dated October 24, 1980.

B.

By no later than December 1,1980, complete and auditible records must be ava.ilable and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to docu-ment the degree of compliance with the DOR Guidelines or NUREG-0588. Thereaf ter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

388 Order da ted Octobcr 5,1980-AmendmentNo.f,43 w

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6.10 Integrity of Svstems outside Containment 1L program shall be imple=ented to reduce leakage from systems curside containnent 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 preventive maintenance and periodic visual inspection requirements at a frequency not to exceed refueling cycle intervals. Systems subject to this program are (1) residual heat.

removal,,(2) core spray, (3) reactor water: cleanup, (4) HPCI, and (5) RCIC.

d by system e System leak test requirements, to the extent permitte 2) design and radiological conditions, for each system at a frequency in The systems subject to this accordance with ASME code section XI.

testing are (1) residual heat removal, (2) core spray, (3) HPCI, and (4) RCIC.-

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'3.11 Iodine Monitoring A program shall 'be implemented which will ensure the capability to Laccurately. 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 31 Provisions for maintenance of sampling and analysis equipment.

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• Areas requiring personaal access for establishing hot shutdown condition.

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6.0 ADMINISTRATIVE CONTROLS Table 6.8.A Minimum shift Crew' Requirements Units in Operation shift Position J_

J 3.

Tvoe of License Shift Engineers (SE) 1 1

1 SRO Assistant Shift Engineers (ASE) 0

,1 2

SRO

-Licensed Reactor Operator 1 1

1 1

RO Unit Operators (UO) 1 2

3 RO Assistant Unit Operators (AUO) 4 4

6 None 2

Shift Technical Advisor 1

1 1

None

' Health physics Technician 1

1 1

None Minimum Shift Crew 9

11 15 Notes:

SRO - Senior Reactor Operator RO - Reactor Operator Note for Table 6.8.A 1.-

This position is normally filled by an assistant shift engineer, but as a minimum it may be filled by a licensed reactor operator.

When the incumbent is not a senior reactor operator, he shall not be assigned duties requiring him to direct licensed activities of reactor operators.

l 2.

The Shif t Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant l

design and transient and accident response and analysis.

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390 i

Amendment No. 43 l~

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