ML20009A089

Amends 65 & 62 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs to Incorporate Requirements for Decay Heat Removal Capability & to Further Define Operable for Sys & Components

ML20009A089
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	06/22/1981
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009A088	List: ML20009A087 ML20009A089 ML20009A090
References
NUDOCS 8107080050
Download: ML20009A089 (39)

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UNITED STATES

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WASHINGTON, D. C. 20555 Qc COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-39 1.

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

A.

The applications for amendments by Commonwealth Edison Company (the licensee) dated May 23, September 24, October 22, November 7, 1980 and May 1 and May 29, 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 Conmission; 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 Commission's regulations; i

l D.

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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Commission's regulations and all applicable requirements have l

been satisfied.

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'8107080050 810622 M PDR ADOCK 05000295-1 i

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

(2) Technical Specifications The Technical. Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

F0 THE NUCLp%R'RE LATORY COMMISSION A

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. V5rga, Chigf Operating Reactors Bianch No. 1 Division of Licensing Attac hment:

Changes to the Technical Specifications i

Date of Issuance:

June 22,1981 I

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UNITED STATES 2

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COMM0?alEALTH EDISON COMPANY DOCKET NO. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-48 1.

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

A.

The applications for amendments by Commonwealth Edison Company (the licensee) dated May 23, September 24, October 22, November 7,1980 and May 1 and May 29, 1981, complies with the standards and require-ments 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 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 (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 tiie Commission's regulations; D.

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 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.

i

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices-A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.

3.

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

THE NUCL,R TORY COMMISSION e

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Operating Reactors B'an h No. 1 Division of Licensin

Attachment:

Changes to the Technical Specifications

- Date of Issuance:

June 22,1981 4

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 65 TO ' FACILITY OPERATING LICENSE NO. DPR-74 AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE N0. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Pages 11 ii iv iv v

v 3

3 6

6 27a 27b 27c 27d 41 41 42 42 47c 73 73 73a 73b 74 74 74a 74a 77a 78 78 21 9 219 225a 225a 235 235 244a 244a 245 245 247a 247b 247c 248 248 2 51 251 275a 275a 283 283 292A 292A 295N 295N 295AB 295AC 178 178 J -

TABLE OF CONTEN15 (Continued) g 4

SURVEILLANCE LIMITING CONDITION FOR OPERATION RErNIREMENT PAGE I

3.0 General 4.0 27a i

Bases 27c

?

3.]

Reactor Protection Instrumentation and Logic 4.1 28 Dases 37 1

l

~3.2 Reactivity Control and Power Distribution 4.2 39 3.2.1 Reactivity Control 4.2.1

~39 3.2.2 Power Distribution Limits 4.2.2 45 i

.3.2.3 Control' Rod System Operability (per unit) 4.2.3 51 3.2.4 ONB Parameters 4.2.4 55 Bases 64 4

3.3 Reai: tor. Coolant System (per unit) 4.3 73 3.3.1 Operational Components 4.3.1 73

~

Basen 78 3.3.2 Pressurization a,nd System Integrity 4.3.2 79 90 Bases 3.3.3 Leakage (per unit) 4.3.3 95 Bases 98 j

3.3.4 Structural Integrity 4.3.4 99 Bases 118 a

l

' 3.5 Chemistry (per unit) 4.3.5 120 Bases 123 3.3.6 Activity 4.3.6 124 Bases 125 i

3.4 Safeguards Instrumentation and Control 4.4 127 l

Bases 144 3.5 Reactor Containment Fan Coolers 4.5 146 I

Bases 149 3.6 Containment Spray 4.6 150 Bases 154 i

t J

Amendment Nos. 65 & 62 J

11 2

1 ABLE OF CONIENTS (Continued) 8 SURVEILLANCE LIMITING C0f10ITION FOR OPERATION REQUIREMENI PAGE-3.13 Refue1ing Operations 4.13 243 e

3.13.1 Core Reactivity 4.13.1 243 3.13.2 Protection from Damaged Spent fuel 4.13.2 244 3.13.3 Containment Status 4.13.3 245 3.13.4 Radiation Monitoring 4.13.4 246 l

3.13.'5 Refueling Equipment Checkout 4.13.5 246 3.13.6 Refueling Equipment Operability 4.13.6 246 3.13.7.

Spent Fuel Pit Cooling Systems 4.13.7 246 2

3.13.8 Fuel Inspection Program 4.13.8 247 i

3.13.9

'- Itcsidual ficat itemoval i

System Operation 4.13.9 247a Bases 2.;g 3.14 Plant Radiation Monitoring 4.14 250 Bases 254 3.15 Auxiliary Electrical Power System 4.15 255 Bases 271 i.

3.16; Environmental Radiological Monitoring Program 4.16 275 i

i Bases 279 3.17.1 ventilation 4.17.1 281 3.17.2 Aircraf t Fire Detection 4.17.2 283 i

Bases 287 2

3.18 Steam Generator Activity 4.18 289

{

Bases 290 i

3.19 Failed Fuel Monitoring 4.19 292 s

Bases 293 l

3.20 Deleted 1

^

3.21 Fire Protection 4.21 2950 Bases 2950 3.22 Shock Suppressors (Snubbers) 4.22 295W Bases 2952 i

3.23 Special Test Exceptions 4.23 295A0 Hayes iv 295AC 4

Amendment Nos. 65 & 62

+.

b_f.

TAllLE OF CONTEllTS (continued) 5.0 Design Features...........................................................

296 5.1 Site................................................................ 296 5.2 Re a c to r Coo l a n t S y s t em............................................... 2 9 6 5.3 Reactor Core...............................'..........................

296 5.4 Containment System.................................................. 296 5.5 Fuel Storage....'..................................................... 298 5.6,.Scismic Design.......................................................

299 6.0 AD?tIMISTRATIVE CONTROLS...................................................

300 6.1 Organi7.ation, Review, Inves t. ig a l.lon a nd Audit........................ 3 0 0 6.2 Plant Operating Procedures............................................

307 1

6.3 Actions to be Taken in the 1: vent of a Reportabic Occurrence in Plant Operation........................................

315 s

n, 6.4 Action to be Taken in the Event A Safety I,imit is Exceeded...........

315 6.5 Plant Operating Rccords..............................................

315 6.6, P la n t ' Repo r t i ng Requ i reme n t s......................................... 317 Amendment Nos. 65 & 62 f

v

E.

OPERATIONAL MODES -(wIth fue1 ini,the reactor verse 1)

COOLANT REACTIVITY FISSION TEMPERATU1E MODE (a K/K)

POWER (Tavg.)-

1 Power Operation

>0 2% < P < 100%

Tayg

-2 Hot Standby

>0

< 2%

Toper 3

Hot Shutdown Fig. 3.2-1 0

350' F < Tavg i Toper 4

Hot Shutdown and Tavg 1350'F Fig. 3.2-1 0

200' F < Tavg i 350'F 5

Cold Shutdown 5 -l%

0 1 200'F 6

Refueling 1 -10%

0 1 In0'F 7

' Low Power Physics Tests 1 5%

n Where:

I

- Average temperature across a reactor vessel as measured by the hot and cold leg temperature gyg detectors.

o T

- Any temperature at which a reactor is critical, limited by Specifications 3.2.1.C.1 and oper 3.3.2.A.

NOTE:

Where Hot Shbtdown is mentioned in any Specification it means either Mode 3 or 4 unless Tavg is specifically stated.

i To be stated for specific tests.

+

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Amendment Nos. 65 & 62 3

G.

Quadrant Power Tilt Ratio K.

Operabic The quadrant power tilt ratio is defined

[

A system, subsystem, train, component or device shall be OPERABLE or have OPERABil!ITY when it is capable of as the ratio of the maximum upper excore detector current to the average of the upper performing its specified function (s).

All necessary excore detector currents or the ratio of the attendant instrumentation, controls, a normal (NORf1AL maximum lower excore detector current to the AC Off-Site or Reserve AC Off-Site) and an emergency average of the lower excore detector currents (Standby AC On-Site) AC electrical power source, whichever is greater.

cooling or seal water,. lubrication or other auxiliary equipment that are required for the system, subsystem train, component, or device to perfrom its function (sf 11.

Rated Thermal Power shall also be capable of perfonning their related support function (s).

A steady-state reactor core output of 3250 MWt per unit.

The operability requirement for both~ normal and emergency AC power supplies does not apply to AC instrimient buses and associated instruments.

I.

Reactor Pressure Operability as it pertains to Auxiliary Electrical Power System requires Normal AC Off-Site, Reserve AC The pressure in the steam space of a Off-Site and Standby AC On-Site power.

(See Section pressurizer.

3.15).

J.

Refueling Outage L.

Ope _ra ting When Refueling Outage is used to designate Performing the intended functions in the intended a surveillance interval per unit, the manner.

surveillance will be performed during the refueling outage or.up to six months before M.

Operatinq Cycle the refueling outage. When a refueling outege occurs within 8 months of the The interval between the end of one major refueling previous refueling outage for a unit, the outage and the end of the next subsequent major surveillance testing need not be performed.

refueling ourage per unit.

The maximum interval between sury.eillance tests is 20 months per unit.

N.

Surveillance _' Interval See Specification 4.0.2, page 27a for description of the surveillance intervals.

Amendment Nos. 65 & 62 6

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SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION c.

Exceptions are stated in the individual specifi, cations.

n-3.0.4 Entry into an OPERATIONAL MODE or other 4.0.4 Entry into an OPERATIONAL MUDE or other specified applicability condition shall not be specified applicability condition shall not made unless the conditions of the Limiting be made unless the Surveillance Condition for Operation are met without Requirement (s) associated with the Limiting reliance on provisions contained in the ACTION Condition for Operation have been performed statements unless otherwise excepted.

This within the stated surveillance interval or provision shall not prevent passage through as otherwise specified.

OPLRATIONAL MODES as required to comply with ACTION statements.

3.0.5 When a system, subsystem, train, component or 4.0.5 Not Appilcable, 4

device is originally determined to be inoperable solely because its emergency AC power source is inoperable, or solely because its normal AC power source is inoperable, it may be considered OFERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provfUed:

a.

Its corresponding normal or emergency power source is OPERAGLE, and b.

> ' All of its redundant system (s),

subsystem (s), train (s), component (s),

device (s) are OPERABLE, or likewise

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satisfy the' requirements of this specification.

NorE:

This Technical Specification does not apply to AC instrument buses and associated instrume,ts nor during MODES 5 and 6.

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27b Amendment Nos. 65 & 62

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LIlilTINd CONDITION FOR OPERATI0li SURVEILLANCE REQUIREMENT 3, 2,1. D.1,

drawn and the contro). group rods 4.2.1.D.1

' past t wo uceks thiring non' mal shall be no further inserted than operat ion need not be verified, the limits nhown on l'igure 3.2-2 Control rod Imnk positions with for tipit I and l'igure 3.2-4 for respect to its insertion limit Unit 2 for 4-loop operation and shall be veri fied once per shif t.

Figstre 3.2-3 for linit I and Figtire 3,2-5 for Linit 2 for 3-loop operation.

2.

Control bank innertion may be 2.

Control rod back worths shall further restricted if the measured be measured following each refue1<

cen t rol rod wort h of all nods, ing outage.

less I.lic wor th of the most reac-

.t i.Ve rod (wornL case sLuck rod),

is Jens than the reactivi ty re-cpii red to provide the design value cf available shutdown an shoun in P.igure 3.2 1,

3 Itur i ng t,hyn i en lest.n and control 3.

FJot Appli cable.

rod exe rci nen, the innertion limits need not be observed, but s

Ihe 1i.miin in Figure

'l. 2 - 1 uninL be observed c:< cept dur tng the low power physics t.ca t t o de te r--

mine total control rod worth and shutdown margin.

For thin t.en t the reactor may be cri t i cal with all' full Jength contro] rods fu1]y i nne rlud, except for the predicted most reactive rod.

~

4 l-

.u.

Amendment Nos. 65 & 62

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l.iF.ITili". Coll!)1T10fl F0lt Ol'El(ATIOli SUflVEII,1.Af;CE IlE0(1TilEMEf1T e

4.2.1.

.1.2.1

~

P..

Hod 11ank Ansignment l'.

Ioad.,ilaitk As s i gninen t t

11od nani: Ar.bignment shall lic au Rod naak Ansignment shall be de l i nea teil in Figure 3.2-0.

I:xcept verified after cach refueling during physics tents, s.hc acquence of outage, for the refueled unit.

withelrawal of the control banks, when going from zero to 1001 power, in A, n, C,

D with control bank overlap.

P.

11oric Aclil System (per uni t)

P.

Doric Acid Syntem (per unit) 1.

A reactor shall not be taken from 1.

Surveillance and testing of hot shutilown in hot utandl,y untenn t.he boric acid system shall the following conili tions exist:

he performed as follows:

a.

Onc boric aciel

• ik for dhat a.

11oric acid tank level, reactor conta at leant 5140 concentration and tempera-gallons of 11..

(Ins t. no t g re a t-Ltite shall be verified cr than 1M) by weight boric prior to starttip and acid sol ut.J on a t n' temperature weekly thereafter.

of at least 145"P.

J 42 Amendment Nos. 65 & 62

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LIMITitG CONDITION l'OR OP13t% TION Stil&l'iLING RIUJIRIBisill'

.. d.

.3.1.A.3 b.

With no heat removal -loop in operation:

4.3.1.A.3

d. With no RHR loop in operation the core exi 1) suspend all 6perations involving a temperature shall be monitored utilizing reduction.'in boron concentration of data from 2 or more core exit thermocouple (

the Reactor Coolant System and:

The frequency of temperature readings shal{

2) immediately initiate corrective action he adequate to insure that the temperaturei to return the required heat removal will not increase above the 10*F subcoolin{

loop to operation.

limit between temperature readings.

j 3.3.1.A.4 Two residual heat removal (Ri!R) loops shall 4.3.1.A.4 a.

The residual heat renoval loop shall be OPEPABIE.* At least one of these tr determined to be in operation and loops nhall be OPICIMTItG.

Ilowever, the circulating reactor coolant at least requitement for an OPIJmTIrG nliR loop nny be once per shift.

deleted provided a) no evolutions that would cause a reduction of the reactor 4.3.1.A.4. b.

With no RIrn loop in operation the core i

coolant system toron concentration are in exit temirrature shall be monitored progress or initiated, and b) the core outlet utilizing data frcm 2 or more core temperature as measured by the core exit therno-exit thernncouples. The frequency couples is kept at least 10 F below saturation of temperature readinas shall tr temperature.

adequate to insure that the tenperature will not increase atove the 10"r APPI.tCABILITY: 11 ode 5 Subcooling limit between tmperature readi$

With only one of the above required ACT1rti:

a.

loops OPIJmniE, ininoliately initiate corrective action to return the irotrrable f

loop to OPEPAULE status as soon as possible, i

b.

With no RI!R loop OPEPABIE:

i

1) surtwrvi all operations involviry a i

reduction in toron concentration of the l

Reactor Coolant System and; l

2) imnediately initiate corrhetive action j

to return both RilR loops to OPEPABLE l

status, or operation if necesrary, in order 1

to maintain core outlet temperature at least j

10 C below saturation temperature.

c.

The provisions of Fpecification 3.0.3 are not applicable, t

One RC loop capable of natural circulation may in substitJtex1 for one OPERABLE RHR loop.

An ItitR loop tray still be considered OPI7mnIE with only onr of either the nornnl or emergency piser sources OPElmIE.

f Amendment Nos. 65 A 62 73h

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O LIllITIt!d C0tIDITIOff FOR OPERATIOil SURVEILLANCE REQUIREl1EllT

~

4. 3. 1. 11. 2 l'.

a.

Where experience in similar plants with similar water chemistry indicates critical areas to be o

inspected, then at leas t 50% of the tubes in-spected shall be from these critical areas.

3.3, 1

b.

The first sample inspection,during each inser-vice inspection (subsequent to the preservice inspection) of each steam generator shall in-clude:

,3 1

All nonplugged tubes that previously had detectable wall penetrations ( ) 201) and i;

2 Tubes in those areas where experience has indicated potential problems.

s The second and third sample inspections duting c.

each inser.vice. inspectidn may be less than a full tube inspection by concentrating the in-spection on those areas of the tube sheet array e

and on those portions of the tubes where tuber with imperfections were previously found.

d.

The tube inspection shall be conducted accord-ing to 4.3.1.B,4.A.R.If a tube does not permit.

the passage of the eddy current 17spection probcl the entire length and through th; U-bend; this shall be recorded and an adjacer t tube shall bc

n inspected.

The tube which did not allow pas-sage of the eddy current probe shall be corisid-

.t.

cred degraded.

74a Ame'dment Nos. 65 & 62 n

Bases:

3.3.1 Operational Components During flode 5, one reactor coolant loop capabic of providing natural 4.3.1 The plant is designed to operate with all circulation may also be substituted reactor coolant loops in operation and for an OPERABLE RilR loop.

At least maintain DNBR above 1.30 (1) during all normal one RllR loop must be OPERABLE at all operations and anticipated transients.

In times.

MODES 1 and 2 with one reactor coolant loop not in operation this specification reouires that the plant be in at least il0T SIUTDOWN within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

When the Unit has been in Mode 5 for an ex-In MODE 3, a single reactor coolant loop tended period of time, decay heat addition provides sufficient heat removal capabil-to the reactor coolant is very slow. During ity for removing decay heat; however, these periods, the requirement for an operating single failure considerations require that Rift pump may be relaxed to require two RfR two loops be OPERABLE.

pumps to be OPERABLE.

Operation with no forced coolant flow is considered to be an In MODES 4 and 5, a single reactor coolant unusual and undesirable mode of plant opera-loop or Rift loop provides suf ficient heat Lion.

If it becomes necessary to interrupt removal capability for removing decay heat; forced coolant flow for testing, maintenance, but single failure considerations require or any other reason, the Technical that at least two loops bt OPERABLE.

Specification will assure that the onset of Thus, if the reactor coolann loops are pol potential boiling can be detected and core OPERABLE, this specificatior requires cooling initiated before boiling occurs.

The two RIR loops to be' 0KR&BLI..

rate of reactor coolant system heatup with no forced flow is estimated to be less than 6'F The operation of one Reactor Coolant Pump per minute af ter 1 day, 5'F per minute af ter or one RFf1 Dump provides adeouate flow 4 days, and 3'F per minute af ter 1 month of to ensure mixing, prevent stratification plant shutdown.

This estimate is based on no and produce gradual reactivity changes natural circulation flow through the coolant during boron concentration reductions loops and reactor vessel water level at the in the Reactor Coolant System.

The reac-centerline of the nozzles.

tivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition anu control.

7 7a Amendment flos. 65 & 62

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LIMITING CONDITION IN)R OPFHATION SUHVEILLANCE REQUIRIMENT 3.8 7 se rvice Wa te r 'sys t.em" 1.8 7.

Service water syst,em (Ta ble i.8-6 )

• 1 t

A. Three service wa ter pumps 1A, lH, ]C A.

Surveillance and test,ing of t.he service t

(2A, 21), 2C) per unit, shall be operabic un ter syst,em shall be performed as whenever t he react,or is going from hot follcws:

shut.down t.o hot, s tandby.

1. The service wa ter pumpn shall be operat,ed each month.

I'erronnance will be acceptable if t.he pump sta rts upon ac,ua tion, opera tes for at, least four hours, and sa tisfies t,he cooling re-quirement,s necessary for the routine opera t,lon of t,he servMe wa ter syst,em.

2. The service wa ter pump system power opera ted va lves r,.sall be s troked mar.ually from the control roo-cach m o r.t h.

Performance will be accept-able if valve motion is indicated upor. act,uat1on

1. Until complet.lon of ci rcula tor / wa t,er pump ma in-

"Unti l comple t.i on of ci rcula tory wa ter pump T.a in-tenance p rsg ram scheduled for ccmple t, loo a hmi t, 8

t,enance program $1scheduled for completion ab:ut December 31, 19 1, one service water pump may December 31, 19 the surveillance require:ents

'e ;ut of service for maint.cnance purposes.

During o f II. 8. 7. C d o not pe r t,a i n t.o t,he service water c

,his pe riod, the required r.uT.ber of operable pur.ps pump out, of service for maintenance purposes.

na s t,a t.ed in 3. 8.7. A., 3. 8.7. B., a nd 3. 8.7. C. may oc reduced by one for a single unit provided 'the main Il8-inch service wa ter headers for each unit a re c ron s - 1,i ed.

While in the cross-tied mode, an cpera ting service wa t,er pump f rom the ot,her uni t wit.h independent s t,andby AC and DC powe.r supply

~r.ay be used t o fulfill t.Pe requirement,s of 3.8,.7 n addition, the service wa ter pump out of service for Tai ntenance purposes is not considered a re-dondint syst,em per the require c.ents of 3.0.3.

178 Amendment Nos. 65 & 62 l

/

SUBVEILLAllCE REQUIREf1ENT LIMITING CO,NDITION FOR OPERATIOli 3.10.4 4.10.4 If changes in the inward deformation greater than 0.25 inches occur,

,an investigation will be made to determine the cause and corrective action.

If no corrective action is necessary during the duration of the program described, the program shall be discontinued.

5.

If the containment internal press-5.

The containment pressure shall ure exceeds 1.0 psig or the inter-be verified once a shift.

nal vacuum exceeds 1.5 psig, the condition shall be corrected immediately or the, reactor shall be brought to the hot shutdown condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

6.

If the containment ambient temp-6.

The containment temperature shall 120 F or is,1can be verified once a shift.

0 crature exceeds than 65 F the condition shall be corrected immediately or the reactor shall be brought to the hot shut-down condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

7.

The provisions of Specification 3.03 7.

Not Applicabic.

are not applicable to Specification 3.10.

Amendment fios. 65 & 62

,,g

~

LIMITING CONDITION FOR OPERATION SURVEILLA11CE REQUIREMElli

)

[

3.11' 4.11 8.

When the release rate of radioactive B.

tiot Applicable.

materials, excluding tritium and dissolved gases, exceed 2.5 curies / unit i

during any calendar quarter, the licensee shall notify the Director, Directorate of Licensing,within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates.

9.

the provisions of Specification 3.0 3 9.

tiot Applicabic, are not applicable to fipecification 3.11.

Amendment tios. 65 & 62

/

? ? r, a

t

~

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREt1ENT 3.12.

4.

The maximum activity to be con-4.12.

4.

Prior to isolating a tank for tained in one gas decay tank decay the tank will be sampled she:11 not exceed 22,000 curies.

per Table 4.12-2 and total (Equiva len t to Xe-13 3).

activity determined.

5.

When the annual projected release 5.

Records rate of radioactive materials in gaseous wastes, averaged over-A.

Facility records of iodine a calendar quarter exceeds twice and particulate releases with the annual objectives, the licensee half-lives greater that eight shall notify the Director, days shall be maintained on Directorate of Licensing within 30 the basis of all the iodine days, identifying the causes and sampling devices and particulate describing the proposed program filter analyses.

of action to reduce such release rates.

B. Records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section (Plant Reporting Require-men ts ) 6 of these Specifications.

6.

The provisions of Specification 3.0 3 6.

Not Applicable, are not applicable to Specification 3.12.

Amendment flos. 65 f. 62 235

LIMITING CONDITIOt1 FOR OPERATIO!!

SURVEILLAtlCE REQUIREf1Et1I' 3.13.2.A 1.

Operating with ventilation flow 4.13.2.A 1.

Observe and document shiftly that through the IIEPA and charcoal fi l ters the ventilation system is OPERATIl1G if there is any irradiated fuel stored as required by Specification in the pool with less than 60 days 3.13.2.A.

decay time.

2.

Operable with automatic initiation of 2.

When operability is required by flow through the IIEPA filters,and Specification 3.13.2.A.2, the charcoal adsorbers upon detection of following shall be done at least high radiation at the fuel pool if all once per 31 days:

1)

Place the irradiated fuel stored in the pool has Fuel Building Ventilation System in 60 days or greater decay time since the Fuel llandling ttode for a minimum irradiation ceased.

If automatic of 15 minutes, 2)

Verify flow th rou<

actuation is inoperable, the system the llEPA and charcoal adsorber train shall be manually placed in the 3)

Verify the Fuel Building is

" charcoal adsorber mode".

maintained at 's inch of water ru:gati' pressure with respect to the atmos-APPLICAB II,I TY :

All riodes phere.

ACT 10ti :

With the requirements df 3.13.2.A$

not satisfied, suspend all irra-diated fuel movements or crane operation with loads over irra-diated fuel after first, if applicable, placing loads in a safe condition.

.g.

Amendment flos. 65 & 62 g 4,

h h

LIli1 TING CONDITION FOR OPERATION

!!URVEILLANCE REQUIRF2iENT 3.13.2,,D. Ventilation filters for the fuct fulldity 4.13,2 D.

Ibr each HEPA or charcoal filter, at Icant c incitallry charcoal adsorbern aryl tle auto.

per la nniths or (1) af ter every 720 loirs o k

rnatic actuation of die cinrcoil filter syntem charcoal adsorber oteration or (2) af ter any i

i shall le periodically testel, structural nuinte narre of the filter tousirrj or (3) followiry ruintirn, fire, or chrinical release in any ventilation zme ormtrunicatin with t he system, or (4) af ter each cortplete <

rurtial replacement of the filter Innk, surveillance will be gerforrrw31 per Table 4.I' 1

Verify that on a high radiation test sigi the system autcmitically starts (unless.

already in operation) anri directs fts I

exhaust flow throt.qh the In:PA filter 3 arn charctut adsorter Innks. If autcmitic actintion is inoperable the system shall be rnanually placed in the charcoal c:Isort e -

rrnle.

3.13.3 Contairrrent status 4.13.3 (Contairrrent status A. Dirirn refuelity operations contal:nent integrity A.

Contairent (bor status sin 11 be verifiel onc

=

isce section 1.0.C) shall im nuintained as a shift.

specified in sectico 3.9.5 except as specified i

in 3.13.3.B.

n. 'the egiipnent hatch or both doors cc the D.

Itcactor coolant loron concentration arvi Tavg }

}

tersonnel batch nuy le qened durity the re-shall le verified once a chif t when the equi [/

fuellrn operation proildal the shutdown trorgin lutch is open or loth doors cn the personnel is rnalntained egnal to or greater than 10%

hatch are open.

AK/K arxl Tavg is enaintained at or less than l

140 p.

4 245 Amendment Nos. 65 1. 62

/

SURVEILLANCE REQUTHEMENT LIMITING C0f0ITION FOR OPERATION 1

1 i

l ti j

9.

Residual Heat Removal System Operation

9. Residual Heat Removal System Operation A.

1.

The required Residual Heat Removal A.

Two independent Residual Heat Removal loops shall be determined OPERABLE (RIH) loops shall be OPERABLE

• with at least one loop operating.

per Specification 4.8.3.A.I.

APPLICARILITY:

Mode 6 when the water level above 2.

At least one Residual Heat Removal Loop shall be verified to be the top of the reactor pressure OPERATING and circulating reactor vessel flange is less than 22 'ect.

coolant at least once per shift.

• The normal or emergency power source may be inoperable for each Rift loop.

I 2 '47a Amendment Nos. 65 & 62 l

/

• s t

LIMITItIG CONDITION FOR OPERATION SURVEILLANCE REQUIREME!!T

.l.

3.13 9. A.

4.13 9 A.

ACTION:

a.

Wit h less than the required RIIR loops OPERABLE, immediately initiate corrective

,g action to return the required RilR loops to OPERADLE status as soon as possible.

b.

With no residual heat removal loop in operation, suspend all operations that would cause a decrease in decay heat removal capabilities or a redtiction in boron concentrat ion of the Reactor Coolant System.

Close all containment I

penetrations providing direct access f rom the containment atmosphere to the outside l

a trnosphere within f our hours.

i B.

At least one residual heat rernoval ( RilR)

D.

At least one Residual lleat Removal loop loop shall be OPERATING.

j shall be verified to be OPERATING and I

circulating reactor coolant at least e

APPLICABILITY:

Mode 6 when the water level above once per shift.

the top of the reactor pressure vessel flange is greater than 22 f t.

ACTITy a.

With no residual heat removal loop in operation, except as provided in b.

below, suspend;all operations that would cause a decrease in decay heat remova1 capabilitics or a reducti~on in boron concentration of the Reactor Coolant System.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within four hours.

N 247b Amendment Nos. 65 & 62

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1

n, LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.14.1 4.14.1 The monitor shall be recalibrated if the results are outside this span.

B.

Instrumentation may be taken B.

The instrumentation of Tabic out of service for short 4.12-2 shall be calibrated periods'of time for testing; every six months.

This however, the requirements of calibration procedure shall 3.14.1.C will apply.

consist of an initial electronic calibration and then a veri-fication of the calibration, using two known sources of radiation fields.

~"

C.

When any of the instrumentation listed C.

Not Applicable.

in table 4.14-1 is out of service, manual surveys or " grab" sampling shall be done once cach shift...

D.

Radiation sensitive instrumentation D.

Other radiation instrumentation and laboratory equipment not listed and laboratory equipment shall be in Table 4.14-1 or elsewhere in the calibrated at regular intervals.

Technical Specifications shall be The Radiation Protection Depart-operable on an "as needed basis."

ment supervisor shall determine these intervals based on operating requirements and experience.

2. The provisions of Specification 3.0. 3 and 3.0.4

2. Not Applicable.

are not applicabic to Specification 3.14.

251 Amendment Nos. 65 & 62

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3,16 3.16 2.

Within a 5-mile radius, enumeration 2.

Not Applicable.

j by using referenced information from county agricultural agents or other reliable sources.

If it is learned from this census t ha t an-imals are present at a location which yields a calculated thyroid dose greater than from previously sampled animals, the new loca-tion sha11 be added to the survei11ance program as soon as practicable.The sampling locaLion having the lowest calcu1ated dose may then be dropped from the sur-veillance program at the end of the grazing season during which the census was conducted.

Also, any location from which milk can no i

longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that milk-producing animals are no longer present at that location.

The provisions of Specification 3.0 3 3.

Not Applicable.

3.

and 3.0.4 are.not applicable to Speci fication 3.16 Amendment tios. 65 & 62

'79,

l' e

LIMITING CdNDITION FOR OPERATION SURVEILLANCE REQUIREf1Et1T 3.17.2 Aircraft Fire Detection 4.17.2 Aircraft Fire Detection Applicabilijy Applicability _

Applies to the testing of the aircraft Applies to the testing of the aircraft fire detectors installed on diesel fire detectors installed on diesel generator and switchgear intakes, Aux.

generator and switchgear intakes, Aux.

Bldg. intakes and cribhouse.

Oldg. intakes and cribbouse.

Objective Objective To verify that the control circuit To verify that the control circuit will trip the corresponding fan and will trip the corresponding fan and close the corresponding lampe r.

close the corresponding damper.

Specification Specification 1.

The aircraft fird detection system 1.

Surveillance on the Aircraft Fire shall be operational,-

or tile failed Detection system shall be as componenta shall be placed in th e follOWS:

accident mode.

a.

Each air compressor shall be verified operational once a month.

b.

Each fire detection circuit shall be tested every six mont by simulating a signal equiva-lent to a fire condition and I trip and associated damper closure verfied to occur withi 2 seconds.

2.

The provisions of Specif.i ca tion' 3.0. 3 2.

Not Applicable.

are not applicable to Specification 3.17.2.

Amendment flos. 65 & 62 2n3

SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION

=

4.19 3.19 2.

Instrumentation may be taken out of 2.

The instrumentation in Table 4.19-1 service for short periods of time for shall be calibratcd initially electrol The calibration shall be testing; however, the requirements of ically.

verified during refueling operations 3.19.3 will apply.

using the following methods.

A.

For RTPR18, at Icast two different levels of radiation shall be used.

B.

For RTPR21 at least two known concentrations cf radio-active materials shall be used.

3.

When the instruments in Table 4419-1 3.

An iodine analysis of the reactor are out of service, a radioactive iodine coolant system shall be done once analysis of the reactor coolant system per shif t on a unit whose failed ' fuel shall be done on the unit whose detec-instrumentation is inoperable.

tors are inoperable.

4.

The provisions of Specification 3.0 3 4.

Not Applicable, are not applicable to Specification 3.19.

r M ndment flos. 65 & 62

/

29M

I LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

,jj 3.21 4.21

a 6.

Penetration Fire Barriers 6.

Penetration Fire narriers A.

All penetration fire barriers pro-A.

Each of the safety related

'i tecting safety related areas shall penetration fire barriers shall be functional at all times.

be verified to be functional by a visual inspection.

3 l.

At least once per 18 months, and 2.

Prior to declaring a penetri tion fire barrier functional l

following repairs or mainte-i nance.

i.

I D.

With one or more of the above re-j quired penetration fire barriers j

not intact a continuous fi,rc watch shall be established on at Icast one side of the affected penetra-tion within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

If an oper-able fire detector is located in the i

area, an hourly inspection of the penetration fire barrier may be performed rather than establishing a continuous fire watch.

~

j 7.

The provisions of Specifications 3.0. 3 7.

Not Applicable.

are not applicabic to Specification j

3.21.

I i

en en Nm. 65 & 62 295N

t SURVEILLAtlCE REQUIREf1EllP LI!!ITIllG CONDITION FOR OPERATIOll 4.23 Special Test Exceptions 3.23 Special Test Exceptions 1.

The limitations of Specification 3.3.1.A.1 1.a.1 The T!!Ellf-1AI,POWI:R shall be determined may be suspended during the performance to be less than P-7 I n terlock - Se tpoi n t at least once per hour during start ur of start up tests and PilYSICS TESTS tests and PilYSICS TESTS.

provided:

i.

The TilEllf1AL POWER does not exceed the 1.b.2 Each Intermediate, Power Range Channe P-7 Interlock Setpoint (Table 3.1-1),

and P-7 Interlock shall be subjected to a CilAtitIEL FUt1CTIO!3AL TEST within and ii.

The Reactor Trip Setpoints on the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up OPERABI.E Intermediate and Power Range tests or PilYSICS TESTS.

Channels ace set less than or equal to 25% of RATED TIIERf1AL POWER.

APPLICABILITY:

During operation below the P-7 Interlock Setpoint.

ACTIOti:

With the TilERt1AL POWER grqater than the P-7 Interlock Setpoint, immedi-ately open the reactor trip breakers.

I 295 AB Amendment flos. 65 & 62-

j',

4 4

5 Bases:

e i

3.23 Reactor Coolant Loops i

l This special test exception permits reac-tor criticality under no flow conditions and is required to perform certain etart-up and PIIYSICS TESTS while at low TIIEllMAL

)

POWER levels.

t r

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I.

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i 1

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Amendment Nos. 65 & 62 295AC

.