ML20003H893
| ML20003H893 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/01/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20003H890 | List: |
| References | |
| NUDOCS 8105080153 | |
| Download: ML20003H893 (26) | |
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I Revisions to Zion Technical Specifications Originally Submitted on November 7, 1980 The attached pages completely replace the pages originally submitted. explains where the revisions were mace.
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TABLE OF CONTENTS (Continued)
SURVEILLMCE LIMITING C0tOITION FOR OPERATION REQUIREMENT PAGE 3.0 General 4.0 27a 27c Bases 3.1 Reactor Protection Instrumentation and Logic 4.1 28 37 Bases 3.2 Reactivity Control and Power Distribution 4.2 39..
4.2.1 39 3.2.1 Reactivity Control, 3.2.2 Power Distribution Limita 4.2.2 45 3.2.3 Control' Rod System Opetsnility (per unit) 4.2.3 51 3.2.4 DNB Parameters 4.2.4 55 64 Bases 3.3 Reactor Coolant System (per unit) 4.3 73 4.3.1 73 3.3.1 Operational Components 78 Bases 3.3.2 Pressurization and System Integrity 4.3.2 79 90 Bases 3.3.3 Leakage (per unit) 4.3.3 95 98 Bases 4.3.4 99 3.3.4 Structural Integrity 118 Bases 3 3.5 Chemistry (per unit) 4.3.5 120 123 Bases 4.3.6 124 3.3.6 Activity 125 Bases 4.4 127 3.4 Safeguards Instrumentation and Control 144 Bases 3.5 Reactor Containment Fan Coolers 4.5 146 149 Bases 4.6 150 3.6 Containment Spray 154 Bases 4*
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TABLE OF CONTENTS (Continued)
SURVEILLANCE LIMITING CONDITION FOR OPERATION REQUIREMEN T PAGE'
+
3.13 Refueling Operations 4.13 243 3.13.1 Core Reactivity 4.13.J 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 Raolation Monitoring 4.13.4 246 3.13.5 Refueling Equipment Checkout 4.13.5 246 3.13.6 Refueling Equipment Operability 4.13.6 246
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3.33.7 Spent Fuel Pit Cooling Systems 4.13.7 246 3.13.8
. Fuel,In_spection Program 4.13.8 247 3.13.9 Residual Heat Removal System Operation 4.13.9 247a Bases 248 3.14 Plant Radiation Monitoring 4.14 250 Bases 254 3.15 Auxiliary Electrical Power System 4.15 255 4
Bases 271 3.16 Environmental Radiological Monitoring Program 4.16 275
' Bases 279 3.17.1 Ventilation 4.17.1 281 3.17.2 Aircraft Fire Detection 4.17.2 283 Basec .287 3.18 Steam Generator Activity 4.18 289 Bases 290 i.
3.19 Failed Fuel Monitoring 4.19 292' Bases 293 3.20 Deleted 3.21 Fire Protection 4.21 2950 Bases-
-2950 3.22 Shock Suppressors (Snubbers) 4.22-
'295n Bases 2952 3.23
'Special Test Exceptions 4.23 295A8 Bases 295AC
TABLE OF CONTEtJTS (continued) t 5.0 Dp s i g n F e a t u re s........................................................... 2 9 6 5.1 Site................................................................ 296 5.2 Re a cto r Coo l a n t S ys tem............................................... 2 9 6
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5.3 R e a c t o r C o re......................................................... 2 9 6 5.4 Containment System.................................................. 296 5.5 F u e l S t o ra g e....'..................................................... 2 9 8 5.6 Seismic Design....................................................... 299 6.0 ADM I N I ST RAT I VE CONT RO LS................................................... 3 0 0 6.1 Organization, Review, Investigation and Audit........................
300 6.2 Plant Operating Procedures...........................................
307 6.3 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation........................................
315 s
6.4 Action to be Taken in the Event A Safety Limit is Exceeded...........
315 6.5 Plant Operating Records..............................................
315 6.6, Plant Reporting Requirements.........................................
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O_PERATIONAL MODES (cith fuel in the reactor vessel)
-COOLANT REACTIVITY FISSION TEMPERATLRE MODE (a K/K)
POWER
( Tavg.')
1 Power Operation
>0 2% 1 P 1 100%
Tavg 2
Hot Standby
>0 1 2%
T oper 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 1 -1%
0 1 200'F.
6 Refueling 1 -104 0
1 140'F 7
Low Power Physics Tests 1 5%
Where:
T Average temperature across a reactor vessel as measured by the hot and cold leg temperature avg detectors.
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 Shutdown-is mentioned in any Specification it means.either Mode 3 or 4 unless Tavg is specifically stated.
To be stated for specific tests.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.0 GEN 8RAL 4.0 GENERAL 3.0.1 Limiting Conditions for Operation (LCO's) 4.0.1 Surveillance Requirements shall De and ACTION requirements shall be applicable during the OPERATIONAL MUDES applicable for each specification during or other conditions specified for the stated OPERATIONAL MODES or other individual Limiting Condition; for conditions.
operation unless otherwise stated in an individual Surveillance Requirement.
3.0.2 Adherence to the requirements of the 4.0.2 Each Surveillance Requirement shall be Limiting Condition for Operation and/or performeo within the specified time associated ACTION within the specified interva? with:
time interval shall constitute compliance with the specification. The ACTION a.
maximum allowable extension not statement need not be completed if the
- o exceed 25% of the surveillance LCO is restored prior to expiration of interval, and the time interval.
b.
Tne comoined time interval for arj three consecutive surveillance 3.0.3 If a Limiting Condition for Operation intervals shall not exceed 3.25 and/or associated ACTION requirements times the specified surveillance cannot be sutisfied, action shall be interval.
initiated within one hour to place the unit in at least HOT SHUTDOWN within the following four hours, and in at least 4.0.3 Performance of a Surveillance COLD SHUTDOWN within the following 48 Requirement within the specifleo time hours. This requirement need not be interval shall constitute compliance completed if:
with OPERASILITY requirements for a Limiting Condition for Operation.
If a.
The reactor is placed in a MODE in there are exceptions to the OPERA 81LITY which the specification is not requirements, they are stated in tne applicable; or individual specifications.
Surveillance Requirements do not have b.
Corrective measures which permit to be performed or, inoperaole equipment.
operation are completed within the specified time interval as measured from initial discovery; or 27a 1
a LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT c.
Exceptions are stated in the individual specifications.
3.0.4 Entry into an OPERATIONAL MODE or other 4.0.4 Entry into an OPERATIONAL MODE 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 coc'ained 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.
OPERATIONAL MODES as required to comply with ACTION statements.
3.0.5 When a system, subsystem, train, component or 4.0.5 Not Applicable.
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 OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:
a.
Its corresponding normal or emergency power source is OPERABLE, and b.
All of its redundant system (s),
subsystem (s), train (s), component (s),
device (s) are OPERABLE, or likewise satisfy the requirements of this specification.
NOTE:
This Technical Specification does not apply to AC instrument buses and associated instruments nor during MODES 5 and 6.
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3.0 Bases
3.0.5 This specification delineates The specifications of this section provide what additional conditions must be sat-the general requirements applicable to each of isfied to permit operation to continue, the Limiting Conditions for Operation and Sur-consistent with the ACTION statements for veillance Requirements within Section 3/4 power sources, when a normal or emergency power source is not OPERABLE.
It specifi-3.0.1 This specification defines the applica-cally prohibits operation when one divi-bility of each specification in terms of defined sion is inoperabic because its normal or OPERATIONAL MODES or other specified conditions emerger.cy power source is inoperable and and is provided to delineate specifically when each a system, subsystem, train, component specification is anplicable, or device in another division is inoper-able for another reason.
3.0.2 This specification defines those conditions necessary to constitute compliance with the terms The provisions of this specification per-of an individual Limiting Condition for Operation mit the requirements associated with indi-and associated ACTION requirement.
vidual systems, subsystems, trains, com-ponents, or devices to be consistent with 3.0.3 This specification delineates the actions the requirements for the associated elec-to be taken for circumstances not directly pro-trical power source.
It allows operation
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vided in associated specifications and whose oc-to be governed by the time limits of the currence would violate the intent of the specifi-specification associated with the Li:.iting cation.
Condi tion for Operation for the normal or emergency power source, not the indi-3.0.4 This specification provides that entry into vidual specification requirements for an OPERATIONAL MODE cc other specified applicabil-
.each system, nubsystem, train, component ity condition must be made wi th (a) the full com-or device th a t is determined to be inop-plement of required systems, equipment, or compon-erable solely because of the inoperabil-ents OPERABLE and (b) all other parameters.as ity of-i ts nor.nal or emergency power source, specified in the Limiting Conditions for Operation being met without regard for allowable deviations In MODES 5 or 6, Specification 3.0.5 is and out-of-service provisions contained in the not applicable, and thus the individual ACTION statements.
ACTION statements'for each applicable Limi ting Condition for Operation in these The intent of this provision is to insure that fac-MODES must be adhered to, ility operation is not initiated.with either required equipment or systems inoperable or other specified
- imits being exceeded.
Exception 1 to this provision have been provided for limited number of specifications when startup a
with inoperable equipment would not affect plant safety.
These exceptions are stated in the ACTION s tatements of the appropriate specifications.
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4.0 Bases
4.0.1 This specification provides that surveil-operable, when such items are found or know'n
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lance activities necessary to insure the Limiting to be inoperable although still meeting the Conditions for Operation are met and will be per-Surveillance Requirements.
formed during the OPERATIONAL MODES or other con-ditions for which the Limiting Conditions for 4.0.4 This specification ensures that the
' Operation are applicable.
Provisions for addition-surveillance activities associated with a al surveillance activities to be performed with-Limiting Condition for Operation have been o u t-regard to the applicable OPERATIONAL MODES performed within the specified time interval or other conditions are provided in the individ--
prior to entry into an OPERATIONAL MODE'or ual Surveillance Requirements.
Surveillance other applicable condition.
The inten* of Requirements for Special Tes t Exceptions need this provision is to ensure that surveillance only be performed when the Special Test Exception activities have been satisf actorily demons tra-is being utilized as an exception to an individ-ted on a current basis as required to meet ual specification.
the OPERABILITY requirements of the Limiting Condition for Operation.
4.0.2 The provisions of this speci fication provide allowable tolerances for performing surveillance Under the terms c f this specification, for activities beyond those specified in the nominal example, during i ni tial plant startup or surveillance interval.
These tolerances are neces-following extended plant outages, the appli-sary to provide operational flexibility because of cable surveillance activities must be per-scheduling and performance considerations.
The formed within the s ta ted surveillance i.ter-phrase "at least" associated uith a surveillance val prior to placing or returning the system frequency does not negate this allowable tolerance or equipment into OPERABLE status.
value and permits the performance of more frequent surveillance activities.
The tolerance values, taken either individually or consecutively over 3 tes t intervals, are sufficient-ly restrictive to ensure that the reliability asso-elated with the surveillance activity is not signif '
icantly degraded beyond that obtained from the nom-inal specified interval.
4.0.3 The provisionc of this specification set forth the criteria for determination of compli-ance with the operability requirements of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be operable if the associated surveil-lance activities have oeen satisfactorily per-formed within the specified time interval.
Nothing in this provision is to be construed as defining equipment, systems or components n, a
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O LIMITINd CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3 2al.D.'l drawn and the control group rods 4.2.1.D.1 past two weeks during normal 0
shall be no further inserted than operation need not be verified.
the limits shown on Figure 3.2-2 Control rod bank positions with for Unit 1 and Figure 3,2-4 for respect to its insertion limit Unit 2 for 4-loop operation and Figure 3,2-3 for Unit 1 and shall be verified once per shif t.
Figure 3,2-5 for Unit 2 for 3-loo;.
operation.
2.
Control bank insertion may be 2
Control rod back worths shall 2
further restricted if the measured be measured following each refuel-control rod worth of all rods, ing outage.
less the worth of the most reac-
,tive rod (worst case stuck rod),
is less than the reactivity re-quired to provide the design value of available shutdown as shown in Figure 3.2-1, 3
During physics tests and control 3
Not Applicable.
rod exercises, the insertio.
limits need not be observed, but the limits in Figure 3.2-1 must be observed except during the low power physics test to deter-mine total control rod worth and shutdown margin.
Por this test the reactor may be critica1 with all full. length control rods fully inserted, except for the predicted moat reactive rod.
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LIMITINd CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.1 E.
Rod Dank Assignment 4,2,1 E.
Rod Dank Assignment Rod bank assignment shall be as Rod bank assignment shall be delineated in Figure 3,2-8, verified after each refueling Except during physics test, the outage', for the refueled unit, sequence of withdrawal of the control banks, when going from zero to 100% power, is A, D, C, D with control bank overlap.
P, Boric Acid System (per unit)
F.
Doric Acid System (per unit) 1 A reactor shall not be taken 1,
Surveillance and testing
.from bot shutdown to hot of the horic acid system standby unless the following shall be performed as conditions exist:
follows:
a, one boric acid tank for a,
Boric acid tank level, that reactor contains at concentration and tem-least 5140 gallons of perature shall be ver-11,5% (but not greater ified prior to start-up than 13%) by weight boric and keekly thereafter, acid solution at a temper-ature of at least 1450F O
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I LINITING CONDITION-FOR OPERATION SURVEILLANCE REQUIREMENT a
3.3. REACTOR COOLANT SYSTEM (per unit) 4.3 REACTOR COOLANT SYSTEM (per unit) 1.
Operational Components 1.
Operational Components A.
Reactor Coolant Leaps and Coolant A.
Reactor Coolant Loops and Coolant Circulation Circulation 1.
a.
All reactor coolant loops shall be OPERATING.
1.
The reactor coolant loops shall be b.
Startup of one inactive verified to be OPERATING and unisolated loop will not be circulating reactor coolant at least performed at levels greater than once per shift.
25%.*
APPLICABILITY: Modes 1 and 2*
ACTION: With less than the above required reactor coolant loops OPERATING, be in at least HOT SHUTDOWN within one hour, i
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At least two of the reactor coolant 2.
a.
The required reactor coolant loops shall be OPERABLE with at pumps, if not in operation, least one of the OPERABLE loops shall be determined to be OPERATING.**
OPERABLE once per week by verifying' correct breaker APPLICABILITY: Mcde 3 alignments and indicated power availability.
ACTION:
a.
With less than the above required b.
At least on;.coling loop shall reactor coolant loops OPERABLE, be verified to be OPERATING and restore the required loops to
' circulating reactor coolant at-l OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or least once per shift.
All reactor coolant pumps may be de-energized for up to one hour provided (1) No operations;are permitted that would cause dilution of the reactor coolant system baron concentration, and (2) Core' outlet temperature is maintained at least.10*F below saturation temperature.
See Special Test Exception 3.23.1 5
-This power level is contingent upon the results of inactive loop startup tests performed under: carefully-controlled conditions.
If the results of these tests indicate that startup can only be safely' performed from-a lower power level, the value.of 25% will be replaced with this new power level. Startup'of an inactive. loop -
l will not be performed on a routine basis until the controlled startup tests are evaluated.
u LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.1.A.2 be in FUT SHUTDOWN and Tavg < 350'F, 4.3.1.A.2 within the next twelve hours, b.
With no reactor coolant loop in operation suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediate)y initiate corrective action to return the required coolant loop to operation.
3.
At least two of the six heat removal 3.
a.
The required reactor coolant pump (s),
loops (four reactor coolant loops
- and if not OPERATING, shall be determined two residual heat removal loops) shall be to be OPERAdLE once per week by OPGRABLE. At least one of these loops verifying correct breaker alignments shall be OPERATING **
and indicated power availability.
APPLICABILITY: Mode 4 b.
The required steam generator (s) shall be determined OPERABLE by verifying ACTION:
secondary side wide range water.'2Vei to be greater than or equal tu 174 at a.
With less than the above required least once per shift.
loops OPERABLE, immediately initiate corrective action to return two loops c.
At least one heat removal loop shall to OPERABLE status as soon as be verified to be in operation and possible; be in COLD SHUTDOWN within circulating reactor coolant at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, once per shift.
See Section 3.3.2.C for low temperature overpressure protection considerations before starting a reactor coolant pump.
All reactor coolant pumps and decay heat removal pumps may be de-energized for up to one hour pro-vided: 1) No operations are permitted that would cause dilution of the reactor coolant system baron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.
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LIMITIFG CONDITION FOR OPERATION SURVEIIJRICE RBDUIRDIENT 3.3.1.A.3 b.
With no heat removal loop in operation:
4.3.1.A.3 l) suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and; 2) immediately initiate corrective action to return the required heat removal loop to operation.
3.3.1.A.4 Two residual heat removal (Rim) loops shall 4.3.1.A.4 a.
The residual heat removal loop shall be OPERABLE.* At least one of these te determined to be in operation and loops shall be OPERATItE. However, the circulating reactor coolant at least requirement for an OPERATIIG RIB loop may 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 RIR loop in operation the core coolant sys.em 'coron concentration are in exit temperature shall be nonitored progress or initiated, and b) the core outlet utilizing data fran 2 or more core temperature as measured by the core exit thermo-exit thermocouples. The fregaency 0
couples is kept at least 10 F below saturation of temperature readinas shall be temperature.
adequate to insure that the te:rperatt e will not increase above ~ the 104 APPLICABILITY: Fiode 5 Subcooling limit between temperature reading @
ACPION:
a.
With only one of the above required loopa OPERABLE, immediately initiate corrective action to return the inoperable loop to OPEPNU.E status as soon as possible.
b.
With no RIE loop OPERABLE:
- 1) suspend all operations involving a reduction in boron cercentration of the Reactor Coolant System and;
- 2) inmediately initiate corrective action to return both RIR loops to OPEPABLE status, or cperation if nececsary, in order to maintain core outlet. temperature at least 10 F below saturation temperature.
c.
The provisions of Specification 3.0.3 are not applicable.
One RC loop capable of natural circulation may be substitattd for on OPERABLE Rim loop.
o An RIR loop tray still be considered OPERABLE with only one of either the normal or emergency power sources OPERABLE.
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m LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.1.8 Steam Generators 4.3.1.B.
1.
All steam generators shall be Each steam generator shall be demonstrated OPERABLE as defined in Section OPERABLE by performance of the following 4.3.1.B.
augumented inservice inspection program and the requirements of Specification 4.3.4.
APPLICABILITY: Modes 1, 2, 3, and 4 1.
Steam Generator Sample Selection and ACTION:
With one or more steam generators Inspection inoperable, restore the inaperable generator (s) to OPERABLE status prior Each steam generator shall be determined to increasing Tavg above 200'F.
OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.3.B-1.
2.
Steam Generator Tube Sample Selection and Inspection The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.3.B-2.
The inservice inspection of steam generatar tubes shall be performed at the f requencies specified in Specification 4.3.1.B.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Speclification 4.3.1.B.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be stalected on a random basis except:
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O LI!41TINd C0NDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.3.1.B.2 a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes in-spected shall be from these critical areas.
b.
The first sample inspection,during each inser-vice inspection (subsequent to the preservice inspection) of each steam generator shall in-clude:
1 All nonplugged tubes that previously had detegtable wall penetrations ()20%) and 2
Tubes in those areas where experience has indicated potential problems.
s c., The s'econd and third sample inspections during each insenvice inspectidn may be less than a full tube inspection by concentrating the in-spection on those areas of the tube shbet array and on those portions of the tubes where tubes with imperfections were previously found, d.
The tube inspection shall be conducted accord-ing to 4.3.1.B.4.A.8.If a tube does not permit the passage of the eddy current inspection probe the entire length and through the U-bend; this shall be recorded and an adjacent tube shall be inspected.
The tube which did not allow pas-sage of the eddy current probe shall be consid-ered degraded..
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Bases:
3.3.1 Operational Components During Mode 5, four filled and intact reactor coolant loops may be substituted for an GPERABLE 4.3.1 The plant is designed to operate with all RFH loop in order to provide a passive heat sink.
reactor coolant loops in operation and This heat sink is available in the event the maintain DNBR above 1.30 (1) during all normal other RFR loop becomes inoperable. One reactor operations and anticipated transients.
In coolant loop capable of providing natural MODES 1 and 2 with one reactor coolant loop circulation may also be substituted for an not in operation this specification reauires OPERABLE RHR loop. At least one RHR loop must that the plant be in at least HOT SFUTDOWN be OPERABLE at all times.
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 RtB pump may be relaxed to require two RFH 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 RfC loop provides sufficient heat tion.
If it becomes necessary to interrupt removal capability for removing decay heat; forced coolant flow for testing, maintenance, out single failure considerations require or any other reason, the Technical that at least two loops be OPERABLE.
Specification will assure that the onset of Thus, if the reactor coolant loops are not potential boiling can be detected and core OPERABLE, this specification reauires cooling initiated before boiling occurs.
The two RtR loops to be OPERABLE.
rate of reactor coolant system heatup witn no forced flow is estimated to be less than 6'F The operation of one Reactor Coolant Pump per minute after i day, 5'F per minute after or one RHR pump provides adequate flow 4 days, and 3'F per minute after 1 month of to ensure mixing, prevent stratification plant shutdown.
Inis estimate is based on no and produce gradual reactivity changes natural circulation flow through the Coolant during boron concentration reductions loops and teactor 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 ano control.
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Bases:
3.3.1 & 4.3.1 (Cont.)
Operation with a primary system safety valve setting of 2485 psig is less than the safety limit of 2735 psig.
(See Bases 1.2 and 2.2).
The requirement for steard bubble formation in the pressurizer when the reactor has passed 1% subcritically will ensure that the Reactor Coolant System will not be solid when criti-cally is achieved.
The reactor coolant loop isolation valve specifications will insure that adequate cooling is available for the reactor when the residual heat removal system is not in d
operation. The requirements relating to baron concentration and startup of an iso-lated loop will ensure that no reactivity insertion takes place when the loop stop valves are opened. (2)
Startup of a loop will inject cool water into the core which will result in a power spike. Limiting the power to 25% at the time of startup of a loop will minimize the effect the cool water will have on the core. (2)
When the reactor coolant loop isolation valve interlocks are bypassed and the unit is in the COLD SHUTDOWN mode, the specification for refilling a drained and isolated loop ensures that proper boron concentration is maintained.
References:
(1) FSAR Section 14.1.6 (2) FSAR Section 14.1.7 78
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'lp LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENP 3.13.2.A 1.
Operating with ventilation flow 4.13.2.A 1.
Observe and document shiftly that 3 l:
through the IIEPA and charcoal filters the ventilation system is OPERATING 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.
l' 2.
Operable with automatic initiation of 2.
When operability is required by flow through the !! EPA filters,and Specification 3.13.2.A.2, the
- 4 charcoal adsorbers upon detection of following shall be done at least
'I 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 Mode for a minimum
- j irradiation ceased.
If automatic of 15 minutes, 2)
Verify flow througg actuation is inoperable, the system the !! EPA and charcoal adsorber train, shall be manually placed in the 3)
Verify the Fuel Building is
" charcoal adsorber mode".
maintained at % inch of water negativ(
pressure with respect to the atmos-i APPLICABILITY:
All 11 odes phere.
ACTION:
With the requirements of 3.13.2.A not satisfied, suspend all irra-diated fuel movements or crane operatior with loads over irra-diated fuel after first, if applicable, placing loads in a safe condition.
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i, LIl41 TING CONDITION FOR 0?ERATION SURVEILI.ANCE REQUIREMENT 3.13.2, B.
Ventilation filters for the fuel building 4.13.2i B.
Ebr each IIEPA or charcoal filter, at least once incitaling charcoal adsorbers and the auto-I per 18 nonths or (1) after every 720 leurs of matic actuation of the charcoal filter system charcoal adsorber operation or (2) after any shall be periodically tested.
structural maintenance of the filter housirvja -
I or (3) following painting, fire, or chemical I
release in any ventilation zone conmanicating with the system, or (4) after each emplete or partial replacement of the filter bank, i
surveillance will be performed per Table 4.17-1,
)
1 Verify that on a high radiation test signal the system autcznatically starts (unless already in operation) and directs its I
exhaust floe through the ifEPA f11ters and I
charcoal ad wrber banks. If autcrnatic actuation is inoperable the system shall l
be mapually placed in the charcoal adsorber
.i mode.
3.13.3 containment status 4.13.3' ;Cbntairrrent status A. Daring refuelirn operations contai:r.ent integrity A.
Contairrrent door status shall be verified once (See section 1.0.C) shall be maintained as a shift, specified in section 3.9.5 except as specified in 3.13.3.B.
B. 'Ihe equipnent hatch or both doors on the B.
Reactor coolant toron concentration and Tavg i
personnel hatch tray be opened ducirg the re-shall be verified once a shift when the equipnen i
fueling operation prcuided the shutdown margin hatch is open or both doors on the personnel is maintained equal to or greater than 10%
hatch are open.
AK/K and Tavg is maintained at or less than 140 F.
245 i
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LIMITING C0f0ITION FOR OPERATION SURVEILLANCE REQUIREMENT i
i 9.
Residual Heat Remo.al System Operation
- 9. Residual Heat Removal System Operation A.
Two independent Residual Heat Removal A.
1.
The required Residual Heat Removal (R$) loops shall be OPERABLE + with at loops shall be determinec OPERABLE least one loop operating.
per Specification 4.8.3.A.1.
APPLICABILITY:
Mode 6 when the water level above 2.
At least one Residual Heat Removal the top of the reactor pressure Loop shall be verified to be vessel flange is less than 22 feet.
OPERATING and circulating reactor coolant at least once per snift.
- The normal or emergency power source may be inoperable for each R $ loop.
2473 m.
j
r LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.13 9. A.
4.13 9. A.
ACTION:
a.
With less than the required RHR loops OPERASLE, immediately initiate corrective action to. return the required RHR loops to OPERABLE status as soon as possible.
b.
With no residual heat removal loop in operation, suspend all operatfons that would causo a decrease in decay heat removal capabilities or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access f rom l
the containment atmosphere to the outside
{
atmosphere within four hours.
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B.
At least one residual heat renioval (RHR)
I, B.
At least one Residual Heat Removal loop loop shall be OP3 RATING.
{
shall be verified to be OPERATING and I
circulating reactor coolant at least APPLICABILITY:
Mode 6 when the water level above i
once per shift.
the top of the reactor pressure veesel flange is greater than 22 f t.
ACTION:
a.
With no residual heat removal loop in j
operation, except as provided -in b.
below, suspend all operations that would cause a decrease in decay heat removal capabilities or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside attrsphere within four hours.
247b 1.
']
. LIMITING C0tOITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.13 9.B.
4 13 9 B-b.
The residual heat removal loop may be removed from operation for up to one hour per an eight-hour period during the performance of CORE ALTERATIONS.
c.
The provisions of Specification 3.0.3 are not applicable.
I'
- 10. Tne provisions of Specification 3.0.3 are not
- 10. Not applicable, applicable to Setion 3.13.
l.
247c l
I
Bases:
3.13 The restriction on shutdown margin insures adequate The verification of fuel handling system interlocks core protection that no inadvertent return to prior to refueling operation provides assurance that criticality could occur through control rod an unsafe operating condition will not be approved.
removal.
(1)
(1).
Two source range neutron monitors continuously The fuel inspection program is intenced to provioe measuring neutron flux during fuel movements information on anomalous conditions of the fuel resulting from power operation.
The results of the provides the operators with innediate redundant visual examinations and the tests for faileo fuel indication of an unsafe condition. Whenever changes are not being made in the core geometry, will be reviewed as a basis for determining the one flux monitor is sufficient.
This permits requirements for further off-site destructive fuel maintenance on the instrumentation.
Examinations. FSAR Section 3 2.3.5 provioes further Jiscussion of the fuel inspection program.
The fuel handling accident assumes that the first fuel assembly is moved 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after initial reactor shutdown.
(2)
Direct communication between the control room and the containment allows for immediate notification of any impending unsafe condition.
The presence of a licensed fuel handling foreman or senior reactor operator at the refueling cavity provides qualified supervision on the refueling
~
The requirement that at least one residual heat operation during changes in core geometry.
removal (RHt) loop be in operation ensures tnat (a)
The charcoal filters in the ventilation train from sufficient cooling capacity is available to remove the fuel building insure that site boundary doses decay heat and maintain the water in tne reactor will be below 10 CFR 100 limits assuming all rods pressure vessel below 140'F as required curing the on a dropped fuel assembly break during a REFUELING MODE, and (b) sufficient coolant postulated fuel assembly break during a nostulated circulation is maintained through the reactor Core to fuel drop accident.
(3) The containmen, fuel minimize the effect of a baron dilution incioent and building, and radiation monitoring requirt 'ents prevent boron stratification.
insure the capability to isolate these areas frem the environment in the event of an activity release The requirement to have two RH1 loops OPERABLE when there is less than 22 feet of water above the flange from the fuel.
ensures that a single failure of the operating drH loop will not result in a complete loss of resioual heat removal capability. With the reactor vessel head removed and 22 feet of water above the flange a (1) FSAR, Section 9.7.2 (2) FSAR, Section 14.2.1.2 large heat sink is available for core cooling. Thus, in the event of a failure of the operating RH1 loop, (3) FSAR, Section 14.2.1.5 adequate time is providea to initiate emergency 248 procedures to cool the core.
i
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i:
SURVEILLANCE REQUIREMENP LIMITING CONDITION FOR OPERATION i
4.23 Special Test Exceptions t
i 3.23 Special Test Exceptions o
N 1.
The limitations of Specification 3.3.1.A.1 1.a.1 The TilERMAL POWER shall be determined to be less than P-7 Interlock Setpoint
,[
may be suspended during the performance at least once per hour during start up of start up tests and PilYSICS TESTS tests and PIlYSICS TESTS.
ja provided:
l i.
The TilERMAL POWER does not exceed the 1.b.2 Each Intermediate, Power Range Channel t
P-7 Interlock Setpoint (Table 3.1-1),
and P-7 Interlock shall be subjected to a CilANNEL FUNCTIONAL TEST within i:
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 OPERABLE Intermediate and Power Range tests or PilYSICS TESTS.
i Channels are set less than or equal to 25% of RATED tiler)JAL POWER.
APPLICABILITY:
During operation bclow the P-7 i
Interlock Setpoint.
ACTION:
Wi th the TilERMAL POWER greater than the P-7 Interlock Setpoint, immedi-ately open the reactor trip breakers.
e f
e d
295 AB
i Bases:
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3.23 Reactor Coolant Loops i
This special test exception permits reac-tor criticality under no flow conditions and is required to perform certain start-up and PHYSICS TESTS while at low TIIERMAL POWER levels.
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3 L
1 295AC
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