ML20043F473
| ML20043F473 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/30/1990 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| GL-87-09, GL-87-9, NUDOCS 9006150049 | |
| Download: ML20043F473 (13) | |
Text
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N Comm nw:alth Edison r',1400 Opus PI:ce i
j Downers Grove, Illinois 60515
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May 30, 1990 Dr.-Thomas E. Murley Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Attn.: Document Control Desk
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Supplement to Application for Amendment to Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77, Appendix A, Technical Specifications NRC Docket Mos. 50-454. 50-455. 50-456 and 50-457
References:
(a) Nov ': er 30, 1988, S.C. Ilunsader letter to
. E. Murley (b) Lay 15, 1989 L.N. 01shan letter to T. J. Kovach
Dear Dr. Muricy:
In reference (a) pursuant to 10 CFR 50.90, Commonwealth Edison (Edison) proposed.to amend Appendix A, Technical Specifications, of Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77.
The proposed amendment requested a change to Technical Specifications 3.0.4, 4.0.3 and 4.0.4 and the Technical Specifications that are affected by these sections.
The changes were requested and made per the requirements of Generic Letter 87-09, to remove unnecessary restrictions on operational mode changes and to prevent unnecessary plant shutdowns when surveillance intervals have been inadvertently exceeded.
In reference (b), the NRC staf f made the following two (2) requests:
1)
"In order for the NRC staff to conclude that the safety basis...is satisfied, we request that for each proposed Technical Specification exception to be granted under Generic Letter 87-09, you affirm that remedial measures prescribed for the affected ACTION STATEMENTS are consistent with the Updated Safety Analysis Report and its supporting safety analyses."
2)
"In addition, we request that you identify and affirm those procedures, management directives, on-site safety reviews, etc. that have been established to limit the use of the Specification 3.0.4 exceptions granted.
Your affirmation should address training necessary for ensuring that plant operators are made aware of, and are instructed to exercise, the controls promulgated in limiting the use of such exceptions."
9006150049 900530 AMl PDR ADOCK 05000454 VVf P
PDC f ({t
Dr. T.E. Murley-May 30, 1990 In regards to Request # 1, Edison has divided the Byron and Braidwood Station Technical Specifications into four (4) categories.
In the first category are those specifications that currently contain a 3.0.4 not applicable statement.
For these specifications transition to a higher mode of applicability is currently allowed, and no supplemental information is being supplied. The change to these specifications is purely administrative. Thesc spec 3fications are listed in Attachment A.
The annond category contains those specifications that currently do not contain a 3.0.4 not applicable statement which, under the proposed revision to the Technical Specifications, would allow the transition into a higher mode of-applicability while operating within the action statement.
Attachment B contains a listing of these Specifications; a brief discussion of the bases for the specification; a statement of compliance with the safety analyses: and supportive information.
The third category consists of those Technical Specifications that:
a, contain actions that either restore the limiting condition for operation or effectively exit the plant from the mode of applicability, or b.
have been reviewed and found that the safety analyses may not be bounding, or could result in a reduction in the margin of safety.
Edison believes that intent of Generic Letter 87-09 does not allow for a mode change while actions are being taken in accordance with this third category of specifications. Administrative actions will be taken at Byron and Braidwood Stations to preclude transition to a higher mode if the plant is operating within the action statement for these specifications.
These specifications are listed in Attachment C.
The fourth category of Technical Specifications includes those that have shutdown requirements. The restrictions of Specification 3.0.4 will apply to all of these Technical Specifications unless otherwise stated.
Con:pliance with Technical Specification action statements are tracked through operating surveillance procedures.
These procedures reflect the requirements of the action statements.
In these procedures there currently is a statement outlining the applicability of Specification 3.0.4.
These procedures will be revised to state that for the specification contained in Attachment B, transition to a higher mode may be allowed.
These procedures will also be revised to state that, for the specifications contained in Attachment C, transition to a higher mode of applicability will be prohibited while operating within the action statement.
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l' 3 -
May 30, 1990 l
Dr. T.E. Murley i
i In regards to Request #2, the proposed Technical Specification bases for Specification 3.0.4 state: "The provisions of this specification would not, however, be interpreted as endorsing the failure to exercise i
good practice in restoring systems or components to OPERABLE status before-plant startup." In addition to this, the following actions will be taken j
to promote this philosophy:
The Station " Conduct of Operations" procedure will be revised to provide guidance to operations personnel on the l
importance of maintaining all equipment important to safety in an operable condition.
Licensed operator training programs will be revised to reinforce the importance of maintaining equipment in an operable status whenever the equipment is required to be in an operable state per the Technical Specifications, j
Edison is notifying the State of Illinois of this supplement to the application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.
Please direct any questions you may have concerning this submittal to this office.
Very truly yours, 0
S.C. Ilunsader Nuclear Licensing Administrator
/sc1:1037T:1-3 Attachments: A) Tech Spec's that contain a 3.0.4 not applicable statement.
B) Tech Spec's that do not contain a 3.0.4 not applicable statement C) Tech Spec's that do not require unit shutdown for all l
conditions l
Enclosures:
Reference (a), November 30, 1988, S.C. Ilunsader letter to T.E. Murley Reference (b), May 15, 1989 L.N. 01shan letter to T.J. Kovach cc:
Resident Inspector-Byron Resident Inspector-Braidwood P.C. Shemanski-NRR S.P. Sands-NRR W. Shafer-RIII M.C. Parker-IDNS
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ATTACHMENT A j
TECHNICAL GPECIFICATIONS THAT CONTAIN A 3.0.4 NOT APPLICABLE STATEMENT FACILITY OPERATING LICENSES NfF-37. NPF-66._HEF-72. AND NPF-77 The following Technical Specifications contain a statement that the provisions of Specification 3.0.4 are not applicable.
For these specifications transition into a higher mode of applicability is currently allowed.
The change to these specifications is purely administrative.
Specification Number Description 3.1.1.3 Moderator Temperature coef ficient, Actiori a.
I 3.2.4 Quadrant Power Tilt Ratio.
-j 3.3.1 Reactor Trip System Instrumantation. Table 3.3-1 Items 2.a. 2.b. 3, 4, 7, 8, 9, 10, 11, 12.a 12.b. 13, 14, 15, 16.a. 16.b, 18.
I 3.3.2 Engineered Safety Features Actuation System Instrumentation. Table 3.3-3 Items 1.c, 1.d, i.e, 4.c, 4.d, 4.e, 5.b, 6.c.1, 6.c.2, 6.d, 6.f. 6.g, 8.a.
8.b.
3.3.3.2 Movable Incore Detectors.
3.3.3.3 Seismic Instrumentation.
3.3.'3.4 Meteorological Instrwnentation.
3.3.3.8 Loose-Part Detection System.
3.3.3.9 Radioactive Liquid Effluent Monitoring Instrumentation.
3.3.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation.
3.3.3.11 High Energy Line Break Isolation Sensors.
3.7.9 Sealed Source Contamination.
3.9.7 Crane Travel - Spent Fuel Storage Facility.
3.9.9 Containment Purge Isolation System.
3.9.11 Water Level - Storage Pool.
3.9.12 Fuel Handling Building Exhaust Filter Plenums.
3.11.1.1 Liquid Effluents.
3.11.1.2 Dose.
3.11.1.3 Liquid Radwaste Treatment System.
3.11.1.4 Liquid Holdup Tanks.
3.11.2.1 Gaseous Effluents.
3.11.2.2 Dose-Noble Gases.
3.11.2.3 Dose - Iodine-131 and 133, Tritium, and Radioactive Material'in Particulate Form.
3.11.2.4 Gasesous Radwaste Treatment System.
3.11.2.5 Explosive -Gas Mixture.
3.11.2.6 Gas Decay Tanks.
3.11.3 Solid Radioactive Wastes.
3.11.4 Total Dose.
3.12.1 Monitoring Program.
3.12.2 Land Use Census.
3.12.3 Interlaboratory comparison Program.
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ATTACHMENT B TECHNICAL SPECIFICATIONS THAT DO NOT CONTAIN A 3.0.4 NOT APPLICABLE STATEMENT EACILITY OPEIATING_ LICENSES NPF-37. NPF-ffuliRF-72 AND_NPF-7Z The following Technical Specifications dn_not currently contain a 3.0.4 not applicable statement. For these Technical Specifications, the proposed change would allow transition into higher modes while operating within the associated action statements. A discussion of the bases and a statement of compliance with the safety analysis for each specification is included below.
LLLLEnlLlens11Lahutdown_and_c.ontr.oLrodsmantion_c Full length shutdown and control rods ensure that acceptable power distributions are maintained, shutdown margin is maintained, and the potential effects of a rod misalignment on associated accident analyses are limited.
The proposed change to the Technical Specifications will allow transition from Mode 3 up to and including Mode 1 while operating w3 thin the prescribed action statement.
By following Action Statement c for this specification, one of three different actions could be taken:
- 1) The first action is to restore the affected control rod to operable status.
- 2) The second is to declare the affected rod inoperable, align the remaining rods in the affected group to the inoperable rod's position, and restrict power in accordance with rod group position.
- 3) The third is to declare the affected rod inoperable; ensure that the appropriate shutdown margin requirements are met; reduce thermal power to less than or equal to 75% power; reduce the high flux neutron trips to less than or equal to 85% power; perform a flux map to ensure that all peaking factors are within their required values; and perform a reevaluation of several accident analyses to ensure these analyses remain valid.
l These cetions will either restore compliance with the limiting condition for operation, or in the second and third actions, the affected rod must be maintained in a trippable condition, while ensuring that all peaking factors are within the bounding limits assumed in the accident analysis.
Therefore, transition from Mode 3 up to and including Mode I will still be bounded by the accident analysis and there is no reduction in the margin of safety.
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LM.4 Rod drop _timea. Action b.
Maximum rod drop times are specified to assure compliance with the assumptions made in accident analysis. The proposed change to the Technical Specifications will allow transition from Mode 3 up to and including Mode 1 while operating within the prescribed action statement.
By following the
. action statement for this specification, thermal power will be limited to 66%
if the rod drop times are within limits but determined with three reactor coolant pumps in operation.
Byron and Braidwood are not currently licensed j
for three-loop operation, and cannot envision any situation which would render the application of this action a viable option.
Should such circumstances arise, the rod drop times would be within limits and a conservative power restriction applied to ensure the integrity of the accident analyses results.
3.1.315 Shutdown Rod Insertion Limit The shutdown rod insertion limit ensures that acceptable power distributions are maintained, shutdown margin is maintained, and the potential effects of a rod misalignment on associated accident analyses _are limited. The proposed change to the Technical Specifications will allow transition from Mode 2 with a Keff of less than 1 up to and including Mode 1 while operating within the prescribed action statement. The associated action statement allows I hour to restore a single shutdown tod to the fully withdrawn position.
This action would place the unit in compliance with its LCO. The second option would be to declare the control rod inoperable and apply Specification 3.1.3.1.
The actions associated with Specification 3.1.3.1 permit limited variations from these requirements by imposing additional restrictions which ensure that the original thermal design criteria is met.
These additional restrictions consist of measuring peaking factors, restricting reactor power level, and reevaluation of those safety analyses impacted by a misaligned control rod.
These actions are described above.
By following the action statements for this specification, transition from Mode 2 with Keff less than 1 to Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
M.1 Axial Flux Difference The axial flux difference (AFD) provides assurance that fuel thermal limits are maintained.
The limit established for AFD assures that the upper bounding envelope for FQ(Z), the Fg Limit times the normalized axial peaking factor, is not exceeded during normal operation and xenon :edistribution following power changes.
The proposed change to the Technical Specifications will allow transition from Mode 1 less than or equal to 15% power to Mode 1 greater than 15% power while operating within the prescribed action statement.
By following the action statement for this specification, power level would be
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rcstricted by tha cetion stattments.which maintcin tha powar distribution within analyzed limits. Based on complying with the prescribed action statements, transition from Mode 1 less than or equal to 15% power to Mode 1 greater than 15% power will still be bounded by the accident analyses and there is no reduction in the margin of safety.
3.2.2 Heat Elux Hot Channel Factor - FO(Z)
The limits placed on FQ(Z) assure that the rainimum DNBR limits, the-design limits for peak local power density, and the 10CFR 50.46 peak cladding temperature of 2200 degrees farenheit are not exceeded.
The proposed change to the Technical Specifications will allow transition into Mode 1 while operating within the prescribed action statement.
By following the action statement for this specification, FQ(Z) will be maintained within acceptable limits through the application of power restrictions.
In addition, the Over-Power Delta Temperature trip setpoints will be reduced to ensure the FQ(Z) limits are not exceeded.
By performing the required actions the margin of safety is maintained, and transition into Mode 1 will still be bounded by the accident analyses.
LLl_ Reactor Trip System InstrumentatiRD Action 8 of Table 3.3-1 is applicable to the following five Reactor Trip System Interlocks:
- 1) P-6: With increasing reactor power the P-6 interlock:
permits manual blocking of the Source Range Instrument liigh Flux Trip, allows manual de-energization of the Source Range Monitors, provides automatic backup blocking of the Boron Dilution Protection logic, and ensures proper overlap is obtained with the Intermediate Range Monitors prior to the source range being blocked. With decreasing reactor power, the P-6 interlock automatically reenergizes the Source Range neutron monitors.
The proposed change to the Technical Specifications will allow transition from mode 3 into mode 2 up to the P-6 setpoint. The action statement for this specification requires that the P-6 interlock function be determined to be in its required state. This action will assure the proper operation of required protective features, hence transition from mode 3 to mode 2 up to the P-6 setpoint will still be bounded by the accident analysis and there is no reduction in the margin of safety.
- 1) P-7: With increasing reactor power, the P-7 interlock automatically enables Reactor trips on:
low flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant bus undervolta6e and underfrequency, pressurizer low pressure, and pressurizer high level.
Below the P-7 interlock, these trips are automatically blocked to l
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cllow for plant cooldown cnd dspraccurization. Th3 propo:cd chtngs to the Technical Specifications will allow transition from Mode 2 to 1 while operating within the prescribed action statement.
The action statement for this specification requires that the P-7 interlock f unction to be deterhilned to be in its required state. This action will-assure the proper operation of required protective features, hence transition from Mode 2 to 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
- 3) P-8: With increasing power the P-8 interlock enables automatic Reactor trips from Turbine trip and low reactor coolant pump flow in any single loop.
-The propose (change to the Technical Specifications will allow transition from Mode 2 to 1 $ tile operating within the prescribed action statement. The action statement for this specification requires that the P-8 interlock function be determined to be in its required state.
This action will assure the proper operation of required protective features, and therefore transition from Mode 2 to Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
- 4) P-1D: With-increasing power the P-10 interlock allows manual blocking of the Power Range Low Setpoint and Intermediate Range Reactor Trips and rod stops.
In addition, the P-10 interlock automatically de-energizes the high voltage power supply for the Source Range detectors and provides a backup Source Range Reactor Trip block signal.
The proposed change to the Technical Specifications will allow transition from Mode 3 up to and including Mode 1 while operating within the prescribed action statement.
The action statement for this specification requires that the F-10 interlock function be determined to be in its required state. This action will assure the proper operation of required protective features, so the transition from Mode 3 up to and including Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
- 5) P-13: The P-13 interlock senses the high pressure turbine first stage impulse pressure greater than or equal to 10% turbine load to provide input into the P-7 interlock. The actions associated with the P-13 interlock are identical to those required for P-7.
As such, the justification given for P-7 is directly applicable to P-13.
l.
3.3.2 Engineered Safety Features Actuation System Instrumentation 1
Action 16 of Table 3.3-3 will effect RWST level - low-low coincident with i
Safety Injection, and Containment Pressure-fligh-3.
Both of these functions i
contain 4 channels. Neither the RWST level low-low or the Containment l
Pressure-High-3 provide input to any controlling functions.
Because they provide no controlling functions, sufficient redundancy will be maintained to insure that required actuations will occur.
l l
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Th3 propoa d ch:nga to th] TechnicIl Sp3cifiestions will allow transition from Mode 5 up to and including Mode 1, while operating within the prescribed action statement for these functions. Based on the above discussions, it can
'be concluded that the accident analyses will still be bounding, and there is no significant reduction in the margin of safety.
Action 17 of Table 3.3-3 is associated with the Containment Ventilation Isolation Actuation Logic and Relays. The purpose of this specification is to ensure that a containment vent isolation will be initiated if radiation levels in the containment reach the setpoint.
The proposed change to the Technical Specifications will allow transition from Mode 5 to and including Mode 1 while operating within the prescribed action statement.
By following tt.e action statement for this specification, all containment ventilation purge supply and exhaust isolation valves would be closed.
With the valves placed in the closed position, Containment Ventilation is in its required position.
Therefore, the isolation function is no longer needed and the. transition f rom Mode 5 up to and including Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
Action 20 of Table 3.3-3 is applicable to 3 Engineered Safety Function Interlocks:
- 1) The P-11 interlock permits normal unit cooldown and depressurization without actuation of a safety injection or main steamline isolation.
P-11 also enables the main steamline isolation on high depressurization rate.
P-11 is manually blocked by the operators during cooldown and depressurization, and is automatically instated during heatup and pressurization. The proposed change to the Technical Specifications will allow transition from Mode 4 up to and including Mode 1 while operating within the prescribed action statement.
By following the action statement for this specification, the P-11 interlock function will be placed into its required state thus assuring proper operation of the associated Safety Injection and Main Steamline Isolation functions.
With these functions placed into their required state, transition from Mode 4
'up to and including Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
- 2) With increasing reactor coolant temperature, P-12 provides an automatic arming signal to enable normal steam dump system operation. With decreasing reactor coolant temperature the P-12 interlock removes the steam dump arming l
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sign:1'in ordtr to prIv:nt cxesssiva ructor systcm cooldown. With temperature less than the F-12 setpoint. tiiree or ths *welve steam dump valves can be manually. armed to allow for nckmal reactor coolant a,p tem cooldown.
The proposed change to the Technical Specifications will allow transition from Mode 4 up to and including Mode 1 while operating within the prescribed action-statement.
The action statement for this specification requires the P-12 interlock function to be determined to be in its required state. This action i
will assure the proper operation of required features, hence the trat.sition l
from Mode 4 up to and including Mode 1 will still be bounded by the accident t
analyses and there is no reduction in the margin of safety.
- 3) The P-14 interlock is actuated whenever any 2 out of 4 level transmitters i
on any 1 of the 4 steam generators er.ceeds the F-14 level setpoint. The F-14 interlock will automatically close all feedwater and feedwater flow control l
valves to all steam generators.
In addition, all main feedwater pumps will receive a trip signal (startup feedwater pump excluded).
This interlock will
{
remain in effect until the condition is cleared and the reactor trip breakers
]
are closed. Turbine trip and feedwater isolation logic is addressed as
]
Functional Unit 5 in Table 3.3-3 of the Byron and Braidwood Technical Specifications. This specification ensures that the minimum number of steam generator level transmitters and bistable loops are available to provide the necessary protective functions.
The action statement associated with Functional Unit 5 requires a minimum of 3 out of the 4 loops to be operable, I
and currently contains a 3.0.4 not applicable statement.
The proposed change to the Technical Specifications will allow transition from Mode 3 up to and including Mode 1 while operating within the prescribed action statement.
The action statement for this specification requires the F-14 interlock function to be determined to be in its required state.
These actions will assure the proper operation of required protective features, and so the transition from Mode 3 up to and including Mode 1 will still be bounded by the accident analyses and there is no reduction in the margin of safety.
L3.4 Turbine Overspeed Protection The purpose of the overspeed protection system is to protect the turbine from excessive overspeed conditions that could result in missiles being generated.
The proposed change to the Technical Specifications will allow transition from Mode 4 up to and including Mode 1 while operating within the prescribed action statement. By following the action statement for this specification, the steam supply to any affected component would be isolated.
By isolating the affected component from its steam supply, the motive force for an overspeed event emanating from the failed component would be eliminated.
This method of operation results in no reduction in the margin of safety, and would still be bounded by the safety analyses.
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3.4.1'.5.2 Loop Isolation Jalyga
'The purpose of this specification is to ensure that no reactivity addition
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events occur due to the opening of these valves and subsequent startup of an isolated reactor coolant loop. This event is precluded by ensuring that boron concentration and temperatures are within acceptable limits prior to opening either of the loop stop valves. The proposed change to the Technical Specifications will allow transition from Mode 6 to 5 while operating within the prescribed action statement. This action statement precludes the opening of the loop stop valves unless boron and temperature limits are met.
By following the action statement for this specification, transition from Mode 6 to 5 will not result in a reduction in the margin of safety.
3.4.2.1 RCS Safety Valysa The purpose of this specification is to provide relief capacity sufficient to mitigate an overpressure event that could occur during shutdown periode. The proposed change to the Technical Specifications will allow transition from Mode 5 to 4 while operating within the prescribed action statement. The action statement requires immediate suspension of operations involving positive reactivity changes, and placing an operable RHR loop in the shutdown cooling mode of operation.
Low temperature overpressure protection is required by Technical Specification 3.4.9.3, and Byron /Braidwood utilize either the pressurizer PORVs or RH suction relief valves to fulfill this requirement. Additionally, controls are in place which prevent an overpressure transient due to mass addition and energy addition. With these requirements in place, an overpressure transient of sufficient magnitude to challenge the safety valves is precluded.
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ATTAC11 MENT C TECHNICAL SPECIFICATION THAT DO NOT REQUIRE UNIT SHUTDOWN FOR ALL CONDITIONS FAClLIIL0f1RAllN9_ItLCFESEJEE-3LJEE-fi. NPF-72 AND NEf-21 t
The following is a listing of the Technical Specifications that house action statements that do not directly requir.q_a unit shutdown for al) conditions, but either restore the limiting condition for operation; effectively exit the l
plant from the mode of applicability; or preclude mode ascension. Mode ascension for some of the following Technical Specifications would be non-conservative with respect to the safety analysis and might lead to a decrease in the margin of safety.
As such, at the Byron and Braidwood Stations ascension into a higher mode of f
applicability will not occur while operating within the action statements associated with these-specifications.
Specification Numbgr hescription i
3.1.1.1 Shutdown Margin - Tavg > 200 F 3.1.1.2 Shutdown Margin - Tavg < 200 F 1
3.1.2.1 Boration Flowpath - Shutdown 3.1.2.3 Charging Pump - Shutdown 3.1.2.5 Borated Water Sources - Shutdown 3.1.3.2 Position Indication Systems - Operating 3.1.3.3 Position Indication Systems - Shutdown 3.1.3.6 Control Rod Insertion Limits 1
3.2.3 RCS Flow an6 Enthalpy Rise
)
3.2.5 DNB Parameters
.i 3.3.1 Reactor Trip System Instrumentation, Actions 3, 4, and s
10 3.4.1.2 Reactor Coolant System - Hot Standby 3.4.1.4.1 Reactor Coolant Gystem - Cold Shutdown - Loops Filled 3.4.1.4.2 Reactor Coolant System - Cold Shutdown - Loops Not Filled 3.4.5 Steam Generators 3.4.7 Reactor Coolant System Chemistry 3.4.9.1 Reactor Coolant System Pressure / Temperature Limits 3.4.9.2 Pressurizer Pressure / Temperature Limits 3.7.2 Steam Generator Pressure / Temperature Limits 3.8.1.2 AC Sources - Shutdown 3.8.2.2 DC Sources - Shutdown 3.8.3.2 Onsite Power Distribution - Shutdown 3.9.1 Refuel Operations - Boron Concentration i
3.9.2 Refuel Operations - Source Range Instrumentation
]
3.9.3 Refuel Operations - Decay Time J
3.9.4 Refuel Operations - Containment Building Penetrations
]
3.9.5 Refuel Operations - Communications l
3.9.6 Refuel Operations - Refueling Machine 3.9.8.1 Refuel Operations - RHR & Coolant Cire. - High Water Level 3.9.8.2 Refuel Operations - RHR & Coolant Cire. - Low Water Level 3.9.10 Refuel Operations - Water Level - Reactor Vessel l
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ENCLOSURE T0-n,
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- SUPPLEMENT TO THE APPLICATION FOR' AMENDMENT TO
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FACILITY OPERATING' LICENSES NPF-37. NPF-66' NPF-72 AND NPF-77 q
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WASHINGTON, D. C. 20666 k.....,o/
May 15, 1989 1
1 Docket Hos. 50-454, 50-455, 50-456, and 50-457 Mr. Thomas J. Kovach a
Nuclear Licensing Manager Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Kovach:
Subject:
REQUEST FOR ADDITIONAL INFORMATION ON THE LICENSEE AMENDMENT APPLICATION UNDER GENERIC LETTER 87-09 FOR BYRON /BRAIDWOOD (TAC NOS. 72042,72043,72044,and72045)
The basis for accepting Specification 3.0.4-related amendments under Generic Letter.87-09 is predicated on two assumptions, namely, (1) that the remedial measures prescribeo by the Technical Specification ACTION STATEMENTS for which the exception will be granted, provide a sufficient level of protection to permit operational mode changes and safe long-term operation consistent with the licensing basis described in the Updated Safety Analysis Report for Byron and Braidwood; ano (2) it will be the exception when plant startup connences with important safety features inoperable, irrespective of the exception granted in response to applications under Generic Letter 87-09.
We have reviewed your license amendment application under. Generic Letter 87-09 submitted by your letter dated November 30, 1988.
In order for the NRC staff to conclude that the safety basis relative to the above stated assumptions is satisfied, we request that for each proposed Technical Specification exception to be granted under Generic Letter 87-09, you affirm that remecial measures prescribed for the affected ACTION STATEMENTS are
- consistent with the Updated Safety Analysis Report and its supporting safety analyses.
In addition, we request that you identify and affirm those procedures, management directives, onsite safety reviews, etc. that have been established to limit the use of the Specification 3.0.4 exceptions grantea.
Your affirmation should address training necessary for ensuring that plant operators are made aware of, and are instructed to exercise, the controls promulgated in limiting the use of such exceptions.
Please advise, within five days after receipt of this letter, when we may expect to receive your response. Should there by any questiens concerning this request, please let me know.
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Mr. Thomas J. Kovach
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The request in this letter affects fewer than ten respondents; therefore, OMB
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clearance is not required under P.L.96-511.
Sincerely, M
/MA v --
Leonard N. 01shan, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects cc:
See next page I
l
l Mr. Thomas J. Kovach Byron /Braidwood Power Station Connonwealth Edison Company Units 1 and 2 CC:
Mr. Jack Tain Dr. Bruce von Zellen Atomic Power Distribution Department of Biological Sciences Westinghouse Electric Corporation Northern Illinois University Post Office Box 355 DeKalb, Illinois 61107 Pittsburgh, Pennsylvania 15230 U. S. Nuclear Regulatory Connission Joseph Gallo, Esq.
Byron / Resident Inspectors Office Hopkins and Sutter 4448 North German Church Road 1050 Connecticut Ave., N.W.
Byron, Illinois 61010 Suite 1250 Washington, D.C. 20036 Ms. Lorraine Creek Rt. 1, Box 182 C. Allen Bock, Esquire Manteno, Illinois 60950 Post Office Box 342 Urbana, Illinois 61801 Mrs. Phillip B. Johnson 1907 Stratford Lane Regional Administrator Rockford, Illinois 61107 U. S. NRC, Region III 799 Roosevelt Road, Bldg. d4 Douglass Cassel, Esq.
Glen Ellyn, Illinois 60137 109 N. Dearborn Street Suite 1300 Ms. Bridget Little Rorem Chicago, Illinois 60602 Appleseed Coordinator 117 North Lincen Street Ms. Pat Morrison Essex, Illinois 60935 913 N Main Street #707 Rockford, Illinois 61103-7058 Mr. Edward R. Crass l
~
Nuclear Safeguards and Licensing David C. Thon.as, Esq.
Division 77 S. Wacker Drive Sargent & Lundy Engineers Chicago, Illinois 60601 55 East Monroe Street Chicago, Illincis 60603 Mr. Charles D. Jones, Director Illinois Emergency Services U. S. Nuclear Regulatory Connission and Disaster Agency Resident Inspectors Office 110 East Adams Street RRil, Box 79 Springfield, Illinois 62706 Bracev111e, Illinois 60407 L
l l
a
1, Mr. Thomas J; Kovach-Byron /Braidwood Commonwealth Edison Company-1; l:
cc:
Mr. Michael C. Parker, Chief Division of Engineering i
Illinoic Department of Nuclear Safety J
- 1035 Outer Park Drive Springfield, Illinois 62704 y
Michael Miller, Esq.
Sidley and Austin One First National Plaza l
Chicago, Illinois 60603 George L. Edgar Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, D.C. 20036 Commonwealth Edison Company 1
Byron' Station Manager i
1 4450 North German Church Road l
Byron, Illinois 61010 y
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Tr i
0 Commonwealth Ed6 son One Fast Nanona! Pia:a. Chcago. llunos K5aTeUT4e3y to PosTOffee Box 7C
~
Chcago. Uhnos 60693 0767 November 30, 1988 Dr. Thomas E. Murley, Director Office of Nucleat Reactor Regulation U.S. Nuclear Regulatory Comission ~
Washington, DC 20$$$
Attnt Document Control Desk Subject Dyron Station Units 1 and 2 Braidwood Station Units 1 and 2 Application for Amendment to racility Operating Licenses Nrr-37, NPT-66.
NPT-72, and NPr-77 Appendis A, Technical Specifications HRC DeclutLitos. 50-41(dd-iE5J.{L-AL6 and %,151 Deat Dr. Murley:
Pursuant to 10 CTR 50.90. Commonwealth Edison proposes to amend Appendis A, Technical Specifications, of racility Operating Licenses NPT-37, NPr-66, NPT-72, and NPF-77.
The proposed amendment requests changes to Technical Specifications 3.0.4, 4.0.3 and 4.0.4, and those Technical Specifications that are affected by these sections. The changes are being requested per the requirements of Generic Letter 87 09, to remove unnecessary restrictions on operational mode changes and to prevent unnecessary plant shutdowns when surveillance intervals have been inadvertently esceeded.
The revised Technical ispecification pages are contained in Attachment A.
The description and summary of the proposed changes is presented in Attachment B.
Attachment C provides the Safety Evaluation and Environmental Assessment.
'Ibe proposed changes have been reviewed and approved by both on-site and off-site review in accordance with Commonwealth Edison procedures.
Commonwealth Edison has reviewed this proposed amendment in accorcance with 10 CTR 50.92(c) and has determined that no significant hazards consideration esista. This eval"r.t.icn is documented in Attachment D.
Commonwealth Edison is notifying the State of Illinois of our application for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.
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'18 HRC N;vember 30,;3988 s
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y In accordance with 10 CFR 170, a fee remittance in the amount of
$150.00 is enclosed.
ll Please direct any questions you may have concerning this matter to-f a
this office.
t
_ Very truly yours, f,
3 4
l'
(
S. C. Hunsader Nuclear Licensing Aeministrator lU l
cs F
Enclosures-Fee Remittance L
Attachmes.ts (A): Proposed Technical Specification Changes (B): Iescription and Summary (C):- Safety Evaluation and Environmental Assesament l
t (D): Evaluation of Slgnificant Hasards Consideration t
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cci Resident Inspector - Byron-1
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Resident Inspector - Braldwood s
S. Sands - NRR Region 111 Office M. C. Parker - State of Ill.
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h ERQEQSto enuggs To ArrtunIx_A, IEClitlLCAL.itECirICAT10 tis or fat 1Lin QEggAT1Hg _LLCgtiggs._}i[F 37. l{ff-6 6. Nrr-7 2. and NT M EJLQn.ELAL12.D IL&idW.09d StatiDD Registd_Eages: 3/4 0-1 Bevised rages:
3/4 0-1 3/4 0-2 3/4 0 2 3/4 2-2 3/4 2-2 3/4 2-6 3/4 2-6 3/4 2 9 3/4 2-9 3/4 2-12 3/4 2-12 3/4 32 3/4.3-2 3/4 3 3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-$
3/4 3-$
3/4 3-12 3/4 3-12 3/4 3-15 3/4 3-15 3/4 3-17 3/4 3-17 3/4 3 18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-21 3/4 3-21 3/4 3-43 3/4 3 43 3/4 3 44 3/4 3-44 j
3/4 3 47 3/4 3 47 3/4 3-56 3/4 3-58 3/4 3-57 3/4.3-$9 3/4 3-62 3/4 3-64 3/4 3-71 3/4 3-73 3/4 7-28 3/4 7-26 3/4 9-8 3/4 9-8 3/4 G-11 3/4 9-11 3/4 9-13 3/4 9 la 3/4 9-14 3/4 9-14 3/4 11-1 3/4 11-1 3/4 11-6 3/4 11 6 3/4 11 7 3/4117 3/4 11-8 3/4 11-B 3/4 11-9 3/4 11 0 3/4 11-13 3/4 11 11 3/4 11-14 3/4 11-14 3/4 11 15 3/4 11-15 l
3/4 11-16 3/4 11-16 3/4 11 17 3/4 11-17 3/4 11-18 3/4 11-18 l
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(cont'd) 3.
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Byron SLStlon Braldwood Station if Revised Pages:
Reviand Papst 3/4 11-19 3/4 11-19 it 3/4 12-02 3/4 12-02 r,
3/4 12-13 3/4 12-13
-3/4 12-14 3/4-12-14 Bases Pages B 3/4 0-1 through B 3/4 0-3 are being replaced with B 3/4.0-1 through B 3/4 0 6.
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3/4 LIMITING CONDITIONS FOR OFERATION AND SURVEILLANCE REQUIREMENTS b 4d OeSSS6C W A M "*
"* S A SW 8" "
- 1 "
[ neerne.t wakin a sperJRed H@me in+erval. Ente 3 snte an 3/4.0 APPLICABILITY L *PanATiowAL mops c=- specified cenctihew mq be. made in O
cceresonu. w% ACT1oc rwpicements when ccefernance to '
LIMITING CONDITION FOR OPERA 110NWm werm4 c onhneed coere m o4 *e fatV;N 4'd
/v*nhmtW 3.0.1 succeeding specifications is required during the OPERAT]ONAL MODES or conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.
If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in a M00E in which the specification does not apply by placing it, as applicable, in:
a.
At least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and c.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of f ailure to meet the Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual specifications.
This specification is not applicable in MODE 5 or 6.
Owhe.n 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not v
a L
be mace 444+9 the conditions for the Limiting Condition 6for Operation are met b e -
_n
. _ = _
- _.._.: - - r ge This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
Exceptions to these requirements are stated in the' individual specifications.
3.0.5 Limiting Conditions for Operation including the associated ACTION require-ments shall apply to each unit individually unless otherwise indicated as follows:
a.
Whenever the Limiting Conditions for Operation refers to systems or components which are shared by both units, the ACTION requirements will apply to both units simultaneously.
b.
Whenever the limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and c.
Whenever certain portions of a specification contain operating param-eters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.
BYRON - UNITS 1 & 2 3/4 0 1 l
APPLICABILITY SURVE!LLANCE REQUIREMENTS i
4.0.1 Surveillance Regoirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance interval, but b.
The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance (dehned ty Spec.ICioho"k'" obi, (noncomphance. wi4@
Callowed sorveillan@
4.0.3 Failure to DTrform a Surveillance l
22mm intervalfshall constitute = f=M-- jRequirement within theAW e
^ the OPERABILITY requirements for a Limiting Condition for Operation. -
4 t _ _. : g_g g : ' _ ?
Surveillance Requirements do x_
[
not have to be performed on inoper equipment.
sa o-4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance equirement(s) associated with Limiting Condition for Operation been performed within the stated surveillance interval or as otherwise specified. This Provision sho/l not throv3h o.- to CNAATIONAL MODES as resucred ts cc4y w%pfeventpassaa 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves
'shall be performed in accordance with Section XI of the ASME Boiler and Pressure vessel Code and applicable Addenda as required by 10.CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);
b.
Surveillance intervals specified in Section XI, 1980 Edition, Winter 1981 Addenda, of the ASME Boiler and Pressure Vessel Code for the inservice inspection and testing activities shall be applicable as follows in these Technical Specifications:
l The time limWS of the AC. TION r-virement.5 ore. c9plicable. of the. time. it is identified + hat o, Su ve.illance. Reguire. ment has not been perbmed. The ACTION reguiremenis may be de.loyed b up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to Permit %e. cempietion oF the. sur vei1)ance. whew
-the. allowable. outage. time. Limit s of %e. AC.11ot4 re guir e rnents t ore _ less %n 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,5.
y BYRON - UNITS 1 & 2 3/4 0-2
The initial datterminabn of +0rget flux diMerence felbing a F-
- futh$ evroeja, shou be, based em design predic.Hom. o+her wise.
LIMITING CONDITION FOR OPERATION ACTION (continued) c.
With the indicated AFD outside of the above required target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative penalty deviation time during the previev's 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER less than 50% but greater than 1E% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band.
$URVE!LLANCE REQUIRfMENTS 4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
j a.
Monitoring the indicated AFD for each OPERABLE excore channel:
1)
At least once per 7 days when the AFD Monitor Alam is OPERABLE, and 2)
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status, b.
Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereaf ter, when the AFD Monitor Alarm is 4
inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.
j 4.2.1.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outsice the target band. Penalty deviation outside of the above required target band shall be accumulated on a time basis of:
c.
One minute penalty deviation for each I minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.
One half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and
(
50% of RATED THERMAL POWER.
4.2.1.3NhetargetfluxdifferenceofeachOPERABLEexcorechannelshallbe determined by measurement at least once per 92 Effective Full Power Days.
4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.3 above or by linear interpolation between the most recently measured value and the predicted value at the end of the cycle life.
l BYRON
- UNITS 1 & 2 3/4 2 2 AMEN 0MENTNO,[
u
+
POWER 0!$TRIBUTION LIMITS (but Prior to utsch$ 50 7*
SURVEILLANCE RE0VIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 F,y shall be evaluated to determine if F (Z) is within its limit ty:
g a.
Using the movable incore detectors to obs in a power distribution
.hea[h'ooYc afe i
t t e6v s a s t
6 Nc~rea$$ngYh Ys*urY8F,y b.
component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties; Comparing the F,y computed (F,C) obtained in Specification 4.2.2.2b.,
c.
j above, to:
1)
The F,y limits for RATED THERMAL POWER (F,RTP) for the appropria measured core planes given in Specifications 4.2.2.2e. and f..
below, and 2)
The relationship:
F,f=F,RTP(1+0.2(1-P))
Where F is the limit for fractional THERMAL POWER operation P
expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F,ywas measured.
Remessuring F,y according to the following schedule:
d.
When F,C is greater than the F limit for tM appropHate P
l 1.
measuredcoreplanebutlessthantheF,frelationship, additional power distribution maps shall be taken and F compared to F and F, :
a)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20% of RATED THERMAL POWER or greater, the THERMAL POWER at which F,f was las determined, or b)
At least once per 31 EFPD, whichever occurs first.
l BYRON - UNITS 1 & 2 3/4 24
k n
POWER O!STRIBUTION LIMITS
, dTING COM0! TION FOR OPERATION ACTION (ContinueO i
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above Itaits, verify b.
through incore flux mapping and RCS total flow rate comparison %at the combination of Fh and RCS total flow rate are restored to within the above Itaits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; and Identify and correct the cause of the eut of-limit condition prior c.
to increasing 1HERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of Ffg and indicated ACS total flow rate are demonstrated, through incere flux mapping and RCS total flow rate comparison, to be within the region of acceptable i
operation defined by Specification 3.2.3 prior to exceeding the foi-lowing THERMAL POWER levels:
1.
A nominal 50% of RATED THERMAL POWER, i
2.
A nominal 75% of RATED THERMAL POWER, and 3.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95% of RATED THERMAL POWER.
SURVE!LLANCE REQUIREMENTS
[pe)or to caccedirwj 95% e4 RATED THEgrnh pcS46 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 The combination of indicated RCS total flow rate and FN shall be determined to be within the region of acceptable operation of AN Specification 3.2.3:
Prior to operation above 75% of RATED THERMAL POWER after each fuel a.
loading, and b.
At least once per 31 Effective Full Power Days.
4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the most recently obtained value of Fh, obtained per Specification 4.2.3.2, is assumed to exist.
4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months."
d 4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 month. The measurement instrumentation shall be calibrated within seven days prior to the performance of the calorimetric flow measurement.A Prior to the precision heat balance measurement, at least Ftwo of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.
J "The specified 18 month interval may be extended to 32 months for Cycle 1 only.
d BYRON - UNITS 1 & 2 3/4 2-9 AMENDMENT NO. # _
The. 29 hour3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> ceaplebm he, provisions ef SpeciReaHm N.o.s are ne+ OPP '**)
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POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 2.
Reduce THERMAL POWER to less than 50% ef RATED THERMAL P within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and~ reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to SSE of RATED THERMAL-POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and Ident'ify and correct the cause of the out-of-liett condition 3.
prior to increasing THERMAL POWER; subsequent POWER OPERATION above 505 of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.
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SURVEILLANCE REQUIREMENTS l
4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within th limit above 50% of RATED THERMAL POWER by:
Calculating the ratio at least once per 7 days when the alarm is a.
OPERABLE, and l
b.
Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steacy-state operation when the alarm is inoperable.
t 4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incere detectors to confirm that the normalirca symmetric power distribution, obtained from two sets of four symmetric thimole locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t l
BYRON - UNITS 1 & 2 3/4 2-12 I
e
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TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUNENTATION MINIMUM e
TOTAL NO.
CHANNELS CHANNELS APPLICA8tE i
c FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8tE N00E5 ACTION w
1.
1 2
1, 2 1
2 1
2 3*, 4*, 5*
10 e
m 2.
Power Range, Neutron Flux 2[/
a.
High Setpoint 4
2 3
1, 2 b.
Low Setpoint 4
2 3
1888, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2/
i.
High Positive Rate t'
4.
Power Range, Neutron Flux, 4
2 3
1, 2 2f
[
High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
1998, 2 3
6.
Source Range, Neutron Flux a.
Startup 2
1 2
2ff**
4 b.
Shutdown 2
1 2
3,4,5 5
7.
Overtemperature AT 4
2 3
1, 2 d
8.
Overpower AT 4
2 3
1, 2 67 9.
Pressurizer Pressure-Low
_j (Above P-7) 4 2
3 1
W **
i
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e-P TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEN INSTRUNENTATION MINifRM TOTAL NO.
CHANNELS CHANNEL 5' APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE NODES ACTION N
- 10. Pressurizer Pressure-High 4
2 3
- 1. 2 6V 11.
Pressurizer Water Level-High (Above P-7) 3 2
2 1
p m
i 12.
Reactor Coolant Flow-tow Single loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1
67 '
a.
any oper-each oper-ating loop ating loop 6f b.
Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop in 1
below P-8) two oper-each oper-ating loops ating locp
{
Y
- 13. Steam Generator Water 4/sta. gen.
2/sta. gen. 3/sta. gen.
1, 2 6$*/**
Level-Low-Low in any each operating operating sim. gen.
sim. gen.
14.
Undervoltage-Reactor Coolant 6N *
- Pumps (Above P-7) 4-1/ bus 2
3 1
1
- 15. Underfrequency-Reactor Coolant Pamps (Above P-7) 4-1/ bus 2
3 1
6f 16.
(Above P-7 or P-8)****
g E
Energency Trip Header Pressure 3/ Train 2/ Train 2/ Train 1
m a.
b.
Turbine Throttle Valve Closure 4
4 1
1 5
""*A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modification is implewr*.ed
'y which enables Reactor trip on Turbine trip above P-8 (301).
ll
.~
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TABLE 3.3-1 (Continued)
T REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM g
TOTAL NO.
CHANNELS CHANNELS APPLICABLE q
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE NODES ACTION 17.
Safety Injection Input.
from Esr 2
1 2
1, 2 9
n 18.
Reactor Coolant Pump Breaker Position ^ Trip 11 [
Above P-7 1/ breaker 2
1/ breaker 1
per operating loop 19.
Reactor Trip System Interlocks
~
i i
w1 a.
Intermediate Range Neutron Flux, P-6 2
1
- 2 2ff 8
m*
b.
Low Power Reactor Trips Block, P-7 P-10 Input 4
2 3
1 8
or i
P-13 Input 2
1 2
1 8
c.
Power Range' Neutron Flux, P-8 4
2 3
1 8
d.
Power Range Neutron Flux, P-10 4
2 3
1, 2 8
e.
Turbine Impulse Chamber.
Pressure, P-13 2
1 2
1 8
20.
Reactor Trip Breakers 2
1 2
1, 2 9
2 1
2 3*, 4*, 5*
10 21.
Automatic Trip and Interlock Logic 2
1 2
1, 2 9
2 1
2 3*, 4*, 5*
10
~
i TABLE 3.3-1 (Continued)
TABLE NOTATIONS "With the Reactor Trip System breakers in the closed position and the Control Rod Drive System capable of rod withdrawal.
""The boron dilution flux doubling signals may be blocked during reacto-startup.
- These channels also provide inputs to ESFAS. The Action Statement for the p
channels in,_ Table 3. 3-3 i.s more conservative and, therefore, controlling.
. 1.
__m m
- ,, y.
- ##Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPEriABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hoes or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; j
b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
)
for surveillance testing of other channels per Specification 4.3.1.1; and c.
Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron l
Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once otr 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
l a.
Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and b.
Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing. THERMAL POWER above 10% of RATED THERMAL POWER.
BYRON - UNITS 1 & 2 3/4 3-5 L
~
i
{ 7%e inihal.rin9 t point comperism e>f Juert h e.ncora Altht. Ft.UK 'D1FFERE%KE '
I f folle>J3 a refuelin ovhage.Theil bn performed pHor h exceediny 1G % ofj (RATO THERmAt cwtR. C%erwl.te the.
TABLE 4.3-1 (Continued)
TABLE NOTATIONS "With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.
- These channels also provide inputs to ESFAS. The Operational Test Freov ncy for these channels in Table 4.3*2 is more conservative and, therefore, controlling.
~
- A Reactor trip on Turbine trip is enabled above P 7 (10%) until the modifica-p/
tien is implemented which enables Reactor trip on Turbine trip above P 8 (30%)."
- The specified 18 month interval may be extended to 32 months for Cycle 1 only.
)
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) If not performed in previous 7 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1,. m d
(3)'I / ingle point comparison of incore to excore AX1AL FLUX DIFFERENCEfabTve t
15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. TheprovisionsofSpecification4g.4 ate,,.fj,,ge ry
$vsYI of't$t-lY Y2 St Neutron cetectors may be excNed f rom hHANNEL CAllBRATION. j,,,ff,Q ng e
o (4)
(Sa) Initial plateau curves shall be measured for each detector. Subsequent plateau curves shall be obtained, evaluated and compared to the initial curves. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
($b) With the high voltage setting varied as recommenced by the manufacturer, an initial discriminator bias curve shall be measured for each detector.
Subsequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provi-keYh$$h,9 aske'hil N ef ehehe
$N.
PD.
Each train shall be tested at leasfveSheb ys$nb ee?eevery 62 (7)
(8) With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.
(9) Surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
Surveil-lance shall include verification of the Boron Oilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.
BYRON - UNITS 1 & 2 3/4 3-12 AMENOMENTNO.[
1 l
r
^
TABLE 3.3-3 j
l er f
j ENGINEERED SAFETY FEATURES ACTUATIGII SYSTEN INSTRISENTATION l
2 minsfase l
Treat no.
CnAMELS
.CNeelELS APPLICABLE g
OF CNMSIELS TO TRIP _
OPERABLE fesES ACTISN FUNCTIONAL UNIT l
q
=
w 1.
Safety Injectfen (Reecter l
Trip, Feeduster Isoletten, l
o=
w Start Ofesel Generators, Containment Coelfag Fans, Centrol Rees Iselotten, Phase "A" Isoletten, Turbine Trip, Aemillary Feeduster, Containeent Vent Isoletten.
and Essential Service Water).
a.
Stoneel Initiation 2
1 2
1, 2, 3, 4,
18 Y
b.
Autemette Actuetten 2
1 2
1, 2, 3, 4 14 Y
topic and Actuotfen G
Relays c.
Centalement 3
2 2
1,2,3 15 [
Pressere-nfgle-1 d.
Presserirer Pressere-4 2
3 1, 2, 38 1
M Lew (Above P-11) e.
Steam Line Pressere-3/steen Ifne 2/steen Ifne 2/stese Ifne 1, 2, 3F 15f Law (Abw P-11) eny stees Ifne 2.
thetainmint Spray I
stoneel inttf atten 2 pefr 1 pefr 2 pefr 1, 2, 3, 4 19 a.
E x
b.
Automatic Actuetten 2
1 2
1, 2, 3, 4 14 Logic and Actuatfen Relays c.
Containment Pressere-4 2
3 1, 2. 3 16 HIgh-3
[S
[5
[9 NO I
3 2 1 4
T 2
2 2 I
1 1
2 1
C d
A na sno E
i LBS t
c AE 3
3 3 3
3 n
CD u
IO f
N LM 2
2 2 2
2 2
2 O
P f
g I
P f
n T
A 1
1 1 1
1 3
1 1
i A
t T
a N
i E
e e
r t
N l
g n
n
.e i
t ne i
I np n
R i n l
I eom i
T SE ti g i S
MLL al m
m
.hs n
N UE8 r
2 2 2
a a
2 c
o MNA em e
e aag I
i NR pa t
n I
t en
. t N
NAE oe s
s in c E
I HP
/t
/
/
/nte e
)
T MCO 1 s 2
2 3iagj d
S n
e Y
I u
S n
e e
e y
N n
n n
.r t
i t
O f
i i
ne.
e
~
n I
I l m l m epm f
o T
S a
a goi a
C A
LP m
me me s
S
(
U EI a
at at
.y T
NR e
1 1 2
es es 1
ang l
3 C
NT t
t e t e
t an l
A s
syn syn s
in a 3
HO
/
/ni/ni
/nt e S
CT 1
2al 2al 2iag r 3
E o
R f
E U
L T
e e
e e
B A
.S n
n n
v A
E L
i i
i n
o T
F OE l
l l
e b
NN g
a.
Y N
m m
m s
T LA a
a a
.t E
AH e
2 2 3
e e
2 a
1 n F
TC t
t t
t e
A O
s s
s s
mm S
TF
/
/
/
/
ee O
1 3
3 4
t r D
Ii E
u R
eq E
ee E
sr N
e I
nn r
e nn G
oo u
rh oo N
n ii s
ug ii E
o tt s
si tt
)
n n
il aa e
sH aa r
4 o
o t a uu r
e-n uu o
1 i
i au tt P
r 'e o tt t
t t id cc w) Pt) i cc aP c
a ti n AA t
o1 a1 t AA rl(
e l
iv e
n et1 ep1 a
ee j
o ni t
cd e
n-
- n
&l cd nvh n
s Id s i n
m eP i eP o in eeg i
i I
n y t a n
Lr Lv ps t a Gli l I S a s i2 ue iwiI a
s H
y T
e a mcy a: msv mt o r mcy mr-t I
n u oia th aso aal Tr oia aeh e
n t gl ng eeb ege e t g1 et g f
N i
U L a)
)
uoe oi t ra t eb et uoe t ai a
L m
SN( na ALR SWH S
iw A
a bd N
e re O
t ue I
S a b
c d
e TF a b
c T
C N
U F
4 5
c 3 N w e- "
y* 3w
,!l
.i
!i' i
i
,f j
l
TABtE 3.3-3 (Continued)
~
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION g
MININIM q
TOTAL NO.
CHANNELS CHANNELS APPLICA8tE 4
e FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8tE N00E5 ACTION 6.
Manual Initiation 2
1 2
1,2,3 22
. b.
Automatic Actuation Logic 2
1 2
1, 2, 3 21 and Actuation Relays c.
Ste. Gen. Water tevel-Low-Low
- 1) Start Motor-I 19f Driven Pump 4/sta. gen.
2/sta. gen.
3/sta. gen.
1, 2, 3 1
w in any opera-in each e-ting sta gen. operating w
sim. gen.
9*
- 2) Start Diesel-Driven Pump 4/sEm. gen.
2/stm. gen.
3/sto. gen.
1, 2, 3 19 [
fn any in each operating operating stm. gen.
sto. gen.
d.
Undervoltage - RCP 4-1/ bus 2
3 1, 2 19 [
Bus-Start Motor-l Driven Pump and j
Diesel-Driven Pump l
l e.
Safety Injection -
I Start Motor-Driven Pump See Item 1. above for all Safety Injection initiating functions and and Diesel-Driven Pump requirements.
f.
Division 11 for Unit 1 (Division 21 for Unit 2)
ESF Rus Undervoltage-Start Motor-Driven Pump (Start as part 2
2 2
1, 2, 3, 4 25af i
of DG sequencing)
1 TABLE 3.3-3 (Contirsued)
ENGINEERED SAFETY FEATURES ACTUA7L7 SYSTEM INSTRUNENTATION c
.flNIMUM i
5 TOTAL NO.
CHANNELS CHANNELS APPLICABLE t
M FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE N00ES ACTION 6.
Auxiliary Feedwater (Continued)
~
g.
Auxiliary feed-water Pump Section PressurePLow (Transfer to 15f Essential Service Water) 2 2
2 1, 2, 3 7.
Automatic Opening of Containment Sump Section 1
{
Isolation Valves T
a.
Automatic Actuation logic 2
1 2
1,2,3,4 14 5
and Actuation Relays b.
RWST Level - Low-Low 4
2 3
1,2,3,4 16
~
Coincident With l
Safety Injection See Item 1. above for Safety injection initiating functions and requirements.
8.
Loss cf Power a.
ESF Bus Undervoltage 2/ Bus
- 2/8vs 2/Bes 1, 2, 3, 4 25af b.
Grid Degraded Voltage 2/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 25b 4
I i
P, TABLE 3.3 3 (Continued)
TABLE NOTATIONS
- Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.
- Trip function automatically blocked above P-11 and may be blocked b low P-11 when Safety Injection on low steam line pressure is not blockec.
__, -- - -- ; 4 - - -
- e. : ;;-i-----
t ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channeis one less than the Minimum Channels OPERABLE requirement, be in at lea'st HOT STANOBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD $HUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 tours for surveillance testing per Specif{ cation 4.3.2.1, provided the other channel is OPERABLE ACTION 15 - With the number of CPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.
i ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 17 - With less than the Minimus Channels OPERABLE requirement.
operation may continue provided the containment purge supply and exhaust valves are maintained closed.
ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
BYRON - UNITS 1 & 2 3/4 3-21 i
INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection Systen shall be OPERABLE with:
,a.
At 1 east 75% of the detector thimbles, b.
A minimum of two detector thimbles per core quadrant, and Sufficient movable dete,ctors, drive, and readout equipment to map c.
these thimbles, i APPLICABILITY: When the Movable Incore Detection System is used for:
Recalibration of the e'xcore neutron flux detection system, or a.
b.
Monitoring the QUADRANT POWER TILT R$TIO, or MeasurementofFh,F(Z)andF c.
q q
ACTION:
With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specificatio 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required fur:
a, Recalibration of the Excore Neutron Flux Detection System, or b.
Monitoring the QUADRANT POWER TILT RATIO, or Measurement of Fh, F (Z), and F,y.
9 BYRON - UNITS 1 & 2 3/4 3 43 l
4 r
,,e-
~-
j ESTRUMENTATION SEl$MIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring in_strumentation shown in Table 3.3-7 sha11 Le OPE P.S.E LE.
APPLICABILITY: At all times.
ACTION:
With one or more of the above required seismic monitoring instruments a.
inoperable for more than 30 days, prepare and submit a special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.
The provisions of Specification [ 3.0.3 e are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.3.1 The seismic monitoring instrumentation shall be determined OPERABLE:
a.
At least once per 31 days byJverifying operable status indications of the seismic monitoring instrumentation, b.
At least once per 92 days by verifying that:
1)
The triaxial acceleration sensors and the time-history accelero-graphs properly process the equipment internal test signals.
2)
The response spectrum analyzer properly executes its diagnostic routine.
c.
At least once per 184 days by verifying that the triaxial acceleration i
sensors and the time-history accelerographs properly record the equipment internal test signals. The test may be performed in lieu of the test required by Specification 4.3.3.3.1.b.1), and I
d.
At least once per 18 months by:
i 1)
Verifying the electronic calibration of the time history accelerographs.
2)
Installing fresh magnetic recording plates in the triaxial peak l
accelerographs.
l 4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the equipment i
listed in Table 3.3-7 shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be preparea and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spect, rum and resultant effect upon facility features important to safety.
AMENDMENTNO.[
BYRON - UNIT $ 1 & 2 3/4 3-44
-~
INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels given in f oale 3.3-8 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
a.
With one or more required meteorological monitoring channels inoperable l
for more than 7 days, prepare and submit a Specidl Report to tne Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERA 8LE status.
The provisions of Specification [ 3.0.3 e are not applicable.
b.
SURVEILLANCE REQUIREMENTS l
4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies given in Table 4.3-5.
BYRON - UNITS 1 & 2 3/4 3-47
INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.8 The Loose Part Detection System shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
- With one or more Loose Part Detection System channels inoperable for a.
more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
The provisions of Specificationf'3.0.3 : : E 0 ; are not applicable.
b.
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each channel of the Loose-Part Detection Systems shall be demonstrated OPERABLE by performance of:
A CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a.
An ANALOG CHANNEL OPERATIONAL TEST except for verification of setpoint b.
at least once per 31 days, and A CHANNEL CALIBRATION at least once per 18 months.
c.
l l
l l
BYRON - UNITS 1 & 2 3/4 F56 Amendment No.
1NSTRUMENTAT10N RADI0 ACTIVE L10U10 EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid offl.uent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 8tE with their Alare/ Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The Alarm /
Trip Setpoints of these channels shall be determined and adjusted in accordance with the, methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY: At all times.
ACTION:
With a radioactive liquid effluent monitoring instrumentation channel a.
Alarm / Trip Setpnint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.
t b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3 12.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to specifica-tion 6.9.1.7 why this inoperability was not corrected within the time specified, l
TheprovisionsofSpecificationy'3.0.3ma#+**arenotapplicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the fre-quencies shown in Table 4.3-8.
BYRON - UNITS 1 & 2 3/4 3-57 AmendmentNo.JI L
~~
INSTRUMENTATION RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0lTION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring ir.strumentation channels shown in Table 3.3-13 shall be OPERA 8LE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.
The Alarp/ Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 3.3-13 ACTION:
With a radioactive gaseous effluent monitoring instrumentation a.
channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected within the time specified, The provisions of Specificationf 3.0.3 1_ 3.-3A are not applicable.
c.
7 SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and O!GITAL CHANNEL OPERATIONAL TEST at the fre-quencies shown in Table 4.3-9.
cy'
<f BYRON - UNITS 1 & 2 3/a 3-62 Amendment No. JO 4
INSTRUMENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS
}lMITINGCONDITIONFOROPERATION 3.3.3.11 The high energy line break instrumentation shown in Table 3.3-14 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-14.
ACTION:
With the number of OPERABLE auxiliary steam isolation instruments less a.
than the Minimum Channels OPERABLE as required by Table 3.3-14, restore l
the inoperable instrument (s) to OPERABLE status within 7 days, or suspend the supply of auxiliary steam to the Auxiliary Building, or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status.
b.
With the number of OPERABLE steam generator blowdown line isolation instru-ments less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or limit the total steam generator blowdown flow rate to less than or equal to 60 gpm or establish a continuous watch in the affected ares (s) until the inoperable sensors are restored to OPERABLE status, The provisions of Specificationf'3.0.3 =-j 10.- are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the perfomance of an ANALOG CHANNEL OPERATIONAL TEST AND CHANNEL CALIBRATION at least once per 18 months.
i i
e BYRON - UNTTS 1 & 2 3/4 3-71 APOOMENTNO.}8
[
.-s.
I PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 1
3.7.9 Each sealed source containing radioactive material either in exceu of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie i
of removable contamination.
~
APPLICABILITY: At all times.
ACTION:
a.
With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and 3
either:
1.
Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission Regulations, TheprovisionsofSpecification[3.0.3 sac *mlt::8arenotapplicable.
b.
SURVEILLANCE REQUIREMENTS l
4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.
a.
Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
1)
With a half-life greater than 30 days (excluding Hydrogen 3),
and 2)
In any form other than gas.
BYRON - UNITS 1 & 2 3/4 7-28 l
REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL. - SPENT FUEL STORAGE FACILITY LIMITING CONDITION FOR OPERATION' 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel ovei fuel assemblies in the spent fuel storage facility.
APPLICABILITY: Withfuelassembliesinthespentfuelstoragefacility.
ACTION:
dA the requirements of the above specification not satisfied, a.
v a the crane load in a safe condition.
The provisions of Specification [3.0.3 suo:::8;t* are not applicable.
b.
SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation."
- Physical stops are not required until Oc'tober 31, 1985.
BYRON - UNITS 1 & 2 3/4 9-8 8,
REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge Isolation Systes shall be OPERABLE.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within' the containment.
ACTION:
With the Containment Purge Isolation System inoperable, close each a.
of the purge valves providing direct access from'the containment atmosphere to the outside atmosphere.
b.
The provisions of Specificationf'3.0.31 sus:3** are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge Isolation System shall be demonstrated CPERABLE within 100-hours prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment purge isolation occurs on-an ESF test signal from each of the containment radiation monitoring instrumentation
- channels, t
l BYRON - UNITS 1 & 2 3/4 9-11
i REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irraciated fuel assemblies 14:ted in the storage racks.
MQRM' Qenever irradiated fuel assemblies are in the storage pool, f
i ACTIOk.
a.
With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, The provisions of Specification [ 3.0.3 e are not applicable.
b.
i SURVEILLANCE REQUIREMENTS-j 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per:7 days when irradiated fuel assemblies are in the fuel storage pool, j
BYRON - UNITS 1 & 2 3/4 9-13 i
~
v i
E i
REFUELING OPERATIONS
[
3/4.9.12 FUEL HANDLING BUILDING EXHAUST FILTER PLENUMS LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Exhaust Filter Plenums shall be OPERABLE.
)ll APPLICABILITY: Whenever irradiated fuel is in the storage pool-ACTION:
a.
With one Fuel Handling Building Exhaust Filter Plenum inoperable, fuel movement within the storage pool, or crane dpsration with loads over the storage pool, may proceed provided the OPERABLE Fuel Handling Building Exhaust Filter Plenum is capable of being powered l
from an OPERABLE emergency, power,Jource and is in operation and j
taking suction from'at~least one train of HEPA filters anc charcoal I
adsorbers.
t I
b.
With no Fuel Handling Building Exhaust Filter Plenums OPERABLE, suspend all operations involving movement of fuel within the storage pool, or crane operation with loads over the storage poc1, until at least one Fuel Handling Building Exhaust Filter Plenum is restored to OPERABLE status.-
The provisions of Specification [3.0.3 e are not applicable.
l c.
SURVEILLANCE REOUIREMENTS 4.9.12 The above required Fuel Handling Building Exhaust Filter Plenues shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least l
15 minutes; b.
At least once per 18 months, or (1)-after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following i
j painting, fire, or chemical release in any ventilation zone communicating with the system, by:
I C
l s
BYRON - UNITS 1 & 2 3/4 9-14
_ _ _ - - - ---- - --- - -- - - - - - - - - ~ ~
~~
~~
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION p
LIMITING CONDITION FOR OPERATION
.=
3.11.1.1 to UNRESTRICTED AREAS (see Figure 5.1-1) shall be lim specified in 10 CFR Part 20 Appendix B, Table II, Column 2, for radionuclides-other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 8 total activity.
microcurie /ml APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive saterial released in liquid effluents a.
to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, b.
The provisions of Specificationf'3.0.3 ang=3:** are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 to the sampling and analysis program of Table 4.11-1. Radioactive liquid 4.11.1.1.2 The results of the radioactivity analysis shall be used in accord-ance with the methodology and parameters in the ODCM to assure that.the con-centrations at the point of release are maintained within the limits of Specification 3.11.1.1.
BYRON - UNITS 1 & 2 3/4 11-1 I
-. - - - = = = = ' = = = = =
RADI0 ACTIVE EFFLUENTS:
DOSE LIMITING CONDITION FOR OPERATION i
3.11.1.2 The dose-or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED' AREAS (see Figure 5.1-1) shall be limited:
t a.
During any calendar quarter to less than or equal to 1.5 areas to the whole body and to less than or equal to 5 areas to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the l
whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) fer exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, The provisions of Specificationf 3.0.3 and=*;W4 are not applicable.
b.
SURVEILLANCE REOUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accorcance with the methodology and parameters in the ODCM at least once per 31 days.
l.
l BYRON - UNITS 1 & 2 3/4 11-6
1 RADICACTIVE EFFLUENTS l
LIQUID RADWASTE TREATMENT SYSTEM 1
.I LIMITING CONDITION FOR OPERATION j
1 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when-the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see figure 5.1-1) woula exceed 0.06 aren to the whole body or 0.2 mrom to any organ in a 31-day period.
APPLICABILITY: At all times.
ACTION:
a.
With radioactive liquid waste being discharged without treatment and i
in excess of the above limits and any portion of the Liquid Radweste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1.
Explanation of why liquid radweste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to CPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
L b.
The provisions of Specification 73.0.3 ane:te;* are not applicable, l
SURVEILLANCE-REQUIREMENTS
~
i 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS l
shall be projected at least once per 31 days in accordance with the methodology l
and parameters in the ODCM when the Liquid Radwaste Treatment System is not y
l being fully utilized.
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered i
OPERABLE by meeting Specifications 3.11.1.1'and 3.11.1.2.
l BYRON - UNITS 1 & 2 3/4 11-7 l
h RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANK $
LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material, excluding trittun and dissolved or entrained noble gases, contained in any outside tanks shall be Itaited to the following:
f-Primary Water Storage Tank 5 2000 Curies, and a.
b.
_0utside Temporary Tank
$ 10 Curies.
APPLICABILITY: At all times.
ACTION:
- a.. With the quantity of radioactive saterial in any of the above listed tanks exceeding the above Ifait, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specification [3.0.3 ent*0;* are not applicable.
i SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
i l
BYRON - UNITS 1 & 2 3/4 11-8 AmendmentNo.,k
RADIDACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION i
3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mress/yr to the whole I
body and less than or equal to 3000 mrems/yr to the skin, and b.
For Iodine-131 and 133, for tritium, and for all radior.uclices in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 mress/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate (s) exceeding the above limits, immediately restore a.
the release rate to within the above limit (s),
The provisions of Specification [3.0.3 emp= twt:* are not applicable.
b.
SURVEILLANCE REOUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to Iodine-131 and 133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
BYRON - UNITS 1 & 2 3/4 11-9
.RADIDACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2
~
f The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE SOUNDARY (see Figure 5.1-1) shall be limited to the following:
a.
During any' calendar quarter:
Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and-b.
During any calendar year:
Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous a.-
effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce
(-
the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
The provisions of Specification [ 3.0.3 e b.
are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l BYRON - UNITS 1 & 2 3/4 11-13
~.
k Y
RADIDACTIVE EFFLUENTS DOSE - 10 DINE-131 AND 133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION i
3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritiu4n, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 7.5 areas to any organ, and b.
During any calendar year:
Less than or equal to 15 areas to any organ.
APPLICABILITY: At all times.
ACTION:
-a.
With the calculated dose from the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases-will be in compliance with the above limits, b.
The provisions of Specification [3.0.3 e are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l BYRON - UNITS 1 & 2 3/4 11-14 l
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be i
used to reduce releases of radioactivity when the projected doses in 31 days-due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure $.1-1) would exceed:
a.-
0.2 mrad to air from gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 mrem to any organ of a MEMBER OF THE PUBLIC, APPLICABILITY:
At all times, l
ACTION:
i a.
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence, The provisions of Specification [ 3.0.3 e are not applicable.
b.
SURVEILLANCE REOUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31-days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.
4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLOUP SYSTEM shall be considered OPERABLE by meeting Specification 3.11.2.1 and 3.11.2.2 or 3.11.2.3.
BYRON - UNITS 1 & 2 3/4 11-15
1 RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be.
limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.
With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a. above, The provisions of Specification [ 3.0.3 m are not applicable.
c.
i SURVEILLANCE REQUIREMENTS
')
4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP l
SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen l
and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
l-
)
l l
l
\\
1 i
L t
l BYRON - UNITS 1 & 2 3/4 11-16
t RADIDACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION
~
3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x104 Curies of noble gases (considered as-Xe-133 equivalent).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas decay tank 4.
exceeding the above limit, immediately Fuspend all additions of radioactive material.to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the t
tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification-6.9.1.7.
The provisions of Specification [3.0.3 mw+-*-e-t are not applicable.
b.
SURVEILLANCE REQUIREMENTS 4.11.2.6-The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
1 BYRON - UNITS 1 & 2 3/4 11-17
i il RADIOACTIVE EFFLUENTS i
3/4.11.3 SOLIO RADIDACTIVE WASTES LIMITING CONDITION FOR OPERATION 3
3.11.3 Radioactive wastes shall be solidified or dewatered in accordance vith the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
~
l APPLICABILITY: At all times.
ACTION:
With SOLIDIFICATION or dewatering not meeting disposal' site and a.
shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the solid waste system as necessary to prevent recurrence, b.
With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence, TheprovisionsofSpecification[3.0.3 enc 3*t2arenotapplicable.
c.
SURVEI'LLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every. tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall-be verified in accordance with the PROCESS CONTROL PROGRAM:
If any test specimen fails to verify SOLIDIFICATION, the SOLIO!FICATION a.
of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be detemined in accordance with the PROCESS CONTROL PROGRAM, an f a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; b.
If the-initial test specimen from a batch of, waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM st.all provide for the collection and testing of representative test-specimens from each j
consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens-demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and With the installed equipment incapable of meeting Specification 3.11.3 c.
or declared out-of-service, restore the equipment to operable status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.
BYRON - UNITS 1 & 2 3/4 11-18
1 RADIDACTIVE EFFLUENTS I
q 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose connitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium f cycle sources shal body or any organ,l be limited to less than or equal to 25 meems to the whole equal to 75 areas. except the thyroid, which shall be limited to less than or APPLICABILITY: At all times.
ACTION:
With the calculated doses from the release of radioactive ma a.
in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,
3.11.2.3a., or 3.11.2.3b., calculations should be made including tanks to determine whether.the above limits of Spec have been exceeded.
If such is the case, prepare and submit to the Report that defines the corrective action to be taken t and includes the schedule for achieving conformance wi limits.
This Special Report, as defined in 10 CFR 20.40Sc, shall MEMBER OF THE PUBLIC from uranium fuel cycle effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.
It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concen-trations.
If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
b.
The provisions of Specification [3.0.3 :sup*4M at 2 not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 shall be determined in accordance with SpecificationsCumulative dose c 4.11.2.3, and in accordance with the methodology and parameters in the ODCM4.11.1.2 4.11.4.2 and from radwaste storage tanks shall be determined in accordan methodology and parameters in the ODCM.
under conditions set forth in ACTION a. of Specification 3.11.4.This requirement is app BYRON - UNITS 1 & 2 3/4 11-19 l
l
RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION ACTION (Continued)
With milk or fresh leafy vegetable samples unavailable from one or c.
more of the' sample locations required by Table 3.12-1, identify specific. locations for obtaining replacement samples and add them within 30, days to the Radiological Environmental Monitoring Program given in the CDCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program.- Submit controlled version of the 00CM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples t
and justifying the selection of the new location (s) for obtaining
- samples, The provisions of Specification [ 3.0.3 e are not applicable.
d.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and i
figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1, l
j L
i BYRON - UNITS 1 & 2 3/4 12-2
[
L
1 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify.within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, and the nearest residence. For dose.
calculation, a garden will be assumed at the nearest residence.
.j APPLICABILITY: At all times.
ACTION:
With a Land Use Census identifying a location (s).that yields a a.
calculated dose or dose cosnitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Annual Radiological Environmental Operating i
Report, pursuant to Specification 6.9.1.6.
b.
With a Land Use Census identifying a location (s) that yields a calculated
-dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.
{
The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program'after October 31 of the year in which this Land Use Census was conducted.
Pursuant to Specification 6.14, suosit in the next Annual Radiological Environmental Operating Report documentation for a change in the i
00CH including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting.the change in sampling locations.
The provisions of Specificationf'3.0.3 ano=t*** are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census.shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
~
l BYRON - UNITS I & 2 3/4 12-13
l l
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by fable 3.12-1.
APPLICABILITY: At all times.
ACTION:
With analyses not being performed as required ab6ve, report the a.
corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
b.
TheprovisionsofSpecification[3.0.3asukMk;*arenotapplicable.
L SURVEILLANCE REQUIREMENTS L
4.12.3 The Intulaboratory comparison Program shall be described in-the ODCH.
i A summary of the results obtained as part of the above required Interlaboratory l
Comparison Program shall be included in the Annual Radiological Environmental i
Operating Report pursuant to Specification 6.9.1.6.
i l'
l
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l BYRON - UNITS 1 & 2 3/4 12-14
i bc-u&RcviScA'bh e-P
--M4 4M14MS- *0^:0!':0'? 'OE ":":0:: '::: :Jn;;;
.,;; ;L;;Dae 3/4.0 APPLICABILITY-L ITING CONDITION FOR OPERATION
/
?
N
- 3. 0.1 ompliance with the Limiting Conditions for Operation contai succeed g specifications is reautred during the OPERATIONAL MODES d in tne condition specified therein; except that upon failure to meet t r other Conditions or Operation, the associated ACTION requirements sh Limiting be met.
3.0.2 Nonco iance with a specification shall exist when t the Limiting Co ition for Operation and associated ACTION requirements of not met within th 'specified time intervals. If the Limit g Condition for quirements are Operation is resto completion of the A d prior to expiration of the specifi time intervals, s
ON requirements is not required.
3.0.3 When a Limiting ndition for Operation is no in the associated ACTION met, except as provided to place the unit in a MODequirements, within 1 hou action shall be initiated in which the specific ion does not apply by placing it, as applicable, a.
At least HOT STANDBY ithin the nex 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
At least HOT SHUTDOWN ' thin the f lowing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and c.
At least COLD SHUTDOWN w hin th subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures'are complet requirements, the action may be taken.
hat permit operation under the ACTION as measured from the time of failure
.accordance with the specified time limits Exceptions to these requirements at et the Limiting Condition for Operation.
o state in the individual specifications.
This specification is not applic le in MODE or 6.
3.0.4 Entry into an OPERATIO L MODE or other s cified condition shall not be made unless the condition s contained in the ACT(IQN requirementsfor the L without reliance on provisi provision shall not prove This passage through or to OP TIONAL MODES as required to comply with ACTION re itements.
Exceptions to the requirements are stated in the'individu specifications.
3.0.5 Limiting Con ions for Operation including the asso ments shall apply ' each unit individually unless otherwise ndicated as follows:
ated ACTION require-a.
Whene r the Limiting Conditions for Operation refers systems or como ents which are shared by both units, the ACTION r wil uirements apply to both units simultaneously.
b.
enever the Limiting Conditions for Operation applies to un unit, this will be identified in the APPLICABILITY section of one he specification; and Whenever certain portions of a specification contain operating par' -
eters, Setpoints, etc., which are different for each unit, this will.
be identified in parentheses, footnotes or body of the requirement.
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The intent of this provision is to ensure that facility operation is iot
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Exct tions to this provision have been provided for a limited nus6er of.
specificat ns when STARTUP with inoperable equipment would not affedt plant safety. The e exceptions are stated in the ACTION statements of the appropriate s cifications.
3.0.5 Thi specification delineates the applicability of Aach specifica-tion to Unit 1 an Unit 2 operation.
/
4.0.1 This sp ification provides that surveillance activities necessary to ensure the Limitin Conditions for Operation are met and will be performed during the OPERATIONAL ODES or other conditions for which the Limiting Condi-tions for Operation are plicable.
Provisions for additional surveillance activities to be performe without regard to the appi) cable OPERATIONAL MODES l
or other conditions are pr ided in the individual Serveillance Requirements.-
Surveillance Requirements fo Special Test Exceptipfis need only be performed when the Special Test Excepti is being utilize ens an exception to an individual specification.
4.0.2 The provisions of this specifica.on provide allowable tolerances for performing surveillance activit s beyo d those specified in the nominal surveillance interval. These tolera es e necessary to provide operational flexibility because of scheduling and orsance considerations. The phrase "at least" associated with a surveilla frequency does not negate this allowable tolerance value and permits he erformance of more. frequent surveillance activities.
The tolerance values, taken ither indiv ually or consecutively over three test intervals, are suffi ently restrict ve to ensure that the reliability associated with th surveillance act vity is not significantly degraded beyond that obtaine from the nominal sp ified interval.
4.0.3 The provisions of this specification set orth the crit'ria for e
determination of complia e with the OPERABILITY requ ements of the Limiting Conditions for Operatio. Under these criteria, equipm t, systems, or components are assumed to be OPEJldBLE if the associated surveillancesactivities have been satisfactorily performed within the specified time interva Nothing in this provision is to be Monstrued as defining equipment, systems, or components OPERABLE, when sucfi items are found or known to be inoperable 1though still meeting the Surveillance Requirements.
Items may be determine inoperable during use, duy'ing surveillance tests, or in accordance with thi specification.
Therefore ACTION statements are entered when the Surveillence Re irements should have een performed rather than at the time it is discovere that the tests were, tiot performed.
4.
.4 This specification ensures that the surveillance activities sso-ciate#with a Limiting Condition for Operation have been performed withi the 11-specified time interval prior to entry into an OPERATIONAL MODE or other a cabfe condition. The intent of this provision is to ensure that surveillan
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activ its have been satisfactorily demonstrated on a current basis as requir to meet the OPERABILITY requirements of the Limiting Condition for Operatio Under e terms of this specification, for example, during inftial plant STARTUP or f lowing extended plant outages, the applicable surveillance activities aus beperformedwithinthestatedsurveillanceintpvalpriorto placing or retu ing the system or equipment into OPERABLE status.
4.0.5 This s cification ensures that inservice inspe on of ASME Code
-j Class 1, 2 and 3 to onents and inservice testing of ASMEfode Class 1, 2 and 3 pumps and valves wi 1 be performed in accordance with a periodically updated
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version of Section XI the ASME Boiler and Pressure % ssel Code and Addenca as required by 10 CFR 50.55a.
Relieffromanyofthe/aboverequirementshas been provided in writing the Commission and is n a part of these Technical Specifications.
This specification inclu s a clarification of the frequencies for performing-I the inservice inspection and te ing activitias' required by Section XI of the ASME Boiler and Pressure Vessel de and applicable Addenda. This clarification is provided to ensure consistency surveiflance intervals throughout these Technical Specifications and to re e any' ambiguities relative to the frequencies for performing the requir nservice inspection and testing activities, Under the terms of this specif atickthemorerestrictiverequirements of the Technical Specifications-ta e precedence over the ASME Boiler and Pressure Vessel Code and applica e Addenda.\\for example, the requirements of r
Specification 4.0.4 to perform ryeillance activities prior to entry into an OPERATIONAL MODE or other spe fled applicability condition takes precedence over the ASME Boiler and Pre ure Vessel Code pro'v(sion which allows pumps to be tested up to 1 week aft return to normal oper ~ ion. And for example, the Technical Specificati definition of OPERABLE d s not grant a. grace period before a device at is not capable of perform g its specified function is declared inoperable nd takes precedence over the AS'AE Boiler and Pressure-Vessel Code provisio hich allows a valve to be incapabh of performing its specified function rup-to24hoursbeforebeingdeclarNinoperable.
4.0.6 This ecification delineates the applicability f the surveillance 4
activities to U t 1 and Unit 2 operations.
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Soecification 3.0.1 throuch 3.0.bstablish the general requirements applicable to Limiting conditions for Operation. These requirements are based on the L
requirements for Limiting Conditions for Operation stated in the Code of.
Federal Regulations.10 CFR 50.36(c)(2):
" Limiting conditions for cperation are the lowest functional capability or perfomance levels of equipment reevired for safe operation of the I
facility. When a limiting condition for operation of a nuclear reactor is not met.- the-licensee shall shut down the reactor or follow any remedial action pemitted by the technical specification until W condition can be met."
Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The 1
ACTION requirements establish those remedial measures that must be taken within,specified time limits when the requirements of a Limiting Condition for Operation are not met, There am two basic types of ACTION requirements. The first specifief the remedial measures that pemit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION recuirements continue to be met. The second type of ACTION requirement specifies a time limit in which confomance to the conditions of the Limiting Condition for Operation _must be met. This time limit is the allowable outage time to l.
restore an inoperable system or component to CPERABLE status or for restoring l
parameters within specified limits. 'If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION requirements be used as an operational convenience which pemits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.
The specified time limits of the ACTION requirements am applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.
In this case, the allowable outage time
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vised 'E 4 bC3 3/4.0 APPLICABILITY BASES-(C W limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION reovirements the plant may have entered a MODE in which c new specification becomes applicable. In this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition
- for Operation are net met.
S)ecification 3.0.2 establishes that noncompliance with a specification exists wien the reoutrements of the Limiting Condition for Operation are not met and l
the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified tirie interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not requimd when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.
Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented wher a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements.
The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE when plant o>eration cannot be maintained within the limits for safe operation defined 1y the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time pemits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and L
availability of the electrical grid. The time limits specified to reach lower MODES of operation pemit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the
.cooldown capabilities of the facility assuming only the minimum required equipment is' OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.
)
l If remedial measures pemitting limited continued operation of the facility l
under the provisions of the ACTION requirements are completed, the shutdown l
may be teminated. The time 11rif ts of the ACTION requirements are applicable I
from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be teminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.
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The time limits.of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in the COLD SHUTDOWN MODE when a shutdown is requimd during the POWER MODE et operation. If the plant is in a. lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation ap-plies. However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced. For example, if H07 STAND 8Y is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach H0T SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Therefore, if remedial measures are completed that would permit a return to POWER operation, a perialty is not incurred by having to reach a lower MODE of j
operation in less than the total time allowed.
The same principle applies with regard to the allowable outage time limits of the ACTION requiremer.ts, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operatier, may not be used to extend.
the allowable outage time that is appifcable when a Limiting Condition for Operation is not met in a lower MODE of operation.
The shutdown requirements of Specification 3.0.3 c% not apply in MODES 5 and-6, because the ACTION requirements of individual specifications define the-remedial measures to be taken.
Specification 3.0.4 establishes limitations on MODE changes when a Limiting condition for operation is not met. It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting condition for Operation are not. net and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements'if a change ir, i
MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to 0PERABLE status or parameters-to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an accept-able level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.
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t 3/4'.0 APPLICABILITY i.5ej ~Bcts BASES M W When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation, Specifications 4.0.1 throuch 4.0.5'Qestablish the general requirements applicable to Surveillance Reuuirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Reculations, 10 CFR 50.36(c)(3):
- Surveillance requirements are requirements relating to test, calibra-tion, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
Specification 4.0.1 establishes the reovirement that surveillances must be performee during the OPERATIONAL MODES or other conditions for which the l
requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this speci-fication is to ensure that surveillances are perfomed to verify the opera--
tional status of systems and components and that parameters are within speci-fied limits to ensure safe operation of the facility when the piant is in a.
MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the reovirements of the-associated Limiting Condition for Operatiorfdo not apply unless otherwise specified. The Surveillance Requirenents associated with a.Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the reouirements of a specification.
Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a. permits an allowable extension of the nomal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being perfomed is the verification of confomance with the Surveillance Requirements. These provisions
-are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERAPILITY requirements for a Limiting Condition for Operation. Under the e-i n -
R 3/4.0 4 B1RON - UNITS I S 2.
1 i
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I BASES % ': 1 provisions of this specification, systems and components are assumed to be ORERABLE when Surveillance Requirements have been satisfactorily perfomed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been perfomed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
However, this does not negate the fact that the failure to have performed the surveillance within the allowed i
surveillance interval, defined by the provisions of Specification 4.0.2, was a violaticn of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perfom a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under-
't thereouirementsof10CFR50.73(a)(2)(1)(B)becauseitisacondition prohibited by the plant's Technical Specifications.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,
Specification 3.0.3, a 24-hour allowance is provided to pemit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to pemit the completion of a surveillance before a shutdown is required to comply with ACTION reouirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence-of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is teminated.
Surveillance Requirer'ents do not have to be perfomed on inoperable equipment because the ACTION requirements cefine the remedial measures that apply.
However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.
l B 3/4.0-5 BYRON - UthT 5 i f 2 L
hev{ sed 3Me-)r 3/4;0 APPLICABILITY B_ASES 6 : m Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.
The purpose of this specification is to ensure that system and component OPERABILITY requirements.
or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL PODES or other specified conditions associated with plant shutdown as well as startup.
i Under the provisions of this specification, the applicable Surveillance Requirements must be perfomed within the specified surveillance interval' to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.
i When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.
Specification 4.0.5 establishes the requirement that inservice inspection of A5ME Code Class 1, 2. and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be perfomed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure -
Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief.has been provided in writing by,the Comission.
This specification includes a clarification of the frecuencies for perfoming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the p
Technical Specifications and to remove any ambiguities relative to the frequencies for perfoming the required inservice inspection and testing l
activities.
Under the tems of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Poiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of perfoming its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
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3/4 LIMITING CONDITIONS FOR OPERATION AND $URVEILLANCE REQUIREMENTS 3f4.0 APPLICABILITYTnote n d % assec.e + d acleon rep <sres e s ai + d w n,1 t h e y n so cM/ 6 4, +'W t 8'*t +
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3.0.1 Compliance with the Limiting Conditions for Operation contained in th:
succeeding specifications is required during the OPERATIONAL MODES or other I conditions specified therein; except'that upon failure to meet the Limiting 'g J
t Conditions for Operation, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.
If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION reovirements, withiti 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
a.
At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and c.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(
Where corrective measures are completed that permit operation under the ACTION reouirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual specifications.
This specification is not applicable in MODE 5 or 6.
I m_3.0.4_ Entry into an OPERATIONAL MODE or other specific ^ ndition shall no nof
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be mace'<es4to the conditions for the Limiting Conditi r Operation are met s
'it%t re!!r:0 er p ev44m art &d ' r e ;,CT;0n r4w i....,.u.
This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
Exceptions to thesc requirements are stated in the individual specifications.
3.0.5 Limiting Conditions for Operation including the associated ACTION require-ments shall apply to each unit individually unless othirwise indicated as follows:
a.
Whenever the Limiting conditions for Operation refert to systems or components which are shared by both units, the ACTION requirements will apply to both units cimultaneously, b.
Whenever the Limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and c.
Whenever certain portions of a specification contain operating param-eters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.
BRAIDWOOD - UNITS 1 & 2 3/4 0-1
1 APPLICABIRTJ SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be set during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
i 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance interval, but i
b.
The combined time interval for any three consecutive surveillance interva
<n+-run,ls shall not exceed 3.2$ times the specified surveillance 1
d e M ntJ by Spex.4, c.4..
n 9 o. 2.
[r) on c.e,ms lia nc.e u>sWC a t/.we 4 surveillance 1 tone interva}fshall constitute W.../ Requirement within th e
4.0.3 Fililurt/to' perform urveillance e
^.. _... the OPERABILITY requirements for a Limiting Condition for Operation. E; th.; w i.nm i n. k;n nt:
yet stated " tM "dSSd ;;;;im........ ; Surveillance Requirements do 1
I not have to be performed o noperable equipment.
es 4.0.4 Entry into an OPERAT AL MODE or other specified condi n shall not be made unless the Surveillanc Requirement (s) associated with Limiting Dndition for Operation been performed within the stated surveillance interval or as otherwise specified. Th J -prous sion shss il not p/ eNent fo & sap /
.+-a ro gh a co c> FE A AT:f o 4 A L. rn o c e S m a_,.. upe d or
+ c.w / v _wi+A M C WCA 5urveiTland Requirements for inservice inspection and testing of ASk*P'h'
.0.5 Code Class 1, 2, and 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1, 2, and 3 components and a.
inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as recuired by 10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50 Section 50.55a(g)(6)(i);
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspec-tion and testing activities shall be applicable as follows in these Technical Spscifications:
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h45 no4 L '* n tss r ;or #t S. Tk e A c T't o M (s c( a iremen &s un s y A1e d< la y e
.(o r up
+o M hours += p ermi t the Cem p h.t on o f + h e A ca s o y i
rt guire mtd> o re. I t + 5 than 1.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 5, BRAIDWOOD - UNITS 1 & 2 3/4 0-2 l-
"rh t i n i 4 l a l d a,+ c e m s' H 4 + io n of t e.e 3 c. t-4 k Y-d i Efore m t.
et.f ut II S b l/ he beJc.cl on de. s ip es 4*ilo wi eg a-w.~. _ ~..N o w + y t-LIMITING CONDITION FOR OPERATION I
ACTION (Continued)
With the indicated AFD outside of the above required target band for c.
more than I hour of cumulative penalty deviation time durtig the i
previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER Iess than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band.
SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AFD shall be detemined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
a.
Monitoring the indicated AFD for each OPERABLE excore channel:
1)
At inst once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)
At least once per hour'for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alam to OPERABLE status.
b.
Monitoring and logging the indicated AFD for each OPERABLE excere channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AFD Monitor Altre is inoperable.
The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.
4.2.1.2 The indicated AFD shall be considered outside of its target band when two or more OPERAELE excore channels are indicating the AFD to be outside the target band. Penalty deviation outside of the above required target band shall be accumulated on a time basis of:
I a.
One minuts penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.
One half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.
4.2.1.3[hetargetfluxdifferenceofeachOPERABLEexcorechannelshallbe determined by measurement at least once per 92 Effective Full Power Days.
The R.,ision. vi h iiiu W on 4.0.0 eie n;t :;;P r e k 4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant tc Specification 4.2.1.3 above or by linear interpolation between the most recently measured value and the predicted value at the end of the cycle i
life. M: p... ta; M 4;; Mlcei nn 4.0.4 n; n;; :;; Fr e k l
j BRAIDWOOD - UNITS 1 & 2 3/4 2-2
POWER DISTRIBUTION LIMITS X Cet d S07e]
SURVEILLANCE REQUIREMEKTS 4.2.2.1 The provisions of Spectfication 4.0.4 are not applicabl.
4.2.2.2 F, shall be evaluated to determine if F (Z) is in its limit by-o a.
Using the movable incore detectors to ob n a power ditstribution
,h map a THERMAL POWER i a,
dp % c.? b T i.4 eater (han RATED THERMAL POWER a%".'##%'t e power distribution
~f+/ low 8 b.
__no the measured F component of y
by 3% to account for manuf acturing tolerances and further increasing the value by 5% to account for measurement uncertainties; C
c.
Comparing the F computed (F*Y) obtained in Specifi:ation 4.2.2.2b.,
above, to:
- Y 1)
The F,y limits for RATED THERMAL POWER (F,RTP) for the appropriate measured core planes given in Specifications 4.2.2.2e and f.,
below, and 2)
The relationship:
F,
=F
[1+0.2(1-P)]
Where F, is the limit for fractional THERMAL POWER operation expressed as a function of F,RTP and P is the fraction of RATED THERMAL POWER at which F,ywas measured.
Remeasuring F,y according to the following schedule:
d.
When F,C is greater than the F, P limit for the appropriate 1.
measuredcoreplanebutlessthantheF,frelationship, additional power distribution maps shall be taken and F C compared to F,RTP and F, :
a)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding ry 20% of RATED THERMAL C
POWER or greater, the THERMAL POWE' at which F*Y,,, ),,g determined, or b)
At least once per 31 EFPD, whichever occ es first.
BRAIDWOOD - UNITS 1 & 2 3/4 2-6
POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that thecombinationofFhandRCStotalflowratearerestoredto within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; and c.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b, above; subsequent POWER OPERATION mayproceedprovidedthatthecombinationofFhandindicatedRCS total flow rate are demonstrated, through incore flux sapping and RCS total flow rate comparison, to be within the region of acceptable operation defined by Specification 3.2.3 prior to exceeding tte fol-lowing THERMAL POWER levels:
1.
A nominal 50% of RATED' THERMAL POWER, 2.
A nominal 75% of RATED THERMAL POWER, and 3.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS (p rTo e
~~
+o ersec uns os % s + R areD,.yed m m. rowe Q 4.2.3.1 The provisions of Specification 4.v.4 are not applicabu.
t The combination of indicated RCS total flow rate anc Fh shell be de 4.2.3.2 ained to be within the region of acceptable operation of Specification 3.?.3:
a.
Prior to operation above 75% of RATED THERMAL POWER af ter each fuel loading, and b.
At least once per 31 Effective Full Power Days.
4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the most recently obtained value of Fh, obtained per Specification 4.2.3.2, is assumed to exist.
4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL N
L CALIBRATION at least once per 18 months."
l 4.2.3.5 The RCS total flow rate shall be ermined by precision heat balance measurement at least once per 18 months The measurement instrumentation shall
__be calibrated within seven days prior to the performance of the calorimetric
( flow measurement.h Prior to the precision heat balance measurement, at least f
two of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.
'The specified 18 month interval may be extended to 32 months for cycle 1 only.
pq BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AMENDMENTNO.X (Th Of, hour com e l e Won +-i.n t p ro v.'s.ico
.4 spe c.i f co G n
'f.
3 m.
n-w wwe
l W ' ri..*eW.m m ; :.
.7, g._, s,.. i '; r,).x,3..,
Vf
' i :.
l POWER 61stRItUTION LIMITS LIMITING CONDITION FOR 6PERATION ACTION (Continued}
2.
Reduce THERMAL POWER to less than SW of RATED THERMAL PMR within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flua Migh Trip letpoints to-less than er equal to 65% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and i
3.
Identify and correct the cause of the out of liait condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above SOE of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its 11elt at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greatsr AATED THERMAL POWER.
1
% e;..iei.... vi ipecnication 5.L.4... ; ^. ;;;ii;eMe.
l c.oevsisisure ernnterucwtc 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to'be within the limit above 60R of RATED THERMAL POWER by:
a.
Calculating the ratio at least once per 7 days when the alam is OPERABLE, and b.
Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when the alars is inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be detemined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confire that the normalized syssetric power distribution, obtained free two sets of four symmetric thimble locations or a full-core flux sap, is consistent with the indicated QUADRANT POWER TILT RAllo at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
BRAIDWOOD - UNITS 1 & 2 3/4 2 12 i
t t
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BRAIDWOOD - UNITS 1 & 2 3/4 3-3 AMENDMENT NO. 3 m
a p_
.sa_
m a
u 4
._m
-...Aam em;.
,h
...*.sm 4,r..A.dha_m.Ia-h-,ua-4-J..3y A.4.3._m-_s.
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BRAIDWOOD - UNITS 1 & 2 3/4 3 4 l
l t
m I
(
1
/
.t.*
I J TAkt 3, M (Continued) i TABLE ISTAT!0k$
agggh gh, geacter Trip Systee breakers in the tiesed position and the Centrol Red Drive $ystes capable of red withdrawal.
- The boren dilution flua Goubling signals may be blocked during reactor st4rtup.
I
'"These channels else provi6e inputs to $$FA$. The Action $tatement.9e the
{
thannels in Table 3.3 3 is more conservative end, therefore, contros.ing.
)
- H ;r;;':':t: ? S::t?':W = !.t.t r ; = n ; m d ;.
Hlelow the P 6 (Intermediate Range heuteen Flua Interlock) Setpoint.
Nplelow the P*10 (Low letpoint Power Range Neutron Flua Interlock) Setpoint.
l
[
ACTION $7ATEstENT$
t ACTION 1 - With the number of CPERASLE thannels one less than the Minism Channels OPERABLE reeutrement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> er be in MDT STAND 8Y within j
the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2
- With the number of OPERABLE channels one less than the Total Number of Channels, $TARTUP and/or POWER OPERATION may proceed i
i provided the following conditions are satisfied:
The inoperable channel is placed in the tripped condition a.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; i
b.
The Minteum Channels OPERABLE reevirement is met; however, the inoperable channel may be bypassed for w to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1; and c.
Either THERMAL POWER is restricted to less than or ecual to 75E of RATED THERMAL POWER and the Power Range Neutron Flux Trip 5etpoint is reduced to less than or eeval tp 455 af RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the OuADRANT POWER TILT RAT 10 is monitores at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
ACT]ON 3
- With the number of channels OPERABLE one less than the Minise Channels OPERA 8LE requirement and with the THERMAL POWER level; 4.
Selow the P 6 (Intermediate Range Neutron Flua Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P 6 Setpoint; and 4
b.
Above the P 6 (Intermediate Range heutron Flum Interlock) 5etpoint but below 105 of RATED THERMAL POWER.
I restore the inoperable channel to OPERA 8LE status
- prior to increasing THERMAL POWER above 10E of RATED THERMAL POWE R.
l BRAIDWOOD - UNITS 1 & 2 3/4 3*5 i
r
-,-.--,,....,,,..,,_,.,,,,-.,,,,n.,,..--n,.,,..--,,,-.,.,-,
.,-,,..,..,~,,-----.-----,,e,gn.g,ww.w
i ses
....r...
3,.
'01FFCAENCE
- f t> ll o W 8 j
" b I ' k o u + % e.
she 4 he p e r g.c m e d 9Noe
+o escee,dinj ? g to o f 6 A TED TH e 8m A L Fo a)ept, cerwuy o
_ p TABLE 4.3-1 (Continued)
TABLE NOTATIONS I
'With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.
- These channels also provide inputs to ESFAS. The Operational Test Frequency for these channels in Table 4.3-2 is more conservative and, therefore, controlling.
- The specified 18 month interval may be extended to 32 months for cycle 1 only.
MBelow P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
MWBelow P 10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) If not performed in previous 7 days.
(2) Comparison of calorimetric to excere power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or '.
g
%g (3) / ingle point comparison of incore to excore AX1AL FLUX DIF NCEAabove 15% of RATED THERMAL POWER. Racalibrate if the absolute difference is
_ orester than or ecual to 3%. The nreviti m e' 9-e4fientian A ^'P=
0 l *E8MiM on"c In%Y i9t,0[b. CN'skl.
[e
- #. n v[N ei 3.n u iy p a si E e +3 r
neutron detectors may De excludec Trom CHANNEL CALIBRATION.(
@)
- 4. 8 3, *"
net e##lece6/t.
(Sa) Initial plateau curves shall be measured for each detector.
suosequen6 plateau curves shall be obtained, evaluated and compared to the initial curves.
For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
($b) Vith the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector. Sub-sequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The provi- %
h"bd MN!"D"d,0 4gr,e,, nog,aypkgg,fg,9ptrgggeE,2ogly,,, y,
j r
7)
Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS. /v (8) With power greater than or equal to the interlock Setpoint the requir ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.
(9) Surveillance in MODES 3*,
4", and 5" shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Surveil-lance shall include verification of the Boron Dilution Alam Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.
(10) Setpoint verification is not applicable.
(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.
I BRAIDWOOD - UNITS 1 & 2 3/4 3-12 AMENDMENT NO.
+
W
.A.
i.7
. gn l
- I f-;
i
=
taste 3.3-3 by EfEGINEERED 5AFETY FEAT 11RES ACTUATI0st 5YSTEUI IIf5TaipElffATION V
i 8
- ,4.h mistsase
'q TOTAL 110.
CNtf51ELS CIsuuuEL5 APPLICABLE
'4 FUNCT10HAL till!T OF CHNWIEL5 TO TRIP OPERAStE 1100E5 ACTICII Ed i
E Z
1.
Safety injection (Reactor
~Y.
'N<
Tr1p Feedwater IsoletIon.
i l
i Start Olesel Generators, Containment Cooling Fans,
- d i
j Control Roon Isolation,
~*
~-
Phase "A" Isolatton, Turbine
[
{
Trip, Auxillary Feedwater.
Contefneent Vent Isolation.
- 1.,
and Essential Service water).
"pd j
4 o
a.
flanwel InitIetien 2
1 2
1, 2, 3; 4 IS
}
l g
i t
b.
AvtomatIc Actwation 2
1 2
1,2,3,4 14
~*7 4 w
Logic and Actuation Relays
.f:
i i
,7 l
c.
Contetneent-3 2
2 1,2,3 1
Pressure-Hfgh-1 y
d.
Pressertrer Pressure-4 2
3 1, 2, 39 3
Low (Above P-11)
.g e.
Steam Lfne Pressure-3/steen Ifne 2/steem ifne 2/stees Ifne 1, 2, 3r 1
low (Above P-11) any steam 1
l Ifne 2.
i
,.,(
a.
Hanwel Inftlation 2 pair 1 pair 2 pair 1, 2, 3, 4 IS r
r b.
Automat 1c ActwatIon 2
1 2
1,2,3,4 14 Logic and Actuation I
Relays
. j '.
j
- ~
c.
Contefament Pressere-4 2
3 1, 2, 3 30
~.s.t) nfon-3
+
5 4.,
" ! e, t,
taste 3.3-3 (Continued)'
.: Y '
b j)p
~~
Ef8GIIIEERED SAFETY FEATURES ACTUATISI SYSTEM INSTRUMENTATION k
b f
MININUM TOTAL 110.
CNANIIELS C8WWWIELS APPLICABLE E
FUNCTIONAL UIIIT OF CfWWWEELS TO TRIP OPERABLE IWWE5 ACTIGII 3
i O
4.
Steam Line Isoletten e,
s.
Menus) InftIat1on 1)
. Individual 1/steen line 1/ steam line 1/eperating 1, 2, 3 23
' ',N-
=
l steam ilne 2)
System 2
1 2
1,2,3 22 i
l b.
Autometic Actuation 2
1 2
1,2,3 21
~
l Logic and Actuation
'3 I
Relays t'
c.
Containment Pressure-3 2
2 1,2,3 15k Nigh-2
\\
w a
d.
Steam Line 3/ steam Ifne 2/ steam line 2/steen line 1, 2, 38 15 Pressure-Low any steen (above P-II) line i
s l
d e.
Steam Lfne Pressere -
3/ steam Ifne 2/ steam Ilne 2/steen line 3ff 15 90egative Rate-Mfg 4:
any steen l
(below P-31) line 5.
.h Feedwater Isolation
)
a.
Automatic Actuation 2
1 2
1, 2 24 4
l l
Logic and Actuation l
Relays i
b.
Steam Generator 4/sta. gen.
2/sta. go..
3/sta. gen.
1, 2 19k l
Water Level-In any ep-r in each oper-
\\
.d]'9 High-High (P-14) sting sta ating sta.-
j 9'a-98#.
"g l
c.
Safety injection See Item 1. above for all Safety Injection inttleting funct. ns and l
requirements.
.! e
=- 1
e A.
- R i
l N
i TAttE 3.3-3 (Coatinmed) i b
EIICINEERED SAFETY FEATURES ACTUATIINI SYSTEN INSTWisIENTATION l
3' RENItant l'
TOTAL NO.
CHAf51EL5 CfgWWIELS APPLICA0tf s
E FUNCTIONAL INelT OF CHANNEL 5 TO TRIP OPEllAetE se0E5 ACTIGII h
6.
Auxfifery Feeduster
,f-
[
i a.
fienwal Initiation 2
1 2
1, 2, 3 22
~
b.
AutometIc Actuation Logfc 2
1 2
1,2,3 21
.s u
~
and Actuation Relays
- ,3 c.
Ste. Gen. Water Level-4 g
Low-tow
~
i t
i
- 1) Start Motor-i
{.
4 Driven Pump 4/ste. gen.
2/sta. gevi.
3/ste. gen.
1, 2, 3 19j T3-i 5:'
fn any eye re-1a each i
11ng sta ien. eperatfng Y
sim. gen.
c4 f
g i
- 2) Start Olesel-Driven Pump 4/sta. gen.
2/ste. goes.
3/sta. gen.
1, 2, 3 1
j fn any in each
, a.;f i
eperating operating I
sto. gen.
sto. gen.
-},
1
=- ?%
d.
Ifndervoltage - RCP 4-1/ bus 2
3 1, 2 1
Ses-Start Motor-(.
3 Driven Pump and 1
i DIese1-Driven Pump
~,%
i e.
Safety Injection -
i.[
Start teotor-Driven Pump See Iten 1. above fer all Safety Injectfen leftleting functfens and i
i and Diesel-Driven Pump requirements.
f.
Olvision 11 for Unit 1
.,'k' l
i
- ~..
(Division 21 for Unit 2)
~;'
I ESF Ses Undervoltage-
~
Stort Motor-Driven f
re Pump (Start as part 2
2 2
1,2,3.4 25e
"'*"~~'d*"'
i l
5 1
N.
i TASTE 3.3-3 (Continued)
..s.s. l e
E ENGINEERED SAFETY FEATURES ACTunTION SYSTER INSTRINENTATION
- M he
- dj o
RININum TOTAL NO.
CfWWWIELS CNanNEL5 APPLICABLE i
5 FUNCTION 4L fpt!T OF CNANNELS 70 TRIP OPERA 0tE BWWE5 ACTION
,' ' [-
l 6.
Awx111ery Feedwater (Continued)
.'i 4
e g.
Auxf1Iary Feed-
),
J water Pump Soctfen
- i Pressure-tow (Transfer to
^j 1
(
Essential Service Water) 2 2
2
- 1. 2, 3 IS}
- j r,
7.
Automatic Opening of
,'+
Containment Semp Section
.}
Iseletion Valves 3."
i
[
a.
Automatic Actuation Logic 2
1 2
1,2.3.4 14 l
l and Actuation Relays a
t
.l b.
AWST tevel - tow-tow 4
2 3
1, 2. 3. 4 16
~t i
Cefncfdent With
.;h4 j
Safety Injection See Ites 1. above for Safety injectlen inttfatlag functless and
- f l
regelresents.
8.
Loss of Power n5
~4
~
a.
tSF.ws.pder.oi e
w ws m es m e.
- 1. 2. 3..
4 I
t,.
b.
Grid Oegraded Voltage 2/ Bus 2/ Bus 2/ Sus
- 1. 2. 3. 4 256k l
},
j 1
h i
N*
i
L U
TAtt! 3.3 3 (Continued)
TAlli NOTATIONS
- firip function may be blocked in this MDDE below the P 11 (Pressuriter Pressure Interlock) Setpoint.
Mirip function automatically blocked above P-11.and may be blocked below P-11 when Safety injection on low steam line pressure is not blocked.
" % r e-8eie : e' herinte+_ie-3,n A.ars aot-appite9e.
ACTION $TATEMENT$
ACTION 14
- With the number of OPERABLE channels one less than the Minioum Channels OPERABLE requirement, be in at least NOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the fc11 swing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per specification 4.3.2.1, provided the other channel is OPERABLE.
ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may mee*4 vat" re***~?*:: : '
the next required ANALOG CHANNEL OPERATIONAL TEST provided the inocerable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 16 - With the number of OPERABLE channels one less than the total l
Number of Channels, operation may proceed provided the inoperable channel is placed in' the bypassed condition and the Minimum Channels OPERABLE requirement is set. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 17 With less than the Minimum Chennels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.
ACTION 18 - With the number of OPERABLE channels one less than the Minimue Channels CPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H01 $1ANDBt within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the followi g 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
htAIDWOOD - UNITS 1 & 2 3/4 3*21 1
I
,e-e e,
na
,,m.
---,---,,,-e
-,a e,p
l L
(
TABLE 3.3 3 (Continued)
)
TABL[ NOTATIONS firip function may be blocked in this MODE below the P 11 (Pressurizer i
Pressure Interlock) Setpoint, i
- firip function automatically blocked above P 11.and say be blocked below P 11 when Safety injection on low steaa line pressure is not blocked.
1 n9..g 4..., e
.,4 e a,. 4.--3 A 4.4re-not-sopitcable.
e ACTION $ TAT (M[NT$
ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement be in at least HOT STANDBY 4
4 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.
l ACTION 15 With the number of OPERABLE channels one less than the Total Number of Channels, peeration may pneeM UM' re** - ! :: :*
the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 16 - With the number of CPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in' the bypassed condition and the Minimum Channels CPERABLE requirement is set. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.
ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
BRAIDWOOD - UNITS 1 & 2 3/4 3-21 l
(.I
(
IN$ttlMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT '0PERATIONS LINITING COND1110N FOR OPERATION 3.3.3.1*
The radiation monitoring instrumentation channels for plant operations shown in Table 3.3 6 shall be OPERABLE with their Alarm / Trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3 6.
A,CTION:
a.
With a radiation monitoring channel Alare/ Trip Setpoint for plant operations exceeding the value shown in Table 3.3 6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.
The provisions of Specificatio/ 3.0.3 rd 3.0.0 are not applicable.
l c.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be cemonstrated OPERABLE by the perforinance of the CHANNEL CHECK CHANNEL CAllBRATION and O!GITAL CHANNEL OPERATIONAL TEST for the MODES and at the frecuencies shown in Table 4.3-3.
' Control Room isolation not required prior to initial criticality on Cycle 1.
l l
BRAIDWOOD - UNIT 5 1 & 2 3/4 3 39 l
L
D b
INSTR M NTATION MOVABLE Ilocott OtitCTOR$
LIMITING CONDITION FOR OPERATION I
3.3.3.2 The Movable incere Detection $ystes shall be OPERA 8LE with:
a.
At least 7&% of the (etector thimbles, b.
A einimum of two detector thimbles per core quadrant, and c.
Suf ficient movable detectors, drive, and readout equipment to esp these thiebles.
APPLICABILITY: When the Movable Incore Detection Systen is used for:
Recalibration of the encore neutror flux detection systee, or a.
b.
Monitoring the QUADRANT POWER TILT RATIO or MeasurementofFh,F(2)andF,y, c.
g AtiluN:
With the Movable Incore Detection Systes inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification /3.0.3;=0.0.'arenotapplicable, i
SURvi!LLANCE R[QUIREMENTS 4.3.3.2 The Movable Incore Detection Systes shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when requirea for:
a.
Recalibration of the Excore Neutron Flum Detection System, or b.
Monitoring the QUADRANT POWER TILT RATIO, or C.
Measurement of F
, F (2), and F,y.
g 4
BRAIDWOOD UNITS 1 & 2 3/4 3-43 i
I
-,+ -
l.
t N
INsfetztNTATION s f.
St!$NIC INsTRLMENTATION E
LIMITING CONDITION FOR CPERATION --
3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3 7 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
With one or more of the above required seismic monitorin0 instruments a.
inoperable for more than 30 days, prepare and subelt a 5pecial Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERA 8LE status, b.
The provisions of Specification /3.0.3 --f L 0.0 are not applicable.
l
$URVE!LLANCE REQUIREMENTS i
4.3.3.3.1 The seismic monitoring instrumentation sha11 be determines CPERABLE:
a.
At least once per 31 days by verifying operable status indications of the seismic monitoring instrumentation b.
At least once per 92 days by verifying that:
i 1)
The trianial acceleration sensors and the time history accelero-graphs properly process the equipment interr.41 test signals.
2)
The response spectrum analyzer properly executes its diagnostic routine.
c.
At least once per 184 days by verifying that the triamial acceleration sensors and the time history accelerographs properly record the equipment internal test signals. The test may be perfonned in lieu of the test required by Specification 4.3.3.3.1.b.1), and d.
At least once per 18 months by:
1)
Verifying the electronic calibration of the time history accelerographs.
2)
Installing fresh magnetic recording plates in the triamiei peak accelerographs.
4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the ecuipment listed in Table 3.3 7 shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum-and resultant effect upon facility features important to safety.
BRAIDWOOD - UNITS 1 & 2 3/4 3 44 I
4
.~
k.
h g
IklTR M WTATION
~
.k.
MEff0f0 LOGIC 8L INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological sonitoring instrumentation channels given in Table 3.3*4 shall be OPERABLE.
APPLICA81LITY: At all times.
ACTION:
4 a.
With one er more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Cossission pursuant to specification 6.9.2 within the next 10 days outlining the cause of the salfunction and the plans for restoring the channel (s) to OPERABLE status.
b.
The provisions of Specification 3.0.3
- M ' are not applicable.
I SURVE!LLANCE REQUIREMENTS l
4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated CPERABLE by the performance of the CHANNEL CHECK and CHANNEL CAL 1 BRAT 10N operations at the frequencies given in Table 4.3*5.
i l
l:.
l l
l BRA 10WOD - UNITS 1 & 2 3/4 3*47 1
INSTRUMENTATION
'C> LOOSE PART DETECTION SYSTEM l
LIMITING CONDITION FOR OPERATION 3.3.3.8 The Loose Part Detection System shall be OPERA 8LE.
APPLICA81LITY: MODES 1 and 2.
ACTION:
1 a.
With one or more Loose Part Detection Systes channels inoperable for more than 30 days, prepare and submit a $pecial Report to the Commission pursuant to $pecification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
b.
The provisions of Specification 3.0.3 :n: 3.0.4-are not applicable.
l f
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each channel of the Loose rart Detection Systems shall be demonstrated OPERABLE by performance of:
4.
A CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, l
b.
An ANALOG CHANNEL OPERATIONAL TEST except for verification of setpoint at least once per 31 Jays, and c.
A CHANNEL CAtlBRATION at least once per 16 months.
l BRAIDWOOD - UNITS 1 & 2 3/4 3-58 f
i
-. ~., -. - _,, _.
,m-,.-.-w r
L L
INSTRUMENT ATION RA010ACTivt L10010 EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.312 6 hall be OPERABLE with their Alara/ Trip Setpoints set te ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alare/
Trip Setpoints of these channels shall-be determined and. adjusted in accordance with the methodology and parameters in the 0FFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel Alare/ Trip Setpoint less conservative than required by the.above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.7 why this inoperability was not corrected within the time specified, TheprovisionsofSpecificationf3.0.3rd3.0.6arenotapplicable.
l c.
SURVE1LLANCE REOUIREMENTS 4.3.3.9 Each radioactive licuid ef fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK CHANNEL CALIBRATION and 01GITAL and ANALOG CHANNEL OPERATIONAL TEST at the fre quencies snown in Table 4.3-8.
I BRAIDWOOD - UNITS 1 & 2 3/4 3-59 I
A.
INSTRUMENTATION r
RADICACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION
\\
3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.313 shall be OPERABLE with their Alars/ Trip 5etpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.
The Alare/ Trip 5etpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 3.313 ACTION:
a.
Wif,h a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than requ' ired by the above specification, immediately suspend the release of radioactive gaseous ef fluents monitored by the af fected channel, or declare the channel inoperable.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Ef fluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected within the time specified.
TheprovisionsofSpecificationf3.0.37 er.: 3.0.4 are not applicable. I c.
$URVE!LLANCE REQUIREMENTS 4.3.3.30 Each radioactive gaseous ef fluent monitoring instrun.entation channel shall be demonstrated OPERABLE by performance of the CHANNf.L CHECK, SOURCE CHECK. CHANNEL CAllBRATION and OlGITAL CHANNEL OPERATIONAL TEST at the fre-quencies shown in Table 4.3-9.
BRAIDWOOD - UNITS 1 & 2 3/4 3-64 l
l
L b
INSTRukENTATION HIGH ENERGY (INE BREAK ISOLATION $ENSOR$
LIMITING CONDITION FOR OPERATION 3.3.3.11 The high energy line break instrumentation shown in Table 3.3-14 sha11 be OPERABLE.
APPLICABILITY:
As shown in Table 3.3 14 l
ACTION:
?
a.
With the number of OPERABLE auxiliary steam isolation instruments less l
than the Minimum Channels OPERABLE as required by Table 3.314, restore the inoperable instrument (s) to OPERABLE status within 7 days, or suspend i
the supply of auxiliary steam to the Auxiliary Building, or establish a 1
centinuous watch in the af fected area (s) until the inoperable sensors are res*ered to OPERABLE status.
I -
b.
With the number of OPERABLE steam generator blowdown line isolation instru-ments less than the Minimum Channels OPERABLE as required by Table 3.314, restore the inoperable instrument (s) to OPERABLE status within 7 days, or limit the total steam generator blowdown flow rate to less than or equal to 60 gpa or establish a continuous watch in the af fected area (s) until the inoperable sensors are restored to OPERABLE status, The provisions of $pecificationf 3.0.3 :::: 3.0." are not applicable.
/
{
c.
SURVEILLANCE REQUIREMENTS l
4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST and CHANNEL CALIBRATION at least once per IB sonths.
1 1
P
/
BRA]DWOOD - UNITS 1 & 2 3/4 3-73 I
l
._. ~ _
o.
PLANT $YSTDt$
3/4.7.9 SEAlf0 $00RCE C0wt4pthAT10N LINIT!E CONDITION FOR OPERATION i
3.7.9 Each sealed source containing radioactive saterial either in excess of 100 eicrocuries of beta and/or gamma esitting material or 5 microcuries of alpha esitting motorial shall be free of greater than or equal to 0.005 sitroCurie of removable contamination.
APPLICABILITY: At all times.
ACTION:
a.
With a sealed source having removable contamination in encess of the above limits, tenediately withdraw the sealed source from use and either:
1.
Decentaminate and repair the sealed source, or 2.
Dispose of the sealed source in ac;;ordance with Commissior.
Regwia*ione.
6 TheprovisionsofSpecificationf 3.0.3 4 4 3.0.4 are not applicable.
b.
SUPVE!LLANCE RE0V!REMENTS 4.7.9.1 Test Reewirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Coesission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 sicroCurie per test saeple, 4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below, s.
Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
1)
With a half-life greater than 30 days (excluding Hydrogen 3),
and 2)
In any fors other than gas.
4 BRA 10 WOOD - UNIT 51 & 2 3/4 7-26 I
(
t[FU[ LING CPERATIONS 3/4.9.7 CRAN [ TRAV[L * $P[WT FU[L $TORAGE FACILITY LIMITING CONDITION FOR OP[ RATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the spent fuel storage facility.
APPLICABILITY: Wita fuel assemblies in the spent fuel storage facility.
ACTION:
With the requirements of the above specification not satilfted, 4.
place the crane load in a safe condition.
Theprovisionsof5pecificationf b.
3.0.3 = 3.0.0 are not applicable.
I SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loans in excess of 2000 pounds over fuel assemolies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereaf ter during crane operation.
)
1 BRAIDWOOD - UNITS 1 & 2 3/4 9-8 l
l
)
D S.
REFUELING OPERATIONS 3/4.9.9 CONTAletENT PubGE ISOLATION $Y$ TEN i
e LINITING CONDIT!DN FOR OPERAT!0N 3.9.9 The Containment Purge Isolation Systen shall be OPERABLE.
s APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within 8
the containment.
ACTION:
With the Containment Purge Isolation System inoperable, close each s.
of the purge valves providing direct access from the containment atmosphere to the outside atmosphere.
i b.
The provisions of Specification 3.0.3 -=0 0.0.1 are not applicable.
l l
SURVEILLAktE REQUIREMENTS O
4.9.9 The Containment Purge Isolation Systen shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment purge isolation occurs on an ESF i
test signal from each of the containment radiation monitoring instrumentation channels.
i i
l l
BRAIDWOOD - UNITS 1 & 2 3/4 9-11 l
/
C, d
REFutLING OPtitATIONS 3/4.9.11 WATER trytt. STORAGE POOL LIMITING CON 0! TION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top' of irradiated fuel assemblies seated in the storage racks.
APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool.
ACTION:
With the requirements of the above specification not satisfied, a.
suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.
The provisions of Specificationd 3.0.3 rd 3.0.0-are not applicable.
l 1
SURVEILLANCE REQUIRENENTS 4.9.11 The water level in the storap pool shall be determined to be at least its sinious required depth at least voc per 7 days when irradiated fuel assemblies are in the fuel storage pc-LRAIDWOOD - UNITS 1 & 2 3/4 9-13 1
1 I
t
(-
REFUELING OPERATIONS
~
(,
3/4.9.12 FUEL HANDLING BUILDING EXHAUST FILTER PLENU4$,
LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Exhaust Filter Plenues shall be OPERABLE 1
AoPLICABILITY:~ Whenever irradiated fuel is in tree storage pool.
ACTION:
a.
With one Fuel Handling Su11 ding Exhaust Filter Plenum inoperable, fuel movement within the storage pool, or crane operation with loads over the storage pool, asy proceed provided the OPERABLE Fuel i
Handling Building Exhaust Filter Plenum is capable of being powered from an OPERABLE emergency power source and is in operation and taking suction from at least one train of HEPA filters and charcoal adsorbers.
b.
With no Fuel Handling Building Exhaust Filter Plenums OPERABLE, su per.d :11 :p:tsti:n: i..v;,1.ir.g s,uant of feel.itnin the storage pool, or crane operation with loads over the storage pool, until at least one Fuel Handling Building Exhaust Filter Plenum is restored to OPERABLE status.
c.
The provisions of Specification 3.0.3 =d 3.0.4 are not applicable.
/
SURVEILLANCE REQUIREMENTS 4.9.12 The above required Fuel Handling Building Exhaust Filter Plenums shall be demonstratec OPERABLE:
l a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, j
l-from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes; b.
At least once per 18 months, or (1) af ter any structural saintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system, by:
l l^
t BRAIDWOOD - uni h I & 2 3/4 9-14 I
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3/.4.11 ItADICACfivt (FFlutNTs j
3/4.11.1 L10VID EFFLUENTS RfCENTRATION LINITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in Itquid effluents to LNRESTRICTED AREAS (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-* eicroCurie/a1 total activity.
l APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive saterial released in liquid offluents a.
to UNRESTP.!CTED AP.E AS eremin; the. te e limit a. lwd at*1;
- tte't the concentration to within the above limits, b.
The provisions of Specificationi 3.0.3 e ~ 3.0.* are not applicable.
/
l SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.
4.11.1.1.2 The results of the radioactivity analysis shall be used in accora-ance with the methodology and parameters in the 00CM to assure that the con-centrations at the point of release are maintained within the limits of Specification 3.11.1.1, i
l:
i BRAIDWOOD - UNITS 1 & 2 3/4 11-1 l
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. RAD 10 ACTIVE EFFLUCKT5-(
DOSE LIMITING CONDITION FOR OPERATION i
l
'3.11.1.2 The dose or dose consiteent to a MDSER OF THE PutLIC free radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited:
l a.
During any calendar quarter to less than or equal to 1.5 areas to the whole body and to less than or equal te 5 areas to any organ, and l
b.
During any calendar year to less than or equal to 3 areas to the i
1 whole body and to less than or equal to 10 oreas to any organ.
(-
APPLICABILITY: At all times.
ACTION:
4.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and
~
~
subeit to the Consission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, Theprovisionsof.Specificationf3.0.3n:3.0.0-arenotapplicable.
b.
/
1
-SURVEILLANCE REQUIREMENTS J
'4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accorcance with the methodology and parameters in the ODCM at least once per 31 days.
L r-I' l
BRAIDWOOD - UNITS 1 & 2 3/4 11-6 l
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'I 4A0iOACT!vE EFFLUENTS LIQUID RADWA$TE TREATMENT SYSTEM LIMITING CON 0! TION FOR OPERATION 3.11.1.3 The Liquid Radweste Treatment Systes shall be OPERABLE and appropriate portions of the system shall be-used to reduce releases of radioactivity when -
1 the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.11) would exceed 0.06 ores to the whole body or 0.2 aren to any organ in a 31-day period.
APPLICABILITY: At all times, i
ACTION:
With radioactive liquid waste being discharged without treatment and a.
in excess of the above limits and any portion of the Liquid Raewaste Treatment Systes not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special 4
Rap?rt that tricledn tree fulipwing inforsetton:
1.
Explanation of why liquid redweste was being discharged without treatment, identification of any inoperable equipUent or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
The provisions of Specification! 3.0.3 end 3.0. ' are not appitcable.
b.
SURVE!LLANCE REQUIREMENTS 4.11.1.3.1 Ooses due to liquid releases from each unit to UNRESTRICTED AREA $
shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radweste Treatment System is not being fully utilized.
4.11.1.3.2 The installed Liquid Raewaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.
BRAIDWOOD - UNITS 1 & 2 3/4 11-7 I
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LA010 ACTIVE (FFLUENT$
s L10VfD N0 LOUP TAhK5 i
LIMITING CONDITION FOR-0PERATION 3.11.1.4 The quantity of radioactive material, excluding tritium and dis'.olved or entrained noble gases, contained in any outside tanks shall be limitea to the following:
a.
Primary Water Storage Tank
$ 2000 Curies, and 1
b.
Outside Temporary Tank
$ 10 Curies.
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive saterial in any of the above listed tanks exceeding the above limit, immediately suspend all additions of racicacti.a satarial tc ti.e teni, either. 46 h0we 6 e'eduSe the tenA r
contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Ef fluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions'of Specification-3.0.3 en: 0.0.0 are not applicable, i
1
$URVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above i
tanks shall be determined to be within the above limit by analyzing a representative samole of the tank's contents at least once per 7' days whet radioactive saterials are being added to the tank.
BRAIDWOOD - UNITS 1 & 2 3/4 11-8 l
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RADICACT!vE EFFLUENTS-i l
3/4.11.2 CASE 005 EFFLUENTS DOSE RATE LIM] TING CONDITION FOR OPERATION a
3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE SOUNDARY (see i
Figure 5.1-1) shall be limited to the following:
a.
For noble gases: Less than or ecuel to 500 arees/yr to the whole body and less than or equal-to 3000 arems/yr to the skin, and For lodine-131 and 133, for tritium, and for all radionuclides in b.
particulate fore with half lives greater than 8 days: Less than or equal to 1500 arems/yr to any organ.
APPLIC a.*! L ITY:
..t :11 ti=c:,.
ACTION:
With the dose rate (s) exceeding the above limits, immediately restore a.
the release rate to within the above limit (s).
b.
The provisions of SpecificationL 3.0.3 " ' ^ ' are not applicable.
f.
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SURVEILLANCE REOUTREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and paraetters in the ODCM.
j 4.11.2.1.2 The dose rate due to Iodine-131 and 133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the.above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples j
and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
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BRAIDWOOD - UNITS 1 & 2 3/4 11-9 l
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j RADI0 ACTIVE EFFLUENTS 00$E N06LE GASES I
LIMIT]NG CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluent's, iros.
each unit, to areas at and beyond the SITE SOUNDARY (see Figure 5.1-1) shall be limited to the following:
4.
During any calendar quarter: Less than or equal to 5 erads for-genea radiation and less than or equal to 10 mrads for beta radiation, and b.
During any calendar year: Less than or equal to 10 erads for passna radiation and less than or equal to 20 erads for beta radiation, i
APPLICABILITY: At all times.
l ACTION:
a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to-the Coenission within 30 days, pursuant to Specification 6.9.2, a Special Repor', that identifies the cause(s) for exceeding the limit (s)'
and defines the corrective actions that have been taken to reduce j
the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
3.0.3 rd 3.0.4 are not applicable.
I.
b.
The provisions of Specification-L SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative cose contributions for the current calendar quarter and current calendar year. for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
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BRAIDWOOD - UNITS 1 & 2 3/4 11-13 I
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kb RAD 10ACT!vt EFFLUENTS u
DOSE - 10 DINE 131 AND 133, TRIT!UM, AND RADICACTIVE MATERIAL IN PARTICULATE FORM ~
LIMIT!>C CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium,-
and all radionuclides in particulate fore with half-lives greater than 8 eays in gaseous ef fluents released,- from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 5.1-1) shall be lietted to the following:
a.
During any calendar quarter:
Less than or equal to 7.5 arens to any organ, and i
b.
During any calendar year: Less than or equal to 15 areas, to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of lodine-131 and-133, tritius, anc radionuclides in particulate fore with half-lives i
greater than 8 days, in gaseous effluents exceeding any of the above licits, prepare and submit to the Consission within 30 aays, pursuant-to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the'above limits, b.
The provisions of Specificationo 3.0.3 r.e 3.0.4 are not applicable.
I h
SURVEILLANCE REQUIREMENTS I
l 4
4.11.2.3 Cumulative dose contributions for the current calendar guarter and current calendar year for Iodine 131 and 133, tritium, and radionuclides in particulate fore with half-lives greater than 8 days shall be determined in-accordance with the methodology and parameters in the 00CH at least once per 1
31 days, i
i BRAIDWOOD - UNITS 1 & 2 3/4 11-14 l
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E LAD 10 ACTIVE EFFLUENTS GASEOUS ILADwASTE TREATMENT SYSTEM l
LIMITING CONDITION FOR OPERATION l
3.11~.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WAST SYSTEM shall be 6PERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity. when the projected doses in 31 days i
due to gaseous effluent releases, from each unit, to areas at and beyond the
$1TE BOUNDARY (see Figure 5.1-1) would oscoed:
0.2 arad to air from gaana radiation, or a.
i b.
0,4 arad to air froe beta radiation, or 0.3 aren to any organ of a MEMBER OF THE PUBLIC.
c.
i APPLICABILITY: At all times.
ACTION:
l' With radioactive gaseous waste being discharged without treatment a.
and in' excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
'1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
i i
b.
The provisions of Specification, 3.0.3 ::: 0.0.e are not applicable.
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l SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and-i beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized.
4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Specification 3.11.2.1 l-and 3.11.2.2 or 3.11.2.3.
BRAIDWOOD - UNITS 1 & 2 3/4 11-15 i
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-RAD 10 ACTIVE EFFLUENTS EXPLOS!VE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS N0 LOUP SYSTEM shall be limited to less than or equal to-3 by volume whenever the hydrogen concentration j
exceeds 41 Dy volume, i
APPLICA8!LITY: At all times.
ACTION:
a.
With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 3 by volume but less than or equal to 4% by volume,.
reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, i
b.
With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume ~4nd the hydrogen concentration greater than 4% by volume, immediately suspend all additions of welte ottes to the system and reduce the concentration of oxygen to less than or equal to 41 by volume, then take ACTION a. above.
g c.
The provisions of Specification 3.0.3 4M ?.0.4 are not applicable.
l SURVEILLANCE RE0V!REMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP l.
SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLOUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
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BRA 10 WOOD - UNITS 1 & 2 3/4 11-16 l
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f RADI0 ACTIVE [FFLUENT$'
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QASOfCAYTANKS LIMITING CONDITION FOR OPERATION
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3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to.less than or equal to 5x100 Curies of noble gases (consieered as Xe 133 equivalent).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive saterial in any gas decay-tank 4.
exceeding the above lielt, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit, and describe the events leading to this condition in the next Seelannual Radioactive Effluent Eviesse Report, pursuant tu Specification 6.9.1.7.
b.
The proyisions of Specificatieru 3.0.3 =t--.
.?-are not_ applicable.
I
^
i SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
~
i BRAIDWOOD - UNITS 1 & 2 3/4 11-17 I
e RAD 10 ACTIVE EFFLUENTS t
3/4.11.3 SOLIO RADICACTIVE WASTES E
LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with t.he PROCESS CONTROL PROGRAM to meet shipping and transportation requiremen o during transit, and disposal site requirements when received at the disposel site.
APPLICABILITY: At all times.
ACTION:
a.
With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the
'i inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the solid waste system as necessary to prevent recurrence.
b.
With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that'it meets burial ground and shipping tv,".!rv vnLs and take appr:priate ::rinictrative' action to prevent recurrence, c,
The provisions of Specification ; 3.0.3 W 3.^ ' are not applicable.
I j
SURVEILLANCE REQUIREMENTS
-i 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoes, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:
a.
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be-obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; b.
If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and c.
With the installed equipment incapable of meeting Specific-tion 3.11.3 or declared out-of-service, restore the equipment te operable status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.
BRAIDWOOD - UNITS 1 & 2 3/4 11-18 1
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3/4.11.4 TOTAL 005E L
LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calender year) dose er dose coseitsent to any IWSER OF4 THE PUBLIC due to releases of radioactivity and to radiation. free urantes. feels cycle sources shall be Itaited to less t,han er equal to 25 ereas to the whe1ej body or any organ, except the tityroid, which shall be lietted to less them er-equal = to 75 arees.
I APPLICABILITY: At all times.
-[
ACTION:
~
L a.
With the calculated doses from the release of radioactive materials
~
in liquid or gaseous effluents anceeding twice the limits of Specification 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,
f 3.11.2.3a., or 3.11.2.36., caleviations should be nede %cluding direct radiation contributions free the units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been eveeeded. If such is the case, prenare and submit to the 1
Commission within 30 days, pursuant to Specification 6.9.2, a Special.
Report that defines the corrective action to be taken to reduce sub-sequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above l
limits. This Special Report, as defined in 10 CFR 20.406c, shall include an analysis that estimates the radiation exposure (dose) to a MEMER OF THE PUBLIC from uranius fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive eaterial involved, and the cause of the exposure lavels or concen-trations.
If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of
~
40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request
[
is complete.
l-b.
The provisions of Specificationo 3.0.3 and-ih0-+ are not applicable.
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I SURVEILLANCE REQUIREMENTS i
4.11.4.1 Cumuistive dose contributions from liquid and gaseous affluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and carameters in the 00CM.
4.11.4.2 Cumulative dose contributions from direct radiation from the units and free radwaste storage tanks shall be determined in accordance with the methodology and parameters in the 00CM. This requirement is applicable only j
under conditions set forth in ACTION a. of Specification 3.11.4.
I BRAIDWOOD - UNITS 1 & 2 3/4 11-19 I
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9 RADIOLOGICAL (WIROSENTAL DONITORING
\\.
LINITING CO@iTION FOR OPERATION
.1 1
ACTION (Continued)~
c.
With milk or fresh leafy vegetable samples' unavailable from one or -
more of the sample locations required by Table 3.121, identify specific locations for obtaining replacement samples and add thenc within 30 days to the Radiological Environmental Monitoring progres 4
given in the 00CM. The specific locations free which samples were unavailable may then be deleted from the monitoring program. Seesit controlled version of the 00CM within 180 GRys including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.
L i
d..
The provisions of Specifications 3.0.3 " ' ^ ^ are not' applicable.
1 SURVEILLANCE REQUIREMENTS 4.12.1 - The radiological environmental monitoring samples shall be collected pareuant to TaHe 3.12-1 from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3.12-l'and the detection capabilities required by Table 4.12-1.
BRAIDWOOD - UNITS 1 & 2 3/4 12-2
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L RADIOLMICAL ENVIR0feUTAL 90tITOR!W J
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3/4.12.t LAS USE 'CDr$U$
LIMIT!88G C0e! TION POR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest slik animal, and the nearest residence. For dose calculation, a garden will be assumed at the nearest residence.
APPLICABIL17Y: At all time's.
ACTION:
a.
With a Land Use Census identifying a location (s) that yields a calculated dose er dose commitment greater than the values curmntly being calculated in Specification 4.11.2.3, identify the new-location (s) in the next Annual-Radiological Environmental Operating Report,-pursuant to Specification 6.g.1.6.
b.
With a Land Use Census-identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 205 greater than at a location from which samples are currently beino obtained in accordance with Specification 3.12.1, and the new location (s) witnin 30 days to the Radiological Environmental flonitoring Program given in the 00CM.
The sampling location (s), excluding the control station location, i
having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.
Pursuant to Specification 6.14, submit in the next Annual Radiological Environmental Operating-Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s) with information supporting the change in sampling locations.
c.
The provisions of Specificationo 3.0.3 r d 0.0.4 are not applicable.
)
SURVEILLANCE REQUIRDENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by e door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
I BRAIDWD00 - UNITS 1 & 2 3/4 12-13 l
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f RADIOLOGICAL EWit0SENTAL DONITORING 3/4.U.3 INTERLABORATORY CO WAtl$0N PROGRAM LIMITING C0eIT10N FOR OPERATION
{
- 3. U.3 Analyses shall be performed on radioactive materials, s oplied as part of an'Interlaboratory Comparison-program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a.
With analyses not being perfomed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
b.
The provisions of Specificationf 3.0.3 n: 0.0.0 are not applicable.
SURVEILLANCE REQUIREMENTS 4
4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
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i i.pecifinu of us. =cun previa, u. eenemi ree.im ts -
s..ech.f me u.iu g C.wiu f.r Op.muen and sune o
appu Iance virements within Section 3/4. In the event of a disagreement tween l
the regu nts stated in these Technical Specificattens and those s tad in en applic e Federal Regulation er Act,ll take precedence and she the requirements stated la applicable rol Regulation er Act she te set.
3.0.1 Th specification defines the applicability of each pecification in terms of def OPERATIGEL 20E6 er other specified eenet s and is provided to deli te specifically when each specification is Itcele.
3.0.2 This e ification defines these condittens ese sary to constitute i
cespliance with the res of an individual Limiting Condi for Operation and associated ACTION quirement.
3.0.3 The speciff ten delineates the seasures be taken for these circostances not direct) revided for in the ACTI statements and whose occurrence would violate intent of a specificat For amample, Speciff-cation 8.5.2 requires two i t ECCS sesys to to GPERABLE and provides espiteit ACTION regu ts if one ECC subsystas is insperable.
Under the r6quirements of Spect catten 3.0.3, both the required ECCS subsystems are inoperable, withi 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> seas s must be initiated to place the unit in at least ICT STA28Y la the at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least NOT SWTDOW within the feitawing 5 at fmther evearle. Specification 3.6.2.1 requires two Containment Spra Sy s to be OPERABLE and provides I
a W, explicit ACTION requirements if one $p System is (noperable. Gnder the N
requirements of Specification 3.0.3 f f th the required Containment Spray Systems are inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a res must be inittsted to place the v
unit in at least lei stale 8Y within ne 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in at least leT SWTDOW 1
A within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and n COLD wIthinthesubsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 'It is acceptable to i tlate and c lete a reduction in OPERATIOEL 9
800ES in a shorter time interv than required the ACTION statament and to i
t-add the unused portion of thi allevable out-of-rvice time to that provided l
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for operation in seseguent r OPERATIOEL
).
Stated alleueble v pr out-of-service times are licable regardless of OPERATIOEL 8eDE(5) in 4
which the inoperability i discovered but the times vided for achieving a -
mode reduction are not licable if the inoperabi.11ty s discovered in a mode t'
10 lower than the appli e nose. For example, if the Co inment Spray Systee M'
was discovered to be noperable while in STARTUP, the AC Statement would allow up to 156 to achieve COLD SWT00m. If leT ST Y is attained in 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> rather n the a11 owed 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />,140 hours would s III he available before the plan uld be required to be in COLD SWTDOW.
ver,.if this l.
system was dis wered to be inoperable while in ICT STAND 8Y, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided to ieve 00T STAND 8Y would not be additive to the ti available to achieve LD SWTDOWN so that the total allowable time is red d free 156 hours0.00181 days <br />0.0433 hours <br />2.579365e-4 weeks <br />5.9358e-5 months <br /> 150 hours.
3.
4 This specification provides that entry into an OPERATI ICDE or l
i ether cified applicability condition must be made with: (1) the ful complement o
of utred systems, equipment, or components.0PERABLE, and (2) all othe par ters as specified in the Limitine Conditions for Operation being me w hout regard for allowable deviations and out-of-service provisions ntained in the ACTION statements.
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ICABILITY 5
1stant of this provision is to ensure that facility operation initia s not with either required equipment er systans inoperele or et r sMified 1_
limits l
ag enceeded.
I-i Encep ons to this prevision have been provided for a list na ber of specificatt when STARTLP with inoperable equipment would not ffectt.lant y
safety. Thes eaceptions are. stated in the ACTIOR statements the appropriata ificetiens.
t 3.0.5 W s 1HeaMon GeMneates the appHeaMH of each specifica-
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tien to Unit 1 it I speretten, i
k 4.9.1 TMs fication provides that surveilla activities necessary to ensure the Limitin Condittens for Operetten are and will be performed I.
during the OPERATIONA.
er other confittens for ich the Limiting Condi-tiens for Operetten are licable..Provistens for addittenal surveillance activities to be perto thout regard to the licable OPERATIONAL 800E5 l
4 or other condittens are p ded in the indivi Surveillance Seguirements.
Surveillance Requirements fo Special Test Esc tiens need only be performed when the special Test Excepti is being util ed as en exception to an individual specification.
4.0.2 The pevvisions of this peci cation previce alloweste tolerances for perforet surveillance activit s and those specified in the nominal k
surveillance 1nterval.These toler s are necessary to provide operational flexibility because of scheduling a rformance considerations. The phrase s
3
- at least* associated with a survei a frequency does act negate this allowable tolerance value and pe ts the rformance of more frequent i
surveillance activities, y
The tolerance values, ta n either indiv 11y or consecutively ever p'
three test intervals, are s ficiently restrict e to ensure that the reliability associated wi the surveillance act ity is not significantly g
degraded beyond that ab d free the nominal s (fied interval.
j 4.0.3 The provis ns of this specification set orth the criteria for
-l determination of c iance with the OPERABILITY requi nts of the Lietting Conditions for Oper ion. Under these criteria, equi t, sydeos, or components !
are assumed to be ERABLE if the associated surveillance etivities have been
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satisfactorily formed within the specified time interva flothing in this provision is construed as defining equipment, systees, r components OPERABLE, whe such it.ees are found or known to be inoperable 1though still l
meeting the urveillance Requirements. Items may be determine inoperable during use during surveillance tests, or in accordance with thi specification.
Therefo ACT]ON statements are entered when the Surveillence Re irements should ye been perfereed rather than at the time it is discovere hat the tests re not performed.
4.0.4 This specification ensures that the survelliance activities sso-ted with a Limiting Condition for Operation have been performed withi the c
ecified time interval prior to entry into an OPERATIONAL MODE or other a li-cable condition. The intent of this provision is to ensure that surveillan SRAIDWOOD - UNITS 1 & 2 8 3/4 0-2 t
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activities ve been satisfactority demonstrated en a current basis as required to t the OPERABILITY requirements of the Lietting Condit for
. Operation.
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'Undertheth of this specification, for esemple, durt nitial fi. int l
STARTUP or followf extenced plant outages, the applicable s 111ance activities must be rfereed within the stated surveillance rval prior to
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placing er esterning system er equipment ints OPERAB tatus.
[l 4.0.5 This specif tion ensures that faservice spection of ASE Code Class 1, 2 and 3 camponen and inservice testing of Code Class 1, 2 and 3 peps and valves will be rformed in accordance th a perledically updated i
version of Section XI of the Boiler and Pres re Wessel Code and Adeanda as required by 10 CFR 60.55a.
elief free a v the above requirements has been provided in writing by the camission s not a part of these Technical Specifications.
This specification includes a arif stion of the frequencies for performing j
the inservice inspection and testing vities required by Section XI of the Fy ASME loller and Pres:gre Wessel.Ced:
applicabla Asser.aa. -Tai 6 clarst scatiw.
is provided to ensure consistency i 111ance intervals throughout these 4,
Technical Specifications and to ve a ambiguities relative to the
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frequencies for performin0 the trod ins ice inspection and testing
.ctivities.
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Under the teras of thi specification, the re restrictive requirements h
of the Technical Specific tons take procedence er the ASE Ooiler and J
Pressure Wessel Code a applicable Aedenda. For ample, the requirements of g
T 5pecification 4.0.4 to rfore surveillance activit s prior to entry into an OPERATIONAL MODE or her specified applicability co ition takes precedence l
i over the ASE Soil and Pressure Wessel Code previst which allows pumps to be tested w to ek after return to normal operation. And for example, I
the Technical cification definition of OPERABLE does grant a grace l
period before device that is not capable of performing it specified function I
L is declared noperable and takes precedence over the ASME to er and Pressere l'
I Vessel C provision which allows a valve to be incapable of rforming its specifie function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared ino rable.
. 0. 6 This specification delineates the applicability of t surveillance
.l acti ities to Unit 1 and Unit 2 operations.
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Specification 3.0.1 through 3.0[ stab 11sh the general requirerer.ts spolicable no Lietting conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, lo CFR 50.36(c)(2):
'Lietting conditions for operation are the lowest functional capability or performance levels of equipment etouired for safe operatica of the facility. - When a limiting condition for operation of a nuclear reactor is not set, the licensee shall shut down the reacter or follow any remedial action permitted by the technical specification untti the condition can be set.'
Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Lietting Conditions for Operation is required for safe operation of the' facility. The ACTION requirements establish those remedial measures that must to taken within specified time limits when the requirements of a Lietting Condition for Operation are not met.
There are two basic types of ACTION requirements. The firrt specifies the remedial measures that persit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements, in this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION recuirements continue to be met. The second type of ACTION requirement specifies a ti-r:
limit in which conformance to the conditions of the Limiting Condition for Operation s'ust be met. This time limit is the allowable outage time to-restore er inoperable system or component to 0FERABLE status or for restoring parameters within specified limits. If these actions are not ccrpieted withe the allowable outage time limits, a shutdown is required to phre the f acility in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION reovirements be used as an operational convenience which permits-(routine) voluntary removal of a systamb) or component (s) from service in lieu of other alternatives that wwM not result in redundant systems or components being inoperable.
The specified time limits of the ACTION requirements are appliw;Ie from the point in time it is identified that a Limiting Corditinn for Operation is not met. The time limits of the ACTION requirements are also applicable when a systee or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the completion of a Surveillance Pequireernt when equipment is removed free service. In this case, the allowable cut aga ttre
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3/4.0 APPLICABILITY SA$E$ L N limits of the ACTION reovirements are applicable when this limit espires 1.
the surveillance has not been coupleted. When a shutdewn is reoutred to comply with ACTION reovirements, the plant may have entered a MODE in which a new specification becomes applicable. In this case, the tine Ilmits of' the ACTION requirements would apply from the point in time that the t.ew specification becomes applicable if the requirements of the lieting Condition for Operation are mot met.
$>ecification 3.0.? establishes that noncompliance with a specification exists wwn the reovirements of the Limiting Condition for Operation are not met and
.I the associated ACTION requirements have not been implemented within the specified time intervA1. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within-the specified tire Interval constitutes compitance with a specification and (2) canoletion of the' remedial measures of the ACTION requirements is not required when compliance with a Lleiting Condition of Operation is restored within the tine internal specified in the associated ACTION requirements.
Specification 3.0.3 establishes the shutdown ACTION requirements that must 5 taplemented when a Limiting Condition for Operation is not met and the-condition is not specifically addressed by the associated ACTION requirecerits.
i The purpose of this specification is to delineate the time lirits for placi.g
'the unit in a safe shutdown MODE when plant operation < arnet be t cir.tair.e.'
within the limits for safe operation defined by the Limiting Concitions for
.0peration and its ACTION requireeents. It is not intended to be used as an operational convenience which perrits (routine) voluntary rannai of redundant
-systems or components free service in lieu of other alterratius t5st would not result-in redundant systars or components being increrable. Cre teur is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to ccordina'e the redLction in electrical generation with the load dispatcher to eneure the stabillt) and availability of the electrical grid. The time limits 5;r if tM tn "3cb %.r MODES of operation perwit the shutdown to proceed in a cor:rn: led and orderly manner that is well within the specified manir um cof A *n r"* yd within the cooldown capabilities of the f acility assuring only tne minirvr reoutred equipment is OPERAuts. This reduces thermal stresses on c cn nents of the primary coolant system and tM antential for a plant up:et that could challence safety systems under conditions for which this specificet me 3:r!!es.
If remedial measures permitting Ilmited continued operation of the facility under the provisions of the ACTION requirements are crepletA1, t'e shutdown may be terminated. The time limits of the ACTION requircrents are arplicable from the point in time there was a failure to meet a limiting (Wition for Operation. Therefore, the shutdown may be termintted if the ACilM requirements have teen met or the time limits of the iCil0h twois. cents have not expired, thus providing an allowance for the certrietion ni ne requiral attions.
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BASES ' t 'd The time llatts of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for & plant to 1 in
. l the COLD SHUT 00WN MODE when a_shutd:wn is requ' rad 6 ring the POfER '400E af operation. If the plant is in a Icwer % DE of :rerat Mr when a shutdevn is required the time limit for reachirg the next Imr MDtf et varttien 90-plies. However, if a lower MODE of naeration is reached la 'ef s (One tFan j
allowed, the total allowable time to reach COLD tw.itrW, or etbar **pitceble MODE. is not reduced. For example, if h0T $7.8.'CBY is res:r?d tn 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTOOWN is the next 11 hcurs because the total time to reach NOT SHUTDOWN is not reduced from the allowable Ilmit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
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Therefore if remedial measures are c mleted that wrdi fa.mit a reture, to POWER operation. a penalty is not incurred by having to reacn a lower ITUE of operation in less than the total ti:ae 411cwed.
The same principle applfes with regard to the.s11cwabla cuttge tire limits of the ACTION requirements. If compliance with the ACT10ft rtoutrements for cne specification results in entry into a MODE or condition of n$erition f.)r another specification in which the requirerents of the Lim!ti g Condition for Operation are not met. If the new specification becas ippilcable in less time than specified. the difference may be added to the allwable outage t!:a limits of the second specification. However, the allwa' ale outsge tise 11' sits of ACTION requirements for a higher MODE of eperati:n 'nay rot be u:?d to ':: tend the allowable outage time that is applicable when s L*miting Co d't'an ':;r Operation is not est in a 1 ewer P0 lit of operation.
The shutdown requirements of Specification 3.0.3 dB not wply h :800ES 5 srd
- 6. because the ACTION requirements of individual specificati. irs.'?f he the remedial seasures to be taken.
Specification 3.0.4 establishes Itaitations on M00! c%;ts +en i Lfatting Conottion for operation is not met.
It precludes pisci.19 tr.e ficility :n a higher 800E of operation when the requirements for a I I niti ; conditlen for Operation are not met and continued noncespliance to :'iese cerditions would result ta a shutdown to comply with the ACTION requirerents if a *:harje in MODES were permitted. The purpose of this specification is :e encure that facility operation is not initiated or that higher enES of sparition tre not entered when corrective action is being taken to ebhh compilance 9ith a specification by restoring equipment to OPERAPLE <ht's or parem =+e" to specified limits. Cosp11ance with ACTION requirwets that pe.rvH c ntimd operation of the facility for an unilmited perled of th e rv. ides in accept-able level of safety for continued operation without ragard to the status of the plant before or after a MODE change. Therefore, in this cise tntry into an OPERATIONAL PODE or other specified condition my 'u' Wa la m edance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted is ender * 't t'ie failure to esercise good practice ir restoring systems or cer.Torents to UE MBLE status before plant startup.
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'NC O y S.O E AI.ana an L mf.an L.lh ef Mc4 sp d.a.a n M to Wr /eas iL., g apn,.g 3/4.0 APPLICABILITY BASES L N When a shutdown is required to temply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the f acility in a lower MODE of operation.
5pecifications 4.0.1 throvoh 4.0#estab11sh the general requirements applicable to 5urve111ance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Repulations, 10 CFR 50.36(c)(3):
" Surveillance requirements are requirements relating to test, calibra-tion, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met.'
$pecification 4.0.1 establishes the rew.trement that surveillances must be perforved during the OPERATIONAL 8CDES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this spect-fication is to ensure that surveillances att performed to verify the opera-tional status of systems and temponents and that parameters are within spect-fled limits to ensure safe operation of the facility then the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL pp0E for which the reovirecients of the associated Limiting Condition for Operatioerdo not apply unless otherwise specified. 1he Surveillance Requirements associated with a special fest Exception are only applicable when the Special Test Exception is used as an allowable enception to the requirements of a specification.
Specification 4.0.7 establishes the conditions under which the specified time interval for Survelliance Requirements may be entended. Itee a, permits an allowable extension of the normal surveillance ifiterval to facilitate surveillance scheduling and consideration of plant operating conditions t%t may not be suitable for conducting the surveillance; e.g., transient ccnditions or other ongoing surveillance or asintenance activities. Iten b. limits the use of the provisions of ites a to ensure that it is not used repeatedly to estend the surveillance interval btyond that specified. The limits of Specification 4.0.7 are based on engineering judgment and the recnoritier that the most probable result of any particular surveillance being perforre/ it t%
verification of conformance with the Surveillance Requirements. These ornvis ors are sufficient to ensure that the reliability ensured through surveillance actisities is not significantly degraded beyond that obtained from the specified surveillance interval.
Lcitication 4.0.3 establishes the failure to perfore a Surveillance SRequirerient within the allowed surveillance interval, defined by the provisines of Srecificatf on 4.0.7. as a condition that constitutes a failure to meet t*e Untier N OPf VPHITY requirements for a limiting Condition for Operation.
9 3/4.0 4 Btubu:ce4 d u.T s N
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hv.sn b st 3/4.0 APPt!CASTLfTY BASE $ 5'M pro <isions of this specification, systems and components are assumed to be 04f RABLE when Surveillance Requirements have been satisfactorily perfomed within the specified time interval. However, mothing in this provision is to be co strued as implying that systems or components are OPERABLE when they are found or known to be inoperable although st111 meeting the Surveillance-Requirements. This specification also clariffes that the ACTION requimments are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time Ilmits of the ACTION requirements apply from the point-la time it ts fdentified that a surveillance has not been performed and not at the time that the allowed surveillance interval was esceeded. Completion of the Surveillance Requirement within the allowable outage time Itmits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3. However, this does met negate the fact that the failure to have performed the surveillance within the allowed survet11ance interval, defined by the previsions of Specification 4.0.F. was a violation of the OPERASILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further. the failure to perfom a surveillance withic the provisions of Specification 4.0.2 is a otolation of a Technical Specification requirement and is,)therefore, a reportable event unde the reevirements of 10 CFR 50.73(a)(2)(1)(B because it is a condition prohibited by the plant's Technical Specifications.
If'the alloueble ontage ties Ilmits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to cessly with ACTION reevirements, e.g..
l-Specification 3.0.3. e 24-hour allemence.is providfd to permit a delay in.
implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose' of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before-other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning. eva11 ability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the_ required suryejllanced hitslHi41sloCalioTrovides a time limit for the (completion of SurveitlaFee Requirements that become applicable as a consecuence.
I of MODE changes imposed by ACTION requirements and for completing Surveillance Requirement:, that are applicable when an exception _to.the requirements Ef._
i
-Specification 4.0.4 is. allowed.7f1 sGWilliance is not completed within the 74-hour allowance, the time limits of the ACTION requirements are applicable at H
that time.
When a surveillance is p' rfomed within the 24-hour allowance and e
the Surveillance Requirements are not met, the time limits of the ACTION l
requirements are applicable at the time that the surveillance is teminated.
Surveillance Requirerents do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.
However, the Surveillance Requirements have to be met to demonstrate that inoperable equinnent has been restored to 0PERABLE status.
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i 5pecification 4.0.4 establishes the requirement that all applicable surveillances 1
swst be met before entry into en OPERATIONAL M or other condition of
- eperation specified in the Applicability statement. The purpose of thit 3
specification is to ensure that system and cosponent OptRAtiLITY requirements t
er parameter limits are set befom entry tote a 900E er condition for a41ch these systems and components ensure safe operation of the facility. This 3
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provision applies to changes in OptRATIONAL p50t$ or other spectfled conditions L
esso (lated with plant shutdown as sell as startap.
Under the provisions of this specification, the applicable Serve 111anc'e'
~
Requirements must be perfomed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plar.t startup or following a plant eutage.
When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the factitty in a lower SODE of operation.
Specification 4.0.5 establishes the requirement that inservice inspection of Amt Code class 1. 2. and 3 components and inservice testing of ASE Code Class 1. 2. and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section II of the ASME Setter and pressure-Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply L
except when relief has been provided in writtog by,the Cannission.
i This specification includes a clartftcation of the frequencies for perfoming the intervice inspection and testing activities required by Section II of the ASME Boiler and pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities, h
Under the teres of this specification, the more restrictive requirements of f
the Technical Specifications take precedence over the ASME poiler and pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4
[
to perfora surveillance activities before entry into an OPERATIONAL MOM or g
other specified condition takes precedence over the ASME Soiler and pressure Wessel Code provision which allows pumps and valves to be tested up to one week after return to nomal operation. The Technical Specification definition I
of CPERABLE does not allow a grace period before a component, that is mot g
[
i capeble of performing its specified function. is declared inoperable and takes precedence over the ASME Boiler and pressure Vessel Code provision which l'
allows a valve to be incapable of perforwing its specified function for up to 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> before being declared inoperable.
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p ATTACHKENI D 1
DESCRIfR ON AHE.31&fBRY OF PROPOSED CHANGES As a part of recent initiatives to improve Technical Specifications, the NRC in cooperation with the Atomic Industrial Forum
-(Alf), has developed a program for Technical Specification improvements.
One of the elements of this program'is the implementation of short-term improvements to resolve immediate concerns that have been identified in investigations'of Technical Specification problems by both NRC and Alr. The guidance provided in Generic Letter 87-09 addresses three specific problems that have been encountered with the general requirements on the applicability of Limiting Conditions for Operation (LCO) and Surveillance Requirements in Sections 3.0 and 4.0 of the Standardized Technical Specifications. The proposed changes to Technical Specifications 3.0.4, 4.0.3 and 4.0.4 address these problems.
The first change involves revising Technical Specification 3.0.4, the~ bases section for 3.0.4, and several specifications that reference 3.0.4 This change addresses the problem, as stated in Generic Letter 87-00, involving unnecessary restrictions on mode changes by' Specification 3.0.4, and inconsistent application of exceptions to it.
The practical solution is to change this specification to define the conditions under which its requirements apply. With respect to unnecessary mode changes, Specification 3.0.4 unduly restricts facility operation when conformance with Action Requirements provides an acceptable level of safety for continued operation. For an LCO that has Action Requirements permitting continued operation for an unlimited period of time, entry into an operational mode or other speelfled condition of operation should be permitted in accordance with the Action Requirements. The solution also resolves the problem of inconsistent application of exceptions to Specification 3.0.4 (a) which delays startup under conditions in which conformance to the Action Requirements established an acceptable level of.
safety for unlimited continued operation of the faellity; and (b) which delays a return to power operation when the fecility is required to be in a lower mode of operation as a consequence of other Action R cuirements.
This change will prevent delays in start ups under conditions in which conformance to the Action Requirements established an acceptable levej of safety for unlimited continued operation of the facility.
The second change involves revising Technical Specification 4.0.3, and its associated bases. This chnnge addresses the problem as stated in Generic Letter 87-09, involving unnecessary shutdowns caused by Specification 4.0.3 when surveillance intervals are inadvertently exceeded.
The solution is to clarify the applicability of the Action Requirements, to
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specify a specific circumstance, and t.o clarify when a missed surveillance
^
constitutes a violation of the Operability Requirements of an LCO.
It is 3
overly conservative to assume that systems or components are Inoperable when a
a surveillance has not been performed because the vast majority of l
surveillances do in fact demonstrate that systems or components are operable. When a surveillance is missed, it is primarily a question of operability that has not been verified by the performance of a Surveillance
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Requirement. Because the allowable outage time limits of some Action Pequirements do not provide an appropriate time for performing a missed nurveillance before Shutdown Requirements apply, the Technical Specification 550uld include a time limit that allows a delay of required actions to pormit the. performance of the missed surveillance based on consideration of
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plant conditions, adequate planning, availability of personnel, the time i
required to perform the surveillance, and, of course, the safety significance of the delay in completing the surveillance.
In addition, Generic Letter 87-09 discusses, that if entry into an Action Statement that requires the unit to enter another mode or condition of operation where a surveillance is not in frequency, then revised I
Specification 4.0.3 will allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for completion before the Action Statement applien.
It is our understanding that in this scenario, the surveillance required by the new Action Statement would not constitute a misned surveillance resulting in any reporting requirements or enforcement
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A similar situation that was not addressed in Generic Letter 87-09 but was. discussed in a telephone call between Edison and the NRC on November 15, 1988, was the situation where the unit trips and enters a mode where equipment is required to be operable but the surveillance is not in frequency.
(For Examplo, the source range Instruments are required in Modas 2 (below p-6),
3, 4,
and 5.
With the unit operating in Mode 1 for a period of t ime the source range instruments are not required operable but i f t he s
unit trips, in Mode 3, the instruments are required to be operable but the surveillance is out of frequency).
It is Edison's understanding that the NRC Indicated it would be acceptable to perform the surveillance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into Mode 3.
This situation would not constitute a missed surveillance resulting in any reporting requirements or enforcement action.
For a normal shutdown, the evolution should be controlled such thot-the required surveillances would be performed prior to entering t he mode where -
the equipment would be required to be opetable.
It is not necessary to do the Analog Channel Operational test, quarterly for the source range l
instruments when the unit is in Mode 1.
The third change involves revising Technical Specification 4.0.3, 4.0.4 and their associated bases sections to eliminate two possible conflicts between Specification 4.0.3 and 4.0.4.
The first conflict as stated in Generic Letter R7-09 arises because Specification 4.0.4 prohibits entry into an operation mode or other specified condition whan Suivoillnnea Requit ements have not been performed within the specified surveillance interval. A conflict with this requirement exists when a mode change in required as a consequence of Action Requirements, and when the surveillance Requirements that become applicable have not been performed within the specified surveillance interval. Specification 4.0.4 should not be used to prevent passage through, or to operational modes as required to comply wit h action requirements because to do so would:
1 (a) increase the potential for a plent upset; and (b) would challence safety systems.
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Also, certain surveillances should be allowed to be performed during a shutdown to comply with Action Requirements. Along with the modification of Specification 4.0.3 to permit delay in the applicability of Action :<equirements. Specilication 4.0.4 ht.s been clarlfled to allow passage through or to operational modes as required to comply with Action Requirements.
A second confilet as stated in Generic Letter 87-09 could arise because, when Serveillance Requirements can only be completed af ter entry into a mode or speelfled condition for which the Surveillance Requirements apply, an emeeption to the requirements of Specification 4.0.4 is allowed.
However, upon entry into this mode or condition, the requirements of Speelfication 4.0.3 may not be met because the Surveillance Requirements mey not have been performed within the allowed surveillance interval.
It is not the intent of Specification 4.0.3 that the Action Requirements preclude the performance of surveillances allowed under any emeeption to Specification 4.0.4.
Allowance for a delay in Specification 4.0.3 for the applicability of Action Requirements will provide an appropriate time limit for the completion of those Surveillance Requirements that become applicable as a consequence of allowance of any exception t.o Specification 4.0.4.
It has been noted that some surveillances that state "4.0.4 not applienble", do involve performance t$mes in excess of the P4 hours allowed i
by this change and Generic Letter 87 09.
These specific surveillances have been identified, and changes are proposed to bound both the conditions required to perform the surveillance, as well as limits for completion of j
the surveillance. This should provide an acceptable means to establish i
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required conditions, as well as set a reasonable completion requirement.
These limits are all based on prior emperience, vendor recommerdations f or condition to perform them under and engineering judgement.
The fourth change involves the surveillance frequencies for the testing of nuclear instrumentation. Currently, the single point comparison of incore to encore anlal flux difference and the incore encore calibrations are being performed every 31 and 92 days respectively. These checks and calibrations are core exposure related parameters.
In the case of an i
entended period of low power o?; rations or outage - onditions reper formance of those surveillances would not be warranted. Tsc proposed revision will change the frequency of performance of these surveillances from a flued d
frequency to en exposure related frequency. This change has been previously reviewed and approved for Vogtle Unit 1.
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e ATTACitiEKI_C S hirJLEY1MAnoti.JdilLittufOidNIALAS $1E Stir #7 In Generic Letter 87-09, the HRC staff has concluded that these modifications will result lu Improved Technical Specifications for all plants. Licensees and applicants have been encouraged to propose changes to their Technical Specifications that are consistent with the guidance provided in the enclosures to Generle letter 87-09.
Specification 3.0.4 unduly _ restricts facility operation when conformance to the Action Requirements provides an acceptable level of safety for continued operation. For a Limiting Conditions for Operation (LCO) that has Action Requirements permitting continued operation for an unlimited period of time, entry into an operational mode or other speelfled condition of operation should be permitted in accordance with those Action Requisements. This is consistent with the NRC's regulatory requirementa for an LCO. The restriction on a change in operational modes or other speelfled conditions should apply only where the Action Requirements establish a speelfled time interval in which the LCO must be met or a shutdown of t he facility would be requires. Good practice should dictate that the plant st art up should normally bo initiated only when all required equipment is operable and that startup with inoperable equipment must be the exception rather than the rule.
It in overly conservative to assume t hat systems or components are inoperable when a surveillance requirement has not been performed. The opposite is in fact the cese; the vast majoilty of surveillances demonstrate that systems or components in fact are operabic. When a surveillance is talssed, It is ptimarily a question of operability that has not been verlfled by the performance of the required surveillance. Because the allowable outage time limits of some Action Requirements do not provide an appropriate time limit for performing a missed surveillance before shutdown regulsements may apply, the Technical Specification should include a time limit that would allow a delay of the required actions to permit the performance of the missed surveillance. This time limit should be based on considerations of plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, as well as the safety significance of the delav in completion of the surveillance.
It is reasonable to conclude that most surveillances could be performed wit hin a 24 hout perand, however several surveillances due to the time f rames involved in achieving required plant conditions and with complem l-eniculations and computer run tline, may require additional time to be completed when being done in a continuous manner. Due to the surveillance l
performance times involved, it is necessa.y to estend the NRC Gene:Ac Lette 87-09 time frame of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to include these specific surveillance l
performance times. Any surveillance found with performance times in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> have been provided with bounding limits to dictat a timely completion.
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It is not the intent of Speelfication 4.0.3 that the Action E
Requirements should preclude the performance of a surveillance when an exception to Specification 4.0.4 is allowed. However, slece Specification i
4.0.3 has been changed to permit a delay in the applicability of the Actioni Requirements, an appropriate time limit will now esist for the completion of those Surveillance Requirements that become appilckble when an esceptioni to-L Specification 4.0.4 1s allowed.
t These amwndments do not involve a change in the installation or use of the faellities or components located within the restricted areas as defined in 10 CFR 00.
Commonwealth Edison has determined that these amendments involve no significant increase in the amounts, and no l'
' significant change in the types, of any effluents that may be released of f site. and that t here is no significant increase in Ind!vidual or cumulntive occupat.lonal radiction caposure. Accordingly, t hene amendments meet the eligibility criterla for categorical exclusion set fotth in 10 crR Sec. 51.22(c)(9). Pursuant to 10 CfR $1.22(b) no environmental impact statement or environmenital arsessment need be. prepased in connection w!th i
the issuance of these amendments.
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Commonwealth Edison has evaluated this proposed amendment and i
determined that it involves no significant hasarde consideration. According to 10CTR 50.92(c), a proposed amendment to an operating license involves no significant hasards considerations if operation of the feellity in accordance with the proposed amendment would nott 1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)
Create the possibility of a new or different kind of ace! dent from any accident pieviously evaluateds or 3)
Involve a significant reduction in a margin of safety.
The proposed changes involve Technical Specifications 3.0.4, 4.0.3 and 4.0.4.
plus those technical speelfications that are affected by these-sectionr. These changes ate being made and requested in accordance with NRC dene:Ac Letter 87+09, issued on June 4, 1987.
The first change involves Specification 3.0.4, its bases, and associated Technical Specifications that. teference it.
Inconsistent application of exceptions to Specification 3.0.4 impacts the cperation of the faellity in two ways.
First, it delays startup under conditions in which conformance to the Action Requirements establishes an acceptable level of safety foi unlimited continued operation of the facility. Second, it delays a return to power operation when the facility la required to be in a lower mode of operation as a consequence of other Action Requisements. In this case, the Limiting Condition for Operation must be met without reliance on the Action Requirements, before returning the facility to that operational inode or other specifled condition f or which unlimited continued operation was previously permitted, in accordance with the Action Requi re nents. As a consequence of the change to Speelfication 3.0.4 Speeltications with Action Requirements that permit continued operations no longer need to reference "3.0.4 is not applicable".
The second and third changes involved Specifications 4.0.3 and 4.0.4.
Some Action Requirements have allowable outage time limits t hat do not allow sufficient time for the completion of a missed surveillance.
before the Action Requirements would necessitate a plant shutdown.
If a plant shutdown is required before a mlued survelllance is compicted, it is likely that the surveillance would be conducted during the shutdown in an effort to terminete the shutdown requirement. This cirewnstance is undesirable for two reasons:
(a) increased pressures on plant staff to complete the surveillance could lead to errors that may result in plant upset, and I
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- (b) the plant would be in a transient state involving potential upsets to the plant that could require a demand for the system when the system is removed from service for testing.
The proposed changes will also help clarify the potential cont 11 cts between Speelfications 4.0.3 and 4.0.4.
The first conflict could arise when a plant shutdown is required as a constquence of an Action Requirement.
This will require surveillances to become due prior to entry into a lower mode. This could result in delays in reaching lower modes as a result of a Technical Specification Action Requirement.
The second conflict could arise when Surveillance Requirements can only be completed after entry into a mode or specified condition for which the Surveillance Requirements apply, and an exception to the requirements of
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Speelfication 4.0.4 is allowed.
Ilowever, upon entry into this mode or condition. the requirements of Specification 4.0.3 inny not be met because the Surveillance Hequirements may not have been perf ormed within t he allowed surveillance interval. Allowing for a delay in the applicability of Action Requirements for Speelfication 4.0.3 will provide an appropriate time limit fos the completion of Suaveillance Requisements that are allowed an q
exception to Specification 4.0.4.
state "4.0.4 not applienble", 60It has been noted that some surveillances that involve performance times in excess of the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by this change and Generic Letter B7-09.
These specific surveillances have been identitled, bound the conditions required to per form the surveillance,and changes are proposed to as well as limits for completion of the surveillance. This should provide an acceptable means to establish required conditions, as well as set a reasottable completion requirement.
The fourth change involves a revision to the incore-escore i
surveillance frequency.
Currently, the single point compatison of incore to encore axial flux difference and the incore encore calibrations are being performed every 31 and 92 days respectively.
These checks and callhrations are cose exposure related parameters.
In the case of an extended period of low power operations or outages, re-performance of these surveillances would not be warranted.
The proposed revision will change the frequency of these surveillances from a fixed frequency to an exposure related frequency.
This change has been previously reviewed and approved for Vogtle Unit 1.
The proposed changes do not increase the probability or consequences of a accident previously evaluated.
In regards to the first change. systerns and equipment that hnve indefinit e allowable outage times have been shown not to have a direct impact on accidents.
In regards to the j
second and third change, surveillance requirements are defined in 10 CFR 50.36 as those requirement s that essure the necessary quality of symtems and components are maintained such that safety limits are maintained and limiting conditions for operhtlon are met under t hese changes.
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eppropriate surveillances will still be performed.
The proposed chances wilj only allow flexibilit y in per f or ming t.hese surveillance r equi r ement s pttot t o a plant shutdown heing necessitated in the case of a sutveillance being inadvertently missed, h
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l The conditions and bounding limits proposed on several surveillances are necessary due to the fact that these surveillances cannot be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entry into the required mode. These surveillances in some cases require specific power levels and stability to perform. The limitations chosen do not differ from the present method in which these surveillances are performed. Limitations are speelfled to ensure surveillance completion.
In regards to the fourth change, the required surveillances will still be pe formed. The bases for these surveillances is to calibrate and check the calibration of the encore instruments using the incore instruments. These checks and calibration are required due to shifting flun proflies due to flus redistribution. Flum redistribution is primarily a function of core depletion and not time. The proposed change will tie the performance of these surveillances to a direct measurement of core depletion.
The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. No new equipment is bping introduced as a result of the changes. These changes do not result in equipment being operated in a manner different from present requirements. No change is being made which alters the function of any plant equipment.
The proposed changes do not involve a significant reduction in a 1
margin of safety.
In regards to the first change, conformance to Action Requirements that permit continued operation of the facility have been shown to provide an acceptable level of safety for indefinite operation.
In regards to the second and third changes, allowing an appropriate time period for performance of a missed surveillance, a surveillance required by entry into an action statement or performance of one precluded by plant conditions, would in effect reduce the possibility for a potential plant upset.
In regards to the fourth change, the surveillance frequencies involved are changes due to the parameters being core deplet. ion dependent.
'the best measure for this is in effective full power days. Hense, the proposed change will not reduce the margin of safety, based on its performance being tied to a depletion based frequency.
Therefore, based on the above evaluation, Commonwealth Edleon believes that these changes do not involve significant hasards considetetion.
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