ML20078S821

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Amends 131,125,152 & 148 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,upgrading Sections 1.0,3.0/4.0 & 3/4.3 of Plants TS Re Definitions,Applicability & Reactivity,Per 920729 Request
ML20078S821
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 02/16/1995
From: Stang J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078S827 List:
References
NUDOCS 9502270251
Download: ML20078S821 (61)


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NUCLEAR REGULATORY COMMISSION k..... /

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t COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. DPR-19 l.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, 1993, and February 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The. facility will operate in conformity with the application, the

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prcwisions of the Act and the rules and regulations of the Commission; 1

C.

'There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; i

and E.

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

l 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:

9502270251 950216 PDR ADOCK 05000237 P

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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 131, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented no later than December 31, 1995.

4 FOR THE NUCLEAR REGULATORY COMMISSION L

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un F. Sta

, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation I

Attachment:

Changes to the Technical Specifications Date of Issuance: February 16, 1995 y

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t UNITED STATES NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20085-0001

%,.....j COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. DPR-25 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, 1993, and February 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:

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B.

Technical - Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.125, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and l

shall be implemented no later than December 31, 1995.

FOR THE NUCLEAR REGULATORY COMMISSION C \\.

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'hn F. Stan, Senior Project Manager Project Directorate III-2 l

Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation I

Attachment:

Changes to the Technical j

Specifications i

Date of Issuance: February 16, 1995 7

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g ATTACHMENT TO LICENSE AMENDMENT NOS. 131 AND 125 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment numbers.

UNIT 2 UNIT 3 BEMQYE REMOVE INSERT 1.0-1 1.0-1 1-1 1.0-2 1.0-2 1-2 1.0-3 1.0-3 1-3 1.0-4 1.0-4 1-4 l.0-5 1.0-5 1-5 1.0-6 1.0-6 1-6 1-7 1-8 1-9 l

3.0-1 3.0-1 3/4.0-1 3.0-2 3.0-2 3/4.0-2 B 3.0-3 B 3.0-3 3/4 0-3 B 3 4.0-1 B 3 4.0-2 B 3 4.0-3 B 3 4.0-4 B 3/4.0-5 B 3/4.0-6

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Definitions 1.0 1.0 DEFINITIONS i

The following terms are defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these l

Technical Specifications.

l ACTION ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.

AVERAGE PLANAR EXPOSURE (APE)

The AVERAGE PLANAR EXPOSURE (APE) shall be applicable to a specific planar height and is 1

equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATE (s) for all the fuel rods in the specified bundle at the specified height divided by the number of fuel j

rods in the fuel bundle.

CHANNEL A CHANNEL shall be an arrangement of a sensor and associated components used to evaluate plant variables and generate a single protective action signal. A CHANNEL terminates and loses its identity where single action signals are combined in a TRIP SYSTEM or logic system.

CHANNEL CAllBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the CHANNEL output such that it responds with the necessary range and accuracy to known values of the parameter which the CHANNEL monitors. The CHANNEL CALIBRATION shall encompass the entire CHANNEL including the required sensor and alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping or total CHANNEL steps such that the entire CHANNEL is calibrated, CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of CHANNEL behavior during operation by observation. This determination shallinclude, where possible, comparison of the CHANNEL indication and/or status with other indications and/or status derived from independent instrument CHANNEL (s) measuring the same parameter.

DRESDEN - UNITS 2 & 3 11 Amendment Nos.131 & 12 l

i Definitions 1.0

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1 1.0 DEFINITIONS l

' CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog CHANNEL (s)- the injection of a simulated signalinto the CHANNEL as close to

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the sensor as practicable to verify OPERABILITY including required alarm and/or trip functions and CHANNEL failure trips.

i b.

Bistable CHANNEL (s) - the injection of a simulated signal into the sensor to verify OPERABILITY including required alarm and/or trip functions.

i The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total CHANNEL steps such that the entire CHANNEL is tested.

CORE ALTERATION i

CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuelin the vessel. Normal movement (including replacement) of the SRMs, IRMs,- TIPS, LPRMs, or special movable detectors is not considered a CORE ALTERATION.

Suspension of CORE ALTERATION (s) shall not preclude completion of the movement of a component to a safe conservative position.

l CORE OPERATING LIMITS REPORT (COLR)

The CORE OPERATING LIMITS REPORT (COLR) shall be the unit specific document that provides core operating limits for the current operating cycle. These cycle specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.6. Piant operation within these operating limits is addressed in individual specifications.

CRITICAL POWER RATIO (CPR)

The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the applicable NRC approved critical power correlation to cause some point in the assembly to experience transition boiling, divided by the actual assembly power.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT l 131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic rnixture of I-131,1-132, l-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors For Power and Test Reactor Sites."

FRACTION OF RATED THERMAL POWER (FRTP)

The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.

DRESDEN - UNITS 2 & 3 1-2 Amendment Nos.131 & 125 l

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FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1.

i FUEL DESIGN LIMITING RATIO,(FDLRX)

The FUEL DESIGN LIMITING RATIO (FDLRX) shall be the limit used to assure that the fuel operates within the end-of-life steady-state design criteria by, among other items, limiting the release of fission gas to the cladding plenum.

FUEL DESIGN LIMITING RATIO for CENTERLINE MELT (FDLRC)

The FUEL DESIGN LIMITING RATIO for CENTERLINE MELT (FDLRC) shall be the limit used to assure that the fuel will neither ex;. "ience centerline melt nor exceed 1 % plastic cladding strain for transient overpower ever beginning at any power and terminating at 120% of RATED THERMAL POWER.

IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE shall be: a) leakage into primary containment collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b) leakage into the primary containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

LIMITING CONTROL ROD PATTERN (LCRP)

A LIMITING CONTROL ROD PATTERN (LCRP) shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE (LHGR)

LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST (LSFT)

A LOGIC SYSTEM FUNCTIONAL TEST (LSFT) shall be a test of all required logic components, i.e., all required relays and contacts, trip units, solid state logic elements, etc, of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MINIMUM CR!TICAL POWER RATIO (MCPR)

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

DRESDEN - UNITS 2 & 3 1-3 Amendment Nos.131 & 12!

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Definitions 1.0 1.0 DEFINITIONS L

OFFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and l

liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alar.n/ Trip l

Setpoints, and in the conduct of the Environmental Radiological Monitoring Program..The 1

ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8 and (2) descriptions of the information that should be included in the Annual Radiological Environmenta! Operating and Semi-annual Radioactive Effluent Release Reports required by Specification 6.6.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE An OPERATIONAL MODE, i.e., MODE, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1-2.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14 l

of the FSAR,2) authorind under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall.

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DRESDEN-UNITS 2 & 3 14 Amendment Nos.131 & 12!

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Definitions 1.0 1.0 DEFINITIONS PRIMARY CONTAINMENT INTEGRITY (PCI)

PRIMARY CONTAINMENT INTEGRITY (PCI) shall exist when:

a.

All primary conte.inment penetrations required to be cicsed during accident conditions are either:

1) Capable of being closed by an OPERABLE primary containment automatic isolation valve system, or
2) Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except for valves that are open under administrative control as permitted by Specification 3.7.D.

b.

All primary containment equipment hatches are closed and sealed.

I c.

Each primary containment air lock is in compliance with the requirements of Specification 3.7.C.

d.

The primary containment leakage rates are within the limits of Specification 3.7.B.

e.

The suppression chamber is in compliance with the requirements of Specification 3.7.K.

f.

The sealing mechanism associated with each primary containment penetration; e.g.,

welds, bellows or 0-rings, is OPERABLE.

PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analysis, test, and determinations tc be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

RATED THERMAL POWER (RTP)

RATED THERMAL POWER (RTP) shall be a total reactor core heat transfer rate to the reactor coolant of 2527 MWT.

REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

DRESDEN - UNITS 2 & 3 1-5 Amendment Nos. 131 & 125

Definitions 1.0 1.0 DEFINITIONS SECONDARY CONTAINMENT INTEGRITY (SCl)

SECONDARY CONTAINMENT INTEGRITY (SCI) shall exist when; All secondary containment penetrations required to be closed during accident conditions a.

are either:

1) Capable of being closed by an OPERABLE secondary containment automatic isolation valve system, or
2) Closed by at least one manual valve, blind flange, or deactivated automatic damper secured in its closed position, except as permitted by Specification 3.7.O.

b.

All secondary containment hatches and blowout panels are closed and sealed.

The standby gas treatment system is in compliance with the requirements of Specification c.

3.7.P.

d.

At least one door in each access to the secondary containment is closed.

The sealing mechanism associated with each secondary containment penetration; e.g.,

e.

welds, bellows or O-rings, is OPERABLE.

f.

The pressure within the secondary containment is less than or equal to the value required by Specification 4.7.N.1.

SHUTDOWN MARGIN (SDM)

SHUTDOWN MARGIN (SDM) shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68'F: and xenon free.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of CHANNEL response when the CHANNEL sensor is expo. sed to a radioactive source.

STEADY STATE LINEAR HEAT GENERATION RATE (SLHGR)

The STEADY STATE LINEAR HEAT GENERATION RATE (SLHGR) shall be the limit which protects against exceeding the fuel end-of-life steady state design criteria.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

DRESDEN - UNITS 2 & 3 16 Amendment Nos.131 & 12!

Definitions 1.0 1.0 DEFINITIONS TRANSIENT UNEAR HEAT GENERATION RATE (TLHGR)

The TRANSIENT LINEAR HEAT GENERATION RATE (TLHGR) shall be the limit which protects against fuel centerline melting and 1% plastic cladding strain during transient conditions throughout the life of the fuel.

TRIP SYSTEM A TRIP SYSTEM shall be an arrangement of instrument CHANNEL trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function. A TRIP SYSTEM may require one or more instrument CHANNEL trip signals related to one or more plant parameters in order to initiate TRIP SYSTEM action. Initietion of protective action may require the tripping of a single TRIP SYSTEM or the coincident tripping of two TRIP SYSTEMS.

UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage in the primary containment which is not IDENTIFIED LEAKAGE.

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DRESDEN - UNITS 2 & 3 17 Amendment Nos. 131 & 125

Definiti:ns 1.0 TABLE 1-1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY

1. Shift S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

2. Day D-At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
3. Week W

At least once per 7 days

4. Month M

At least once per 31 days

5. Quarter Q

At least once per 92 days

6. Semiannual SA At least once per 184 days
7. Annual A

At least once per 366 days

8. Sesquiannual E

At least once per 18 months (550 days) i

9. Startup S/U Prior to each reactor startup
10. Not Applicable N.A.

Not applicable DRESDEN - UNITS 2 & 3 1-8 Amendment Nos. 131 & 1;

g-t D:.finitions 1.0 TABLE 1-2 OPERATIONAL MODES r

MODE SWITCH AVERAGE REACTOR MODE POSITION'?

COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature 2.STARTUP Startup/ Hot Standby Any ter.sperature
3. HOT SHUTDOWN Shutdown'"'

> 212*F

4. COLD SHUTDOWN Shutdown'***'

s212*F

5. REFUELING'"

Shutdown or Refuel'*

  • s140*F TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.

(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.10.l.

(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.

(d) See Special Test Exceptions 3.12.A and 3.12.B.

(e) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided the one-rod-out interlock is OPERABLE.

(f) When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be inoperable.

P DRESDEN - UNITS 2 & 3 19 Amendment Nos. 131 & 12!

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Applicability 3/4.0

- 3.0 - LIMITING CONDITIONS FOR OPERATION A.

Complience with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL MODE (s) or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met, i

B.

Noncompliance with a Specification shall exist when the requirements of the L'miting i

i Condition for Operation and associated ACTION requirements are not met within the.

a specified time intervals. If the Limiting Condition for Operation is restored prior.to expiration of the specified time inter >als, completion of the ACTION requirements is not required.

C.

When a Limiting Condition for Operation is not met, except as provided in the associated

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ACTION requirements, within one hour ACTION shall be initiated to place the unit in an OPERATIONAL MODE in which the Specification does not apply by placing it, as applicable, in:

1. At least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and
2. 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 />.

I 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 failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

1 This Specification is not applicable in OPERATIONAL MODE 4 or 5.

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D.

Entry into an OPERATIONAL MODE or other specified condition shall not be made when i

the conditions for the Limiting Conditions for Operation are not met and'the associated ACTION requires placing the plant in an OPERATIONAL MODE or other specified condition of operation in which the Limiting Condition for Operation does not apply if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODE (s) as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.

f DRESDEN - UNITS 2 & 3 3/4.0-1 Amendment Nos. 131 & 125

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Applicability 3/4.0 4.0 - SURVElLLANCE REQUIREMENTS A' ' Surveillance Requirements shall be met during the reactor OPERATIONAL MODE (s)'or

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other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

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Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the surveillance interval.

-1 C.

Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.B, shall constitute noncompliance with the OPERABILITY i

requirements for a Limiting Condition for Operation. The time liniits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has j

not been performed.. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to.

l permit the completion of the surveillance when the allowable outage time limits of the i

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 />. Serveillance requirements do not have to be performed on inoperable equipment.

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Entry into an OPERATIONAL MODE or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise.

specified. This provision shall not prevent passage through or to OPERATIONAL MODE (s)'

as required to comply with ACTION requirements.

E.

Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,2, and 3 components shall be applicable as follows:

1.

Inservice Inspection of ASME Code Class 1,2, and 3 components and inservice

-l 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 50.55alg)(6)(i).

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i DRESDEN - UNITS 2 & 3 3/4.0-2 Amendment Nos.131 & 12 i

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J4.0 - SURVEILLANCE REQUIREMENTS 2.

Surveillance intervals specified in Sec'.fon XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the Iriservice inspection and testing activities required by the ASME Beiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Preasure Vessel Required Frequencies Code and applicable Addenda for performing terminology for inservice inservice inspection l

inspection and testina activities and testina activities Weekly At least once per 7 days-Monthly At least once per 31 days l

Ouarterly or every 3 months At least once per 92 days '

i Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days 3.

The provisions of Specification 4.0.8 are applicable to the above required frequencies for performing inservice inspection and testing activities.

l 4.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

j 5.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

6.

The Inservice inspection Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods, and

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personnel and sample expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

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r DRESDEN - UNITS 2 & 3 3/4.0-3 Amendment Nos. 131 & 125 l

Applicability B 3/4.0 BASES Specifications 3.0.A through 3.0.D establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations,10 CFR 50.36(c)(2):

" Limiting conditions for operation are the lowest functional capabihty or performance levels of equipment required for safe operation of the 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 permitted by the technical specification until the condition can be met."

Specification 3.0. A establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODE (s) or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The 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, it a not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or componem(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION reauirements. The first specifies the remedial measures that permit 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 requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these ACTION (s) are not completed within the allowable outage time limits, a shutdown is required to place the facility in a reactor OPERATIONAL MODE or other specified condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are 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 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 requirements, the plant may have entered an OPERATIONAL MODE in which a new specification becomes applicable. In this case, the time iimits 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 not met.

Specification 3.0.B establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION i

DRESDEN - UNITS 2 & 3 B 3/4.0-1 Amendment Nos. 131 & 125

Applicability B 3/4.0 BASES requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirement within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition for Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.C establishes the shutdown ACTION requirements that must be implemented when 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 condition when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Condition 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 permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODE (s) of operation permit 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 transient that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated 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 ACTION (s).

The time limits of Specification 3.0.C 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 COLD SHUTDOWN when a shutdown is required during POWER 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 applies.

However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL MODE, is not reduced. For example, if HOT SHUTDOWN is reached in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, the time allowed to reach COLD SHUTDOWN is the next 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> because the total time to reach COLD SHUTDOWN is not reduced from the allowable limit of 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. Therefore,if remedial measures are completed that would permit a return to POWER OPERATION, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL MODE or condition of operation for another specification in which the DRESDEN - UNITS 2 & 3 B 3/4.0-2 Amendment Nos.131 & 12E

t

- ApplicIbility B 3/4.0.

h BASES" requirements of the Limiting Condition for Operation are not met. If the new specificationL

.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 l

ACTION requirements for a higher MODE of operation may not be used to extend the allowable cutage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE cf operation.-

f p

The shutdown requirements of Specification 3.0.C do not apply in MODES 4 or 5, because the i

ACTION requirements of individual specifications define the remedial measures to be taken.

l Specification 3.0.D establishes limitations on a change in OPERATIONAL MODE (s) when a Limiting Condition for Operation is not met, it precludes placing the facility in a higher MODE of wsration when the requirements for a Limiting Condition for Operation are not met and continued i

noncompliance to these conditions would result in placing the plant in an OPERATIONAL MODE or

.other specified condition of operation in which the Limiting Condition for Operation does not apply to comply with the ACTION requirements if a change in MODE (s) were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODE (s) of l

operation or other specified conditions are not entered when corrective ACTION is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit co tinued operation of the facility for an unlimited period of time provides an acceptable level of saft ty for continuad

-l operation without regard to the status of the plant before or after a chane in OPERATIONAL MODE (s). Therefore, in this case, entry into an OPERATIONAL MODE or otner 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.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification

{

3.0.D do not apply because they would delay placing the facility in a lower MODE of operation.

i

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I DRESDEN - UNITS 2 & 3 B 3/4.0-3 Amendment Nos. 131 & 125 i

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Applicability B 3/4.0 BASES Specifications 4.0.5 through 4.0.E ntsblish the general requirements applicable to Surveillance Requirements. Thase requirements tae based on the Surveillance Requirements stated in the Code of Federal Reguir.tions,10 CFR 50.36(rJfGh

" Surveillance requirements are requirements relating to test, calibration, 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.A establishes the requirement that surveiilances must be performed during the OPERATIONAL MODE (s) or other conditions for which the requirements of the Limiting Condition for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a reactor OPERATIONAL MODE or other specified condition for which the individual Limiting Condition for Operations are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.8 establishes the limit for which the specified time interval for Surveillance i

Requirements may be extended. It permits an allowable extension of the normal 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 survWlance or maintenance activities, it also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified with and 18 month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. Likewise, i

it is not the intent that refueling outage surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Specification 4.0.B is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Regt.sments.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

j i

Specification 4.0.C establishes that the failure to satisfy a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.B, is a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time DRESDEN - UNITS 2 & 3 8 3/4.0 4 Amendment Nos. 131 & 125

Applicability B 3/4.0 BASES 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 performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the i

allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.C. However, this does not negate the fact that the failure to i

have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.B, was a violation of the OPERABILITY requirements for a Limiting Condition for Operation that is subject to enforcement action. The failure to perform a surveillance within the provisions of Specification 4.0.8 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition 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., in Specification 3.0.C), a 24-hour allowance is provided 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 would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for piant 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.D 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 w: thin 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 terminated.

~

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Surveillance Requirements 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 equipment has been restored to OPERABLE status.

Specification 4.0.D 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 an OPERATIONAL MODE or other specified condition for which these systems and components ensure safe operation of the DRESDEN - UNITS 2 & 3 8 3/4.0-5 Amendment Nos.131 & 12!

V e

Applicability B 3/4.0 t

BASES W

facility. This provision applies to changes in OPERATIONAL MODE (s) or other specified conditions associated with plant shutdown as well as startup.

t Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to assure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION statements, the provisions of Specification i

4.0.D do not apply because this would delay placing the facility in a lower MODE of operation.

Soecification 4.0.E establishes the requirement that 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 i

be performed 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 Commission.

This specification includes a clarification of the frequencies for performing 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 Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical i

Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.D to perform surveillance requirements before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one i

week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function,is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing 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.

1 DRESDEN - UNITS 2 & 3 8 3/4.0-6 Amendment Nos.131 & 12!

a Applicability B 3/4.0 BASES 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 performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable oma3e timo limits of the ACTION requirements restores compliance with the requirements e Specification 4.0.C. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.B, was a violation of the OPERABILITY requirements for a Limiting Concition for Operation that is subject to enforcement action. The failure to perform a surveillance within the provisions of Specification 4.0.B is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition 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., in Specification 3.0.C), a 24-hour allowance is provided 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 would be required to comply with ACTION requirements or before, other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planr.ing, availability of personnel, the time required to perform the surveillance, and the safety significtnce of the delay in completing the required surveillance. This provision also provides a t me limit for the completion of Surveillance i

Requirements that become applicab% as e 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.D 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 terminated.

l Surveillance Requirements 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 equipment has been restored to OPERABLE status.

1 Specification 4.0.D 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 an OPERATIONAL MODE or other specified condition for which these systems and components ensure safe operation of the j

l DRESDEN - UNITS 2 & 3 8 3/4.0-5 Amendment Nos.131 & 12f

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e I

Applicability B 3/4.0

)

BASES t

- facility. This provision applies to changes in OPERATIONAL MODE (s) 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 performed within the specified surveillance interval to assure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

l When a shutdown is required to comply with ACTION statements, the provisions of Specification i

4.0.D do not apply because this would delay placing the facility in a lower MODE of operation.

l Specification 4.0.E establishes the requirement that 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 l

be performed 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 Commission.

This specification includes a clarification of the frequencies for performing 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 Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.D to perform surveillance requirements before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME j

Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one I

week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified j

function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel i

Code provision that allows a valve to be incapable of performing 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.

1 DRESDEN - UNITS 2 & 3 B 3/4.0-6 Amendment Nos.131 & 12:

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UNITED STATES

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j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20085-0001

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COMMONWEALTH EDISON COMPANY 8MD IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 OVAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 152 License No. DPR-29 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, i

1993, and February 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; I

B.

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

There is reasonable assurance (i) that the activities authorized 1

by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be J

conducted in compliance with the Commission's regulations, D.

The issuance of this amendment will not be inimical to the common i

defense and security or to the health and safety of the public; and i

E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby i

amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

152, are hereby incorporated in the i

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

3.

This license amendment is effective as of the date of its issuance, and shall be implemented no later than December 31, 1995.

FOR THE NUCLEAR REGULATORY COMMISSION r

i Robert M. Pulsi er, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications Date of Issuance: February 16, 1995

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UNITED STATES t

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON, o.C. 20E554001

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COMONWEALTH EDISON COMPANY Alm IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 j

00AD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 148 License No. DPR-30 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, 1993, and February 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the l

Act) and the Commission's rules and regulations set-forth in 10 CFR Chapter I; l

.B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i

Commission-C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; i

and E.

The issuance of this amendment is in accordance with 10 CFR. Part 51 of the Commission's regulations and a11' applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the attachment to this license amendment, i

and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby I

amended to read as follows:

l

~

ls -

l B.

-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 148, are hereby incorporated in the license. The licensee shall operate the facility in accordance with.the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance, and shall be implemented no later than December 31, 1995.

FOR THE NUCLEAR REGULATORY COMMISSION

%n 7

R bert M. Pulsif r, Project Manager Project Directo ate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor P.agulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 16, 1995 i

ATTACHMENT TO LICENSE AMENDMENT NOS. 152 AND 148 FACILITY OPERATING LICENSE N05. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment numbers.

UNIT 1 UNIT 2 REMOVE REMOVE INSERT 1.0-1 1.0-1 1-1 1.0-2 1.0-2 1-2 1.0-3 1.0-3 1-3 1.0-4 1.0-4 1-4 1.0-5 1.0-5 1-5 1.0-6 1-6 1-7 1-8 1-9 3.0/4.0-1 3.0/4.0-1 3 4.0-1 3.0/4.0-2 3.0/4.0-2 3 4.0-2 B 3.0/4.0-3 3 4.0-3 B 3/4.0-1 B 3/4.0-2 B 3/4.0-3 B 3/4.0-4 B 3/4.0-5 B 3/4.0-6 i

Definitions 1.0

- The following terms are defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.

ACTION ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.

AVERAGE PLANAR EXPOSURE (APE)

The AVERAGE PLANAR EXPOSUi1E (APE) shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

i AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATE (s) for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

CHANNEL A CHANNEL shall be an arrangement of a sensor and associated components used to evaluate plant variables and generate a single protective action signal. A CHANNEL terminates and loses its identity where single action signals are combined in a TRIP SYSTEM or logic system.

i CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the CHANNEL output such that it responds with the necessary range and accuracy to known values of the i

parameter which the CHANNEL monitors. The CHANNEL CAllBRATION shall encompass the entire CHANNEL including the required sensor and alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total CHANNEL steps such that the entire CHANNEL is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitativa assessment of CHANNEL behavior during operation by observation. This determination shallinclude, where possible, comparison of the CHANNEL indication and/or status with other indications and/or status derived from independent instrument CHANNEL (s) measuring the same parameter.

l QUAD CITIES - UNITS 1 & 2 11 Amendment Nos.152 & 14E

Definitions 1.0 1.0 DEFINITIONS CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog CHANNEL (s) - the injection of a simulated signal into the CHANNEL as close to the sensor as practiceble to verify OPERABILITY including required alarm and/or trip functions and CHANNEL failure trips.

b.

Bistable CHANNEL (s) - the injection of a simulated signal into the sensor to verify OPERABILITY including required alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total CHANNEL steps such that the entire CHANNEL is tested.

CORE ALTERATION CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuelin the vessel. Normal movement (including replacement) of the SRMs, IRMs, TIPS, LPRMs, or special movable detectors is not considered a CORE ALTERATION.

Suspension of CORE ALTERATION (s) shall not preclude completion of the movement of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT (COLR)

The CORE OPERATING LIMITS REPORT (COLR) shall be the unit specific document that provides core operating limits for the current operating cycle. These cycle specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.6. Plant operation within these operating limits is addressed in individual specifications.

CRITICAL POWER RATIO (CPR)

The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the applicable NRC approved critical power correlation to cause some point in the assembly to experience transition boiling, divided by the actual assembly power.

DOSE EQUIVALENT l 131 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone j

would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, i

1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors For Power and Test Reactor Sites."

FRACTION OF LIMITING POWER DENSITY (FLPD)

The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle.

QUAD CITIES - UNITS 1 & 2 1-2 Amendment Nos.152 & 14 i

C; ~

Definitions 1.0 1.0 DEFINITIONS FRACTION OF RATED THERMAL POWER (FRTP)

The FRACTION OF RATED THERMAL POWER (FRTP) shall be me measured THERMAL POWER devided by the RATED THERMAL POWER.

i FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1.

IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE shall be: a) leakage into primary containment collection syster.1s,~ such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b) leakage into the primary containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

LIMITW4G CONTROL ROD PATTERN (LCRP)

A LIMITING CONTROL ROD PATTERN (LCRP) shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE (LHGR)

LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod, it is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST (LSFT)

A LOGIC SYSTEM FUNCTIONAL TEST (LSFT) shall be a test of all required logic components, i.e., all required relays and contacts,' trip units, solid state logic elements, etc, of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD)

The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

MINIMUM CRITICAL POWER RATIO (MCPR)

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core for each class of fuel.

QUAD CTTIES - UNITS 1 & 2 13 Amendment Nos. 152 & 148

l Definitions 1.0 1.0 DEFINITIONS l

OFFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specification 6.6.

OPERABLE - OPERABILITY l

A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

i i

OPERATIONAL MODE An OPERATIONAL MODE, i.e., MODE, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1-2.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14 of the FSAR,2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE PRESSURE BOUNDARY LEAKAGE sha!! be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall.

Amendment Nos.152 & 14 QUAD CITIES - UNITS 1 & 2 14

Definitions 1.0 1.0 DEFINITIONS PRIMARY CONTAINMENT INTEGRITY (PCI)

PRIMARY CONTAINMENT INTEGRITY (PCI) shall exist when:

a.

All primary containment penetrations required to be closed during accident conditions are either:

j

1) Capable of being closed by an OPERABLE primary containment automatic isolation valve system, or
2) Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except for valves that are open under administrative control as permitted by Specification 3.7.D.

b.

All primary containment equipment hatches are closed and sealed.

c.

Each primary containment air lock is in compliance with the requirements of Specification 3.7.C.

d.

The primary containment leakage rates are within the limits of Specification 3.7.B.

e.

The suppression chamber is in compliance with the requirements of Specification 3.7.K.

f.

The sealing mechanism associated with each primary containment penetration; e.g.,

welds, bellows or O-rings, is OPERABLE.

PROCESS CONTROL PROGRAM (PCP) i The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analysis, test, and dete. minations to be made to ensure that processing and packaging of solid i

radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

RATED THERMAL POWER (RTP)

RATED THERMAL POWER (RTP) shall be a total reactor core heat transfer rate to the reactor coolant of 2511 MWT.

I REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

ROD DENSITY ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of coritrol rod notches. All rods fully inserted is equivalent to 100% ROD DENSITY.

QUAD CITIES - UNITS 1 & 2 1-5 Amendment Nos.152 & 14'

l Definitions 1.0 1.0 DEFINITIONS t

SECONDARY CONTAINMENT INTEGRITY (SCI)

SECONDARY CONTAINMENT INTEGRITY (SCI) shall exist when:

a.

All secondary containment penetrations required to be closed during accident conditions are either:

1) Capable of being closed by an OPERABLE secondary containment automatic isolation valve system, or
2) Closed by at least one manual valve, blind flange, or deactivated automatic damper l

secured in its closed position, except as permitted by Specification 3.7.0.

b.

All secondary containment hatches and blowout panels are closed and sealed.

c.

The standby gas treatment system is in compliance with the requirements of Specification 3.7.P.

d.

At least one door in each access to the secondary containment is closed.

e.

The sealing mechanism associated with each secondary containment penetration; e.g.,

welds, bellows or O-rings, is OPERABLE.

f.

The pressure within the secondary containment is less than or equal to the value required by Specification 4.7.N.1.

SHUTDOWN MARGIN (SDM)

SHUTDOWN MARGIN (SDM) shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully inserted except for the i

single control rod cf highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68'F: and xenon free.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of CHANNEL response when the CHANNEL sensor is exposed to a radioactive source.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP SYSTEM A TRIP SYSTEM shall be an arrangement of instrument CHANNEL trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function. A TRIP SYSTEM may require one or more instrument CHANNEL trip signals related to one or more plant parameters in order to initiate TRIP SYSTEM action. Initiation of protective action may require the tripping of a single TRIP SYSTEM or the coincident tripping of two TRIP SYSTEMS.

QUAD CITIES - UNITS 1 & 2 16 Amendment Nos.152 & 14f

..=.

T Definitions.1.0 1.0 DEFINITIONS i

UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

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QUAD CITIES-UNITS 1 & 2 17 Amendment Nos.152 & 14

-. ~ -

D2finiti::ns 1.0 TABLE 1-1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY

1.. Shift S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

2. Day D

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i

3. Week W

At least once per 7 days

4. Month M

At least once per 31 days

5. Quarter Q

At least once per 92 days

6. Semiannual SA At least once per 184 days
7. Annual A

At least once per 366 days

8. Sesquiannual E

At least once per 18 months (550 days) l l

9. Startup S/U Prior to each reactor startup
10. Not Applicable -

N.A.

Not applicable.

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1 i

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1

)

QUAD CIT!"S - UNITS 1 & 2 18 Amendment Nos.152 & 14!

Definiti:ns 1.0 TABLE 1-2 OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR MODE POSITION (f)

COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature 2.STARTUP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown'* d

> 2120F

4. COLD SHUTDOWN Shutdown"**

5212*F

5. REFUELING'd Shutdown or Refuel **

s140 F TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.

(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.10.1.

(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.

(d) See Special Test Exceptions 3.12.A and 3.12.B.

(e) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided the one-rod-out interlock is OPERABLE.

(f) When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be inoperable.

QUAD CITIES - UNITS 1 & 2 19 Amendment Nos. 152 & 148

i 5

Applicability 3/4.0 3.0 - LaMITING CONDITIONS FOR OPERATION A.

Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL MODE (s) or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the l

associated ACTION requirements shall be met.

{

r B.

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.

i C.

When a Limiting Conditiori for Operation is not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in an OPERATIONAL MODE in which the Specification does not apply by placing it, as l

applicable, in:

l

1. At least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and i

I

2. 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 failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL MODE 4 or 5.

D.

Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires placing the plant in an OPERATIONAL MODE or other specified condition of operation in which the Limiting Condition for Operation does not apply if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the ACTION requirements when conformance i

to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODE (s) as required to comply with ACTION requirements. Exceptions to these requirements are stated in the i

individual Specifications.

QUAD CITIES - UNITS 1 & 2 3/4.0-1 Amendment Nos.152 & 14l

.:y a

Applicability 3/4.0 i

i 4.0 - SURVEILLANCE REQUIREMENTS i

A.

Surveillance Requirements shall be met during the reactor OPERATIONAL MODE (s) or other conditions specified for individual Limiting Conditions for Operation unless otherwise j

stated in an individual Surveillance Requirement.

B.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the surveillance interval.

l r

C.

Failure to perform a Surveillance Requirement within the allowed surveillance interval, l

defined by Specification 4.0.B, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to a

permit the completion of the surveillance when the allowable outage time limits of the i

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 />. Surveillance requirements do not have to be i

performed on inoperable equipment.

i D.

Entry into an OPERATIONAL MODE or other specified applicable condition shall not be f

made unless the Surveillance Requirement (s) associated with the Limiting Condition for i

Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODE (s) as required to comply with ACTION reqeirements.

l l

E.

Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, j

and 3 components shall be applicable as follows:

i 1.

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 i

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 50.55alg)(6)(i).

- i QUAD CITIES - UNITS 1 & 2 3/4.0-2 Amendment Nos. 152 & 148 I

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+ --*

U i.

s.r Applicibility 3/4.0

  • ^

4.0 -' SURVEILLANCE REQUIREMENTS 2.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required Frequencies b

Code and applicable Addenda for performing terminology for inservice inservice inspection j

inspection and testino activities and testina activities Weekly At least once per 7 days.

Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days

-l Every 9 months At least once per 276 days Yearly or annually At least once per 366 days a

3.

The provisions of Specification 4.0.B are applicable to the above required frequencies

{

~

for performing inservice inspection and testing activities.

4.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

5.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede i

the requirements of any Technical Specification.

6.

The Inservice inspection Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods, and personnel and sample expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

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OUAD CITIES - UNITS 1 & 2 3/4.0-3 Amendment Nos. 152 & 148 i

Applicability B 3/4.0 BASES Specifications 3.0.A through 3.0.D establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations,10 CFR 50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the 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 permitted by the technical specification until the condition can be met."

Specification 3.0.A establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODE (s) or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The 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. it is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (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.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit 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 operatior as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the ellowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these ACTION (s) are not completed within the allowable outage time limits, a shutdown is required to place the facility in a reactor OPERATIONAL MODE or other specified condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are 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 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 requirements, the plant may have entered an OPERATIONAL MODE in which a 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 not met.

Specification 3.0.B establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION QUAD CITIES - UNITS 1 & 2 B 3/4.0-1 Amendment Nos. 152 & 14

Applicability B 3/4.0 BASES requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirement within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition for Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.C establishes the shutdown ACTION requirements that must be implemented when a Umiting 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 condition when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Condition 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 permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODE (s) of operation permit 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 transient that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdoun may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a f ailure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated 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 ACTION (s).

The time limits of Specification 3.0.C 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 COLD SHUTDOWN when a shutdown is required during POWER 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 applies.

However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL MODE, is not reduced. For example, if HOT SHUTDOWN is reached in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, the time allowed to reach COLD SHUTDOWN is the next 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> because the total time to reach COLD SHUTDOWN is not reduced from the allowable limit of 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. Therefore, if remedial measures are completed that would permit a return to POWER OPERATION, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL MODE or condition of operation for another specification in which the OUAD CITIES - UNITS 1 & 2 B 3/4.0-2 Amendment Nos. 152 & 141

h,.

M Applicsbility B 3/4.0 j

d-BASES 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 1

outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable

'i outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.C do not apply in MODES 4 or 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.D establishes limitations on a change in OPERATIONAL MODE (s) 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 met and continued i

noncompliance to these conditions would result in placing the plant in an OPERATIONAL MODE or i

other specified condition of operation in which the Limiting Condition for Operation does not apply.

to comply with the ACTION requirements if a change in MODE (s) were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODE (s) of operation or other specified conditions are not entered when corrective ACTION is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimhed period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL MODE (s). 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 i

practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification

- 3.0.D do not apply because they would delay placing the facility in a lower MODE of operation.

l l

i OUAD CITIES - UNITS 1 & 2 B 3/4.0-3 Amendment Nos.152 & 14f

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-m

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Applicability B 3/4.0 BASES Specifications 4.0.A through 4.0.E establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations,10 CFR 50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibration, 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.A establishes the requirement that surveillances must be performed during the OPERATIONAL MODE (s) or other conditions for which the requirements of the Limiting Condition for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a reactor OPERATIONAL MODE or other specified condition for which the individual Limiting Condition for Operations are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.B establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal 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. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified with and 18 month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. Likewise, it is not the intent that refueling outage surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Specification 4.0.B is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

This provision is 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.C establishes that the failure to satisfy a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.B, is a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time QUAD CITIES - UNITS 1 & 2 B 3/4.0 4 Amendment Nos.152 & 14E

l Applicability B 3/4.0 BASES

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

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 performed 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.C. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.8, was a violation of the OPERABILITY requirements for a Limiting Condition for Operation that is subject to enforcement action. The failure to perform a surveillance within the provisions of Specification 4.0 B is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition 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., in Specification 3.0.C), a 24-hour allowance is provided 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 would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the 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.D 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 terminated.

Surveillance Requirements 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 equipment has been restored to OPERABLE status.

Specification 4.0.D 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 an OPERATIONAL MODE or other specified condition for which these systems and components ensure safe operation of the QUAD CITIES - UNITS 1 & 2 B 3/4.0-5 Amendment Nos.152 & 14!

Applicability B 3/4.0

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-BASES

' facility. This provision applies to changes in OPERATIONAL MODE (s) or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to assure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION statements, the provisions of Specification 4.0.D do not apply because this would delay placing the facility in a lower MODE of operation.

Specification 4.0.E establishes the requirement that 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 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 Commission.

This specification includes a clarification of the frequencies for performing 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 Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.D to perform surveillance requirements before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that 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, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing 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.

QUAD CITIES - UNITS 1 & 2 B 3/4.0-6 Amendment Nos.152 & 14f