ML20032A572

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Amend 25 to License DPR-45,modifying Tech Specs to Incorporate Changes Resulting from TMI-2 Lessons Learned & Revising Stds Used to Determine Equipment Operability
ML20032A572
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 10/23/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20032A568 List:
References
NUDOCS 8110300402
Download: ML20032A572 (29)
v • d • e


Text

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UNITED STATES

[

p NUCLEAR REGULATORY COMMISSION ej WASHINGTON. D. C. 20555

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DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 25 License No. DPR-45 1.

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

A.

The application for amendment by Dairyland Power Cooperative (the licensee) dated September 12, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regula-tions 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 Commissior's regulations and all applicable requirements have been satisfied.

8110300402 811023 PDR ADOCK 05000409 p

PDR

-a

, 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this lice'nse amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical-Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 25, are hereby

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

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3.

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

FOR' THE N CLEAR REGULATORY ChMMISSION

==

=

Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Speci fications Date of Issuance:

October 23, 1981 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 25 LACROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 Revise Appendix A.by replacing the following pages with the enclosed pages. The revised pages are identified by the captioned amendment numberandcontainmarginallinesfndicatingtheareasofchange.

REMOVE INSERT i

i (23-27x) 23 24 i

1 25 26 27a 27b 27c 27d 27e 27f 279 27h 271 27j 27k-27x (Intentionally Blank) 28 28 44 44 47 47 48 48 49 49 49a 49a 50 50 l

51 51 52 52 6-1 6-1 s

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TABLE OF CONTENTS: g e.,.. 4;.

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1 1.

SITE..............................

1 1.1 LOCATION 1.2 EXCLUSION AND RESTRICTED AREAS 1

1.3 PRINCIPAL ACTIVITIES

l 2.

DESIGN AND PERFORMANCE REOUIREMENTS_

1

.1 2.1 REACTOR BUILDING

....g................

3 2.2 REACTOR VESSEL 4

2. 3' FORCED CIRCULATION SYSTEM.

6 2,4 REACTOR AUXILI ARY SYSTEMS:....._....

11 2.5 MAIN STEAM AND FEEDWATER LOOP...............

12

' 2.6 ELECTRICAL POWER SUPPLY..

REACTOR CORE AND VESSEL INTERNALS.............

13 2.7 15 2.8 CONTROL ROD DRIVE SYSTEM 17 2 9. CONTROL SYSTEMS......................

2.10 SAFETY AND MONITORING SYSTEMS...............

18 2.11 WASTE DISPOSAL 21 22 2.12 FUEL STORAGE AND H ANDLING..................

3.

APPLICABILITY 23 i

i' 2

OPERATING LIMITATIONS 27d ei 4.0.1 DEFINITIONS........................

27d 4.1 GENERAL..........................

28

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4.2 OPERATIONS LIMITS.....................

28 37 5.

"AINTENANCE 37 E.i GENERAL,

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l.n..IJh,G..........................

s 5.3 INSERVICE INSPECTION PROGRAM 53 t

Change No. #,

.i kaend nent No.

, -25

i 3.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable, during the OPERATIONAL CONDITIONS or other specified applicable condition for each I

specification.

3.0.2 Adherence to the requirements If. the Limitiny Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification.

In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval completion of the ACTION statement is not required.

3c0.3 In the event a Limiting Condition for Operation and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed inthe specification, the unit shall be placed in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed that -~mit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery or until the reactor is placed in an OPERATIONAL CONDITION in which the specification is not applicable.

Exceptions to these requirements shall be stated in the individual specifications.

3.0.4 Entry into an OPERATIONAL CONDITION or other"specified applirubility state shall not be made unless the conditions of the Limiting Condition ror Operation i

are met without reliance on provisions contained in the ACTION statements unless otherwise excepted.

This provision shall not prevent passage through OPERATIONAL i

8 CONDITIONS required to comply with ACTION requirements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is h:perable, or solely i

because its normal power source is ir. operable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:

(1) its corresponding normal or. emergency power source j

.is OPERABLE; and (2) all of its redundant systen(s), subsystem (s), train (s),

i components (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification.

Unless both conditions (1) and (2) are satisfied, the unit shall be placed in at least HOT SHUTDOWN,within12 hours, and in at least COLD SHUTDOWN within the following 30 hou'rs.

This specification is not applicable in Conditions 4 or 5.

i SURVEILLANCE REQUIREMENTS 3.0.6 Surveillance Requirements shall be applicable during the OPERATIONAL CONDITIONS or other specified applicable conditions for individual Limiting Conditions for Operation unless otherwise. stated in an individual Surveillance l

Requirement.

ChangeNo.)d Amendment Nos. 3, 9, 70, 73, 25 J

3.0 APPLICABILITY SURVEILLANCE REQUIREMENTS - (Cor.t'd) 3.0.7 Each Surveillan'ce Requirement shall be performed within the specified time

' interval with:

a.

A maximum allowable extensiq,n not to exceed 25% of the surveillance interval.

b.

A total maximum combined interval time for any 3 consecutive surveillance intervals not to e~ ceed 3.25 times the specified surveillance interval.

x 3.0.8 Performance of a Surveillance Requirement within the specified time.

interval shall constitute. compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

Surveillance Requirements do not have to be per-formed on inoperable equipment or on., equipment not required to be OPERABLE.

3.0.9 Entry into an OPERATIONAL CONDITION 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 stated surveillance interval or as otherwise specified.

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Change No. 13 I

Amendment Hos. 3,9,70,,35,25

3.0 APPLICABILITY I

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This page intentionally blank t

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L.'iangeNo.[

Amendment No. X S', 16, 26, 25

- 25.-

3.0 APPLICABILITY BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 3.0.

I 3.0.1 This specification defines the applicability of each specification ~ in terms of defined OPERATIONAL CONDITIONS or other specified applicability conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3' This specification delineater the ACTION to be taken for circumstances not directly provided for in the ACTICN s'tatements and whose. occurrence would violate the intent of specification.

For example, Specification 4.2.5.8, requires all three rod position indicator systems to be available for indication of individual rod positions, and provides for one of these systems to be removed for maintenance-for a time. period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Under the terms of Specification 3.0.3, if more than one red position indication system is out of service, the unit is to be placed in. HOT SHUTDOWN within 12. hours and in COLD. SHUTDOWN within-the next thirty hours.

It is assumed that the unit is brought to the required OPERATIONAL CONDITION within the required times by promptly initiating and carrying out the

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appropriate ACTION statement.

l 3.0.4 This specification provides that entry into an OPERATIONAL CONDITION or other specified applicability condition must be made with (a) the full complement of required systems, equipment or components OPERABLE and (b) all other. parameters as specified in the Limiting Conditions.for Operation being met without regard for allow 1ble deviations and out of service provisions contained in the ACTION stateme .

The intent of this provision is to ensure that unit operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

Exceptions to this provi.sion have been provided for a limited number of specifi-cations when startup with inoperable equipment would r.at affect plant safety.

These exceptions are stated in the ACTION statements of the appropriate specifications.

LACBWR AmendmentNo.E,y,16.)4,25 w,-

3.0 APPLICABILITY BASES - (Cont'd) 3.0.5 This specification delineates what additional conditions must be satisfied i

to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one divisioq,is inoperable because its normal or emergency

, power source is inoperable and a syst'em, subs.vstem, train, component or device in another division is inoperable for another reason.

The provisions of this specificatior permit the ACTION statements associated with individual systems, subsystems, tains, components.or devices to be consistent with the ACTION statements of the associated : electrical power source.

It allows operation to be governed by the time lim.its of tne ACTION statement associated witi, the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be ineserable solely because of. the inoperability of its normal or emergency power source.

For example, Specification 3.8.1.1 requires in part that' both emergency diesel generators be OPERABLE. The ACTION statement provides.for a 72-hour out-of-service time when emergency diese1 generator (lA) or (lB) is not 0PERABLE.

If the defini--

tion of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components, and devicds supplied by the inoperable emergency power source, deisel generator (1A) or (lB), would also be inoperable.

This would dictate making the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Soecification 3.0.,5 permit the time limits for continued operation to be consistent wi h the ACTION statement for the inoperable emergency dPsel generator instead, provided the other specified conditions are satisfied.

In this case, this would mean that the cerresponding normal power source must be OPERABLE, and all redundant systems, subsystsms, trains, components,and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design f anction and have at least one normal or one emergency power source OPERABLE).

If they are

. not satisfied, shutdown is required in accordance with this specification.

In Condition 4 or 5, Specification 3.0.5 is not applicable, and thus the individual,,

ACTION, statements for each applicable Li.miting Condition for Operation in these Conditi~cns must be adhered to.

3.0.6 This specification provides that surveillance activities necessary to ensure that the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL CONDITIONS or other specified applicability conditions for which the Limiting Conditions for Operation are applicable.

Provisions for additional surveillance activities to be performed without regard to the applicable OPEP.ATIONAL CONDITIONS or other specified applicability conditions are provided in the individual Surveillance Requirements.

Surveillance Requirements for Specia; Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.

LACBWR Amendmen6 No. 7, P

' 7X, 25 27a -

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3.0 APPLICABILITY BASFS - (Cont'd) 3.0.7 The previsions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveil-lance interval.

These tolerances are necessary to provide operational flexibility because of scheduling and performance consideration.

The phrase "at least" associated with a surveillance frequeEcy requirement does not negate these

. allowable tolerances for performing surveillance activities; instead it permits more frequent performance of surveillance activities than required by the specification.

The tolerance values, taken either individually or consecutively over three test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval.

3.0.L The provisions of this specifibation set forth the crite/ia for determina-tion of compliance with the OPERABILITY requirements of the Limiting Condition for Operation.

Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.

Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

3.0.9 This specification ensures that the surveillance activities. associated with a Limiting Condition for Operation have been perforned within the specified time interval prior to entry into an OPERATIONP CONDITION or other specified appli-cablity condition.

The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERASILITY requirements of the Limiting Condition for Operation.

Uncer the terms of this specification, for example, following extended plant outages, the applicable turveillance activities must be performed within the stated surveillance interval arior to placing or returning the system or equipment into OPERABLE status.

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i LACBWR Amendment No. g )T, MT, FI, 25

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THIS PAGE INTENTIONALLY LEFT BLANK Amendment No.f. f, M,y, 25

i 4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS For purposes of the Safety Limits and Limiting Safety Systems Settings, Section 4.0.2; Reactor Coolant Activity, Specification 4.2.2.22; Electrical Power Systems, Section 4.2.3; Power Distribution 'imits, Section 4.2.4.2; Fire Detection Instrumentation, Section 4/S.2.17; ' ire Suppression Systems, Section 4/5.2.18; and Penetration Fire Barriers, Section 4/.5.2.19; Technical Specifications only, the following terms are defined and appear in capitalized type so that uniform interpretation may be achieved.

ACTION ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

AVERAGE PLANAR EXPOSURE The AVERAGE PLANAR EXPOSURE 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.

1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE

]

I The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (ALPHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES 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 CALIBRATION A CHANNEL CALIBRATION shall. be the adjustment, as necessary, of the channel output such that is 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 sensor and alarm and/or trip functions, and shall include 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 qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indicating and/or status derived from independent instrument channels measuring the same parameter.

Amendment No./ g, Tb,,23', 25 27d -

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4.0 OPERATING LIMITATIONS 9

4.0.1 DEFINITIONS - (Cont'd)

CHAf!NEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL Tt 1 be:

a.

Analog channel.

injectfon of a simulated signal into the channel as close to the sei.so.

.s pract'1 cable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

Bistable channels - the injection of a real or simulated signal into the b.

sensor to verify OPERABILITY including alarm and/or trip functions.

CONTAltNENT INTEGRITY CONTAINMENT INTEGRITY shall exist when:

a.

All penetrations required to be isolated during accident conditions are either:

1.

Capable o" being closed by an OPERABLE containment automatic isolation valve system, or 2.

Closed by at least one manual valve, Blind flange, or deactivated a.0tomatic valve secured in its closed position, b.

The freight door is closed, c.

Each air lock is OPERABLE, d.

The containment leakage rates are within the limit, and The sealing mechanism associated with each penetration (e.g., welds, e.

bellows, c-rings) is OPERABLE.

. CORE ALT 2 ATION CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sour'ces, incore instrumentation or. reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe conservative position.

CRITICAL POWER RATIO The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in a fuel assembly which is calculated by application of the XN-2 correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

Amendment No. I,g, M,JS, 25

4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS - (Cont'd)

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 pCi/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131 I-132. I-133, I-134, and I-135 actuaU y present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844,

" Calculation of Distance Factors for Power and Test Reactor Sites."

T - XVERAGE DISINTEGRATION ENERGY Y shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the avera_ge beta and garmia energies per disintegraf. ion, in MeV, for isotopes other than iodines with half lives greater,than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table of Surveillance Frequency Notation, IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE shall be:

a.

Leakage into collection systems, such as pump seal or valve packing leaks, that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be -PRESSURE B0UNDARY LEAKAGE.

LIMITING CONTROL ROD PATTERN A LIMITING CONTROL R0D PATTERN shall be 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 LINEAR HEAT GENERATION RATE (LGHR) shall be the power generation in an arbitrary length of fuel rod, usually one foot.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

Amendment No. J J. W. 78, 25

- 27f -

i 4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS - (Cont'd)

MINIMUM CRITICAL POWER RATIO a

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in 5

the core.

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j OPERABLE-OPERABILITY

... x. _

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.w-y 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, a normal and an emergency electrical power source, cooling or seal. water, lubrication I

or other auxiliary equipment _that are required for the system', subsystem, train, component c device to perform its function (s) are also capable of i

performing their related support function (s).

l OPERATIONAL CON 0! TION - CONDITION An OPERATIONAL CONDITION, i.e. CONDITION, shall correspond to any one inclusive 4

combination of power level and average reactor coolant temperature specified in Table of OPERATIONAL CONDITIONS.

c PARTIAL SCRAM A PARTIAL SCRAM signal shall cause t'.ie electric and hydraulic scram motors for 13 preselected control rod drive mechanisms to be actuated for control rod insertion.

Full insertion of PAR 11AL SCRAM control rods during POWER OPERATION shall render the re, actor subcri*.ical.

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 13 of the Safeguards Report, 2) authorized 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 j

Reactor Coolant System component body, pipe wall or vessel wall.

RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the

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reactor coolant and reactor components of 165 MWt.

Amendment No. X B",16, pf, 25 27g--

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4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS - (Cont'd) t REPORTABLE CCCURRENCE A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specification 6.9.1.7 of Technical Specifications, SHUTDOWN MARGIN SHUTDOWN MARGIN shall be the amount of reactivity oy which the reactor is sub-critical or would be subtritical from its present condition assuming all control rods are fully inserted, except for the single control rod of liighest reactivity worth which is cssumed to be fully withdrawn, and the reactor is in the shutdown condition, cold, i.e. < 800F, and Xenon free.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or other designated 7emponents obtained by dividing the specified test interval into n equal subintervals, t*

b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

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

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

I Amendment No. 3', f. If,J, 25

- 27h -

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SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY 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 />.

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 />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.

A At 1 east once per 12 months.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A.

Not ' Applicable.

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Amendment No. Zf, J6, E3', 25

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e TABLE OF OPERATIONAL CONDITIONS OPERATIONAL

% RATED AVERAGE COOLANT CONDITION THERMAL POWER

  • TEMPERATURE 1.

POWER OPERATION

> 3%

Any temperature 2.

STARTUP

< 3%,

Any temperature 3.

HOT SHUTDOWN O

> 2120F 4.

COLD SHUTDOWN O

< 2120F

5. -REFUELING **

0

< 2120F l

  • Excluding decay heat.
    • Reactor vessel head unbolted or removed and fuel in the vessel.

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Amendment No. f F,36, g,25 27j -

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THIS PAGE INTf, fit 10NALLY LEFT BLANK (Pages 27k - 27x)

Amendment No. g,,9',10, 2I, 25 l

1

. 4.1 GENERAL

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4.1. 3 During periods when the reactor is in Condition 3, 4, or 5, eithar Channel 1 or-2 of the Nuclear Instrumentation System shall be in operation and shall be monitored by the operator.

4.1.4 Whenever the reactor contains one or more fuel elements, any operations from points *outside the control room'of equipment which may affect the reactor shall be conducted under the direction, or with the knowledge, of the control room operator.

' ' ' 4.1. 5 If the pla'nt is operational' during a tornado warning, the shift supervisor on duty shall keep infomed of the actual tornado activity which may approach the plant.

In the event th6t reports indicate an imminent tornado strike at or near the LACBWR plant, the shift supervisor shall reduce reactor power to a level which permits prompt reductfon of power generation to station load.

However, the shift supervisor shall be instructed to discontinue plant operation if, in his judgment, this action is required to ensure plant safety.

4.2.1 Reactor Buildi'g 4.2.1.1 CONTAINMENT INTEGRITY shall be maintained in Conditions 1, 2, 3 and during:

(a)

CORE ALTERATIONS, (b) handling of irradiated fuel, or (c) moving a spent fuel shipping cask in the Containment Building.

(d) there is fuel in the reactor and any control rod is withdrawn t'

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_ Amendment No.,2(, 25 l

l

44 _

MINIMUM FREQUENCIES FOR TESTING, CALIBRATING, AND/OR CHECKING OF IN3IRUMENTATION Channels Action Minimum Frecuency 1.

Reactor Water Level Calibration At each refueling shutdown.

t

  • Test Monthly when in service and prior to each reactor startup if test has not been performed within 30 days..

Check Daily 2.

Reactor Pressure Calibration At each refueling shutdown.

  • Test Monthly when in service and prior to each reactor startup if test has not been performed within 30 days.

Check Daily 3.

Reactor Power - Flcw Calibration At each refueling shutdown.

  • Test Monthly when in service and prior to each reactor startup if test has not been performed within 30 days.

Check Daily 4.

Reactor Coolant Flow Calibration At each refueling shutdown.

Rate Lcw

  • Test Monthly when in service and prior to each reactor startup if test has not been performed within 30 days.

Check Daily 5.

Source Range Test (60 Prior to each reactor (Channels 1 and 2) cycler er startup if test has not sec) been performed within 30 days.

Chance No 1 Mienament No. 25 J

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Channels Action Minidum Frecuency

'22.

CRD accumulators low gas Test Prior to.each plant startup if pressure scram relay test has not' been performed within 30 days.

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  • Check pressure Weekly indication

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23.

Turbine stop valve Test

~ Prior tolea_ch.pl' ant startup if

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test has not been performed.

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within 30 days.

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, 24.

Reactor Pressure (RPTS)

Calibration At each refue' ling shutdown-

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25. ~ Reactor Wate" Level Calibration At eabh refueling ' shutdown (RPTS) s 26.

Reactor Safety Valve Check ~.

~ ~ ~ '

s P.osition Indication Monthly'~

)

Calibration.

At each refueling shutdown.

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  • Test shall include tripping of the scran relays K-ll4 5.2.16 Corrosien test coupons shall be inserted ir ne forced circulation 1:cp to evaluate the 'corresion deterioration of cht. tium-molybdenum piping; and that piping shall be replaced if the reduction.n pipe wall thickness, as indicated by weign loss and metallographic evaluation of the test coupons, is greater th'an 0.190 inches.

The replacement piping shall be stainless steel er shall be clad internally with stainless steel and shall reet the design-rec,virements of Section 2.3.2.

47 -

Amendment No, J2F, 25

TABLE 1 (Operating Limits)

ITEM

?!O.

C0f40lTI0t{

CilAfttiEL OR SEilSOR SET P0ltiT ACTI0ff

'KEYSWITCli BYPASS PROVISI0f!S-1

~ reactor power high two of four nuclear Table 4.0.2.2.1-1 full scram none channels 5, 6, 7, and 8 y

if power level is > 57 of full power cither nuclear channel Ta bl e 4.0.2.2.1-1 full scram one channel may be bypassed 5 or 6 if power level for calibration and testing is < 5% of full power

~2 reactor period nuclear channel 3 or 4 Table 4.0.2.2.1-1 full scram (1) both channels may be short bypassed only when et reactor power exceeds 3 Mwt g

(2) one channel may be by-passed for calibration and testing

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3 reactor pressure pressure safety

< 1325 psig (1) full scram one channel may be bypassed high channel 1 or 2 (2) shutdown conden-for calibration and testing ser operates (3) closure of venti-lation inlet and outlet dampers (4) Closure of con-

  • tainment off-gas

?

N vent header valve.

4 reactor power flow power-flow safety Table 4.0.2.2.1-1 full scram one channel may be bypassed l rate abnormal channel 1 or 2 for calibration and testing' 5

reactor coolant flow power-flow safety Ta ble 4.0.2.2.1-1 full scram one channel may be bypassed f

rate low channel 1 or 2 for calibration and. testing L

I TABLE 1 - (Operating Limits)_ - (Cont'd)

NO.

CONDITION CimNNEL OR SENSOR SET POINT

' ACTION KEYSWITCil BYPASS PROVISIONS

' ITEM one channel may be bypassed b

reactor water level water level safety Table 4.0.2.2.1-1 full scram for calibration and testing high channel 1 or 2 (Nominal indicated unvoided saturated water level shall be permitted to vary from 2'9" above the fuel to up to 4'6" above the fuel during reactor heatup and operation) 7 reactor water level water level safety

< 12" below nomi-(1) full scram one channel of Item No. 7 low channel 1 or 2 nal indicated (2) initiation of or channel 3 of Item No. 7A level high pressure may be bypassed for calibra-core spray pumps tion and testing (3) closure of reactor building steam isolation valve and its bypass s

(4)" Closure of et reactor blowdown through decay heat u

removal valve (5) start 1A and 1B diesel generators (6) closure of shutdown condenser condensate drain valve (7) closure of venti-lation inlet and

!i outlet dampers El (8) closure of contain-s 2

  • ment of fgas vent. '

'a header valve (9) closure of heating

=o steam condensate I

return valve R

(10) closure of retention 1(

tank pump discharge valve i%

e

TABLE 1 - OPERATING LIMITS - (Cont'd)

ITEM N0.

CONDITION CIMNNEL 0R SENSOR SET POINT.

ACTION KEYSWITCH BYPASS PROVISIONS 7A reactor water level water level safety

< 12" below nomi-(1) full scram one channel of Item No. 7 low channel 3 -

nal indicated (2) initiation of or channel 3 of Item No. 7A level high pressure

-may be bypassed for calibra-core spray pumps tion and testing 8

main condenser vacuum switches 1 or 2

-> 19" hg (1) full scram (1) one channel may be by-passed d' ring calibration vacuum low (2) closure of reac-u tor building and testing steam isolation (2) may be bypassed during valve plant startup and shut-down 9

reactor building reactor building steam

> 90% full open (1) full scram (1) may be bypassed during steam isolation isolation valve closure travel (2) shutdown conden-testing.

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valve not fully relays 1 or 2 ser operates (2) may be bypassed during plant startup or shut-open down 10 turbine building turbine building steam

> 90% full open (1) full scram' (1) may be bypassed during steam isolation isolation valve closare travel (2) shutdown conden-testing valve not fully relays 1 or 2 ser operates (2) may be bypassed during plant startup or shut-open down 11 turbine stop valve limit switch Table 4.0.2.2.1-1 partial scram (1) may be bypassed during tes ting not fully open (2) may be bypassed whenever the turbine load is less than 10 Mwe 12 low oil level in limit switches Ta ble 4.0.2.2.1 -1 partial scram (1) may be bypassed during -

testing any control rod (2) may be bypassed prior gr drive accumulator to withdrawing control g

rods in order to charge g

accumulators m

3 O

E

.DS

TABLE 1 - OPERATING LIMITS - (Cont'd)

ITEM NO.

CONDITION CHANNEL OR SENSOR SET POINT ACTION KEYSWITCH BYPASS PROVISIONS 13 low gas pressure in pressure switches Table 4.0.2.2.1-1 partial scram (1) may be bypassed during any control rod drive calibration and testing accumulator (2) may be bypassed prior to withdrawing control rods in order to charge accumulators 14 low voltage (for a 2400 v bus lA under-Table 4.0.2.2.1-1 partial scram none time longer than voltage relay 1 or 2 or required for reserve 2400 v bus 1B under-feed breakers to voltage relay 1 or 2 operate autanati-cally) 2400 v bus lA under-Table 4.0.2.2.1-1 full scram.

none voltage relay 1 and t

g; 2400 v bus IB under-voltage relay 1 or 2400 v bus I A under-voltage relay 2 and 2400 v bus 1B under-voltage relay 2 reactor building motor Table 4.0.2.2.1-1 full scram none control center lA relay 1 or 2 turbine building motor Table 4.0.2.2.1-1 full scram none control center lA relay 1 or 2 15' low main steam main steam pressure

> 1000 psig closure of reactor may be bypassed during f

pressure transmitter building steam.

plant startup and shutdown isolation valve" TA

3 Tab k l.

Operating Limita (Con t '<!)

gey,vigeh ypass Provisions

,I tem tio._

Condition' CI',nnel or sconor

.5e t Point Action-B 16 reactor building renctor liullding

$; 5 paig (1) initiation of none pressure high prest. ore transmitter high pressure 1 or 2 core spray pumps

~-

(2) initiation of alternate ~'

core spray pumps (3) closure of vent inlet &

outlet dampers (4) closure of containment off-gas vent header valves (5) closure of retention tank pump discharge valve (6) c.'osure of shutdown condenser condensate drgin valve (7) closure of reactor blowdown through decay heat removal valve u,

(8) closure of containment high pressure service water valve (9) r.losure of containment demin-eralized water valve (10) closure of containment heating steam condensate valve.

li a

x?

P h(

C$

17 o((-gas holdup ra,li a t. t on mon i tor

< ganeous act1v-diversion tank effluent ity Icvels which effluent gas activity high correnpond to to the storage Column 2'of the

. tanks limitations 1

3 ven in sec.

~

4.2.7.2

TABLE 1 - OPERATING LIMITS - (Contd) i ITEM NO.

CONDITION CHANNEL OR SENSOR SET POINT AC1 ION KEYSWITCH BYPASS PROVJSIONS 18 reactor building radiation monitors

< radiation levels (1) closure of ventilationi none ventilation exhaust which correspond inlet and outlet dampers to Column 2 of the (2) closure of containment off-gas limitations given vent header valve in Sec. 4.2.7.2

~~~

i 19 simultaneous low pressure transmitter 25-30 psig and' opening of diaphragm reactor pressure and water level safety

< 12" below nomi-valve allowing water and low water level channel 1 or 2 nal indicated to flow directly from level

. overhead storage tank to core spray nozzles 20 simultaneous high reactor building pres-

< 5 psig and ope.ning of motor reactor building sure transmitter 1 or 2

< 12" below nomi-operating valves and,,

pressure and and reactor water level n'al indicated start of engine driven g

reactor low water safety channel 1 or E level pumps of alternate level core spray system 1350 psig or trip of both recirc-21 high reactor 3 reactor pressure pressure or low or 3 reactor level

< 30 incher below ulation pump breakers reactor water transmitters nominal indicated j[

level level

  • the protective fu.nction) t' a

can be bypassed whenever the reactor is shutdown ?

or recirculation pumpg}[:

a operation is required,-y 2

P for safety reasons.. ')

\\~ -

p.-.

I 2

steam safety valves position switches on open-close none - post accident none g2 not fully closed each of the three indication only

inservice safety valves r,

'~

y ; - -.. -

a.-.

f.

h.,.'

f.

A Fire Brigade of at least 5 me=be'rs shall be maintained on site at

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all times." The Fire Brigade shall not include the two LAC 1NR Plant Operators necessary for safe shutdown of the unit or any other personnel re:;uired for other essential functicns during a fire energency.

g.

At all times.when the s.eactor is critical, or when its controls are being manipulated ith fuel in the reactor, the control room shall be attended by a vainimum of two persons, one of whom shall

.l have a valid Operators License and shall have full responsibility ior operation of the facility.

~~

~

A Shift Technical Advisor shall'be onsite in OPERATIONAL CONDITIONS 1, 2, h.

and 3.

t I

i 6.2.3 SHIFT TECHNICAL ADV130R

~

f The Shif t Technical Advisor shall serve in an acvisory capacity to the Shif t -

Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

w

~~

' fire Brigade composition may be less than the minimum requirements for a pr-ind of time not to.r:xceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to arrommodate unexpected ab'.cnce of I l rc Ort unite im mhcr*. provitlert innurdia t e net ton 1. t aken to re-

. tore the fire lirtynde to within the minimum requirements. This provision ducs not. permit any Ilre Brigade position to be unmanned upon shift change due to,an onecming Brigade memben being late or absent.

l LACBWR 6-1 Amendment No. FJ,.I. 25 t

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