Text

Amend 102 to License NPF-38,changing App a TS by Modifying Spec Having cycle-specific Parameter Limits by Replacing Value of Those Limits W/Ref to Core Operating Limits Rept for Values of Those Limits
	ML20080Q721
Person / Time
Site:	Waterford
Issue date:	03/01/1995
From:	Chandu Patel; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20080Q723	List: ML20080Q721; ML20080Q729;
References
	NUDOCS 9503090030
	Download: ML20080Q721 (49)
	v • d • e

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UNITED STATES 7

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DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 102-License No.-NPF-38 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated August 11, 1994, as supplemented by letter dated December 2,1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations.of the Comission; 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 comon 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 cf the Commission's regulations and all applicable requirements have been satisfied.

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9503090030 950301 i

PDR ADOCK 05000382 4

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. Accordingly,'the. license is amended.by changes to the Technical 1

Specifications as" indicated in the attachment to this' license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby-amended to read as follows-l Technical Soecifications and fnvironmental Protection Plan g

(2).

The' Technical Specifications contained in. Appendix A, as. revised.

as through Amendment No.102,: and the. Environmental Protection P1&n

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contained in Appendix B, are hereby incorporated >in the license.-

The licensee ~ shall operate ~the facility in accordance with the -

Technical Specifications and the Environmental Protection Plan.-

3.

This license amendment is effective as lof its date of issuance.-

FOR THE NU'8 EAR REGULATORY. COMMISSION 1

0 fa $tA' Chandu P. Patel, Project Manager Project Directorate IV-1~

i Division of Reactor Projects - III/IV.

Office of Nuclear Reactor Regulation

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Attachment:

Changes to the Technical Specifications a

Date of Issuance: March 1, 1995 n

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ATTACHMENT TO LICENSE AMENDMENT NO.102 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382-Replace the following pages of the Appendix A Technical Specifications with

.the attached pages. The. revised pages are identified by Amendment number and-contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAGES I

I XVII XVII XIX.

XIX XX XX 1-3 1-3 3/4 1-1 3/4 1-1 i

3/4 1-3 3/4 1-3 3/4 1-3a 3/4 1-4.

3/4 1-4 3/4 1-15 3/4 1-15 i

3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 1-17a 3/4 1-17b 3/4 1-17c 3/4 1-17d 3/4 1-18 3/4 1,

3/4 1-19 3/4 1-19 3/4 1-25 3/4 1-25 3/4 1-27 3/4 1-27 3/4 1-28 3/4 1-28 3/4 1-28a

~3/4 1-28a l

3/4 2-1 3/4 2-1 3/4 2-la-3/4 1-2a i

3/4 2-2 3/4 2-2 3/4 2-2a 3/4 2-4 3/4 2-4 3/4 2-6 3/4 2-6 3/4 2-6a 3/4 2-6a 3/4 2-7 3/4 2-7 3/4 2-8 3/4 2-9 3/4 2-12 3/4 2-12 3/4 9-1 3/4 9-1 B 3/4 1-3 B 3/4 1-3 B 3/4 2-1 B 3/4 2-1 B 3/4 2-la B 3/4 2-la B 3/4 2-2 B 3/4 2-2 B 3/4 2-3 B 3/4 2-3 8 3/4 9-1 B 3/4 9-1 6-20 6-20 6-20a 6-20a m

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-1 INDEX s

.l co DEFINITIONS ~

t v

y SECTION MGE l

'I.0 DEFINITIONS i

1.1 ACTION..............'........................................

1-1 1

1.2 AXIAL SHAPE INDEX...........................................-

1 1.3 AZIMUTHAL P0WER' TILT........................................

1-1

-1.4 CHANNEL' CALIBRATION.........................................

1-1 1.5 CHANNEL CHECK...............................................

11-1 y

1.6 CHANNEL FUNCTIONAL; TEST.....................................

1,

-1.7 CONTAINMENT INTEGRITY.......................................-

1-2

.l 1.8 CONTROLLED LEAKAGE..........................................

1-2 1.9 CORE ALTERATION.............................................

1-3 i

-1.9a CORE OPERATING LIMITS. REPORT................................

1-3 1.10 DOSE EQUIVALENT I-131...............;.......................

1-3 g

1.11 E-AVERAGE DISINTEGRATION ENERGY.............................

1-3 l.12 ENGINEERED SAFETY FEATURES RESPONSE TIME....................

1-3 i

1.13 FREQUENCY N0TATION..........................................

1-3 1.14 IDENTIFIED LEAKAGE..........................................

1-3 r

1.15 MEMBER (S) OF THE PUBL1C.....................................

1-4 1.16 0FFSITE DOSE CALCULATION MANUAL.............................

1-4 t

1.17 OPERABLE - OPERABILITY...................................... 4 1.18 OPERATIONAL MODE - M0DE.....................................

1-4 1.19 PHYSICS TESTS...............................................

1-5 i

1.20 PLANAR RADIAL PEAKING FACTOR - Fxy..........................

1-5 1.21 PRESSURE BOUNDARY LEAKAGE...................................

1-5 l

1.22 PROCESS CONTROL PR0 GRAM.....................................

1-5 1.23 PURGE - PURGING.............................................

1-5 l

1.24 RATED THERMAL P0WER.........................................

1-6 1.25. REACTOR TRIP SYSTEM RESPONSE TIME...........................

1-6 l

1.26 REPORTABLE EVENT............................................

1-6 1.27 SHIELD BUILDING INTEGRITY...................................

1-6 1.28 SHUTDOWN MARGIN.............................................

1-6 j

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'WATERFORD - UNIT 3 I

AMENDMENT NO.102 i

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I I.EEE-

. DEFINITIONS (Continued).

i, i

SECTION=

PAGE i

1.29 SITE 800NDARY................................................

--l-7 1.30 50FTWARE.................................................... 7 1.31 DELETED.'....................................................

1-7

.1.32 SOURCE CHECK................................................

1-7' 1.33 STAGGERED TEST 8 ASIS........................................-

1-7

.1.34 THERMAL P0WER...............................................

1-7 l

1.3s uNioENTIFIEo LEAxasE........................................

1-7 1.36 UNRESTRICTED AREA...........................................

1-8 1.37 VENTILATION EXHAUST TREATMENT SYSTEM........................ 8

'1.38 VENTING.....................................................

1-8 1.39 WASTE GAS HOLDUP SYSTEM.....................................'

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WATERFORD - UNIT 3 II Amendment No. 68 7

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. ADMINISTRATIVE CONTROLS SECTION EAE 6.5.2 SAFETY REVIEW COMMITTEE...................................

6-10

[

FUNCTION...............................................

6-10 COMPOSITION................................

6-10 l

ALTERNATES............................................

6-10 i

CONSULTANTS............................................

6,

. MEETING FREQUENCY......................................

6-11 QU0 RUM.................................................

6-11 REVIEW.................................................

6-11 AUDITS.................................................

6-12 AUTHORITY..............................................

6-13 REC 0RDS................................................

'G-13 6.6 REPORTABLE EVENT ACTI0N.....................................

6-13 i

6.7 SAFETY LIMIT VIOLATION......................................

6-13 t

6.8 PROCEDURES AND PR0 GRAMS......................................

'6-14 6.9 REPORTING REQUIREMENTS......................................

6-16 s

6.9.1 ROUTINE REP 0RTS...........................................

6-16 STARTUP REP 0RT..........................................

6-17 ANNUAL REP 0RTS.........................................

6-17 MONTHLY OPERATING REP 0RT...............................-

6-18' ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.....

6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.............

6 INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............

6-20 CORE OPERATING LIMITS REP 0RT......-.....................-

6-20 6.9.2 SPECIAL REP 0RTS...........................................

6-20a 6.10 ' RECORD RETENT10N...........................................

6-20a t

WATERFORD'- UNIT 3 XVII AMENDMENT NO. 50,04,102

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' ADMINISTRATIVE C00mt0L5 IICTION pgg

.6.11 RADIATION,ROTECTION P m M...............................

6-22 6.12 HIGH RADIATION AREA.........'..................;............

6-22

6. u,RocEss C0 0L,R0.

N....................................

6n 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-24 5

i 1

k WATERFORD - UNIT 3 XVIII Amendment No. 68 l

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s, INDEX LIST OF FIGURES FIGURE PEif 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION......................................

3/4 1-13 3.4-1

-DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131.......

3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (HEATUP)...........................................

3/4 4-30' 3.4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN).........................................

3/4 4-31 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..........

3/4 7-26 5.1-1 EXCLUSION AREA.....................................

5-2 5.1-2 LOW POPULATION 20NE................................

5-3 5.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS...................................

5-4 6.2-1

'0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPP0RT.................................

6-3 6.2-2 PLANT OPERATIONS ORGANIZATION......................

6-4 k

l WATERFORD - UNIT 3 XIX AMENDMENT NO. 13,27,102 9

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- LIST OF TABLES' TABLE EAGE

- 1.1.

FREQUENCY N0TATION....................................

1-9

' 1.2-OPERATIONAL'N00ES......................'...............

1-10 2.2-1 REACTOR PROTECTIVE. INSTRUMENTATION -TRIP SETPOINT:

i LIMITS.................................................

=2-3~

- 2.2 CORE PROTECTION CALCULATOR ADDRESSABLE-CONSTANTS......

225 MONITORING FREQUENCIES FOR BORON DILUTION DETECTION-

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3.3-1 REACTOR PROTECTIVE INSTRUMENTATION....................

3/4 3-3 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................

~3/4 3 :

3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......................................

3/4 3-14 a

3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES...........................

'3/4 3-19:

4.3-2 ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............

3/4 3-25 3.3-6 RADIATION MONITORING INSTRUMENTATION..................

3/4 3-29:

4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-32 3.3-7 SEISMIC MONITORING INSTRUMENTATION....................

3/4 3-36 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3 3.3-0 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-39 l

i WATERFORD - UNIT 3 XX AMENDMENT NO. 9 94r102 7

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4 DEFINITIONS i

IDENTIFIEDLEAKAGE-(Continued)'

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Leakagexinto the. containment atmosphere from sources that are both i

specifically located and known either not to interfere with the i

Loperation of leakage detection systems lor'not. to be PRES $URE SOUWARY LEAKAGE, or Reactor Coolant System leakage.through'a steam generator to the.

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secondary system.

I MEMBERfS) 0F THE PUBLIC

'i 1.15 MEMBER (s 0F THE PUBLIC shall include all persons who are not occupa-tionally assoc)ated with the plant. This. category does not include employees i

i of the licensee, its contractors, or vendors.. Also excluded from.this category are persons who enter the site to service equipment or make deliveries. Th's category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL fnnrM) l 1.16-The 0FFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and~ parameters ustd in the calculation of offsite doses resulting from radio-active gaseous and liquid affluents, in the calculation of gaseous and liquid

.i effluent monitoring Alarm / Trip setpoints, and in the conduct of.the Environmen-tal Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring 1.

Programs required by Section 6.8.4 and-(2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual. Radioactive Effluent Release Reports required by Specification 6.g.1.7.

l and 6.9.1.8.

~

OPERABLE - OPERABILITY 1.U A system, subsystem, train, component, or device shall b OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when-all neces sary 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).,

DPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive n

L combination of core. reactivity condition, power level and average reactor

. coolant temperature specified in Table 1.2.

4 WATERFORD UNIT 3 1-4 Amenhent No. 44, 84

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DEFINITIONS CORE ALTERATION i

1.9 CORE ALTERATION shall.be the movement.or manipulation of any component ~

within the reactor pressure vessel with the vessel head removed and fuel.in-the vessel.. Suspension of CORE ALTERATION shall not preclude completion of i

movement of a component to a safe conservative position.

COLR - CORE OPERATING LIMITS REPORT l

1.9a The CORE OPERATING LIMITS REPORT'is the Waterford 3 specific document that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating' limits-shall be determined for each reload cycle in accordance with Technical Specification 6.9.1.11.

Plant operation within these operating limits is addressed'.in individual specifications.

DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT'I-131 shall be that concentration of 'I-131 (microcuries/

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 actually 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."

- E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of.

1 each radionuclide in the reactor coolant at the time of sampling) of the_ sum of the average beta.and gamma energies per disintegration-(in MeV) for. isotopes, other than iodines, with half-lives greater than 15 minutes, making'up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY-FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values,.etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

i FRE0VENCY NOTATION 1.13 The FREQUENCY NOTATION specified for-the performance of Surveillance Requireme.ts shall correspond to the intervals defined in Table.l.1.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

I a.-

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks.that are captured, and conducted to a sump or collecting tank, or WATERFORD UNIT'3 1-3 AMEN 0 MENT NO.102

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Y 3/4.1' REACTIVITY CONTROLLSYSTEMS-3/4.1.1' B0 RATION CONTROL-i

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SHUTDOWN MARGIN - ANY FULL LENGTH CEA WITHDRAWN

' LIMITING CONDITION FOR OPERATION'

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3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to' that'specified in'the COLR.

APPLICABILITY: MODES 1, 2*, 3, 4, and 5 with any full length CEA fully or l

partially withdrawn.

~

r ACTION:

With the SHUTDOWN MARGIN less than that required above, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution con-taining greater than or equal to 1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS I

4.1.1.1.1 With any full length CEA fully or partially withdrawn, the SHUTDOWN MARGIN shall be' determined'to be greater than or equal to that specified in~ the COLR-a.

Within'1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s) is inoperable.

If the a

inoperable CEA is immovable or untrippable, the above required J

SHUTDOWN MARGIN shall'be verified acceptable with an increased allowance'for the withdrawn worth of the immovable or untrippable CEA(s).

b.

When in MODE 1 or MODE 2 with Keff greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.

c.

When in MODE 2 with Keff less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted j

critical CEA position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1.

I WATERFORD. UNIT 3 3/4 1-1 AMENDMENT NO. 11,23,102

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$URVEILLANCE REQUIREMENTS (Continued)

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d.

Prior to initial operation above SK RATED THERMAL POWER after'each fuel: loading, by consideration of.the factors of e. below, with the CEA groups at the. Transient Insertion Limits of Specification 3.1.3.L I

' s.

When in MODE 3, 4, or 5, at~1 east once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration' of at least the following factors:

1.

' Reactor Coolant System boron concentration,s b

2.

CEA position, 3.

Reactor Coolant Sys. tem everage temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

' Xenon concentration, and 6.

Samarium concentration.

1 4.1.1.1.2 The overall core reactivity balance shall-be compared to predicted

)

values to. demonstrate agreement within + 1.0K delta k/k at least once per 31-Ef feetive Full. Power Days (EFPD). ' This~ comparison shall-consider at least those factors stated.in Specification 4.1.1.1.le., above. -The predicted reactivity values shall be adjusted (normalized) to correspond to the actual _

core conditions prior to exceeding a fuel burnup'of 60 EFPDs after each fuel.

loading.

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WATERFORD - UNIT 3 3/4 1-2 AMENDMENT N0. 11 4 e n-,

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's o-E ACTIVITY CONTROL SYSTEMS-X SHUTDOWN MARGIN - ALL' FULL LENGTH CEAS FULLY INSERTEQ LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater' than or equal to that'specified-

'in-the COLR.

APPLICABILITY: MODES 3,: 4 and 5 with all full : length CEAs : fully inserted.

ACTION:

With the SHUTDOWN MARGIN less than that specified in the COLR, imme'iately j

d initiate and continue boration at greater than or equal to 40 gpm of a solution.

containing greater than or equal to.1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 With al1< full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that specified in~ the.COLR, at1 l

1 east once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

l.-

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant System average temperature, 4.-

Fuel buruup based on gross thermal energy generation, S.

Xenon concentration,and 6.

Samarium concentration.

'WATERFORD - UNIT 3 3/4 1-3 AMENDMENT NO. 11,33,102

g.

REACTIVITY CONTROL: SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR'0PERATION-3.1.1.3, The moderator temperature coefficient (MTC) shall be 'within th'e limits-specified in the COLR..The maximum upper design limit shall bei y

Less' positive than 0.5 x 10. delta k/k/*F whenever THERMAL POWER is' a..

570% RATED THERMAL POWER, and-t b.

Less positive than.0.0 x 10 delta k/k/*F whenever THERMAL POWER is-

>70% RATED THERMAL POWER.

APPLICABILITY: MODES 1 " and 2*#.

r ACTION:

With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i SURVEILLANCE REQUIREMENTS

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4.1.1.3.1 The MTC shall.be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to -

permit direct comparison with the above limits.1 4.1.1.3.2 The MTC shall be determined 'at the following frequencies and THERMAL POWER conditions during each fuel cycle:

a.

Prior to initial operation ~above 5% of RATED THERMAL POWER, after each fuel loading.

b. -

At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup.

I c.

At any THERMAL POWER, within 7 EFPD of reaching two-thirds of expected core burnup.

With K greater than or equal to 1.0.

i ge Sp,e,c,ial Test Exception 3.10.2.

See Special' Test Exception 3.10.2 applicable for Mode 1 during startup test of Cycle 2.

WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. Grl4102 7

REACTIVITY CONTROL SYSTEMS' BORON DILUTION LIMITING CONDITION FOR OPERATION-3.1.2.9:

Boron concentration shail be' verified consistent with SHUTDOWN MARGIN requirements of Specifications 3.1.1.1, 3.1.1.2, and 3.9.1.

Boron dilution events shall. be precluded by either "a" gr "b" below.

a.

1.

Two boron dilution alarms (startup channel high neutron flux)

I shall be OPERABLE with the alarms set in accordance with Specification 4.1.2.9.5 ADA 2.

i.

If the plant is in MODE 4, then remove power to at least one charging pump.

ii.

If the plant is in MODE 5 with k

( 0.97, then remove, power to at least one charging p,u,m,p.

iii. If the plant is in MODE 5 with k,,, > 0.97, then remove power to at least two charging pumps.

iv.

If the plant is in MODE 6, then remove power to at least two charging pumps.

98 b.

1.

The primary makeup water flow path to the reactor coolant system shall be isolated And 2.

Do not operate the plant in the configurations prohibited by the COLR for the current MODE.

APPLICABILITY: MODES 3*,'4, 5, and 6.

While any shutdown CEA is less than~145 inches withdrawn.

ACTION:

a.

With the boron concentration not consistent with required SHUTDOWN MARGIN, initiate emergency boration.

b.

With one boron dilution alarm inoperable and the primary makeup water flow path to the reactor coolant system not isolated, determine reactor coolant system' boron concentration within one hour and at-least at the monitoring frequency specified in' the COLR.

l c.

With both boron dilution alarms inoperable and the primary makeup water flow path to the reactor coolant system not isolated, determine the reactor coolant system boron concentration by two independent means within one hour and~at least at the monitoring frequency specified in the COLR; otherwise, immediately suspend all operations

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involving positive reactivity changes or CORE ALTERATIONS (if applicable).

1:

WATERFORD - UNIT 3 3/4 1-15 AMENDMENT NO. 9,L*,59,102 i

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~ REACTIVITY CONTROL' SYSTEMS' t

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, LIMITING' CONDITION FOR OPERATION-(Continued) 1 ACTION:-(Continued)-

d.

The' provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

o SURVEILLANCE REQUIREMENTS 4.1'.2.9.1 The provisions'of Specification 4.0.4-are not. applicable'for entry into. MODE 3 from MODE 2.

4.1.2.9.2 Each required boron dilution alarm.shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

4.1.2.9.3 If the primary makeup water flow path to the. Reactor Cool' ant System:

~

is isolated to fulfill 3.1.2.9.b, the reqt:# red primary makeup water flow path

.i to the Reactor Coolant System shall be verified to be isolated by either locked-closed manual valves, deactivated automatic valves secured.in the isolation position, or by power being removed.from all. charging pumps, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.1.2.9.4: The requirements-of. Specification 3.1'.2.9.a'.2 or 3.1.2.9.b.2 shall be verified at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.1.2.9.5 Each required boron dilution alarm setpoint'shall, be adjusted to less.than or equal to the. existing neutron flux (cps) multiplied by the value.

specified in the COLR, at the frequencies specified in the COLR.

e l

l WATERFORD - UNIT 3 3/4 1-16 AMENDMENT NO. 0,'0,50,102

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THIS PAGE IS NOT USED WATERFORD - UNIT 3 3/4 1-17 AMENDMENT NO. 9r48r102

N' REACTIVITY CONTROL SYSTEMS'

- 3/4.1.3 MOVABLE CONTROL ASSEMBLIES mo

,4 CEA POSITION LIMITING CONDITION FOR OPERATION-3.1 '. 3.1 All full-length (shutdown and regulating) CEAs, and all part-length

- CEAs.which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 7 inches (indicated position) of all other CEAs in. its f

group.

APPLICABILITY: MODES 1* and 2*.

ACTION:

a.

With one or more full-length CEAs inoperable due 'to being' immovable as a result of excessive friction or mechanical interference or known 1

to be untrippable, determine that the' SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full-length or part-length CEA trippable but misaligned from any other CEA in its group by more than-19 inches (indicated position), be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one full-length or part-length CEA trippable but misaligned from any other CEA in its group by more than 19 inches,' operation in MODES I and 2 may continue, provided that core power is reduced in accordance with the limits specified in the COLR and within l' hour-l.

the' misaligned CEA is either:

1.

Restored to OPERABLE status within its above specified alignment _.

requirements, or-2.

Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. After declaring the CEA inoperable, operation'in MODES 1 and 2 may continue _ pursuant.to the requirements of Specification 3.1.3.6 provided:

a)

Within I hour the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on; the THERMAL POWER l

1evel shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1. is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

See Special Test Exceptions 3.10.2 and 3.10.4.

WATERFORD UNIT 3 3/4 1-18 AMENDMENT NO. 11,81,102

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LIMITING' CONDITION FOR OPERATION (Continuedt

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ACTIONr!(Continued)

s' 1

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With one or' more_ full-length or. part-length CEAs. trippable but

,#w,

misaligned from any other CEAs in its group by more than~-7 inches ~but s

ziess than or equal to'19 inches, operation in MODES I and 2 may q~

~

continue, provided that core power is reduced in accordance with the limits specified in;the COLR and within 1; hour'the misaligned.CEA(s)-

'is either:

1 i

/

1..-

Restored to OPERABLE status within its above specified alignment requirements, or

'~

Declared inoperable and the SHUTDOWN MARGIN requirement of:

2.

Specification 3.1.1.1 is satisfied. After declaring the CEA inoperable, operation in MODES 1-and 2 may continue pursuant to -

i the requirements of Specification 3.1.3.6 provided:-

1 a)l Within I hour the remainder of.the CEAs in the group with-the inoperable CEA shall be aligned to within 7 inches of-the inoperable CEA while maintaining the allowable CEA I

< sequence and insertion limits shown on; the THERMAL' POWER

[

level.shall be restricted pursuant to Specification 3.1.3.6 during. subsequent. operation.-

.lo 4

'~

b)~

The' SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is

~ determined at'least once per 12; hours.

Otherwise, be.in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With one fuil-length CEA trippable but inoperable-due.to causes other.

than addressed by ACTION a., above, and inserted beyond the Long Ters' l

Steady State Insertion Limits but within.its above specified alignment requirements, operation. in MODES.I and.2 may continue l

pursuant to the requirements of Specification 3.1~.3.6.

f.

With one full-length CEA trippable'but' inoperable due to causes vi.ner -

than addressed by ACTION a., above, but within its above specified j

alignment requirements and either greater than or equal to-145 inches i

withdrawn or within the Long Term Steady' State Insertion Limits if in full-length CEA group 6, operation in MODES-'1-and 2 may. continue.

g.

With one part-length CEA inoperable and inserted in the ' core, operation may continue provided the alignment of the inoperable part-i length-CEA is' maintained within 7 inches (indicated position) of all i

other part-length CEAs in its group and the CEA is maintained' pursuant to the requirements of Specification 3.1.3.7.

h.

With more than one full-length or part-length CEA trippable but inoperable due to causes other than addressed by ACTION a., above, restore the inoperable CEAs to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

f WATERFORD - UNIT 3 3/4 1-19 AMENDMENT NO. 11,"1,102 1

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1, ; yg REGULATING CEA INSERTION LIMITS f

LINITING CONDITION FOR OPERATION i

3.1.3.6 ? The' regulating CEA' groups shall be limited to the'withdrawallsequence 4

and'to the insertion limits

specified'in the.COLR**'with CEA insertion.between-

}

, the Long Ters steady State Insertion Limits-and the Transient Insertion' Limits

. restricted to:

a.

Less than or equal to 4 ' hours per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, Less'than~or equ'l to 5 Effective Full Power Days per 301 Effective'.

9

'b.

a Full Power Day interval, and 1

c.

Less than or equal to 14 Effective Fu11 Power Days per calendar' year..

.j APPLICABILITY: MODES 1*** and 2***

f.

ACTION:

.2 s-a.

With the regulating CEA groups inserted beyond the Transient-Insertion Limits, except for surveillance testing pursuant-to Specification 4.1.3.1.2, or Reactor Power Cutback, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months j

either:

~1.

Restore the regulating CEA groups to within the limits, or 2.

Reduce THERMAL POWER to less than or. equal to that. fraction'ofc i

RATED THERMAL POWER which is allowed by the CEA group position-using the COLR.

l t

b.

With the regulating CEA groups inserted between the Long Term Steady.

l State Insertion Limits and the Transient' Insertion-Limits for

~ '

-l

-intervals greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24-hour interval,. operation may proceed provided either:

s 1.

lThe Short Term ~ Steady State Insertion Limits specified in the.

COLR are not exceeded, or 2.

Any subsequent increase in THERMAL POWER is restricted to less-than or equal to 5% of RATED THERMAL POWER per hour.

i

Following a reactor power cutback in which (1) Regulating Groups 5 and/or 6-

+

are dropped or (2) Regulating Groups 5 and/or 6 are dropped and the remaining Regulating Groups (Groups 1, 2, 3, and 4) are sequentially inserted, the Transient Insertion Limit specified in the COLR can be l

exceeded for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .-

L

- CEAs are fully withdrawn in accordance with the Transient Insertion Limit specified in the COLR when withdrawn to' at least 145 inches.

- - SeeLSpecial Test Exceptions 3.10.2 and 3.10.4.

With K,,, gr' eater than or equal to 1.0.

j

. WATERFORD - UNIT 3 3/4 1-25 AMENDMENT NO.102

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' LIMITING CONDITION FOR OPERATION (Continued)-

ee (ACTIONi[(Continued).

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c.

With the regulating CEA groups inserted-between the1Long Term. Steady, State Insertion Limits and the: Transient Insertion Limits ~for intervals

!V9 greater' than:5 EFPD per -30 EFPD sintervalc or. greater than 14 ;EFPD;per I

d calendar-year, either:

1.

Restore the; regulating groups'to within the:Long Term Steady 4

g" State-Insertion. Limits within two hours, or 2.

Be.in at least HOT STANDBY within 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each regulating CEA group shall be determined to be-

- within the. Transient-Insertion Limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals' when ~the PDIL Auctioneer Alarm Circuit is inoperable, then verify!the individual CEA positions.at;least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .'_,The accumulated:

- times during whichf the regulating CEA groups are ic.serted' beyond(the Long Term:

Steady" State Insertion'L'imits but within.the' Transient-Insertion Limits.shall-be determined at least once per 24' hours.

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.WATERFORD'- UNIT 3 3/4 1-27 AMENDMENT. MO. 4ep102.

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.j REACTIVITY CONTROL SYSTEMS PART LENGTH CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.7 The part length CEA groups shall be limited to the insertion limits specified in the COLR with PLCEA insertion between the Long Term Steady State l

Insertion Limit and the Transient Insertion Limit restricted to:-

a.

s 7 EFPD per 30 EFPD interval, and b.

s 14 EFPD per calender year.

APPLICABILITY: MODE I above 20% THERMAL POWER.*

ACTION:

a.

With the part length CEA groups inserted beyond the Transient Insertion Limit, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours, either:

r 1.

Restore the part length CEA group to within the limits, or 2.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the PLCEA group position as specified in the COLR.

[.

b.

With the part length CEA groups inserted between the Long Term Steady State Insertion Limit 'and the Transient Insertion Limit for intervals

> 7 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, either:

1.

Restore the part length group within the Long Term Steady State Insertion Limits within two hours,'or 2.

Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.1.3.7 The position of the part length CEA group shall be determined to be within the Transient Insertion Limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

See Special Test Exception 3.10.2.

WATERFORD - UNIT 3 3/4 1-28 AMENDMENT NO. 4 b 102

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s3/4.2 POWER DISTRIBUTION LIMITS 3/4:2.1 LINEAR HEAT-RATE-LIMITING COND'ITION FOR OPERATION 3.2.1 The linear heat rate limit, specified in the COLR,. shall be maintained.

l

~

by one of the following nethods' as' applicable:

a.

Maintaining COLSS calculated core power less than' or equal-to COLSS calculated core power operating limit based on linear heat-rate (when COLSS is in service); or b.

0>erating within the region of acceptable operation specified in e

tie COLR using any operable CPC channel'(when COLSS is out:of service).

APPLICABILITY: MODE 1-above 20% of RATED THERMAL POWER.

ACTION:

a.

With the linear heat rate limit not being maintained asfindicated by COLSS calculated core power exceeding the COLSS calculated core power operating limit based on linear heat rate, within 15 minutes initiate-corrective action to reduce the linear heat rate to within the limit and either:

1.

Restore the linear heat rate:to within its limits within I hour, or 2.

Reduce THERMAL POWER to less than or equal to 20% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the linear heat rate limit not being maintained as indicated by operation outside the region of acceptable operation specified in the COLR with COLSS out of service, either:

41.

Restore COLSS to service within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or 2.

Restore the linear heat rate to within its limits within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or 3.

Reduce THERMAL POWER to less than or equal to 20% of. RATED THERMAL POWER within the next 6' hours.

SURVEILLANCE REQUIREMENTS 4.2.1.1 The provisions of Specifit.ation 4.0.4 are not applicable.

4.2.1.2 The linear heat rate shall be determined to be within its limits when THERMAL POWER is above 20% of RATED THERMAL POWER by continuously monitoring the core power distribution with the Core Operating Limit Supervisory System WATERFORD - UNIT 3 3/4 2-1 AMENDMENT NO. 12,32,102 l

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( t, POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION

.(COLSS) or, with the COLSS out of service,- by verifying at least once.per

. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that.the linear heat rate, as indicated on any OPERABLE Local Power

{

' Deraity channel, 4 within the limits. specified in the COLR.

l-j 4.2.1.3 At least once per 31 days, the COLSS Margin Alarm shall be verified j

to actuate at a THERMAL POWER level-less thai: or equal to the core power.

operating limit based on kW/ft.

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WATERFORD - UNIT 3 3/4 2-la AMENDMENT NO. Be 102 r

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- WATERFORD"- UNIT 3-3/4 2-2 AMENDMENT NO. M r102

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s POWER DISTRIBUTION LIMITS.

h 3/4'.2.2 ' PLANAR RADIAL PEAKING FACTORS - F,y

^

LIMITING CONDITION FOR OPERATION The measured PLANAR RADIAL PEAKING FACTORS-(F"y) shall be less than or.

3.2.2 equal to the PLANAR RADIAL PEAKING FACTORS (FC ) used in the Core Operating-y Limit. Supervisory System (COLSS) and'in the Core Protection' Calculators (CPC).

APPLICABILITY:

MODE I above 20% of RATED THERMAL POWER.*

l

. ACTION:

With a F*

exceeding a corresponding F y, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

C Adjust the CPC addressable constants to increase the multiplier a.

applied to planar radial peaking by a factor equivalent to greater.

than or equal to F"y/F,C and restrict sut, sequent operation so that a.

y margin to the COLSS operating limits of'at least (F" /FC ) - 1. 0) y x 100% is maintained; or b.

Adjust the affected PLANAR RADIAL PEAKING FACTORS (FC ) used in the COLSS and CPC to a value greater-than or equal to the measured PLANAR RADIAL PEAKING FACTORS (F"y) or c.

Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

The measured PLANAR RADIAL PEAKING FACTORS-(F"y) obtained by using

'4.2.2.2 the incore detection system, shall be. determined to be less than or equal to j

the PLANAR RADIAL PEAKING FACTORS (FC ), used in the COLSS and CPC at the y

'following intervals:

a.

After each fuel loading with THERMAL POWER greater than 40% but prior to operation above 70% of RATED THERMAL POWER, and b.

At least once per 31 effective full power days (EFPD).

"See Special Test Exception 3.10.2.

WATERFORD - UNIT 3 3/4 2-3

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POWER DISTRIBUTION LIMITS c

3/4.2.3: AZIMUTHAL POWER TILT -

T,_.

1 l LIMITING CONDITION FOR' OPERATION"

.sq j

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13.2.3 The AZIMUTHAL 5 POWER TILT (T,)L shall be less1than or' equal to the iFOLLOWING LIMITS:

o.c

.a.-

AZIMUTHAL POWER TILT Allowance used.in theLCore' Protection ^

1 r Calculators (CPCs) and j

b.

the. limit specifiedLin the COLR.

l i

APPLICABILITY: MODE I above 20%'of. RATED THERMAL POWER.*

E-ACTION:

~

a.

With the measured AZIMUTHAL POWER' TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the:CPCs within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ~

either. correct'the power tilt or adjust the AZIMUTHALLPOWER TILT j

Allowance used in the'CPCs to greater than or equal to the i-measured value.-

j e

I 4

b.

With the' measured AZIMUTHAL POWER TILT determined to exceed the r

limit specified in the COLR:

~

l..

Due to misalignment of either a:part length or full length CEA, within 30 minutes verify that the Core Operating Limit

-1 Supervisory System (COLSS) (when COLSS is being used to moniter the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.

1 E

2.

Verify that the AZIMUTHAL POWER TILT.is within its. limit J

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for a CEA misalignment event).or 1

reduce THERMAL POWER to less~than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 'and reduce the Linear Power Level -~

l High trip setpoints to less than or equal to 55% of RATED.

i THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause' of the out of limit condition a

prior to increasing THERMAL POWER; subsequent POWER.

i OPERATION above 50% of RATEDLTHERMAL POWER may proceed

l

~

,provided that the AZIMUTHAL POWER TILT is' verified within j

its limit at least'once per. hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until t-verified acceptable at 95%'or greater RATED THERMAL POWER.

+

See Special Test Exception 3.10.2.

.{

i i

WATERFORD - UNIT 3 3/4 2-4 AMENDMENT NO. W 102 i

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n.

s, POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The AZIMUTHAL POWER TILT shall be determined to be within the limit' above 20% of RATE 0' THERMAL POWER by:

Continuously monitoring the tilt with COLSS when the COLSS is OPERABLE.

a.

b.

Calculating the tilt at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the COLS5 is inoperable.

Ver'fying at least once per,31 days, that the COLSS Azimuthal Tilt c.

Alarm is actuated at an AZIMUTHAL POWER TILT greater than the AZIMUTHAL POWER TILT Allowance used in the CPCs.

d.

Using the incore detectors at least once per 31 days to independently confirm the validity of the COLSS calculated AZIMUTHAL POWER TILT.

1 4

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WATERFORD - UNIT 3 3/4 2-5

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' POWER DISTRIBUTION LIMITS l

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{f 3/4.2.4 DNBR MARGIN w

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[LIMITINGCONDITIONFOR'0PERATION

[,,

' 3.2.4' oThe' DNBR margin shall,be ' maintained by,one of the following methodsi m-a.-

Maintaining'COLSS calculated core power less than or-equal-to-COLSSLcalculated core power operating limit based on DNBR:(when ' >,

l

~

COLSS is in service,.and:either one or both CEACs-are operable) or

.)

P

.b.

Maintaining 00LSS calculated core power less than or equal to.

j

'COLSS calculated' core power operating limit based on DNBR

'l 1

' decreased by the-amount specifled in the COLR-(when COLSS~is in:

service and.neither:CEAC is operable); or 2

c.

' Operating.within the region of acceptable operation specified in'.

the COLR using any operable-CPC channel (when COLSS is out of Li service and either one or both CEACs are operable); or-

't d

d.

Operating'within the region of acceptable. operation specified in L

the COLR-using:any operable CPC channel (when COLSS'is out of' i

service and neither CEAC is operable).

a

~

APPLICABILITY: MODE I above 20% of RATED THERMAL P9WER.

j ACTION:

I a.

With the DNBR limit not being maintained assindicated by COLSS~

calculated cora power exceeding the COLSS calculated core power-operating limit based on DNBR, within 15 minutes initiate corrective action to reduce the DNBR-to within the limits and either:

1.

Restore the DNBR to within its limits within l' hour, or i

2.

Reduce THERMAL POWER to less than or equal to 20% of RATED. THERMAL POWER within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s-b.

With the DNBR limit not being maintained as indicated by operation, outside the region of acceptable operation specified in.the COLR with -

l' COLSS out of service, either:

l 1.

Restore COLSS to service within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

.[

2.-

-Restore the DNBR to within its limits within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or.

3.

Reduce' THERMAL POWER to less than or equal. to 20% of RATED THERMAL POWER within the next 6 bours.

1 j

s WATERFORD - UNIT 3 3/4 2-6 AMENDMENT NO. 12,22, 102 j

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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4.1 The provisions of Specification 4.0.4 are not-applicable.

4.2.4.2. The DNBR shall be determined to be within its limits when THERMAL POWER.is above 20% of RATED THERMAL POWER by continuously monitoring the core power distribution with the Core Operating Limit Supervisory System (COLSS) or, with the COLSS.out of service, by verifying at least once per 2: hours that lthe DNBR, as. indicated.on any OPERABLE DNBR channel, is within the limit-specified in the COLR.

l 4.2.4.3 At least once per 31 days, the COLSS Margin Alarm shall be verified to actuate-at a THERMAL POWER level less than or equal to the core power operating limit based on DNBR.

i i

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l' WATERFORD - UNIT 3 3/4 2-6a AMENDMENT NO. 34 102 7

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WATERFORD - UNIT 3 3/4 2-7 AMENDMENT NO. 44r102:

(Next page is 3/4 2-10) l e

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POWER DISTRIBUTION LIMITS

[

3/4.2.5 RCS FLOW RATE p

.' LIMITING CONDITION FOR OPERATION ~

'3.2.5 The actual Reactor Coolant System total flow rate shall be greater than

jl j

or equal to 148.0 x 105 iba/h.

APPLICABILITY: MODE 1.

ACTION:

With the actual Reactor Coolant System total flow rate determined to be less than the above limit, reduce THERMAL POWER to less than 5% of RATED THERMAL j

POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS I

4.2.5-The actual Reactor Coolant. System total flow rate shall be determined I

to be greater than or equal to the above limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f I

WATERFORD - UNIT 3 3/4 2-10

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LPOWERDISTRIBUTION'L'IMIT5'

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,5 33/4.2.6' REACTOR COOLANT COLD LEG TEMPERATURE v.

i ' LIMITING CONDITION FOR OPERATION Li

$.[

o 3.2.6 ~ The reactor. coolant cold leg temperature (T ) shall. be maintained.

!between 544'F.and 558'F.*

c t

APPLICA8ILITY: : MODE 1 above.30% of RATED THERMAL POWER.

! ACTION:

.t With the reactor coolant cold' leg temperature exceeding'its limit, restore'the

. temperature to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce; THERMAL POWER to less-

<than 30%'of RATED THERMAL POWER:within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE' REQUIREMENTS t

4.2.6 The reactor coolant cold leg temperat.ure shall be determined to be

. within its limit at least once'per-12-. hours-i i

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Following.a reactor power cutback in which (1) Regulating Groups 5 and/or 6 are dropped or (2) Regulating Groups 5 and/or 6 are dropped and the remaining Regulating Groups (Groups 1, 2, 3, and 4) are sequentially inserted, the upper. limit on T may increase to 568*F for up to 30 minutes.

i WATERFORD - UNIT.3 3/4 2-11 I

lu POWER DISTRIBUTION LIMITS

'3/4.2.7 AXIAL SHAPE INDEX LIMITING CONDITION FOR OPERATION 3.2.7 The AXIAL SHAPE INDEX (ASI) shall be maintained within the limits specified in the COLR.

APPLICABILITY:. MODE I above 20% of RATED THERMAL POWER.*-

l ACTION:-

With the AXIAL SHAPE INDEX outside the limits specified in the COLR, restore I

the AXIAL SHAPE INDEX to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 20% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REOUIREMENTS

+

4.2.7 The AXIAL SHAPE INDEX shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months using the COLSS or any OPERABLE Core Protection Calculator channel.

j f

See Special Test Exception 3.10.2.

l WATERFORD - UNIT 3 3/4 2-12 AMENDMENT NO. 13,25,102 w

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1

, /9c 3/4.9~' REFUELING OPERATIONS 3/4;9.1 BORON _ CONCENTRATION

^ IMITING CONDITION FOR OPERATION L

'3.9.1 With the reactor vessel head closure bolts less than-fully tensionsd or i

with the head removed, the' boron. concentration ofia11 filled portions of the.

Reactor Coolant System and the refueling canal shall' be maintained uniform and

-sufficient to ensure that the more restrictive of the reactivity conditions specified in the COLR is met.

i APPLICABILITY: MODE 6*.

ACTION:

With the requirements'of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm of a solution containing at;1 east 1720 ppe boron or its equivalent until K,,

is reduced to less than or equal to the value specified in the COLR or the boron concentration is restored to greater than or equal to the value specified in the COLR, whichever is the more restrictive.

SURVEILLANCE REQUIREMENTS

^

4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full-length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

l

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor-vessel with the reactor vessel head closure bolts less than fully tensioned or with the head rewoved.

WATERFORD - UNIT 3.

3/4 9-1 AMENDMENT N0.102 I

REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be OPERABLE and operating, each with continuous visual indication in the' control room and one with audible indication in the containment and control room.

APPLICABILITY:

MODE 6.

ACTION:

a.

With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b.

With both of the above required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant i

System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i q

SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at letst once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and c.

A CHANNEL FUNCTIONAL TEST at least once per 7 days.

WATERFORD - UNIT 3 3/4 9-2

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REACTIVITY ~(QtLTROL SYSTEMS BASES i

B0 RATION SYSTEMS-(Continued) 3y

. The contained water' volume limits include allowance for water not 3

available because of discharge line ~1ocation, instrument tolerances,' and other i

physical characteristics.

'The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while. in MODE 6.

The lower limit on the contained water volume, the specified boron concentration, and the physical size (approximately 600,000 gallons) of the RWSP also ensure a pH value of between 7.0 and 11.0 for-the solution recirculated within containment:after a LOCA.. This pH band minimizes the evolution of iodine and minimizes the effect:of chloride and caustic stress' corrosion on mechanical systems and components.

The maximum limit on the RWSP temperature ensures that the assumptions used in the containment pressure analysis under design base accident condi-tions remain valid and avoids the possibility of containment overpressure.

The minimum limit on the RWSP temperature is required to prevent freezing and/

or boron precipitation in the RWSP.

3/4.1.2.9 BORON DILUTION l

This specification is provided to prevent a boron dilution event, and to prevent a loss of SHUTDOWN MARGIN should an inadvertent boron dilution event occur. Due to boron concentration requirements for the RWSP and boric acid i

makeup. tanks, the only possible boron dilution that would remain undetected by the operator occurs'from the primary makeup water through the CVCS system.

Isolating this potential dilution path or the OPERABILITY of the startup

'l channel high neutron flux alarms, which alert the operator with sufficient time available to take corrective action, ensures that no loss of SHUTDOWN MARGIN and unanticipated criticality occur.

The ACTION requirements specified' in the event startup channel high neutron flux alarms are inoperable provide an alternate means to detect boron dilution by monitoring the RCS boron concentration to detect any changes. The frequencies specified in the COLR provide the operator sufficient time to l

L recognize a decrease in boron' concentration and take appropriate corrective action without loss of SHUTDOWN MARGIN. More frequent checks are required

- with more charging pumps in operation due to the higher potential boron dilution rate.

The surveillance requirements specified provide assurance that the startup channel high neutron flux alarms remain OPERABLE and that required-i valve and electrical lineups remain in effect.

j l

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power i

distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is WATERFORD - UNIT 3 B 3/4 1-5 AMENDMENT NO. 9r102

=

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.3/4L2' POWER DISTRIBUTION LIMITS BASES

/

3/4.2.1 LINEAR HEAT RATE The limitation.on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200*F.

Either of the.two core power distribution monitoring-systems, the Core -

Operating Limit Supervisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators CPCs), provides adequate 4

monitoring of the core power distribution an is. capable of verifying that the

+

-linear heat rate does not exceed.its limits. The COLSS performs this function by continuously monitoring the core power distritution and calculating a core power operating limit corresponding to the allown.ble peak linear heat rate.

Reactor operation at or below this calculated power level assures that' the limit specified in the COLR is not exceeded.-

l The_ COLSS calculated core power and the COLSS calculated core power.

i '

operating limits based on.11near heat rate are continuously monitored and

-displayed to the operator. A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit. This provides adequate n

margin to the linear heat rate operating limit-for normal steady-state

^

operation. Normal reactor power transients or equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.

In the event this occurs, COLSS alarms will be annunciated.

If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the =

t Reactor Protective Instrumentation. The COLSS calculation of the linear heat rate limit includes appropriate uncertainty and penalty factors necessary to provide a 95/95 confidence level that the maximum linear heat rate calculated by COLSS is greater than or equal to that existing in the core. To ensure that the design margin to safety is maintained, the COLSS computer program includes an F measurement uncertainty factor of 1.053, an engineering y

uncertainty factor of 1.03, a THERMAL POWER measurement uncertainty factor of 1.02 and appropriate penalty factors for rod bow.

Parameters required to maintain the operating limit power level based on linear heat rate, margin to DNB ~and total core power are also monitored by the CPCs (assuming minimum core power of 20% of RATED THERMAL POWER). The 20%

RATED THERMAL POWER threshold is due to the neutron flux detector system being less accurate below 20% core power. Core noise level. at low power is too large to obtain usable detector readings. Therefore, in the event that the COLSS is'not being used, operation within the limits specified in the COLR can l

be maintained by utilizing a predetermined local power density margin and a total core power limit in the CPC trip channels.. The above listed uncertainty and penalty factors are also included in the CPCs.

These penalty factors;are determined from uncertainties associated with planar radial peaking measurements, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.

WATERFORD - UNIT 3 B 3/4 2-1 AMENDMENT NO. 4h102

s.

A!:

BASES

The additional uncertainty terms included ~1n the CPC's for transient -

protection are credited in the limits specified in the:COLR since this curve l-

, is intended to monitor the LCO only during steady state operation.

+

l-b s

f i

WATERFORD - UNIT 3 B 3/4 2-la AMEN 0 MENT NO. 407102

m9 POWER DISTRIBUTION LIMITS I

n ggggg 3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting' the values of the PLANAR RADIAL PEAKING FACTORS (F*

used in i

the COLSS and CPCs to ' values equal to or greater than the measure,d) PLANAR RADIAL PEAKING FACTORS (F" COLSS and the CPCs remain "Ja) lid.- provides assurance that the limits calculated by Data from the incore detectors are used for determining the measured PLANAR RADIAL PEAKING FACTORS. A minimum core power at 20% of RATED THERMAL POWER is assumed in determining the PLANAR RADIAL PEAKING FACTORS. The 20% RATED THERMAL-POWER threshold is'due to the heutron flux detector system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector readings. The periodic Surveillance Requirements for determining the measured PLANAR RADIAL PEAKING FACTORS provide assurance that the PLANAR RADIAL PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the fuel cycle. Determining the measured' PLANAR RADIAL PEAKING FACTORS after each fuel loading prior to' exceeding 70% of RATED THERMAL POWER provides additional assurance that the core was properly loaded.-

3/4.2.3 AZIMUTHAL POWER TILT - Ty The limitations on the AZIMUTHAL POWER TILT.are provided to ensure that design safety margins are maintained. The LCO requires the maximum azimuthal tilt during normal steady state power operation to be less tnan or equal to that specified in the COLR. With AZIMUTHAL POWER TILT greater than the limit specified in the COLR, operation is restricted to only those conditions required to identify the cause of the tilt. However, Action item b.2 allows 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore the tilt to less than or equal to the limit specified in the COLR following a CEA misalignment event (1.e., CEA drop). A CEA misalignment event causes an asymmetric core power generation and an increase in xenon concentration in the vicinity of the dropped rod. This event may cause the azimuthal tilt to exceed the' limit specified in the COLR. The 2

[

hour action time to reduce core power is not sufficient to recover from the xenon transient. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period allows for correction of the misaligned CEA and allows time for the xenon redistribution effects to dampen out due to radioactive decay and absorption. The reduction in xenon concentration (which is aided by operation at full power) will in turn reduce the tilt below the COLR limit.

l The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period is applicable only to a CEA misalignment where the cause of the tilt has been identified.

It is based on the time required or the expected xenon transient to dampen out. All other conditions (not due to a CEA misalignment) where the azimuthal tilt exceeds the limit specified in the COLR require action within the specified 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The tilt is normally calculated by COLSS. A minimum core power of 20% of RATED THERMAL POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power.

Core noise level at low power is too large to obtain usable detector readings.

The Surveillance Requirements specified when COLSS is out'of service provide an acceptable means of detecting the presence of a steady-state tilt.

It-is necessary to explicitly account for power asymmetries in the COLSS and CPCs because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.

WATERFORD - UNIT 3 8 3/4 2-2 AMENDMENT NO. 977102 i

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POWER' DISTRIBUTION LIMITS

BASES AZIMUTHAL POWER TILT

'Ta (Continued)

~

AZIMUTHAL POWER TILT is measured by assuming that the ratio of the. power

,-at any core location in the presence of a tilt to'the untilted power at'the-Llocation is of the fora:

P,iij/Pontig, =.I + T, g cos (0 - 0,)

where:_

j T -is the peak fractional tilt amplitude'at the core: periphery y

g.is' the radia1' normalizing factor 0.is the' azimuthal core: location p

0, is the azimuthal. core' location of maximum tilt.

P,it,/Pongit, is the. ratio of the power at a core location in the presence -

y of a tilt to the power at that-location with no tilt.

j 3/4.2.4 DNBR MARGIN The limitation on DNBR as a function of. AXIAL SHAPE INDEX represents'a conservative envelope of' operating conditions consistent with the, safety analysis assumptions and which have been analytically demnnstrated adequate to

. maintain an acceptable' minimum DNBR'throughout all anticipated.operattonal:

occurrences. Operation of the core with a DNBR at or.above this limit provides assurance that. an acceptable ~ minimum DNBR will be maintained.

Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the'DNBR channels in the. Core Protection Calculators -(CPCs), provides adequate monitoring of the core power -

distribution and is capable of verifying that the DNBR does not violate its

limits. The COLS$ performs this function by continuously monitoring the core power distribution and calculating a core operating limit' corresponding to the i

allowable minimum DNBR. The COLSS_ calculation of core power _ operating limit

=

based on the minimum DNBR limit includes appropriate _ penalty factors which provide a 95/95 probability / confidence level that the core power calculated'by COLSS, based on the minimum DNBR limit, is conservative with respect to the

~

actual core. power limit. These penalty factors are determined from the uncer-tainties associated with planar radial peaking measurements, state parameter.

measurement, software algorithm modelling, computer processing,-rod bow, and core power measurement.

Parameters required to maintain the margin to_ DNB-and total core power are also_ monitored by the CPCs. Therefore, in the event that the COLSS is not-being used, operation within~the limits _specified in the COLR can'be

'l maintained by utilizing a predetermined DNBR as a function of AXIAL SHAPE

.INDEX and by monitoring the CPC trip channels. The above. listed uncertainty i

.and penalty factors plus those associated with startup test acceptance

+

criteria are also included in the CPCs which assume a sinimum core power of 20% of RATED THERMAL POWER. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being less accurate below 20% core power.

Core ' noise _ level at low power is too large to obtain usable detector readings.

j-WATERFORD - UNIT 3 B 3/4 2-3 AMENDMENT NO. 12,07, 102

. a u

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POWER' DISTRIBUTION LIMITS BASES DNBR MARGIN (Continued)

A DNBR penalty factor has been included in the COLSS and CPC DN8R ~calcula-i i

tions to' accommodate the effects of rod bow. The amount of rod bow in each I

assembly is dependent upon the average burnup experienced by that assembly.

Fuel assemblies that incur higher average burnup will experience a greater -

4 magnitude of rod bow.

Conversely, lower burnup assemblies will experience' less rod bow.

In design calculations, the penalty for each batch required to l'

compenote for rod bow is determined from a batch's maximum average assembly burow applied to the batch's maximum integrated planar-radial power peak. J A sing u net penalty for COLSS and CPC is then determined from.the penalties asse lated with each batch, accounting for the offsetting margins due to the lowf " radial power peaks. in the higher burnup batches.

" 2.5 RCS FLOW RATE

)

.This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the LOCA safety analyses, and that the DN8R is maintained within the safety limit for Anti-1 cipated Operational Occurrences (A00).

{

3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses, with adjustment for instrument accuracy of 12'F, and that the peak linear heat generation rate and the moderator temperature coefficient effects are validated.

3/4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of AXIAL' SHAPE INDEX is maintained within the range of values used in the safety analyses, to ensure that the peak linear heat rate and DN8R remain within the safety limits for Anticipated Operational Occurrences (A00).

3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of' pressurizer pressure.is maintained within the range of values used in the safety analyses.

The inputs to CPCs and COLSS are the most limiting.

The values are adjusted for an instrument accuracy of

25 psi.

The sensitive events are SGTR, LOCA, FWLB and loss of condenser vacuum to initial aigh pressure, and MSL8 to initial'10w pressure.

WATERFDRD - UNIT 3 83/42-4 AMEN 0 MENT N0.12 d

s a;~;&}.;,

~3/4.9 REFUELING OPERATIONS

BASES

.3/4.9.1 BORON CONCENTRATION-The limitations on reactivity' conditions during REFUELING ensure'that:

..(1) the reactor will'. remain subcritical during CORE ALTERATIONS, and (2) a-uniform boron concentration is'maintainedffor reactivity control'in the water.

volume having direct' access to the reactor vessel. These limitations are con--

sistent with the initial conditions assumed for the boron dilution incident ~in.

the safety analyses..The Kg value specified in the COLR includes' a 1%

..I delta k/k conservative allowance for uncertainties. Similarly, the boron

. concentration value specified-in the COLR also includes a conservative l.

. uncertainty allowance of-50 ppe boron.

-3/4.9.2 -INSTRUMENTATION The OPERABILITY cf the source range neutron flux monitors. ensures that redundant monitoring capability is available to detect changes in the

. reactivity condition of the core.

3/4.9.3 DECAY TIME.

The minimum requirement for reactor subcriticality prior to movement of-

-irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the safety. analyses.

3/4.9.4 CONTAINMENT BUILDING' PENETRATIONS The requirements on containment penetration closure.and'0PERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure

' restrictions are sufficient to restrict radioactive material release.from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMUNICATIONS The requirement.for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

WATERFORD - UNIT 3 B 3/4 9-1 AMENDMENT N0.102

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REFUELING OPERATIONS-BASES I

3/4.9.6 REFUELING MACHINE' The OPERABILITY requirements for the refueling machine ensure

' that: -(1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) each hoist has sufficierit load capacity to lift a CEA or fuel-assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in'the event they are inadvertently engaged during

- lifting operations.

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction'on movement of loads in excess of the nominal' weight of a fuel assembly, CEA, and associated handling tool over other fuel assemblies in' c

the spent. fuel pool ensures that in the event this load is dropped (1) the

- activity release will be limited to that contained'in a single fuel assembly,.

and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.

i 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION i

The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required

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during the REFUELING MODE, and (2) sufficient coolant circulation is main-tained through the reactor core to minimize-the effects of a boron' dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23_ feet of wate'r above the reactor pressure vessel flange, ensures.

l that a single failure of the operating shutdown cooling train will not result' in a complete loss of decay heat removal capability...When there is no1 irradiated fuel in the reactor pressure vessel, this is not a consideration and only one

- shutdown cooling train is required to be OPERABLE. With the reactor vessel head removed and 23 feet of water above tha reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM I

The OPERABILITY of this system ensures that the containment purge valves will.be automatically isolated upon detection of high radiation levels within the containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

WATERFORD - UNIT 3 B 3/4 9-2 1-.e+

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L.o ADMINISTRATIVE CONTROLS ANNUAL CAD 10 ACTIVE EFFLUENT ArtfASE REPORT 6.9.1.8 The Annual Radioactive Effluent Release Report cc>vering the operation of the unit during the previous 12 months of operation shall be submitted

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within 60 days after January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit The material provided shall be (1) consistent-with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to_10 CFR Part 50.

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l WATERFORD - UNIT 3 6-19 Amendment No. 68, 84 i

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ADMINISTRATIVE CONTROLS INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT i

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6.9.1.9 Surveys and analyses of major. industries in the vicinity of Waterford

3 which could have significant inventories of. toxic chemicals onsite to.

determine impact on ' safety shall be performed and submitted to the Commission'.-

atlleast'once'everyL4 years.

- 6.9.1.10 A ' survey of' major pipelines '( i 4 inches).within a 2-mile radius of

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Waterford 3, which contain explosive or flammable meterials and may represent.

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. a hazard to.Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least'once every.4 years.

CORE OPERATING LIMITS REPORT COLR 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT. prior to each reload cycle or;any remaining part of a.

reload cycle.

6.9.1.11.1 The analytical methods used to_ determine the-core operating. limits shall be those previously reviewed and approved bylthe NRC'as follows:

1) "The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983; and "C-E Methodology for Core Designs Containing Gadolinia '

Urania Burnable Absorber," CENPD-275-P-A, May 1988.

(Methodology for Specificatier.s 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.I'.1.3 for.MTC, 3.1.3.6 for Regulating CEA. Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron Concentratior.).

2) "C-E Method for Control. Element Assembly Ejection Analysis," ~CENPD-0190-A, January 1976.

(Methodology for Specification 3.1.3.6:for Regulating CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt)..

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3) " Modified Statistical Combination of Uncertainties" CEN-356(V)-P-A, May 1988.

(Methodology for Specification 3.2.4 for DNBR Hargin and 3.2.7 for ASI).

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4) " Calculative Methods for the C-E Large Break LOCA Calculation Model For.

The Analysis of C-E and W Designed NSSS," CENPD-132, Supplement 3-P-A,

.i June 1985.

(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for-ASI).

5) " Calculative Methods for the C-E Small Break' LOCA Evaluation Model,"

l CENPD-137-P, August 1974: Supplement 1, January 1977.

(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).

6) "CESEC - Digital Simulation for a Combustion Engineering Nuclear Steam Supply System," CENPD-107, December 1981.

(Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA Insertion Limits, 3.1.3.7 for Part length CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt).

WATERFORD - UNIT 3 6-20

. AMENDMENT NO. 68r102 i

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'S ADMINISTRATIVE CONTROLS ~

- CORE OPERATING LIMITS REPORT COLR.(Continued) 6.9.1.11.2 The core operating limits shall be determined such that all

applicable limits (e.g., fuel thermal limits,' core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.11.3 The CORE OPERATING LIMITS REPORT,1 including any mid-cycle revisions

' or supplements thereto,. shall be provided upon issuance, for. each reload cycle, to the NRC Document Control Desk with copies to the Regional: Administrator and-Resident. Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall'be submitted to the Regional Administrator of the Regional Office of. the NRC within the time ' period specified for each report.!

6.10 RECORD RETENTION 6.10.1. In addition to. the applicable record retention requirements of Title 10, Code of-Federal Regulations, the following records'shall be retained for at least the minimum period indicated.

c WATERFORD - UNIT 3 6-20a AMENDMENT.NO.102 w-,

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