Text

Proposed Tech Specs,Reflecting Removal of cycle-specific Parameter Limits
	ML20072B552
Person / Time
Site:	Waterford
Issue date:	08/11/1994
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20072B538	List: ML20072B534; ML20072B552; ML20072B562;
References
	NUDOCS 9408160161
	Download: ML20072B552 (90)
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i l

INDEX l

DEFINITIONS l l

SECTION PAGE l

1. 0 DEFINITIONS ;

1.1 ACTI0N...................................................... 1-1

1. 2 AXIAL SHAPE INDEX.................... .... ................. 1-1

1. 3 AZIMUTHAL POWER TILT........................................ 1-1 1.4 CHANNEL CALIBRATION.................. ...................... 1-1

1. 5 CHANNEL CHECK.................... ...... .................. 1-1

1. 6 CHANNEL FUNCTIONAL TEST............ ....... ............... 1-2

1. 7 CONTAINMENT INTEGRITY.... ... ............ ................. 1-2

1. 8 C O NT RO L L ED L EA KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.9 CORE ALTERATION....... ..................................... 1-3 1.10 DOSE EQUIVALENT I-131.. .................................... 1-3 1.11 E-AVERAGE DISINTEGRATION ENERGY................... ......... 1-3 1 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME.................... 1-3 1.13 FREQUENCY N0TATION.......................................... 1-3 1.14 IDENTIFIED LEAKAGE................................. ...... . 1-3 1.15 MEMBER (S) 0F THE PUBLIC..................................... 1-4 1.16 0FFSITE DOSE CALCULATION MANUAL............................. 1-4 1.17 OPERABLE - OPERABILITY......... .. ......................... 1-4 1.18 OPERATIONAL MODE - M0DE..................................... 1-4 1.19 PHYSICS TESTS............................................... 1-5 1.20 PLANAR RADIAL PEAKING FACTOR - F .......................... 1-5 1.21 P RESSURE BOUNDARY LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.22 PROCESS CONTROL PR0 GRAM...................... .............. 1-5 1.23 PURGE - PURGING...... ...................................... 1-5 1.24 RATED THERMAL POWER.......... .............................. 1-6 1.25 REACTOR TRIP SYSTEM RESPONSE TIME........................... 1-6 1.26 REPORTABLE EVENT............................................

1-6 1.27 SHIELD BUILDING INTEGRITY................................... 1-6 1.28 SHUTDOWN MARGIN..................... .... 1-6 WATERFORD - UNIT 3 JJC)Pn/No.

9408160161 940811 PDR P

ADOCK 05000382 pyg

IGfl ADMINISTRATIVE CONTROLS SECTION EAGI 6.5.2 SAFETY REVIEW C0mITTEE................................... 6-10 FUNCTION............................................... 6-10 COMPOSITION............................................ 6-10 ALTERNATES............................................. 6-10 CONSULTANTS............................................ 6-10 MEETING FREQUENCY...................................... 6-11 Q U0 R UM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-11 REVIEW................................................. 6-11 AUDITS................................................. 6-12 AUTHORITY.............................................. 6-13 REC 0RDS................................................ 6-13 6.6 REPORTABLE EVENT ACTI0N..................................... 6-13 6.7 SAFETY LIMIT VI0LATION...................................... 6-13 6.8 PROC EDURES AND_ PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14 6.9 REPORTING REQUIREMENTS...................................... 6-16 6.9.1 ROUTINE REP 0RTS........................................... 6-16 STARTUP REP 0RT......................................... 6-17 ANNUAL REP 0RTS......................................... 6-17 MONTHLY OPERATING REP 0RT............................... 6-18 A M UAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..... 6-18 ANNUAL RAD 10 ACTIVE EFFLUENT RELEASE REPORT............. 6-19 l INDUSTRIAL SURVEY 0F T0XIC CHEMICALS REPORT............ 6-20 6.9.2 SPECIAL REP 0RTS........................................... 6-20 6.10 RECORD RETENTION........................................... 6-20 WATERFORD UNIT 3 XVII Amendment No. 68,84

INDEX LIST OF FIGURES ,

l FIGURE PAGE l 3.1-0 SHUTDOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE............................ 3/4 1-3a 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION...................................... 3/4 1-13 3.1-1A REQUIRED POWER REDUCTION AFTER SINGLE CEA DEVIATION 3/4 1-20a 3.1-2 CEA INSERTION LIMITS VS THERMAL P0WER.............. 3/4 1-27 3.1-3 PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER... 3/4 1-28a 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc.............. 3/4 2-2 3.2-1A ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT OF SERVICE......................................... 3/4 2-2A 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE).. 3/4 2-8 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE CEACS IN0PERABLE)......................................... 3/4 2-9 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 I

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 B0UNDARY 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 WATERFORD - UNIT 3 XIX AMENDMENT NO. 13, 27

\

l INDEX LIST OF TABLES I

TABLE PAGE 1.1 FREQUENCY N0TATION...................................... 1-9

1. 2 OPERATIONAL M00ES.......................................

1-10 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETP0lNT LIMITS.................................................. 2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSA8LE CONSTANTS........ 2-5 l MONITORING FREQUENCIES FOR BORON DILUTION DETECTION 3.1-1 K, f f > 0 . 9 8. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-17 3.1-2 0 . 9 8 > K, f f > 0. 9 7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 1-17a ,

3.1-3 0. 9 7 > K, f f > 0. 96 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 1-17b 3.1-4 0 . 9 6 > K, f f > 0 . 9 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 1-17c. 1 3.1-5 K,ff < 0.95............................................. 3/4 1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . 3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES. . . . . .3/4 . 3-8 1

4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................ 3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................... 3/4 3-14 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES............................. 3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES............... 3/4 3-22 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRLMENTATION SURVEILLANCE REQUIREMENTS............... 3/4 3-25 3.3-6 RADIATION MONITORING INSTRUMENTATION.................... 3/4 3-29 4.3-3 RA0!ATION 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 3-37 1 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............... 3/4 3-39 !

l WATERFORD - UNIT 3 XX AMEN 0 MENT NO. 9 1 1

l DEFINITIONS l

CORE ALTERATION !

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 1 l

the vessel. Suspension of CORE ALTERATION shall not preclude completion of '

movement of a component to a safe conservative position.

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-133,1-134, 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 - AVE' RAGE DISINTEGRATION ENERGY 1.11 I 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 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.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

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

'I ,

3/4.1 REACTIVITY CONTROL SYSTEMS l

3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - ANY FULL LENGTH CEA WITHDRAWN l

LIMITING CONDITION FOR OPERATION l

3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 5.15%

delta k/k when T,yg is greater than 200*F or 2.0% delta k/k when T,yg is less than or equal to 200*F.

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

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 With any full length CEA fully or partially withdrawn, the SHUT 00WN MARGIN shall be determined to be greater than or equal to that required above:

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 inoperable CEA is immovable or untrippable, the above required 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 K,7f 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 K,ff 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 critical CEA position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1.

WATERFORD - UNIT 3 3/4 1-1 AMENDMENT NO. II 33 1

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL FULL LENGTH CEAS FULLY INSERTED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that shown in -~~

Figure 3.1-0.

APPLICA8ILITY: MODES 3, 4 and 5 with all full length CEAs fully inserted.

ACTION:

With the SHUTOOWN MARGIN less than that shown in Figure 3.1-0, immediately initiate and continue boration at greater than or equel to 40 gpm of a solu-tion containing greater than or equil to 1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 With all full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that shown in Figure 3.1-0 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1. Reactor Coolant System boron concentration,

2. CEA position,

3. Reactor Coolant System average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon concentration,and

6. Samarium concentration.

WATERFORD - UNIT 3 3/4 1-3 AMENDMENT NO. II,33 l

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100' 2001 300 400! S00* 600 COLD LEG TEMPERATURE (*F)'

Figure 3.1-0 SHUTDOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE WATERFORD - UNIT 3 3/4 1-3a AMENOMENT NO II,33

REACTIVITY CONTROL SYSTEMS i .

MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a. Less positive than 0.5 x 10 ~4 delta k/k/*F whenever THERMAL POWER is f,70% RATED THERMAL POWER, and

b. Less positive than 0.0 x 10-4 delta k/k/*F whenever THERMAL POWER is > 70% RATED THERMAL POWER, and

c. Less negative than -3.3 x 10'4 delta k/k/*F at all levels of THERMAL POWER.

APPLICABILITY: MODES 1 (1) and 2*#

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 .

SURVEILLANCE REQUIREMENTS 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. l 4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL i 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,

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

With K,ff greater than or equal to 1.0.

See Special Test Exception 3.10.2. !

(1)See Special Test Exception 3.1'.2 0 applicable for Mode 1 during startup test of Cycle 2.

j WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. 16 l

REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION 3.1.2.9 Boron concentration shall 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" or "b" below,

a. 1. Two baron dilution alarms (startup channel high neutron flux) shall be OPERABLE with the alarms set in accordance with i

Specification 4.1.2.9.5 d

2. i. If the plant is *n MODE 4, then remove power to at least one charging pump.

ii. If the plant is in MODE 5 with k powertoatleastonechargingp8bh.~<0.97,thenremove iii. If the plant is in MODE 5 with k powertoatleasttwochargingp8bhs>.0.97,thenremove iv. If the plant is in MODE 6, then remove power to at least two charging pumps.

0R

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 !

Tables 3.1-1 through 3.1-5 for the current MODE. I APPLICABILITY: MODES 3*, 4, 5, and 6.

While any shutdown CEA is less than 145 inches withdrawn.

l 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 Tables 3.1-1 through 3.1-5.

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 Tables 3.1-1 through 3.1-5; otherwise, immediately suspend all operations involving positive reactivity changes or CORE ALTERATIONS (if applicable).

WATERFORD - UNIT 3 3/4 1-15 AMEN 0 MENT NO. 9,48,59

REACTIVITY CONTROL SYSTEMS-LIMITING CONDITION FOR OPERATION (Continued)-

ACTION: (Continued)

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, i

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 I) the primary makeup water flow path to the Reactor Coolant System is isolated to fulfill 3.1.2.9.b, the required primary makeup water flow path l 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 . l 4.1.2.9.5 Each required boron dilution alarm setpoint shall be adjusted to less than or equal to twice (2x) the existing neutron flux (cps) at the follow-ing frequencies:

a. At least once per 5 nours if the reactor has been shut down less than 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ;

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if the reactor has been shut down greater than or equal to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months but less than 7 days;

c. At least once per 7 days if the reactor has been shut down greater than or equal to 7 days.

WATERFORD - UNIT 3 3/4 1-16 AMENDMENT NO. 9,48,59

TABLE 3.1-1 REINIRED IOIITORING FREQUENCIES FOR BACKUP BORON

)I .LITION ltitCTION A5 A FUNCT"0N OF OPERATING I CWIGING PMP5 AND PUWT OPERA"MONAL N00E5 FOR K,ff GREATER-THAN 0.98 K,ff >0.98 OPERATIONAL Number of Operatina Charaine Pumos*

MODE O 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed ** !

4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Operation not allowed **

5 RCS filled B hours Operation not allowed **

5 RC5 partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Operation not allowed **

drainod 6 Operation not allowed **

Charging pug OPERABILITY for any period of time shall l constitute OPERABILITY for the entire monitoring frequency.

- The precluded number of charging' peps shall be verified to be l inoperable ity rocking out their motor circuit breakers.

1 i

. l WTERFORD - UNIT 3 3/4 1-17 AMDOENT NO. f. 48

TA8LE 3.1-2 REQUIRED MONITORING FREQUENCIES FOR 8ACKUP BORON ,

D::LUTIONl)ETECTION AS A FUNCTION OF OPl! RATING )

CIWIGING PijMPS AND P! ANT OPERAT::0NA . NO-JES FOR l 1

K,ff GREATER THAN 0.97 MD LESS THnN Olt E0JAL TO 0.98

0. 98 > K,ff >0.97 OPERATIONAL Number of Goeratina Charcina Punos*

MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.0 hours0 days 0 hours 0 weeks 0 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Operation not allowed *a 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.0 hours0 days 0 hours 0 weeks 0 months Operation not allowed **

5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

drained 6 Operation not allowed **

" Charging pump OPERA 8ILITY for any period of time shall constitute OPERA 8ILITY for the entire monitorin8 frequency.

- The precluded number of charging pumps shall be verified to be inoperable by l racking out their motor circuit breakers.

1 WATERFORD - UNIT 3 3/4 1-17a A M MENT NO. 5,48

I TABLE 3.1-3 REIlUIR!D MNITORING FREQUENCIES FOR E KUP 90RON llILU rION )titCTION A5 A FUNCT::0N O OPERATING CN:NG P MP5 AW PLANT OPERA";:0NA . WOES FOR K,ff GREnTER THAN 0.96 AND LESS TM O't EQUAL TO 0.97

0. 97 > K,f f >0. 96 OPERATIONAL Number of Goeratino Charninn Pumps

MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.0 hours0 days 0 hours 0 weeks 0 months 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months Q.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Operation not allowed **

5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Operation not allowed **

5 RCS partially 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

drained 6 Operation not allowesP"

" Charging pug OPERASILITY for any period of ties shall constitute OPERASILITY for the entire monitoring frequency.

- The precluded number of charging pumps shall be verified to be l inoperable by racking out their motor circuit breakers.

WATERFORD - UNIT 3 3/4 1-17b AfGR) MENT NO. 9,48

TABLE 3.1-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP 80RON XLUTION DETECTION AS A FUNCTION OF OPERATING C %RGING PUNPS AND PLANT OPERAT::0NAL MODES FOR K,ff GREATER THAN 0.95 AND LESS THM OR EQUAL TO 0.96

0. 96 > K,f f >0. 95 OPERATIONAL Number of Ooeratino Chargina Punos" M00E 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.0 hours0 days 0 hours 0 weeks 0 months 2.0 hours0 days 0 hours 0 weeks 0 months 1.0 hours0 days 0 hours 0 weeks 0 months 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation I not allowed **

5 ACS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.0 hours0 days 0 hours 0 weeks 0 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Operation drained not allowed" 6 Operation not allowed **

Charging pump OPERASILITY for any period of time shall constitute OPERASILITY for the entire monitoring frequency.

- The precluded number of charging pumps shall be verified to be l inoperable by racking out their motor circuit breakers.

1 WATERFORD - UNIT 3 3/4 1-17c AMENDMENT NO. 5,48

TABLE 3.1-5 RE0f!!RBD MONITORING FREQUENCIES FOR BACKUP 90RON D:.,WJON DETECTION AS A FUNCT"0N OF OPERAT"NG CHA tGING PUNPS AND PLANT OPERA";:0NAL MODES FOR K,99 LESS THAN OR EQUAL TO 0.95 K,gg 5,0.95 OPERATIONAL Number of Operatino Charnino Pumps

MODE O 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 5.0 hours0 days 0 hours 0 weeks 0 months 2.0 hours0 days 0 hours 0 weeks 0 months L O hours 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.0 hours0 days 0 hours 0 weeks 0 months 1.0 hours0 days 0 hours 0 weeks 0 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.0 hours0 days 0 hours 0 weeks 0 months 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 1.0 hours0 days 0 hours 0 weeks 0 months Operation not allowed **

drained 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

Charging p op OPERASILITY for arty period of time shall constitute OPERASILITY for the entire monitoring frequency.

- The precluded maber of charging pups shall be verified to be inoperable by l racking out their , motor circuit breakars.

t=

~

WATERFORD - UNIT 3 3/4 1-17d AMENDMENT NO. I,48

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 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 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 to be untrippable, determine that the SHUTDOWN MARGIN require-ment 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 l misaligned from any other CEA in its group by more than 19 inches (indicated position), be in at least HOT STAND 8Y 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 l l any other CEA in its group by more than 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in :

accordance with Figure 3.1-1A and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned l CEA is either: l

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

2. Declared inoperable and the SHUTDOWN MARGIN requirement of j Specification 3.1.1.1 is satisfied. After declaring the CEA inoperable, operation in MODES I and 2 may continue pursuant to

_the requirements of Spectfication 3.1.3.6 provided:

~

i) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the renainder 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 Figure 3.1-2; the .

THERMAL POWER leve1 M be restricted pursuant to Specification 3.1.3.~5 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 1-1B AMENDMENT NO. II, 81_

~

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

d. With one or more full-length or part-length CEAs trippable but l misaligned from any other CEAs in its group by more than 7 inches but less than or equal to 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3.1-1A,and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA(s) 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 Figure 3.1-2; the THERMAL POWER level 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 STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . l

e. With one full-length CEA trippable but inoperable due to causes other l than addressed by ACTION a., above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue pursuant to the req 0irements of Specification 3.1.3.6.

f. Withinefull-lengthCEAtrippiblebutinoperableduetocausesother l

,~

than addressed by ACTION a., aTove, but within its above specified alignment requirements and either greater than or equal to 145 inches withdrawn or within the Long Tern Steady State Insertion Limits if in

full-lengthCEAgroup6,operagigLinMODES1and2maycontinue. .

g. With one part-length CEA inoperable and inserted in the core,

, operation may continue provided the alignment of the inoperable part- l

length CEA is maintained within 7 inches (indicated position) of all ;

other part-length CEAs in its group and the CEA is maintained pursuant I

! to the requirements of Specification 3.1.3.7. 1 2

i

h. With more than one full-length or part-length CEA trippable but I inoperable due to causes other than addressed by ACTION a., above, l 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 STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I WATERFORD - UNIT 3 3/4 1-19 AMENDMENT NO. II, 81

~ _ _ _

.

i

)

l REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full-length and part-length CEA shall be detemined to be within 7 inches (indicated position) of all other CEAs in its group 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 one CEAC is ,

inoperable or when both CEACs are 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 . i 1

4.1.3.1.2 Each full-length CEA not fully inserted and each part-length CEA l which is inserted in the core below 145 inches shall be determined to be t OPERABLE by movement of at least 5 inches in any one direction at least once l oer 92 days. l l

l i

1 WATERFORD - UNIT 3 3/4 1-20 AMEN 0 MENT NO. 87 1

1

's l l

REQUIRED POWER REQUCTION AFTER SINGt.E CEA DE 5 '

g% 5 WE o ww E 30 -

$-q$

(60 MIN, 30%)

"328 w$3 20 -

IM5w Eg5*

g 10 -

0 i f i 0 15 3Q' 45 60 TflEAFTERCEADEVIATION(MINUTES)

lihan core power is reduced to 60% of rated power per this ifmit curve, further reduction is not required by this specification.

FIGURE 3.1-1A WATERFORO-UNIT 3 3/4 1-20a

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

l REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION i

1 3.1.3.6 The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits

shown on Figure 3.1-2** .with CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits restricted to: ,

a. Less than or equal to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval,

b. Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Day interval, and

c. Less than or equal to 14 Effective Full Power Days per calendar year.

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

' ACTION:

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 either:

1. Restore the regulating CEA groups 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 CEA group position using the above figure.

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

State Insertion Limits and the Transient Insertion Limits for 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:

1. The Short Term Steady State Insertion Limits of Figure 3.1-2 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.

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 of Figure 3.1-2 can be exceeded for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

- CEAs are fully withdrawn in accordance with Figure 3.1-2 when withdrawn to at least 145 inches.

- - See Special Test Exceptions 3.10.2 and 3.10.4. -

With K,ff greater than or equal to 1.0.

WATERFORD - UNIT 3 3/4 1-25' l

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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 shown on Figure 3.1-3 with PLCEA insertion between the Long Term Steady State Insertion Limit and the Transient Insertion Limit restricted to:

a. 5 7 EFPD per 30 EFPD interval, and

b. I 14 EFPD per calender year.

APPLICABILITY: MODE 1 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:

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 using Figure 3.1-3.

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 REQUIREMENTS 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. 13

_S (S3HONI STLL) 4 R';

11W17 N01183SNI 31VIS AOV31S WW31 DN01 -

C 3'

g.

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m w< E4 $< q o m! HE mm w OW mW w wi o.

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8- 8! S 8,1 8: S! 8' ,

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(%) H3 mod 7VWH3Hil FIGURE 3.1-3 PART LENGTH CEA INSERTION LIMIT VS. THERMAL POWER WATERFORD - UNIT 3 3/4 1-28a AMEldtNi' NO. 13 l

l

3/4.2 POWER DISTRIBUTION LIMITS 3/4 2.1 LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.1 The linear heat rate limit (of Figure 3.2-1) shall be maintained by one --

of the following methods 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. Operating within the region of acceptable operation of Figure 3.2-la 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 as indicated 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , l 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 in Figure 3.2-la with COLSS out of service, either:

_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 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.1.1 The provisions of Specification 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. I2, 32

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION i

(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 '

Density channel, is within the limits shown on Figure 3.2-la. __.,

4.2.1.3 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 kW/ft.

4 0

4 WATERFORD - UNIT 3 3/4 2-la AMENDMENT NO. 32 l

l 4L

~

Y 13.4 a 557.5'F

Kw/ FT

-- 13.4 i ,

$ UNACCEPTABLE z OPERATION N

4 13.3 2

9 E

a:

13.2 e

t- 13.1 Kw/FT 6 a 520*F 13'1

\ r ACCEPTABLE OPERATION w

E a

x 6

n. 13.0' ;

51C 520 530 540 550 560 Tc INITIAL CORE COOLANT INLET TEMPERATURE. 'F.

FIGURE 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc WATERFORD - UNIT 3 3/4 2-2 AMENOMENT NO.12

1

[

13.8 a 557.5'F

} Kw / FT -

x g 13.8 g7 g g 0-UNACCEPTABLE i

3w OPERATION b5 w<

HI go 13.7 20 -

90 xx w<

Zc 13.6 ww o8 [

y3 13.5 Kw/FT w2 a 520*F I< ACCEPTABLE c2 OPERATION

<o w-13.5 r b

a x

b 13.4 510 520 S30 540 550 560 Tc INITIAL CORE COOLANT INLET TEMPERATURE. 'F.

FIGURE 3.2-la ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT OF SERVICE WATERFORD - UNIT 3 3/4 2-2a AMENDMENT NO. 12

/

$ ~;.C; l POWER DISTRfBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - T; LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT q (T ) shall be less than or equal to the FOLLOWING LIMITS:

a. AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs) and

b. 0.03%.

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

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 I either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.

b. With the measured AZIMUTHAL POWER TILT determined to exceed 0.03: j

1. Due to misalignment of either a part length or full length ~

CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS) (when COLSS is being used to monitor the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.

2. Verify that the AZIMUTHAL POWER TILT is within its limit 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 j reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within tne next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Linear Power Level -

High trip setpoints to less than or equal to 55% of RATED 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 prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within 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 verified acceptable at 95% or greater RATED THERMAL POWER.

See Special Test Exception 3.10.2.

WATERFORD - UNIT 3 3/4 2-4 AMENDMENT N0. U

POWER OfSTRfBUTf0N LfMfTS I 3/4.2.4 DNBR MARGIN LIMITING CONDITION FOR OPERATION 3.2.4 The DNBR margin shall be maintained by one of the following methods:

l l

a. Maintaining COLSS calculated core power less than or equal to COLSS --

l calculated core power operating limit based on DNBR (when COLSS is I in service, and either one or both CEACs are operable); or

b. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 13% RATED THERMAL POWER (when COLSS is in service and neither CEAC :

is operable); or !

c. Operating within the region of acceptable operation of Figure 3.2-2 using any operable CPC channel (when COLSS is out of service and either one or both CEACs are operable); or

d. Operating within the region of acceptable operation of Figure 3.2-3 using any operable CPC channel (when COLSS is out of service and neither CEAC is operable).

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

ACTION:

a. With the ONBR limit not being maintained as indicated by COLSS calculated core 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or

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

b. _ith W the ONBR limit not being maintained as indicated by operation outside the region of acceptable operation in Figure 3.2-2 or 3.2-3 with COLSS out of service, either:

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 egrAl 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 .

l WATERFORD - UNIT 3 3/4 2-6 AMENDMENT NO. IZ,32

l 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that the DNBR, as indicated on any OPERABLE DNBR channel, is within the limit shown on Figure 3.2-2 or Figure 3.2-3.

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.

W i

I WATERFORD - UNIT 3 3/4 2-6a. AMENDMENT NO. 32 l)

POWER DISTRIBUTION LIMITS StpVEILLANCE REQUIREMENTS (Continued)

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I l

WATERFORD - UNIT 3 3/4 2-7 AMENOMENT NO. 12 1

ICOLSS OUT OF SERVICE DNBR LIMIT LINE J2.5 , , , , ,

12.4 l ACCEPTABLE _

l OPERATION

$ 12.3 -

2:

O g IMINIMUM 1 CEAC OPERABLE D

l(0.0, 2.20) 12.2 -

E , 4.22, 2.20) k O

l2.1 -

iUNACCEPTABLE

( .17,2.07) i OPERATION 12.0 -

l1.9 ' I I I I 4.3 LO.2 1-0.1 l0.0 S.1 10.2 0.3 iCORE AVERAGE ASI i

FIGURE 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE)

WATERFORD - UNIT 3 3/4 2-8 AMENDMENT NO. 12

. l

\

COLSS OUT OF SERVICE DNBR LIMIT LINE 2.8 i i i l ACCEPTABLE i OPERATION 2.7 - -

ICEACs INOPERABLE cc

'sc 2 i(0.0, 2.6) 10 2.6 - -

!E '(0.22, 2.6)

.2

?

if 2

b 12.5 - -

D iUNACCEPTABLE

! OPERATION 2.4 - -

(-0.17, 2.4)

!2.3 ' ' ' ' '

-0.3 LO.2 :-0.1 10.0 10.1 !0.2 0.3 ;

l iCORE AVERAGE ASI l

)

FIGURE 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs INOPERABLE) l WATERFORD - UNIT 3 3/4 2-9 AMENDMENT NO.12 l 1

FCWER 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 following limits:

a. COLSS OPERABLE

-0.22 < ASI < +0.27 for THERMAL POWERS > 70% of RATED THERMAL POWER

-0.27[ASI{+0.27forTHERMALPOWERS770%ofRATEDTHERMALPOWER

b. COLSS OUT OF SERVICE (CPC)

-0.17 < ASI < +0.22 for THERMAL POWERS > 70% of RATED THERMAL POWER

-0.22{ASI{+0.22forTHERMALPOWERS770%ofRATEDTHERMALPOWER APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.*

ACTION:

With the AXIAL SHAPE INDEX outside its above limits, restore 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.

See Special Test Exception 3.10.2.

WATERFORD - UNIT 3 3/4 2-12 AMEN 0 MENT N0. 13, 26

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3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION I LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portion: of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity conditions is met:

a. Either a K,ff of 0.95 or less, or

b. A boron concentration of greater than or equal to 1720 ppm.

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 least 1720 ppm boron or its equivalent until K,ff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 1720 ppm, whicheve'r 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 baron 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 .

"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 removed.

l 1

WATERFORD - UNIT 3 3/4 9-l' l l

REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

The contained water volume limits include allowance for water not available because of discharge line location, instrument tolerances, and other physical characteristics.

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

i The lower limit on the contained water volume, the specified boron concen-tration, 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 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 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 OPERASILI"Y of the startup 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 aftalternate means to detect boron dilution by monitoring:the RCS boron concentration to detect any changes. The frequen-cies specified in Tables 3.1-1 through 3.1-5 provide the operator sufficient time to recognize a decrease in boron concentration and take appropriate correc-tive action without loss of SHUTD0WN MARGIN. More frequent checks are required Z with more charging pumps in operationadue-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 valve and electrical lineups remain in effect.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES

. The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is WATERFORD - UNIT 3 8 3/4 1-3 AMENDMENT NO. 9 h

w-r ,r,---r - - .

_ ~ - . -_ __ _

3/4.2 POWER DISTRIBUTION LINITS

'8ASES 3/4.2.1 LINEAR HEAT RATE The Ifmitation 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 monitoring of the core power distribution and is capable of verifying that the linear heat rate .

does not. exceed its limits. The COLSS performs this function by continuously I monitoring the core power distribution and calculating a core power operating ifmit corresponding to the allowable peak linear heat rate. Reactor operation at or below this calculated power level assures that the limit of Figure 3.2-1 is not exceeded. l The COLSS calculated core power and the COLSS calculated core power operating limits based on linear 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 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 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 xy measurement uncertainty factor of 1.053, an engineering 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 DN8 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, tore noise level at low power is too large to obtain usanle detector rcadings. Therefore, in the event that the COLSS is not being used, operation within the limits of Figure 3.2-la can 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 :

factces are also included in the CPCs. l 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. 12 1

y ,.w-++ - .-. -- - sy-y

BASES

'a The additional uncertainty terms included in the CPC's for transient protection are credited in Figure 3.2-la since this curve is intended to monitor the LCO only during steady state operation.

r k

l 4

i WATERFORD - 3 8 3/4 2-la AMENDMENT NO. 12

l POWER DISTRIBUTION LIMfTS BASES 3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting the values of the PLANAR RADIAL PEAKING FACTORS (F* used in the COLSS and CPCs to values equal to or greater than the measure,d) PLANAR RADIAL PEAKING FACTORS (F" y) provides assurance that the limits calculated by COLSS and the CPCs remain , valid. 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 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 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 LC0 places a 3% limit on the .

maximum azimuthal tilt during normal steady state power operation. With AZIMUTHAL POWER TILT greater than 3%, 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 3% following a CEA misalignment event (i.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 3%. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action time to reduce core power is not sufficient to recover frcm 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 3% limit.

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 3% 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 B 3/4 2-2 AMENDMENT N0. 97

g: m ,, . :: , .:= ...H POSER DISTRIBUTION LIMfTS BASES AZIMUTHAL POWER TILT - To (Continued)

I 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 location is of the form:

P,, t , / P,,i t , = 1 + T, g c o s (0 - 0,)

where:

T, is the peak fractional tilt amplitude at the core periphery g is the radial normalizing factor ,

0 is the azimuthal core location 0, is the azimuthal core location of maximum tilt P,i t , / P,,, t , is the ratio of the power at a core location in the presence of a tilt to the power at that location with no tilt.

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 demonstrated adequate tc.

maintain an acceptable minimum DNBR throughout all anticipated operational ,

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 COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit cor' responding to the 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 i COLSS, based on the minimum DNBR limit, is conservative with respect to the i 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 DNS 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 of Figure 3.2.2 or Figure 3.2-3 can be maintained by utilizing a predetermined DNBR as a function of AXIAL SHAPE INDEX and by monitoring the CPC-trip channels. The above listed uncertainty and penalty factors plus those associated with startup test acceptance criteria are siso included in the CPCs which assume a 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.

.WATERFORD - UNIT 3 B 3/4 2-3 AMENDMENT NO. 4 h 97 j

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3/4.9 REFUELING OPERATIONS l

BASES l 1

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 maintained for 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 value of 0.95 or less for K,ff includes a 1% delta k/k conservative allowance for uncertainties. Similarly, the baron concentration value of 1720 ppm or greater also includes a conservative uncertainty allowance of 50 ppm boron.

3/4.9.2 INSTRUMENTATION The OPERABILITY of 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 OPERABILITY ensure that a release of radioactive material within containment wi',1 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 COMMUNICATIONS 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 8 3/4 9-1

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=a -

ADMINISTRATIVE CONTROLS INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT 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 at least once every 4 years.

6.9.1.10 A survey of major pipelines (> 4 inches) within a 2-mile radius of Waterford 3, which contain explosive or flammable materials and may represent 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.

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.

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L WATERFORD - UNIT 3 6-20 AMENDMENT NO. 68

- - . - + _

NPF-38-155 ATTACHMENT B l

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INDEX DEFINITION SECTION PAGE 1.0 DEFINITIONS 1.1 ACTION. . . .

1-1 1.2 AXIAL SHAPE INDEX. . 1-1 1.3 AZIMUTHAL POWER TILT. .. . 1-1 1.4 CHANNEL CALIBRATION. . . 1-1 1.5 CHANNEL CHECK. . . . . . . .. 1-1 1.6 CHANNEL FUNCTIONAL TEST. . . .. . 1-2 1.7 CONTAINMENT INTEGRITY.. .

1-2 1.8 CONTROLLED LEAKAGE. . . ... 1-2 1.9 CORE ALTERATION. . 1-3 1.9a CORE OPERATING LIMITS REPORT. 1-3a 1.10 DOSE EQUIVALENT I-131. . . . . . 1-3 1.11 E-AVERAGE DISINTEGRATION ENERGY. . .. . 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME. . . . 1-3 1.13 FREQUENCY NOTATION. . .. .. . 1-3 1.14 IDENTIFIED LEAKAGE.. . . . . . .. 1-3 1.15 MEMBER (5) 0F THE PUBLIC. . .. ... . 1-4 1.16 0FFSITE DOSE CALCULATION MANUAL. . ... . . 1-4 1.17 OPERABLE - OPERABILITY.. . .. .. . . . . . 1-4 1.18 OPERATIONAL MODE - MODE. .. . . .. 1-4 l l

1.19 PHYSICS TESTS. ... .. .. . . ... . . 1-5 l 1.20 PLANAR RADIAL PEAKING FACTOR - FXY. . . 1-5 1.21 PRESSURE BOUNDARY LEAKAGE., . . .. . . . .. .. 1-5 1.22 PROCESS CONTROL PROGRAM . . .. . . . .. . . . . . . 1-5 1.23 PURGE - PURGING. . 1-5 l

1.24 RATED THERMAL POWER. . . . ... . . . . .. ... 1-6 j 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 WATERFORD UNIT 3 I

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 SAFETY REVIEW COMMITTEE. 6-10 FUNCTION, . .. . 6-10 COMPOSITION. . . . 6-10 ALTERNATES. .. 6-10 CONSULTANTS. . . . . 6-10 MEETING FREQUENCY, . 6-11 QUORUM. . . 6-11 REVIEW. . . . 6-11 AUDITS. . . .. 6-12 AUTHORITY. . . . . 6-13 RECORDS. , . . 6-13 6.6 REPORTABLE EVENT ACTION. 6-13 6.7 SAFETY LIMIT VIOLATION. . 6-13 6.8 PROCEDURES AND PROGRAMS. . . . 6-14 6.9 REPORTING REQUIREMENTS.. . . . . .. . 6-16 6.9.1 ROUTINE REPORTS. .. . . . 6-16 STARTUP REPORT. . .. .... 6-17 ANNUAL REPORTS. .. . . . . .. 6-17 MONTHLY OPERATING REPORT. .. . .. ... 6-18 ANNUAL RADIOLOGICAL ENVIRONMENTA'. OPERATING REPORT . . 6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT. . .. 6-19 INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT. 6-20 CORE OPERATING LIMITS REPORT. 6-20 6.9.2 SPECIAL REPORTS. . . . . . . . 6-20 6.10 RECORD RETENTION. . . 6-20 l

l WATERFORD UNIT 3 XVII AMENDMENT NO.84 l 1

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INDEX LIST OF FIGURES FIGURE PAGE 3-4-0 SHUT 00c:" "f oGU! f5 ^ FUNCTION OF COLO LEG TEMPEP/ JUPE. 3/4 1 33 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTPATION . . .

3/4 1-13 3-MA REQUIRED POWER RE4XJGT4GN-#TER-54NGLE CE^. OEV!ATION 3/4 1 203 4-4-2 GEA-INSERT!0M LI" "S VS THEPF/L DOWER 3/4 1 27 3-4-3 PAP 7 LENGTu cg3 ;yggg7;gy L;gyr yg_7pgpuf.t og,;EP 344-4-28a 3-2-4 ALLOWASLE PE^? LINEAR HEAT o/TE VS Tc. 2.'" 2 2 3-2-4A ALLOWABLE PE^? LINEAR HE^7 o/TE VS Tc FOR COLSS 007 0F SER"!CE 3/A 2 2A 3-2-2 GNBR "^RGIM OPEPf""G LIMIT S/ SED 0" CORE oROTECTION CALCULATOPS (COLSS OUT OF SERVICE. CE^C OPEPf,BLE) 3/A 28 3-2-3 DNSR "ARG!N OPEP/7!MG LIMIT B? SED OM CORE PROTECTION CALCULATORS-MOL45 00T OF SERVICE CEACS 4NOPEPf,BLE4. 3M 2 0 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCLNT OF RATED THERMAL POWER WITH THE PRIMARY C00LxNT 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 LOA POPULATION ZONE.. . . .. .. . 5-3

[

5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND l

! LIOUID EFFLUENTS. .. . . . .. 5-4 l

6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT. , . 6-3 6.2-2 PLANT OPERATIONS ORGANIZATION. . . . . 6-4 ;

WATERFORD UNIT 3 XIX AMENDMENT N0. 27 l

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INDEX LIST OF TABLES TABLE . . PAGE 1.1 FREQUENCY NOTATION. .. . . 1-9 I 1.2 OPERATIONAL MODES. . 1-10 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS. . 2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSABLE CONSTANTS. . . ... 2-5 MONITORING FRE0VENCIES FOR BORON DILUTION DETECTION 3-M K g ' O.98. 3/d 1 l' 34-2 0.98 _ K g ' O.97 3/4-4-4J,a 3-1-3 0." : Mg; ' O.96. 3/4-14Jb a-t-4 0 96 : Vgg ' O.95. 3/d 1 17c 3- M Kg.r_: 0 95. 3/4-1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION. . . . . 3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES. 3/4 3-8 4,3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS.. . .. . . . 3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION. .. .. . . .. 3/4 3-14 3.3 4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES. . . . .. . 3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES. , . . . .. .. 3/4 3-22 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 3-37 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION. .. . . . . . 3/4 3-39 WATERFORD UNIT 3 XX MENDMENT N0. 9

DEFINITIONS CORE ALTERATIONS 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 movement of a component to a safe conservative position.

COLR CORE OPERATING LIMITS REPORT (SEE PNiE 1-3A) l DOSE EQUIVALENT I-131 1.10 DOSE E00lVALENT 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-131.1-132.1-133.1-134. and 1-135 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 (wcighted in proportion to the concentration of 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-1:ves 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.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1,1.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

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 13

DEFINIT 10tlS COLR - CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the Waterford 3 specific doctment that provides core operating limits for the current operating reload cycle. Thes' 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.

l l

l 1

WATERFORD UNIT 3 1-3a l i

_J

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - ANY FULL LENGTH CEA WITHDRAWN LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to that specified in the COLR frM! delta E/k : hen Tg-*s-9reater than 200 F or ?.0% delta ' hen T3yg is less than er-equal to 200*F.

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

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

SURVEILLANCE REQUIREMENTS 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: required above

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 thereaf ter while the CEA(s) is inoperable. If the inoperable CEA is immovable or untrippable, the above required 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 Trar.sient 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 critical CEA position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1.

WATERFORD UNIT 3 3/4 1 1 Amendment No. 11

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL FULL LENGTH CEAS FULLY INSERTED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that specified in the COLR._shown in Figure 3.1 0.

APPLICABILITY: MODE 3. 4 and 5 with all CEAs fully inserted.

ACTION:

With the SHUTDOWN MARGIN less than that specified in the COLR shown in rigure 3.1 0. l immediately 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 4.1.1.2.1 With all full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that specified in the COLR, shown in rigures 3-1-0 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1. Reactor Coolant System boron concentration.

2. CEA position.

3. Reactor Coolant System average temperature.

4. Fuel burnup based on gross thermal energy generation.

5. Xenon concentration, and

6. Samarium concentration.

l WATERFORD UNIT 3 3/4 1 3 Amendment No. 33 !

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Figure 3.1-0 SHUTOOWN MARGIN AS A FUNCTION

, OF COLO LEG TEMPERATURE -

WATERFORD - UNIT 3 3/4 1-Ja AMEN 0HENT NO II,33

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the COLR. The maximum upper design limit shall be:

a. Less positive than 0.5 x 10 ~4 delta k/k/'F whenever THERHAL POWER is s70%

RATED THERHAL POWER, and

b. Less positive than 0.0 x 10 -4 delta k/k/*F whenever THERHAL POWER is >70%

RATED THERHAL POWER, and

, c-r less m at h: then -3 ? - 10 4 delta k/k/*e at c1' levels of ERMAL-POWEAr APPLICABILITY: MODES 1#Cl) and 2*#

ACTION:

i 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 . ,

SURVEILLANCE RE0VIREMENTS 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.

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.

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

"With Keff greater than or equal to 1.0.

See Special Test Exception 3.10.2.

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

l WATERFORD UNIT 3 3/4 1 4 Amendment No. 16

l REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION i

3.1.2.9 Boron concentration shall 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" o_r "b" below.

i

a. 1. Two boron dilution alarms (startup channel high neutron flux) shall (

be OPERABLE with the alarms set in accordance with Specification 4.1.2.9.5.

.aM

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

charging pump. !

l

11. If the plant is in MODE 5 with keff s 0.97, then remove power to at least one charging pump.

iii. If the plant is in MODE 5, with keff > 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.

0R

b. 1. The primary makeup water flow path to the reactor coolant system shall be isolated ad

2. Do not operate the plant in the configurations prohibited by the COLR Tables 3.1 1 thruogh 3.15 for the current MODE. l APPLICABILITY: MODES 3*, 4. 5. and 6.

While any shutdown CEA 1s less than 145 inches withdrawn.

l 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 Tabic 3.11 through 3.15. 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 Tables 3.11 through 3.15; otherwise immediately suspend all operations involving positive reactivity changes or CORE ALTERATIONS (if applicable).

WATERFORD UNIT 3 3/4 1 15 Amendment No. 59

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

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

SURVEILLANCE REOUIREMENTS 4.1.2.9.1 The provisions of Spec 1fication 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 Coolant System is isolated to fulfill 3.1.2.9.b, the required primary makeup water flow path 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 twice (2;" the existing neutron flux (cps) multiplied by the value specified in the COLR, at the following frequencies specified in the COLR, h At least once per 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months " the reactor has been shut dow" less than 25 hour-s-I b- At least once per 2d hour: " the reacter has been shut dow greater than !

Or equal to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months but 10 0 than ' days; c- ^t least once pe- 7 day: " the reactor has been shut down greater than or equal to ' day .

WATERFORD UNIT 3 3/4 1 16 Amendment No. 59

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THIS PAGE IS NOT USED l WATERFORD UNIT 3 3/4 1 17

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 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 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 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 ene 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 1 and 2 may continue, provided that core power is reduced in accordance with the limits specified in the COLR Figure 3.11.^ and tMt within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the grcup with i the inoperable CEA shall be aligned to within 7 inches of !

the inoperable CEA while maintaining the allowable CEA l sequence and insertion limits shown on cigurc 3.1 2; the l THERMAL POWER level shall be restricted pursuant to- 1 I

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

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

d. With one or more full-length or part-length CEAs trippable but misaligned from any other CEAs in its group by more than 7 inches but less than or equal to 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with the limits specified in the COLR 4 9ure 3.11A and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned (CEA)(s) 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 Agure 3.12: the l THERMAL POWER level 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 the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

e. With one full-length CEA trippable but inoperable due to causes other than addressed by ACTION a., above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6.

f. With one full-length CEA tripable but inoperable due to causes other than addressed by ACTION a., above, but within its above specified alignment requirements and either greater than or equal to 145 inches 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 length CEA is maintained within 7 inches (indicated position) of all 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 then one full length or part length CEA trippable but inoperable due to causes other then addressed by ACTION a., above, restore the 1 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 l STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

WATERFORD - UNIT 3 3/4 1 19 l 1

l i

l REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS 1

LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits

specified in the COLR ***~' ~ rigure 3.12 with CEA insertion l between the Long Term Steady State Insertion Limits and the Transient Insertion Limits restricted to:

a. Less than or equal to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Interval,

b. Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Day interval, and

c. Less than or equal to 14 Effective Full Power Days per calendar year.

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

ACTION:

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 either:

1. Restore the regulating CEA groups 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 CEA group position using the COLR above figure. l

b. With the regulating CEA groups inserted between the Long Term Steady State Insertion Limits and the Transient Insertion Limits for 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:

1. The Short Term Steady State Insertion Limits specified in the COLR.

of cigure 3.12 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.

"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 of rigurc 3.12 can be 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 Figure 3.12 when withdrawn to at least 145 inches.

- - See Special Test Exceptions 3.10.2 and 3.10.4.

With Keff greater than or equal to 1.0.

WATERFORD UNIT 3 3/4 1 25

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THIS PAGE IS NOT USED l WATERFORD UNIT 3 3/4 1-27 .

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 chown on Figure 3.13 with PLCEA insertion between the Long Term Steady State Insertion Limit and the Transient Insertion Limit restricted to:

a. s 7 EFPD per 30 EFPD interval, and

b. s 14 EFPD per calendar year.

APPLICABILITY: MODE 1 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:

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 using rigure 3.1 3.

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 REQUIREMENTS 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.

l WATERFORD UNIT 3 3/4 1-28 AMENDHENT NO. 13

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(%) H3 mod 7VWH3Hil FIGURE 3.1-3 PART LENGTH CEA INSERTION LIMIT VS. THERMAL POWER WATERFORD - UNIT 3 3/4 1-28a AMEN 0 MENT NO. M

3/4.2 POWER DISTRIBUTION LIMITS 3/4 2.1 LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.1 The linear heat rate limit. specified in the COLR. (of rigure 3.21) shall be l maintained by one of the following methods as applicable:

a. Maintaining COLSS calculated core power less than or equal to COLS$

calculated core power operating limit based on linear heat rate (when COLSS is in service); or

b. Coerating within the region of acceptable operation specified in the COLR of rigure 3.2 la 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 as indicated 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 in rigure 3.2 la with COLSS out of service, either:

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 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 I

3. 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 . 1 SURVEILLANCE RE0VIREMENTS 4.2.1.1 The provisions of Specification 4.0.4 are not applicable. i l

4.2.1.2 The linear heat rate shall be determined to be within its limits when i THERMAL POWER is above 20% of RATED THERMAL POWER by continuously monitoring the l core power distribution with the Core Operating Limit Supervisory System I l

l WATERFORD - UNIT 3 3/4 2 1 AMENDMENT NO. 32

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 Density channels, is within the limits specified in the COLR cho'cm or. rigure 3.2 la. l 4.2.1.3 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 kW/ft.

WATERFORD UNIT 3 3/4 2 la AMENDMENT NO. 32

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FIGURE 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE V Tc WATERFORD - UNIT 3 3/4 2-2 , AMENOMENT NO.12 ;

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FIGURE 3.2-la ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLS5 OUT OF SERVICE ,

WATERFORD - UNIT 3 3/4 2-2a AMENOMENT NO. 12

l l

l i

This page intentionally lef t blank l WATERFORD UNIT 3 3/4 2 2

POWER DISTRIBUTION LIMITS 3/4.2.3 AZIHUTHAL POWER TILT Tg LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (Tq ) shall be less than or equal to the FOLLOWING LIMITS:

a. AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),

and

b. 0-034W. the limit specified in the COLR. l APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.*

ACTION:

a. W1th 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 AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.

b. With the measured AZIMUTHAL POWER TILT determined to exceed 0-03 the limit specified in the COLR:

1. Due to misalignment of either a part length or full length CEA. within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS) (when COLSS is being used to monitor the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.

2. Verify that the AZIMUTHAL POWER TILT is within its limit 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 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 - high trip setpoints to less than or equal to 55%

of RATED 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 prior to increasing THERMAL POWER: subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within 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 verified acceptable at 95% or greater RATED THERMAL POWER.

See Special Test Exception 3.10.2.

WATERFORD - UNIT 3 3/4 2 4 AMENDHENT NO. 97 l

l i

POWER DISTRIBl1 TION LIMITS 3/4.2.4 DNBR MARGIN LIMITING CONDITION FOR OPERATION 3.2.4 The DNBR margin shall be maintained by one of the following methods:

a. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR (when COLSS is in service, and either one or both CEACs are operable); or

b. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by the amount specified in the COLR 13% PATED FPMAL POWER (when COLSS is in service and neither CEAC is operable); or

c. Operating within the region of acceptable operation specified in the COLR cf rigure 3.2 2 using any operable CPC channel (when COLSS is out of service and either one or both CEACs are operable); or d, Operating within the region of acceptable operation specified in the COLR of Figure 3.2 3 using any operable CPC channel (when COLSS is out of service and neither CEAC is operable).

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

ACTION:

a. With the DNBR limit not being maintained as indicated by COLSS calculated core 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or

2. Reduce THERMAL POWER to less than or equal to 20% or 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 DNBR limit not being maintained as indicated by operation outside the region of acceptable operation specified in the COLR " rigure 3.2 2 or 3.2-3 with l COLSS out of service, either:

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 j 3. 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 .

WATERFORD UNIT 3 3/4 2 6 AMENDMENT N0. 32 l

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4.1 The provision 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that the DNBR. as indicated on any OPERABLE DNBR Channel. is within the limit specified in the COLR show^ on c19er^ 3.2 2 or ciguro 3.2 3. 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.

l l

WATERFORD UNIT 3 3/4 2 6a AMENDMENT NO. 32 i l

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FIGURE 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERA 8LE)

WATERFORD - UNIT 3 3/4 2-8 AMENDMENT NO. 12

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COLSS OUT OF SERVICE DNBR LIMIT LINE 2.8 i i i i l ACCEPTABLE l OPERATION 2.7 - -

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i FIGURE 3.2-3 ,

DNBR RGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs INOPERA8LE) 1 WATERFORD - UNIT 3 3/4 2-9 AMENOMENT NO.12

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 C0lf_f1110wingli-its:

a- COLSS OPEP/SLE 0.22 : ASI c 0.27 #0- 7"rP"/1 P0c!EPS 2 70! cf of.TED THEP"/1 P0c!ER 0.27 c AS! c *0.27 for THEP"/1 P0c!EPS : 70% of o/TED THER"/1 P0c!ER b- GOL-SS DF-OF SEPV!CE 'CPC)

~.! c ^SI c *0.22 for THEP"^1 o0c!ERS 2 70% of Pf,TED mEP"/1 P0c!ER 0.22 c ?SI c -0.22 for T G M P0c!EPS : 70! Of o/TED m EP."/1 P0c!ER APPLICABILITY: MODE 1 above 20s of RATED THERMAL POWER.*

ACTION:

With the AXIAL SHAPE INDEX outside the 4ts-above limits specified in the COLR. restore l 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 RE0VIREMENTS 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.

See Special Test Exception 3.10.2.

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WATERFORD UNIT 3 3/4 2 12 AMENDHENT NO. 26

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed. the boron concentration of all 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 f0llowing reactivity conditions specified in the COLR is met: l a- E4ther a Kef' cf 0.9C cr les-se 6 A boron concentration of greater than or equal to 1720 ppm-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 least 1720 ppm boron or its equivalent until Keff is reduced to less than or equal to the value specified in the COLR 04 or the boron concentration is restored to greater than or equal to the value specified in the COLR 1720 ppm, 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 .

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 removed.

WATERFORD - UNIT 3 3/4 9-1

REACTIVITY CONTROL SYSTEMS BASES B0 RATION SYSTEMS (Continued)

The contained water volume limits include allowance for water not available because of discharge line location. Instrument tolerances, and other 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 conditions 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 i

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 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 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 4 l

the RCS boron concentration to detect any changes. The frequencies specified in the COLR Tabic 3.11 through 3.15 provide the operator sufficient time to recognize a decrease in i boron concentration and take appropriate corrective action without loss of SHUTDOWN l MARGIN. More frequent checks are required with more charging pumps in operation due to the higher potential boron dilution rate. l The surveillance requirements specified provide assurance that the startup channel high neutron flux alarms remain OPERABLE and that required valve and electrical lineups i remain in effect. l 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained. (2) the minimum SHUTDOWN MARGIN is WATERFORD - UNIT 3 8 3/4 1-3 AMENDMENT N0.9 I

(

3/4.2 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 2200aF.

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 monitoring of the core power distribution and 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 distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate. Reactor operation at or below this calculated power level assures that the limit specified in the COLR of Figurc 3.21 is not exceeded. l The COLSS calculated core power and the COLSS calculated core power operating limits based on linear 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 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 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 Fxy measurement uncertainty factor of 1.053. an engineering 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 cf 9;urc 3.2 la can 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. i software algorithm modelling, computer processing, rod bow, and core power measurement.

WATERFORD - UNIT 3 B 3/4 2-1 AMENDMENT NO. 12 l

BASES l

The additional uncertainty terms included in the CPC's for transient protection are credited in the limits specified in the COLR Figure 3.2 la since this curve is intended l to monitor the LC0 only during steady state operation.

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WATERFORD - UNIT 3 8 3/4 2-la AMENDMENT NO. 12

-. ._ _ - = - -_ - - -- - . .-

POWER DISTRIBlRION LIMITS BASES 3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting the values of the PLANAR RADIAL PEAKING FACTORS (Fcxy) used in the COLSS and CPCs to values equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (Fmxy) provides assurance that the limits calculated by COLSS and the CPCs remain valid. 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 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 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 Tn The limitations on the AZIMllfHAL POWER TILT are provided to ensure that design safety margins are maintained. The LC0 requires f ac = 0 3! it on the maximum azimuthal tilt during normal steady state power operatiori to be less than or equal to that specified in the COLR. With AZIMUTHAL POWER TILT greater than M- 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-M following a CEA misalignment event (i.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 M. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action time to reduce core power l 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 M l limit.

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 for 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 M 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. 97

POWER DISTRIBUTION LIMITS BASES AZIMUT1%L POWER TILT Tq (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 location is of the form:

Pg /PunW -1+T g cos (e - eg )

q where:

Tg is the peak fractional tilt amplitude at the core periphery 91s the radial normalizing factor e is the azimuthal core location e ois the azimuthal core location of maximum tilt Ptilt untilt is the ratio of the power at a core location in the presence of a tilt to the power at that location with no tilt.

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 demonstrated adequate to maintain an acceptable minimum DNBR throughout all anticipated operational 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 COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the 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 1 DNBR limit. is conservative with respect to the actual core power limit. These penalty factors are determined from the uncertainties 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 of-figure 3.2.2 or Figure-313-3 can be maintained by utilizing l l a predetermined DNBR as a function of AXIAL SHAPE INDEX and by monitoring the CPC trip channels. The above listed uncertainty and penalty factors plus those associated with startup test acceptance criteria are also included in the CPCs which assume a minimum core power of 20% of RATED THERMAL POWER. 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.

WATERFORD UNIT 3 B 3/4 2 3 AMENDHENT 97

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 maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses. The value of 0.05 or less for Keff value specified in the COLR includes a 1% delta k/k conservative allowance for uncertainties. Similarly, the boron concentration value of 1720 ppm or gre'ater specified in the COLR also includes a conservative uncertainty allowance of 50 ppm boron.

3/4.9.2 INSTRUMENTATION The OPERABILITY of 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 OPERABILITY 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 COMMUNICATIONS 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

-- - - .- ... - . . - ~.

ADMINISTRATIVE CONTROLS INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT 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 at least once every 4 years.

6.9.1.10 A survey of major pipelines (6 4 inches) within a 2-mile radius of Waterford 3, which contain explosive or flammable materials and may represent 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. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

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.

The CORE OPERATING LIMITS REPORT, 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 minimua period indicated.

WATERFORD - UNIT 3 '6-20 AMENDMENT N0.68 l

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NPF-38-155 ATTACHMENT C

ML20072B552

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