Text

Amend 50 to License NPF-49,modifying Tech Specs to Remove cycle-specific Operating Limits from Specs & Incorporating Limits in Core Operating Limits Rept,Per Spec 1.42
	ML20043H722
Person / Time
Site:	Millstone
Issue date:	06/13/1990
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20043H723	List: ML20043H722;
References
	NPF-49-A-050 NUDOCS 9006260358
	Download: ML20043H722 (59)
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-c UNITED STATES NUCLEAR REGULATORY COMMISSION g

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l t$RTHEAST NPCLEA,R, ENERGY,C,0MPANY,;E,T, AL; 00gET m. 50-423 ti!LLSTONE NUCLEAR POWER STATIOHn UNIL N,0 y -

AMENDMENT.T0 FACILITY OPERATING LICENSE:

Amendn+nt flo. 50 -

License No. NPF 1.

The Nuclear' Petulatory Commission (the'Comission). has found that:

The app (lications for. amendment by Northeast Nuclear-Energy Company, A.

et al. the licensee) dated February 21 and March 15, 1990',- comply-with the standards and requirements of.the Atomic Energy Act of:1954, as anended (the Act), and the Cermission's rules and regulations tet forth in 10 CFR Chapter I; B.

The facility will operate in ccnformity with the ' application, the l

provisions of the Act, and' the rules :and ' regulations of the Commission; t

C.

There is. reasonable assurance (1) that the activities authorized by.

this"anendment can be conducted without, endangering the, health. and safety of the public, and (ii) that such activities will be conducted in compliar:ce with the Commission's regulations; D.

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

The issuance of this amendment is in accordance with'10 CFR Part 51 I

of the Comission's regulations and all applicable requirements have l

been satisfied.

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9006260359 900613 i

PDR ADOCK 05000423 P

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Accordingly, the. license is amended by changes to the. Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby -

amended to read as follows:

i (2) Technical Specifications-i The Technical Specifications. contained in Appendix A, as' revised' through Amendment No. 50-

, and the Environmental Protection Plan contained.in Appendix B, both of which are attached hereto are i

hereby incorporated in the license. The licensee shall operate.the facility in accordance with the Technical Specifications and the l

Environmental Protection Plan.

i 3.

This license amendment is effective as of:the date of its issuance, to be implemented within 90 days of issuance.

FOR THE NUCLEAR' REGULATORY COMMISSION f

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i oh iT. Stolz, Director Pr ject Directorate I-4 vision of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes ~ to the Technical

. Specifications Date of Issuance: June 13,1990 i,

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ATTACHMENT TO LICENSE AMEN 0 MENT NO.

50 FACILTIY OPERATING LICENSE NO. NPF-49 DOCKET-NO. 50-423-Replace.the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of.. change.

The corresponding overleaf pages are provided to maintain document completeness.

Remove Insert 11 11 iv iv v

v xx xx-1-7 1-7 3/4'1-4 3/4 1-4.

3/4 1 3/4 1-5 3/4.1-14 3/4 1-14 3/4 1-15 3/4 1-15 3/4 1-20 3/4 1-20 3/4~1-21

-3/4 1-21 3/4 1-22 3/4 1-22 3/4 1-23 3/4 1-23 3/4 2-1 3/4 7.-1 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4.2-4 3/4 2-5.

3/4 2-5 3/4 2-6 3/4 2 3/4 2-7 3/4 2-7 3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 3/4 2-10

.3/4 2-10 3/4 2-11 3/4-2-11 3/4 2-13 3/4 2-13 3/4 2-14 3/4 2-14 3/4 2-15 3/4 2-15 3/4 2-18 3/4 2-18 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 3/4 9-1 3/4 9-1 B 3/4 1 B 3/4 1-2 B 3/4 2-1 B 3/4 2-1 B 3/4 2-2 B 3/4 2-2 B 3/4 2-6 B 3/4 2-6 6-21 6-21 6-21a 6-21a 6-22 6-22

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INDEX DEFINITIONS r

SECTION PAGE 1.0 DEFINITIONS 1.1 ACTION.......................................................

'l-1 1.2 ACTUATION LOGIC TEST.........................................

1-1

1. 3 ANALOG CHANNEL OPERATIONAL TEST..................,

1-1 1.4 AXIAL FLUX DIFFERENCE........................................

1-1 1.5 CHANNEL CALIBRATION..........................................

1-1

1. 6 CHANNEL CHECK................................................

1-1 1..

CONTAINMENT INTEGRITY........................................

1-2 1.8 CONTROLLED LEAKAGE...........................................

1-2 1.9 CORE ALTERATIONS...............................................

1-2

'I.10 DOSE EQUIVALENT I-131........................................

1-2 l

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

1-2 1.12 ENCLOSURE BUILDING' INTEGRITY.......................,:.......=.

'l-3 1.13 ENGINEERED SAFETY FEATURES RESPONSETIME.....................

1-3 1.14 FIRE DETECTOR OPERATIONAL TEST....................

1-3 1.15 FREQUENCY N0TATION...........................................

1-3 1.16 IDENTIFIED LEAKAGE............................................

1-3 1.17 MASTER RELAY TEST............................................

1-3

'1.18 MEMBER (S) 0F THE PUBLIC......................................

1-4 1.19 OPERABLE - OPERABILITY........................................

1-4 1.20 OPERATIONAL MODE - M0DE..........................'............

1-4 i

1.21 PHYSICS TESTS................................................-

1-4 1.22 PRESSURE BOUNDARY LEAKAGE....................................

1-4 1.23 P U R G E - P U R G I NG..............................................1-4 1.24= QUADRANT POWER TILT RATI0....................................

1-5 1.25 RADI0 ACTIVE WASTE TREATMENT SYSTEMS..........................

1-5 1.26 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE-CALCULATION MANUAL-(REM 00CM).................................

1-5 1.27 RATEDLTHERMAL P0WER..........................................

1-5 1.28 REACTOR TRIP SYSTEM RESPONSE TIME............................

1-5 1.29 REPORTABLE EVEST.............................................

1-5 1.30 SHUTDOWN MARGIN..............................................

1-5 1.31. SITE B0VNDARY................................................

1 MILLSTONE - UNIT 3 i

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I INDEX

]

0EFINITIONS~

SECTION g

i 1.32 SLAVE RELAY TEST.............'................................

1-6 i

1.33 SOURCE CHECK.................................................

16 1.34' STAGGERED TEST BASIS.........................................-

1-6 1.35 THERMAL P0WER.................................................- 6-1.36 TRIP ACTUATING DEVICE OPERATIONAL TEST.......................

1 1.37 UNIDENTIFIED' LEAKAGE.........................................

1-6 1.38 UNRESTRICTED AREA.............=..............................

1-6.

1.39.. VENTING..................................................~....

1-7 1.40 -SPENT FUEL P00L1 STORAGE. PATTERNS.............................

1-7 1.41' SPENT FUEL POOL STORAGE PATTERNS.............................

1-7 1.42 -CORE OPERATING' LIMITS REP 0RT................................

1-7 TABLE l~.1 FREQUENCY-H0TATION;.....................................

1-8 TABLE 1.2 OPERATIONAL M00ES.......................................

1-9 1

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- MILLSTONE - UNIT 3 ii AmendmentNo.}I,50

INDEX-

. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS-i 1

SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 -REACTOR C0RE................................................ 1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE............................-

2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION.,

2-2 FIGURE 2.1-2' REACTOR CORE SAFETY LIMIT - THREE LOOPS IN OPERATION.

2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS-t 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0lNTS...............

2-4 TABLE 2.2-l' REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS....

2-5 i

BASES 1

i 1

'SECTION

-PAGE 12. 1 SAFETY LIMITS 2.1.1 REACTOR C0RE................................................

B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE.............................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS..............'.B 2-3 i

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LMILLSTONE - UNIT 3 iii

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS q

SECTION P.bE a

3/4.0 APPLICABILITY..........................."....................

~3/4-0 l' 3/4.1-REACTIVITY-CONTROL SYSTEMS t

3/4.1.1 BORATION CONTROL j

Shutdown Margin - T,yg Greater Than 200'F................

3/4 1-1.

Shutdown Margin - T,yg Less Than or Equal to 200*F.......

3/4 1 3 Moderator Temperature Coefficient........................

3/4 1-4 Minimum Temperature for Criticality......................

3/4 1-6 3/4.1.2 BORATION SYSTEMS-Flow Path -

Shutdown.....................................

3/4'l 7 Flow Paths - Operating...................................

3/4 1 8-Charging Pump - Shutdown.................................

3/4'l 9 Charging Pumps - Operating................................

3/4 1-10 Borated heter Source'- Shutdown..........................

3/4'1 -

Borated Water Sources - Operating........................-

3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.............................................

3/4 1 14 TABLE'3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R00...................

3/4 1 M Position Indication Systems - Operating..................

3/4 1-17

. Position Indication System - Shutdown....................

3/4l1-18 Rod Drop Time.............................................

3/4:1-19 Shutdown Rod Insertion Limit.............................

3/4 1-20 Control Rod Insertion Limits.............................

3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE....................................

3/4 2-1 Four Loops 0perating.....................................

3/4 2-1 L

MILLSTONE - UNIT 3 iv Amendment No. 50

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BDIX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENIS-SECTION g

Three Loops Operating....................................

3/4/2-4 3/4.2.2

. HEAT FLUX HOT CHANNEL FACTOR - F (Z).....................

3/4 2-7

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Four Loops 0perating.....................................

3/4 2-7 Three Loops Operating....................................

3/4 2 11 3/4.2.3>

RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT0R...................................................

-3/4 2-15 i

Four Loops Operating.....................................

3/4L2-15.

Three loops 0perating....................................

3/4 2-18 3/4.2.4 QUADRANT POWER TILT RATI0................................

3/4.2-20 3/4.2.5 DNB PARAMETERS...........................................

3/4 2-23:

TABLE 3.2-1 DNB PARAMETERS........................................

3/4 2-24 1

3/4.3 -INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......T...............

3/4=3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM. INSTRUMENTATION.................... !3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSEETIMES.....

3/4 3-8

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TABLE 4.3-1 REACTOR-TRIP SYSTEM INSTRUMENTATION SURVE REQUIREMENTS................................ILLANCE 3/4 3-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM i

INSTRUMENTATION..........................................

3/4 3-15 i

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

3/4 3-17 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

-INSTRUMENTATION TRIP SETP0lNTS...........................

3/4 3-26 i

i MILLSTONE - UNIT 3 v

Amendment No. 50 l

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INDEX-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE ReiOUIREMENTS f

S_,ECTION '

PAGE TABLE 3.3-5 ENGINEERED' SAFETY FEATURES RESPONSE TIMES..............

3/4 3-32 TABLE 4.3-2 ' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-36 3/4.3.3 MONITORING-INSTRUMENTATION Radiation Monitoring for Plant Operations................

3/4 3-42 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.........-............................. -

3/4-3 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS-SURVEILLANCE REQUIREMENTS.....................

3/4'3-45 Movable'Incore Detectors.................................

3/4 3-46 Setsmic Instrumentation.............................-......

3/4 3-47 TABLE 3.3-7 SEISMIC' MONITORING INSTRUMENTATION.....................

3/4'3-48 TABLE:4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE-REQUIREMENTS...............................,.............

3/4 3 Meteorological Instrumentation...........................

3/4 3-50 L

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...........'..

~3/4 3-51 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE o

REQUIREMENTS.............................................

3/4-3-52 Remote Shutdown Instrumentation..........................

3/4 3-53 g

TABLE 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION.......................

-3/4 3-54 L

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION

. 3/4 3-58 SURVEILLANCE-REQUIREMENTS................................

Accident Monito' ring-Instrumentation......................

3/4'3-59 TABLE 3.3-10 ACCIDENT MONITORING' INSTRUMENTATION..................

3/4 3-60

-TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION' SURVEILLANCE REQUIREMENTS.................................:............-

3/4'3 Fire Detection Instrumentation............................

3/4 3-64 TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION.......................

3/4 3-65 Loose-Part Detection System..............................

3/4 3-68 Radioactive Liquid Effluent Monitoring Instrumentation...

3/4'3-69 l

TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-70 i

TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-74

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MILLSTONE - UNIT 3 vi

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INDEX i

i ADMINISTRATIVE CONTROLS i

i SECTION E.Mi 6.8 PROCEDURES AND PR0 GRAMS..........................................

6-16 i

6.9 REPORTING-REQUIREMENTS..........................................

6-19 I

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

. 6 - l'9 i

Startup Report....................................._............-

6-19 An n u al Re po r t s................................................. -

6-19 Annual Radiological-Environmental Operating Report.............

6-20 Semiannual Radioactive Effl uent Release Report.................

6-21}

i Monthly Operating Reports......................................

.6 21 Core Operating Limits Report...................................

~6-21 6.9.2 SPECIAL REP 0RTS................................................

6 22 6.10 RECORD RETENTION.......................................-.........

6-22 6.11 RADIATION PROTECTION PR0 GRAM....................................

6-23

=-1 I

6.12 HIGH RADIATION AREA.................................'............

6-23 6.13 RADIOLOG:: CAL EFFLUENT MONITORING'AND OFFSITE DOSE CALCULAT::0N MANUAL (REM 0DCM)....................................

6-25 6.14' RADIOACTIVE WASTE TREATMENT.....................................

6-25 MILLSTONE - UNIT 3 xx Amendment No. 50

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ADMINISTRATIVE CONTROLS i

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AffJEH PAE t-l l-i 6.5.2 SITE OPERATIONS REVIEW COMITTEE (S0RC)-

Function.................................................... 69 Composition................................................. 6-9 Alternates.................................................. 6-9 Meetiisg Frequency........................................... 69 6-10 Quorum......................................................

4 Re s pon s i b il i t i e s............~................................ 6 - 10 i

. Authority................................................... 6 10 Records..................................................... 6 10

'6.5.3 NUCLEAR REVIEW BOARD (NRB)

Qu al i f i c at i on s.............................................. 6-!!

Composition................................................. 6,

Consultants.................................................. 6-11.

Neeting Frequency'...........................................

6-11.

Quorum...................................................... 6-11 Review...................................................... 16 12 Audits...................................................... 6-12 Authority................................................... 6-12a i

Records..................................................... 6-13 6.5.4 SITE NUCLEAR REVIEW BOARD (SNRB)

Qualifications.............................................. 6-13 l

Composition................................................. 6 13 o

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Con s ul t an t s................................................. 6 -13 a.

Meeting Frequency........................................... 6-13a Quorum...................................................... 6-14 Review................................................'...... 4-14 Audits..................................................... 6-14 Authority................................................... 6-15 ~

j Records..................................................... 5 15 6.6 REPORTABLE EVENT ACTION....................................... 6-15 6.7' SAFETY LIMIT VIOLATION........................................ 6.

MILLSTONE - UNIT 3 xix Amendment No. 26 l

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i DEFINITIONS VENTING 1.39 VENTING shall be the controlled process of discharging air or gas' from a confinement to maintain temperature, pressure, humidity, concentration,: or

-other operating condition, in such a manner that replacement air or gas is not provided or required.during VENTING.

Vent, used in system names, does not imply a VENTING process.

SPENT FUEL P00! STORAGE PATTERNS:

1.40 Region I. spent fuel racks contain a cell blocking device in every 4th location for criticality control.

This 4th location will be referred to as-the blocked location.- A STORAGE PATTERN refers ' to the blocked location. and-all -adjacent and diagonal Region I cell = locations surrounding the blocked location. ' Boundary configuration between Region I-and Region 11 must have cell blockers positioned in the outermost row of-the Region I perimeter, as shown in Figure 3.9-2.

{

i 1.41 Region !! contains no cell blockers.

CORE OPERATING LIMITS REPORT (COLR) 1.42 The CORE OPERATING LINITS REPORT that provides core operating limits for(COLR) is the unit-specific document the current operating reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.6.

Unit Operation within these operating limits is addressed in individual specifications.

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j MILLSTONE - UNIT 3 1-7 Amendment No. g 50

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' TABLE 1.1-i j

FREQUENCY NOTATION, i

NOTAT10N' FREQUENCY l;

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , j

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .-

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W.

_At 1 east once per 7 days.

M At least once per 31 days.

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Q At least once per 92 days.

SA

-At least once per.184 days..

R'

_At least once per 18 months..

S/U Prior to each reactor startup.

N. A.

Not applicable.

P Completed prior to each release.

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. MILLSTONE'- UNIT 3 1-8 n

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i Riatt!v!TV CONTROL SYSTEM 5 5HUTDOWN MARGIN T

LES5 TNAH OR EQUAL TO 200'F LIMITING CONDITJON FOR OPERATION 3.1.1.2 The SHUTDOW MAP. GIN shall be greater than or egaal to 1.6% ak/k.

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APPLICAf1LITY:

MODE 5.

ACTION:

With the $HUTDOWN MARG]N less than 1.6% Ak/k, immediately initiate and continue beration at greater than or equal to 33 ppe of a solution containing greater than or equal to $300 ppm boron or equivalent until the required SNUTDOWN MARGIN is restored.

SURVE!LLAN;E RE0VIREMENTS 4.1.1.2 The SHUT 00mh MARGIN shall be determined to be greater than or equal to 1.6% at/k:

Within I hou'r af ter detection of an inoperable control rod (s) and at a.

least once per'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the i

SHUTDOWh MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.

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)

Control rod position.

3)

Reactor Coolant System everage temperature, 4)

Fuel burnup based on gross thermal energy generation.

5)

Xenon concentration, and 6)

Samarium concentration.

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MILLSTONE

UNIT 3 3/4 1-3 Il l i i II I

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L REACTIVITY CONTROL SYSTEMS M

MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR 6PERATION 3.1.1.3 The moderator tem>erature coefficientL(MTC) shall be within the i

limits specified in the C0tE OPERATING LIMITS REP 0 upper limit shall be less positive than +0.5 x 10'gTS (COLR)..The maximum n'

Ak/k/*F for all the ' rods t

~ withdrawn, beLinning of cycle life (BOL), condition for power levels up to 70% RATED THE W L POWER with a linear ramp to 0 Ak/k/'F-at 100% RATED I

THERMAL POWER.

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.1 APPLICABILITY: BOL - MODES 1-and 2* only**.

End of Cycle life-(EOL)L Limit - MODES 1, 2, and.3 only**..

ACTION:

a.-

With the MTC more positive than the BOL.limiti of Specification 3.1.1.3 above, operation in MODES 1 and 2 may proceed provided:=

l 1.

Control rod withdrawal = limits are established and' maintained sufficient to: restore the MTC to less positive than thecabove

. limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within:the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .-These withdrawal limits shall be in addition to the insertion.11mits' of Specification 3.1.3.6; 1

l 2.

The control rods'are maintained within'the withdrawal' limits established above until:a subsequent calculation verifies that the MTC has:been restored to within its limit for the all rods withdrawn condition; and 3.

A Special Report is prepared and submitted'to the Commiss' ion, pursuant to Specification 6.9.2, within 10' days, describing the

- value of the measured MTC,. the interim control rod withdrawal limits, and the predicted average' core burnup necessary for-e restoring the positive MTC to within its. limit.for the all rods l

withdrawn condition.

b.-

With the MTC more negative than the EOL limit specified'in'the COLR, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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With K,ff greater than or equal to 1.

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- See Special Test Exceptions Specification 3.10.3.

'l MILLSTONE - UNIT 3 3/41-4 AmendmentNo.[,p.I,50

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REACTIVITY CONTROL SYSTEMS i

SU.RVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:

The MTC shall be measured and compared to the BOL limit of Specifi-

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a.

cation 3.1.1.3, above, prior to initial operation above 5% of

-3 RATED THERMAL POWER, after each fuel loading; and

_1 b.

The MTC shall be measured at any THERMAL POWER and compared to the 300 ppe surveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.

In the event this comparison indicates the MTC is more negative than the T

300 ppa surveillance limit specified in the COLR, the MTC shall be remeasured, and compared to the E0L MTC limit specified in the

(

COLR, at least once per 14 EFPD during the remainder of the fuel cycle.

K MILLSTONE - UNIT 3 3/4 1-5 AmendmentNo.JF,50

REACTIVITY CONTROL SYSTEMS j

MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4' The Reactor Coolant System lowest' operating. loop temperature (T,y shall be' greater than or equal to 551'F.

' APPLICABILITY:- MODES 1 and 2* **i P

ACTION:

With a Reactor Coolant System operating 1000 temperature'(T,yg) less than 551*F, restore T,yg to within its limit within 15 minutes or be in NOT STANDBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.1. I' 4 be greater than or equal to 551'F:The Reactor Coolant System temperature (T'#8 Within 15 minutes prior to achieving reactor criticality, and a.

i b.

At least once per 30 minutes when the reactor is critical and the Reactor' Coolant System T,yg is less than 561'F with the T

-T Deviation Alarm not reset.

,yg ref l

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With K,ff greater than or equal to 1.

P

- See Special Test Exceptions specification 3.10.3.

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MILLSTONE - UNIT 3 3/4 1-6

REACTIVITY CONTROL SYSTEMS'-

,o SURVEILLANCE REQUIREMENTS 4.1.2,6! Each borated water source shall be demonstrated OPERABLE:

a.

At least 'once per'7 days by:

1).

Verifying the boron concentration-in the water,'-

2)

Verifying the contained borated water volume of= the water source, and a

H3)

Verifying the Boric Acid Transfer Pump Room temperature and the boric acid storage tank solution 1 temperature, b.

' At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature.

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'h MILLSTONE - UNIT 3 3/4 1-13

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 -MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION

'l 3.1.3.1 All full-length shutdown and controlf rods shall. be OPERABLE and-positioned within 112 steps-(indicated position) of their. group step counter demand position.

APPLICABILITY: ; MODES 1* and 2*,

El108:

-a.

WithLone or more full-length rods inoperable due to being 1

immovable as'a result of excessive-friction or mechanical-.

interference or known to be untrippable, determine thatLthe SHUTDOWN MARGIN: requirement of Specification 3.1.1.1 isisatisfied-within:1 hour and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .t b.

With one full-length-rod trippable butlinoperable due to causes other than: addressed by ACTION a., above,1or misaligned from its i

group step counter demand height by more than il2 steps (indicated

>osition), POWER 0PERATION may continue provided that within 1-iour:

1.

The rod-is restored to OPERABLE status withintthe above

. alignment requirements, or-2.

The rod is declared inoperable-and the remainder of the rods-:

i

.in the group with the. inoperable rod are aligned to within-l 12 steps of the inoperable rod.while maintaining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER level shall be restricted pursuant to-Specification 3.1.3.6 during subsequent operation, or-

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The rod is declared inoperable.and the SHUTDOWN MARGIN l

requirement of Specification 3.1.1.1.is satisfied.

POWER 1

OPERATION may then continue provided that:

a). : A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 ' days; this reevaluation shall.

confirm that the previously analyzed-results of these L

accidents remain valid for'the duration of operation under these conditions; 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 ;

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

L MILLSTONE - UNIT 3 3/4 1-14 Amendment No. 50

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN'THE EVENT OF AN INOPERABLE FULL-LENGTH ~ ROD Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment 1

Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System. Pipe Ruptures (Loss-of-C,olant Accident)

Major Secondary Coolant System. Pipe-Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)

=

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MILLSTONE - UNIT 3 3/4 1-16

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- REACTIVITY CONTROL' SYSTEMS LIMITING CONDITION FOR OPERATION 1

. ACTION (Continued)'

l c)'-

A power distribution' map 'is obta ned from the movable.

incore detectors and'F (Z)'and F a

within their limits.wi9hin 72 ho Ys;re verifled totbe:

and d)

With four loops operating,'the THERMAli POWER!1evel is reduced to less than or equal. to 75% of RATED THERMAL' POWER within the next hour and within the following 4-hours the High Neutron Flux Trip Setpoint-it. reduced.to.

less-than or equal; to 85% of-RATED THERMAL POWER,?or, '

i e)

With-three loops operating,L the THERMAL = POWER level is-reduced to less than or, equal to 50% of. RATED THERMAL

POWER'within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the Neutron Flux High Trip Setpoint is reduced:to less than or equal to 60% of RATED THERMAL POWER.

c.

'With more than one rod trippable butLinoperablo.due= to causes other than addressed by ACTION a..above, POWER OPERATION may continue provided that:

1.

Within I hour, the remainder ofIhe ro'ds in the bank (s) with the inoperable rods are aligned to within 12 steps of the inoperable rods while maintaining the' rod sequence and insertion-limits of Specification 3.1.3'.6.~ - The THERMAL POWER-level shall be restricted-pursuant'to Specification;3.1.3.6-during subsequent operation, and-2.

The inoperable rods are resto' red to'0PERABLE' status within 72 j

hours.

d.

With more than one rod' misaligned from its group ste:p counter demand height by more than 12 steps-(indicated position), be-in HOT-STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS-4.1.3.1.1-The position of each full-length' rod shall' be. determined to be within the' group demand limit by verifying the individual rod. positions at:

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months exce)t during time intervals.when the rod position deviation monitor is inopera)1e, then verify the group positions at least L

once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ..

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined:to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

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. MILLSTONE'- UNIT 3 3/4 1-15 Amendment NO 50 i

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' REACTIVITY CONTROL SYSTEMS

. ROD DROP TIME LIMITING CONDITION FOR OPERATION i

3.1. 3. 4 The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall beiless than or equal to 2.2 seconds from beginning of decay of. stationary gripper coil voltage to dashpot entry with:

T,yg greater than or equal to 551'F, and i

a.-

i 1b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

t

' ACTION:

With the drop time of any full-length rod determined to exceed a.

the-above limit, restore the rod drop time to within'the above limit l

prior to proceeding to MODE 1 or 2.-

l b.

With the. rod drop times within limits but determined with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or-equal to 65% of RATED THERMAL POWER with the reactor coolant stop valves in.the nonoperating loop closed.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated'through 1

measurement prior to reactor criticality:

For all rods following each removal of the reactor < vessel head -

a.

b.

For specifically affected individual rods following any maintenance on or modification _to the Control Rod Drive System which could-affect the drop time of those specific rods, and c.-

At least once per 18 months.

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MILLSTONE - UNIT 3 3/4 1-19 1

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t REACTIVITY CONTROL SYSTEMS'

' SHUTDOWN R0D INSERTION'tIMIT i

LIMITING CONDITION'FOR OPERATION 3.1.3.5 All. shutd'own rods.shall be limited in physical insertion as specified in the core operati_ng limits. report (COLR).-

APPLICABILITY: MODES 1* a'nd 2* **.,

l L

E1108:'

C With a maximum of one shutdown rod inserted beyond the insertion limits-j specified in the COLR except-for surveillance testing pursuant.to j

-Specification 4.1.3.1.2, within I hour either:

i a..

Restore.the: rod to within the~ limit specifled in the COLR,.:or.

j

b..

Declare the rod to be inoperable'and. apply Specification 3.1.3.1.

'I SURVEILLANCE REQUIREMENTS' I

~

4.1.3.5 Each shutdown rod shall be determined to betwithin the insertion-limits specified in the COLR:.

a.

Within 15 minutes: prior to: withdrawal of any rods-in~ Control Bank-A, B, C, or 0.during an approach to reactor. criticality,-and 1

b.

At least once per'12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-thereafter.

ll

See Special Test Exceptions' Specifications 3.10.2.and 3.10.3.:

[

- **With K,7f greater.than or equal to 1.

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MILLSTONE - UNIT 3 3/4 1-20 Amendment No. 50

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3-kEACTIVITY CONTROL' SYSTEMS CONTROL R00' INSERTION LIMITS 1

LIMITING CONDIT10N FOR OPERATION 3.1.3.6 The control banks shall-be limited in physical insertion as i

specified in the core operating limits report (COLR).

j j

l APPLICABILITY: _ MODES _1* and 2* **.

j EllQtli With;the control banks-inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1=.2-

-Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,' or_

l a.

l b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to' that

. fraction-of RATED-THERMAL POWER which is allowed by the bank:posi-i tion using the insertion limits _specified in the COLR, or; c.

Be in at least HOTLSTANOBY within-6 hours; SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be deter 5ined to be:within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except~ during time intervals when the rod insertion limit monitor is inoperable, then1 verify the-individual. rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .-

l!

See Special Test Exceptions Specifications 3.10.' 2 and 3.10.3.

- With K,ff greater than or equal to 1.

r!

MILLSTONE - UNIT 3 3/4 1-21

.Ameindnient No. 50

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t MILLSTONE.- UNIT 3 3/4 1-22 Amendment No. 50

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F MILLSTONE - UNIT 3

_3/4 }.23 Amendment No. 50

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3/4.2 POWER DISTRIBUTION LIMITS I

3/4.2.1 AXIAL FLUX DIFFERENCE FOUR LOOPS C M ATING j

LIMITING CONDITION FOR OPERATION l

3.2.1.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the target band (flux difference units) about the target flux difference.

The target band is provided in the core operating limits report (COLR).

The indicated AFD may deviate outside the required target band at greater than or equal to 50% but less than 90% of RATED THERMAL POW:R provided the indicated i

AFD is within the Acceptable Operation Limits specified in the COLR and the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the required target band at greater than 1

15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty J

deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABillTY: MODE 1, above 15% of RATED THERMAL POWER.*

ACTION:

a.

With the indicated AFD outside of the required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes either:-

1.

Restore the indicated AFD to within the tarCet band limits, or 2.

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

b.

With the indicated AFD outside of the required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time daMng the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits specified in the COLR and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduco:

1.

THERMAL-POWER to less than 50% of RATED THERMAL POWER within 30 minutes, and 2.

The Power Range Neutron Flux - High** Setpoints to less than or equal to 55% cf RATED THERMAL POWl:R within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specification 3.10.2.

- Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits specified in the COLR.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the required target band during testing without penalty deviation, i

MILLSTONE - UNIT 3 3/4 2 1 Amendment No. 50

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POWER DISTRIRUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

With the indicated AFD outside of the required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the required target band.

SURVEILLANCE REQUIREMENTS 4.2.1.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status, b.

Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.1.1.2 The indicated AFD Shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AfD to be outside the target band.

Penalty deviation outside of the required target band shall be accumulated on a time basis of:

a.

One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One half minute penalty deviation for each I minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50%

of RATED THERMAL POWER.

4.2.1.1.3 The target flux difference of each OPERABLE excore channel shall be.

determined by measurement at least once per g2 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

4.2.1.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.1.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi-sions of Specification 4.0.4 are not applicable.

MILLSTONE - UNIT 3 3/4 2-2 Amendment No. 50 l

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- MILLSTONE - UNIT 3 3/42-3 Amendment No. 50 y

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. POWER DISTRIBUTION LIMITS l

AXIAL FLUX DIFFERENCE I

THREE LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2.1.2 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the target band (flux difference units) about the target flux difference.

The target band is provided in the core operating limits report (COLR).

l The indicated AFD may deviate outside the required target band at greater than or equal to 32% but less than 65% of RATED THERMAL POWER provided the indicated AFD is within the Acceptable Operation Limits specified in the COLR and the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l The indicated AFD may deviate outside the required target band at greater than 15% but less than 32% of RATED TEIRMAL POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER.*

ACTION:

I a.

With the indicated AFD outside of the required target band and with l

THERMAL POWER greater than or equal to 65% of RATED THERMAL POWER, l

within 15 minutes either:

1.

Restore the indicated AFD to within the target band limits, or 2.

Reduce THERMAL POWER to less than 65% of RATED THERMAL POWER.

b.

With the indicated AFD outside of the required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits specified in the l

COLR and with THERMAL POWER less than 65% but equal to or greater than 32% of RATED THERMAL POWER, reduce:

l.

THERMAL POWER to less than 32% of RATED THERMAL POWER within l

30 minutes, and 2.

The Power Range Neutron Flux - High** Setpoints to less than or equal to 37% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specification 3.10.2.

- Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits specified in the COLR.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the required target band during testing without penalty deviation.

MILLSTONE - UNIT 3 3/4 2-4 Amendment No. 50 d

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, POWER DISTRIBUTION LIMITS LIMITING C anITION FOR OPERATION ACTION (Ccntinued) c.

With the indicated AFD outside of the required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 32% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or reater than 32% of HATED THERMAL POWER until the indicated AFD is wit in the required target band.

l SURVEILLANCE REQUIREMENTS 4.2.1.2.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each 0"ERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status, b.

Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable.

The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.1.2.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excoro channels are indicating the AFD to be outside the target band.

Penalty deviation ou'; side of the required target band shall be accumulated on a time basis or:

a.

One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above

.~

32% of RATED THERMAL POWER, and b.

One-half minute penalty deviation for each I minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 32%

of RATED THERMAL POWER.

4.2.1.2.3 The target flux difference of each OPERABLE excore channel shall be -

determined by measurement at least once per g2 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

4.2.1.2.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.2.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi-sions of Specification 4.0.4 are not applicable.

MILLSTONE - UNIT 3 3/4 2-5 Amendment No. 50 1__________--.

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i MILLSTONE - UNIT 3 3/42-6 Amendment No. 50-

EQWER DISTRiauTION LIMITS 3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fp FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION 1

3.2.2.1 F (Z) shall be limited by the following relationships:

g F(Z)sFl TPK (Z)forP>0.5 g

P RTP F(I)1F K(Z)forP50.5 q

O 0.5 RTP F

the F limit at RATED THERMAL POWER (RTP) provided in the c0re=operati0glimitsreport(COLR).

Where:

P = THERMAL POWER

, and RATED THERMAL POWER i

K(Z) = the normalized F (Z) as a function of core height specified in the COLR. n APPLICABILITY: MODE 1.

ACTION:

WithF(Z)exceedingitslimit:

q a.

Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the 9

limit within 15 minutes and similarly reduce the Power Range Neutron Flux High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Set-points have been reduced at least 1% for each 1% F (Z) exceeds the limit, and 0

b.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit re-quired by ACTION a., above; THERMAL POWER may then be increased provided F (Z) is demonstrated through incore mapping to be 0

within its 11mit.

MILLSTONE - UNIT 3 3/4 2 7 Amendment No. 50

=. POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS I

4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 F,y shall be evaluated to determine if F (Z) is within its limit by:

g a.

Using the movable incore detectors to obtain a power distribution map i

at any THERMAL POWER greater than 5% of RATED THERMAL POWER, i

b.

Increasing the measured F,y component of the power distribution map 3y 3% to account for manufacturing tolerances and further increasing the value by 5% to acew nt for measurement uncertainties, i

C Comparing the F F

1 Specification 4N. computed (bMe)obtainedin c.

2.1.2b., a to:

1)

The F,y limits for RATED THERMAL POWER (FRTP) for the appropriate x

measured ccre planes given in Specification 4.2.2.1.2e. and f.,

below, and 2)

The relationship:

F,f=F P(3,pp 3,p)),

l Where F is the limit for fractional THERMAL POWER operation RTP exressedasafunctionofF*Tn. the M LR, and P is the fraction PF is the power factor mu tiplier for F*kWER at which F,y specified of RATED THERMAL was measured.

d.

Remeasuring F,y according to the following schedule:

1)

When F,f is greater than the F limit for the appropriate RTP x

l measured core plane but less than the F relationship, C additionalpoppdistrigutionmapsshalFbetakenandF*Y y

compared to Fxy and F,y either:

a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMA!.

POWER or greater, the THERMAL POWER at which F, was last determined, or i

b)

At least once per 31 Effective Full Power Days (EFPD),

whichever occurs first.

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MILLSTONE - UNIT 3 3/4 2-8 Amendment No. 50

POWER DISTRIBUTION llMITS EgylillANCE REQUIREMENTS (Continued) 2)

When the F f is less than or equal to the F P

x limit for the eppropriate measured core plane, additional power distribution maps shall be.taken and F f compared to F andFhy RTP at least x

x once per 31 EFPD.

The F,y limits for RATED THERMAL POWER (FRTP) shall be provided for e.

all core planes. containing Bank "D" control rods and all unrodded core planes in the COLR per Specification 6.9.1.6; f.

The F limits of Specification 4.2.2.1.2e., above, are not applica-xy ble in the following core planes regies as measured in percent of core height from the bottom of the fue12 1)

Lower core region from 0 to 15%, inclusive, i

2)

Upper core region from 85 to 100%, inclusive, i

3)

Within 12% of core height (12,88 inches) of grid plane regions.

The total core height eliminated from the. grid plane regions located between 15% and 85% of core height shall not exceed 20%

of total core height (144 inches).

4)

Core plane regions within 12% of core height li 2.88 inches) about the bank demand position of the Bank "D" control rods, g.

With F exceeding F the effects of F on F (Z) shall be x

x xy q

evaluated to. determine if F (Z) is within its limits.

9 4.2.2.1.3 When F (Z) is measured for other than F determinations, an g

xy overall measured F (Z) shall be obtained from a power distribution map and n

increased by 3% to account for manufacturing tolerances and further increased l

by 5% to account for measurement uncertainty.

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.3/4 2-9 Amendmentlio./,50

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MILLSTONE - UNIT 3 3/42 Amendment No. 50 j

POWER DISTRIBUTION LIMITS HEATFLUXHOTCHANNELFACTOR-'Fg THREE LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2.2.2 F (Z) shall be limited by the following relationships:

q F(Z)sFlTP [K(Z))forP>0.325 g

P F (Z) s (F TP) [K(Z)] for P s 0.325 g

~

0.325 RTP F

The F c0re =perati0g limits report (COLR). limit at RATED THERMAL POWER (R o

Where:

P = THERMAL POWER

, and RATED THERMAL POWER KtZ) = the normalized F (Z) as a function of core height specified in the COLR. g 1

APPLICABILITY: MODE 1.

ACTION:

With F (Z) exceeding its limit:

q Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the a.

q limit within 15 minutes and similarly reduce the Power Range Neutron Flux High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Set-

'3 points have been reduced at least 1% for each 1% F (Z) exceeds q

the limit. The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.

b.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit re-quired by ACTION a., above; THERMAL POWER may then be increased provided F (Z) is demonstrated through incore mapping to be g

within its limit, s

MILLSTONE - UNIT 3 3/4 2-11 Amendment No. 50 l

a

i PdWtt D15TRIBitTION LIMITS s0RVffLLANtf RfoUfREMENTs 1

4.2.2.2.1 The ' provisions of Specification 4.0.4 are not applicable.

4.2.t.t.1 F,y shall.be evaluated to determine if F (Z) is within its limit by:

g Using the novable incere detectors to obtain a power distribution map a.

l at any THERML POWER greater than 85 of MTED THERML POWER, b.

Increasing the esasured F consonent of the power distribution map by

(

3% to account for manufac%riri tolerances and further increasing the value by 5% to account for measurement uncertainties, C

Comparing the F,y computed (F,y)obtainedinSpecification4.2.2.t.tb, i

c.

[

above to The F limits for 65% of MTED THERML POWER 0.65 RTP) for the 1)

Specification 4.2.2.2.te and f., below, planes (F"I approPiate seasured core given in and 2)

The relationship:

F,f=F,045RTP[1+M,y(0.65P)],

g l 'is the limit for fractional THERML POWER operation.

j Where F expresseIasafunctionofF.65RTP,N,y is the F,y multiplie 0

g and P is the fraction of M ED THERML POWER at which F,ywas measured.

1 d.

Remeasuring F,y according to the following schedules C

1)

When F,y isgreater'thantheFh65RTP 1 mit for the appropriate measured core plane but less than the Fxy relationship, additional power distribution maps shall be taken and Fj o 65 RTP compared to F and F either:

g a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of MTED THERML POWER or greater, the THERML P0WER at which Fj was last dete,.ined, o, l

b)

At least once per 31 Effective Full Power Days (EFPD),

whichever occurs first, MILLSTONE - UNIT 3 3/4212 Amendment No. 46

=.

.2

.... ~.

POWER DISTRIBUTION LIMITS-

. SURVEILLANCE REQUIREMENTS iContinued) 2)

When the F C is less than or equal to the F.65 RTP limit for the 0

appropriatF easured core plane, additiona1*#ower distribution gshallbetakenandFfcomparedtoF 65 RTP and F at y

once per 31 EFPD.

The F, limits for 65% of RATED THERMAL POWER (Fh65 RTP) and e.

multipfier(M,y)shallbeprovidedforallcoreplanes xy p

containing Bank "D" control rods and all unrodded core planes in the COLR,

f.

The F,y limits of Specification 4.2.2.2.2e., above, are not applicable in the following core planes regions as measured in percent of core height from the bottom of the fuel:

1)

Lower core region from 0 to 15%, inclusive, 2)

Upper core region from 85 to 100%, inclusive, 3)

Within 12% of core height (12.88 inches) of grid plane regions.

The total core height eliminated from the grid plane regions located between 15% and 85% of core height shall not exceed' 20% of total core height (144 inches).

4)

Core plane regions within i2% of core height ( 2.88 inches) about the bank demand position'of the Bank "0" control rods.

C l

g.

With F exceeding F the effects of F on F (Z) shall be. evaluated to det reine if FQ(Z iswithinitslimHs q

4.2.2.2.3 When F (Z) is measured for other than F determinations, an overall g

xy measured F (Z) shall be obtained from a power distribution map and increased by g

3% to account for_ manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

MILLSTONE - UNIT 3 3/4 2-13 Amendment No.

, _50 i

I This page' left blank intentionally t

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i MILLSTONE - UNIT 3 3/4 2 14 Amendiaent No. 50 t

POWER DISTRIBUTION LIMITS i

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR i

FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION The indicated Reactor Coolant System (RCS) total flow rate and Ffg i

3.2.3.1 shall be maintained as follows:

a.

RCS total flow rate 2 385,210 gpm, and 1 FfgP [1.0 + PFAH (1.0 P))

b.

FAH Where:

I THERMAL POWER 1)

P

=

RATED THERMAL POWER N

N 2)

F Measured values of F iNoredetectorstoobtainkHobtainedbyusingthemovable N

power distribution map.

The measured value of F u should se used since A

Specification 3.2.3.Tb. takes into consideration a measurement l

uncertainty of 4% for incore measurement, RTP N

3)

F

= The F i

1$ttsrepork(COLR), limit at RATED THERMAL POWER in the core ope angg-ThepowerfactormultiplierforFfHprovidedintheCOLR, 4)

PF 5)

The measured value of RCS total flow rate shall be used since uncertainties of 1.8% for flow measurement have been included in l

Specificaticn 3.2.3.la.

l APPLICABILITY: MODE 1.

ACTION:

With the RCS total flow rate or FlH outside the region of acceptable operation:

i a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1.

Restore the RCS total flow rate and FN to within the above limits, or AH 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or e i

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . qual to 55% of RATED THERMAL POWER within the next l

l 1

l MILLSTONE' UNIT 3 3/4 2-15 Amendmentg,50 l

h POWER DISTRIBUTION LIMITS i

I LIMITING CONDITION FOR OPERATION j

4 l

ACTION (Continued) l b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside th0 above limits, verify

(

f through incore flux mapping and RC$ total flow rate that F and g

l RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

c, Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b., above; subsequent POWER OPERATION i

N may proceed provided that F and indicated RC$ total flow rate are f

demonstrated, through incore flux mapping and RC$ total flow rate comparison, to be within the region of acceptable operation prior to exceeding the following THERMAL POWER 1evels:

1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of t

l RATED THERMAL POWER.

l i

I l

SURVE1LLAN:E REQUIREMENTS l

4.2.3.1.1 The provisions of Specification 4.0.4 are not applichble. -

I 4.2.3.1.2 RCS total flow rate and F shall be determined to be within the g

acceptable range:

i Prior to operation above 75% of RATED THERMAL POWEit after each fuel s.

loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.II3 The indicated RCS total flow rate shall be verified to be within the l

l acceptable range at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the most recently obtained i

value of F g, obtained per Specification 4.2.3.1.2, is assumed to exist.

4.2.3.1.4 The RCS total flow rate indicators shall be subjected to a CHANNEL

' CAL 18 RAT 10N at least once per 18 months.

The measurement instrumentation shall be~ calibrated within 'I days prior to the performance of the calorimetric j

flow measurement.

l i

i MILLSTONE - UNIT 3 3/4 2-16 i

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POWft DISTRfkUTfDN LIMITS SURVffLLANtf AfoultfMENT fcantinued) 4.2.3.1.5 The RCS total flev rate shall be determined by precision heat balance measurement at least once per 18 months.

Within 7 days prior to performig the precision heat balance, the instrumentation used for determination of steam pressure, feedwater pressure, feedwater t M erature and feedwater venturi dip in the calorimetric calculations shallbecalibrated.

4.t.3.1.6 If the feedwater venturis are not. ins m ted and cleaned at least once per 18 months, an additional 0.1% will be added to the total RC$ flow measurement uncertainty.

l MILLSTONE UNIT 3 3/4 g.17 Amendment No. 27

_1

]

POWER DISTRIBUTION LIMITS RCS FLOW RATE AND NUCLEAR ENTHALPY R11E HOT CHANNEL FACTOR THREE LUDPS OPERATING LIMITING CONDITION FOR OPERATION l

\\

l 3.2.3.2 The indicated Reactor Coolant System (RCS) total flow rate and FfH shall be maintained as follows:

a.

RCS total flow rate 1 304,780 gps, and Ffg&FhP[1.0+PFg (1.0 - P))

I b.

Where:

l T 4ERMAL POW ER

[

1)

P

=

RATE) THERMAL WER L

N N

F Measured values of F 2) 1No=re deteFors to obtain $ obtained by using the movable power distribution map.

N The mes' value of F

.!.3.2b.takegHshouldbeusedsinceSpeci-ficatiow into consideration a measure-ment uncertainty of 4% for incore measurement, i

3)

FRTP = The F limit at RATED THERMAL POWER in the core operating it$itsreporgH(COLR),

4)

PFAH = The power factor multiplier for FAH in the COLR, and 5)

The measured value of RCS total flow rate shall be used since

[

uncertainties of 2.0% for flow measurement have been included in i

Specification 3.2.3.2a.

APPLICABILITY: MODE 1.

ACTION:

With the RCS total flow rate or FfH outside the region of acceptable operation:

I a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

Restore the RCS total flow rate and Ffg 1.

to within the above limits, or

/,

2.

Reduce THERMAL POWER to less than 32% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less l

than or equal to 37% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I 1[,50 MILLSTONE - UNIT 3 3/4 2 18 Amendment No.

)

CONTAINMENT $YSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve shall be OPERABLE and each 42 inch containment shutdown purge supply and exhaust isola-tion valve shall be closed and locked closed.

APPLICABILITY:

MODES 1.-2, 3, and 4.

ACTION:

With a 42 inch containment purge supply and/or exhaust isolation a.

valve open or not locked closed, close and/or lock close that valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , j

$URVEILLANCE REQUIREMENTS 4.6.1.7.1 The containment purge supply and exhaust isolation valvss shall be verified to be locked closed and closed at least once per 31 days.

d l

l MILLSTONE - UNIT 3 3/4 6-11 Amendment No. 5 i

l

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT DUENCH SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Quench Spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:.

With one Containment Quench Saray subsystem inoperable, restore the inoperable system to OPERABLE status witqin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.)

Each Containment Quench Spray subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days:

1)

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or l

otherwise secured in position, is in its correct position; and 2)

Verifying the temperature of the borated water in the refueling water storage tank is between 40'F and 50'F.

b.

By verifying, that on recirculation flow, each pump develops a differential pressure of greater than or equal to 114 psid when 4

tested pursuant to Specification 4.0.5; c.

At least once per 18 months during shutdown, by:

i 1)

Verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal, and 2)

Verifying that each spray pump. starts automatically on a CDA test signal.

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and veri fying each spray nozzle is unobstructed.

MILT. STONE - UNIT 3 3/4 6 12 Amendment No.

50 1

1 J

CONTAINMENT SYSTEMS R[QEyl& TION $?RAYSYSTEM-LIMITING CONDITION FOR OPERATION l

3.6.2.2 Two independent Recirculation Spray Systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

1 With one Recirculation Spray System inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the i

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable Recirculation Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0UIREMENTS 4.6.2.2 Each Recirculation Spray System shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, a.

i power operated, or automatic) in the flow path that is not locked, I

sealed, or otherwise secured in position, is in its correct position; b.

By verifying, that on recirculation flow, each pump develops a i

differential pressure of greater than or equal to 130 psid when tested pursuant to Specification 4.0.5; At least once per 18 months by verifying that on a CDA test signal, c.

each recirculation spray pump starts automatically after a 660 i20 j

second delay; L

d.

At least once per 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on l

a COA test signal; and i

e.

At least once per 5 years by performing an air or smoke flow test i

through each spray header and verifying each spray nozzle is unobstructed.

l l-MILLSTONE - UNIT 3 3/4 6-13 Amendment No. 50

.CONTA!NW.ENT SYS*EW.S

$ PRAY ADO.!7IVE SYSTEM LIMI!!N CONLITION FOR OPERATION 3.6.2 3 The 3; ray Additive Systes shall be OPERABLE withs a.

A chemical addition tank containing a volume of between 18000 and 19000 gallons of between 2.41 and 3.105 by weight NaOH solution, and b.

Two gravity feed paths each capable of adding NaOH solution fres the chesical. addition tank to each Containment Quench Spray subsysten pump suction.

APPLICABILITY:

MODES.1, 2, 3, and 4 j

A07:0N:

With the Spray Additive Systes inoperable, restore the system to CPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least H07 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restere the Spray Additive System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLO SHU7DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SUPVIILLANCE PE;UIREMENTS H

4.6.2 3 The Spray Additive Systes shall be demonstrated OPERABLEt a.

At least once per 31 days by verifying that eac'h valve (sanual, power-o;. orated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.

At least once per 6 months by:

1)

Verifying the contained solution volume -in the, tank, and 2)

Verifying the enneentration of the NaOH solution by chesical analysis is within the above limits.

I c.

At least once per 18 months, during shutdown, by verifying that each

automatic valve in the flow path actuates to its correct position on a CDA test signal.

i MILLSTONE - UNIT 3 3/4 6-14 Amendment No.12 l

1

r t

l 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1.1 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 following reactivity conditions is met; either:

A K,77 of 0.95 or less, or a.

b.

A boron concentration of greater than or equal to 2300 ppm.

APPLICABILITY: MODE 6.*

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTEPATIONS or positive reactivity changes and initiate and continue boration at greater than or equal. to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or its equivalent until K is reduced to less than or equal to 0.95 or the boron concentration is r$Nored to greater than or equal to 2300 ppm, whichever is the more restrictive, t

SURVEILLANCE REOUIREMENTS 4.9.1.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head.and 1

b.

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

4.9.1.1.2 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 .

4.9.1.1.3 Valve 3CHS-V305 shall be verified closed and locked at least once per 31 days.

4

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

MILLSTONE - UNIT 3 3/4 9 1 Amendment No. 50

RETUELINS OPERA?!0NS DDROM CON 0ENTRATION

\\

Limitir. Condition for Operation

\\

3 9 1.2 The boren concentration of the Spent ruel Fool shall be maintained i

unifora and suff.icient to ensure that the boren concentration is greater than er equal to 800 ppe.

J Applienbility

. j During ALL fuel assembly movements within the spent fuel pool.

Action c

With the boren concentration less than 800 ppa, suspend the movement of all.

fuel assemblies within the spent fuel pool.

j Surve!!1anee Reevirements' 4.9 1.2 Verify that the boron concentration is greater than or equal to 800 pp: prior to any movement of a fuel assembly into or within the spent r

fael pool, and every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter during fuel movement.

2 I

l i

9 l

l MILLSTONE - UNIT 3 3/li 9 1a -

Amendment No.12 l

1 i

9 SW

_, - ~,.

., - - ~. -. -

o ls e

(

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARCIN A sufficient SHUTDOWN MRGIN ensures that:

1 subcritical from all operating conditions, (t) the(re) activity transients asso-the reactor t.inted with postulated accident conditions are controllable within acceptable limits, and 3

preclude inad(ve)rtent criticality in the shutdown condition.the reactor will be m SHUTDDWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T The most restrictive condition occurs.at E0L with T at no load opeNfing temperature, and is associated with a postukated st$$E line break accident and resulting uncon-trolled RCS cooldown.

In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.6% Ak/k is required to control; the reactivity transient.

Accordingly, the SHUTDOWN MRGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions With T less than 2000F, the reactivity transients resulting from a postulated $t0$E line break cocidown are minimal.

provide protection against a boron dilution accident.A 1.6% Ak/k SHUTDOWN MARGIN is 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.

The MTC values of this s plant conditions; accordingly,pecification are applicable to a specific set of verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC, value equivalent to the most-positive moderator density coefficitnt (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.

MILLSTONE - UNIT 3 8 3/4 1-1 Amendment No. 29 l

l z-ma....n.,

'i REACTIVITY CC1 TROL SYSTEMS BASES MODERATOR TEMPERATURE C0 EFFICIENT (Continued)

These corrections involved:

(1) a conversion' of the MDC used in the FSAR safety analyses to its equivalent MTC, based on the rate of change of t

moderator density with temperature at RATED THERMAL POWER conditions, and<(2) subtracting from this value the largest differences in MTC observed' between EOL, all rods withdrawn, RATED THERMAL POWER conditions, and those most ad',erse conditions of moderator temperature and pressure, rod insertion, axial p0wer skewing,^and xenon concentration that can occur in normal. operation and lead to a significantly more negative E0L MTC at RATED THERMAL POWER.

These corrections transformed the MDC value used in the FSAR safety analyses into the -limiting End of Cycle Life (EOL) MTC value.

The 300 - ppm surveillance limit MTC value represents a conservative MTC value at a core condition of 300 apm equilibrium boron concentration, and is obtained by making corrections for surnup and soluble boron to the limiting EOL MTC value.

The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its-limits since this coefficient changes slowly due

)rincipally to the reduction in RCS boron concentration associated with fuel surnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be. made critical with the Reactor Coolant System average temperature less than 551.

This limitation is required to ensure:

(1) the moderator temperature coefficient is within it analyzed temperature range, (3) the(2) the trip instrumentation is within its normal operating range, P 12 interlock is above its setpoint, (4) the pressurizer is capable of being in an OPERABLE status with a L

steam bubble, and (5)the reactor vessel is above its minimum RTNDT' temperature.

3/4.1.2 BORATION SYSTEMS The Boron Injection System ensures that negative-reactivity control is available during each mode of facility operation.

The components req 1 ired to perform-this function include:

(1) berated water sources, (2) charging pumps, (3) separate flow paths, power supply from OPERABLE (4) boric acid transfer pumps, and (5) an emergency diesel generators.

With the RCS average temperature above 200, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable.

The i

boration capability of either flow path is sufficient to provide a SHUTDOWN MILLSTONE - UNIT 3 B 3/4 1-2 Amendment No.

, 50

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

..r.

I 3/4.2 POWER DISTRIBUTION LIMITS BASES l

t l

The specifications of this section provide assurance of fuel integrity duringCondition1(NormalOperation)andII.(IncidentsofModerateFrequency) 2 events by:

(1 maintaining the minimum DN8R in the core greater than or equal to 1.30 during) normal operation and in short-term transients, and (2) limiting the fission gas release,; fuel wilet temperature, and cladding mechanical properties to within assumed des'gn criteria.

In addition,. limiting the peak linear power density during Condition I events provides assurance that-the initial conditions assumed for the LOCA analyses are met and the ECCS acceptarce i

criteria limit of 2200'F is not exceeded.

l The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

1 F (Z)

Heat Flux Hot Channel Factor, is defined as the maximum local heat g

flux on the surface of a fuel rod at core elevation Z divided by the i

average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods; FfH Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated l

power to the avt' ige rod power; and Fxy(Z)

Radial Peaking Factor, is defined as the ratio of peak power density to average power density in the horizontal plane at core elevation Z.

i 3/4.2.1 AXIAL FLUX DIFFFER(1 l

The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the Fn(Z) upper bound envelope of the F limit specified in the Core Operating Lim'its Report (COLR) times the normaliSed axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal positinn for steady state operation at high power levels.

The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER l

for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value l

by the appropriate fractional THERMAL POWER level.

The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

MILLSTONE - UNIT 3 8 3/4 2-1 Amendment No. 50 L

- - - ~.

POWER DISTRIBUTION LIMITS e,,

. ggg 1

AX1AL FLUX DIFFERENCE (Continued);

Although - it is intended that the'- plant willL be-operated with-the AFD within the target band required by Specifications 3.2.1.1-.and 3.?.2.1 about

.the target flux difference, during rapid plant THERMAL POWER reductions,

control rod motion will cause the AFD to deviate outside of the target band at reduced -THERMAL POWER levels.

This deviation will not affect the xenon iredistribution 'sufficiently to change the envelope of peaki:r) factors which may be reached on a -subsequent return to RATED; THERMAL POWER (with the AFD within the target bard provided the time duration' of the deviation is 1

t

_ limited. Accordingly, > Pour penalty deviation limit cumulative during the l

' previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is pi,vuled for operation outside of. the target band but within the limits'specified in.the -COLR= at THERMAL POWER levels between 50%

and 90% of RATED THERMAL POWER:(four-loops operating) or between 32% and 65%

of-RATED THERMAL POWER- (three. loops operating).

For THERMAL POWER levels a

between 15% and 50% of RATED THERMAL POWER-(four loops operating) or. between 15% and 32% of RATED-THERMAL POWER (three loops operating),-deviations of the-1 AFD outside of the: target band are less significant.

The' penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

1 Provisions'for monitoring ths AFD on-an automatic basis are' derived from' the plant process computer through the AFD Monitor Alarm.

The computer deter-mines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message. immediately if the AFD for. two or more -0PERABLE excore channels are outside the target band and:the THERMAL POWER is greater than 90%'of RATED THERMAL POWER.

During four loop operation at. THERMAL POWER i

3 levels:between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message,when the: penalty deviation accumulates beyond j

-the limits of I hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively. _During three-loop operation at THERMAL: POWER levels between 32% and 65% and-between.15% and 32%_ RATED THERMAL'

~ POWER, the com> uter outputs an alarm message when the penalty deviation accumu-lates beyond tie. limits of I hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,-respectively.

Figures B 3/4 2-la and B 3/4 2 lb show typical monthly target bands, t

3/4.2.2 and 3/4.2.3 HEA" FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR EN"HALPY R SE HO" CHANNEL FACTO O 1

The limits on heat flux hot channel factor, RCS flow rate, and nuclear L

enthalpy rise hot channel factor. ensure that:

(1) the design limits on; peak l

local power density and minimum DNBR are not excseded >and (2) in' the event of

=i J

a LOCA the peak fuel clad temperature will not exceed the 22000F ECCS acceptance criteria limit.

1 Each of.these is measurable but will normally only be determined-periodically as specified. in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to ensure that the limits.are maintained provided:

v 1

a.

Contro1' reds in a single group move together with no individual rod insertion. differing by more than 112 steps, indicated, from the 1

group demand position; b.

Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; 4

' MILLSTONE - UNIT 3 B 3/4 2-2 Amendment No. 50 L;

= - -

r..

a-

..q l.

l,'.

POWER DISTR 280'10N LIMITS SASES NEAT FLUX HDT CHANNI:L FA070R AND RCS PLOW RATE AND WUCLEAR SW7NALPY RISE NOT CHANNE'. FACTOR

Continued)

The control rod; insertion limits of speelfications 313 5 and e.

313 6 are maintained; and i

6.

The aula1 power distribution; expressed.in terms of. AX1AL FLUX:

D1FFERENCE, in maintained within the limits.

i F"4 -

i through $.will. be maintained within its limits provideg Conditions a.

- above are maintained.4 7he relaxation of Fan as a function of 7HERVA POWER allows changes in the radial power shapV for'all peraissible rod insertion = limits.

I The F1 as calculated.in speelfications 3 2 31 and 3 2 3.2 are H

y used-in the various accident _ analyses where F influences parameters -

ether than DN3R, e.g., peak clad tosperature,a uaHd thus is the maximus-i l

'as sensured' value allowed.-

i 7ne difference betwegn the three and four-loop F a more restrictive Fe u.used.in the safety analys,e$ equations is due to for threg loop opera tion. In four.2 esp -operation, the allowable measured F ey calcalatedinspecificatibn323.1at655RagedthermalPoweris:

4 1.65.

2n three.1oop operation, however, F.

sensured value f 1.55 to be consistent with thl is restricted to a l

safety analyses for three loop operation. At sero power, both specifications allow the same 4

g sensured F g g.

1 L

Fuel red bowing r x,':n.... value of DNB ratio.

Credit is' available to offset thKs <+;,nction in the generic margin. The generic t-i sargins, totaling 9.1f DNBR Jospletely offset any rod bow penalties..

l-This margin includes t se followiG a.

Design liai' 5' n P L36 vs 1.28, b.

Crid Specit3 th;'? t.f s. N vs.-0.059,

' i

, thermal'Diff. a t 'S-r;icient of 0.038 vs 0.059, c..

1 d.

DNBR Multiplier of 0.86 vs. 0.86, and e.

Pitch reduction, s

The applicable values of rod bow penalties are referenced in the PSAR..

i l>

MILLSTONE - UNIT 3-83/42-5 Amendment No. 12 s

9 0

e

. =. - <

...4...-.<.-,-..

.w..+--

..-e.'

..[-.w.-

,,,-men.

s 4

POWER DISTRIBUTION LIMITS BASES HEAT PLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANN EL FACTOR (Continued).

When an Fg easure m t M. taken,'an allowance for both experimental error m

and manufacturing 16W&ngt must be made. - An allowance of'5% is appropriate for a full-core sep tekea with the Incore Detector Flux Mapping System, and a 3% allowance is yptc3 Mate for manufnMing tolerance.

The Radial Peaking Factor, Fxy(Z), is measured periodically to provide assurance that the Hot Channel Factor, F (Z), remains within its limit.

The F

limit for RATED THERMAL POWER (FN ) asrovided in the_ Core Operatin LNiits Report Specification 6.9.1.6 w8 determi ed from expected power contro manuevers over the full range of burnup conditions in the core.

When RCS flow rate and F H are measured, no additional allowances are Operation. prior to comparison with the -limits of the Limiting Conditien for necessary Measurement errors of 1.8% for four loop - flow and 2.0% for three s

loop flow for RCS total flow rate and 4% for FN have been allowed for in determination of the. design DNBR value.

H The measurement error for-RCS total flow rate is based upon' performing a precision heat balance and using the result to-calibrate -the 'RCS flow rate indicators.

Potential fouling of the feedwatert venturi which might not be detected could bias the result from t the precision heat. balance in a non-conservative manner.

Therefore, a penalty.of 0.1% for undetected fouling of the feedwater veaturi will be added if' venturis are inspected and cleaned at least once for 18 months.

Any fouling which mightibias the RCS flow rate measurement greater than 0.1% can be - detected L by monitoring: and trending various plant performance parameters.

If; detected, action. shall be taken L

before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

The 12-hour periodic surveillance of indicated RCS flow is sufficient.to detect only flow degradation which could lead to operation outside the accept-able region:of operation defined in Specifications 3.2.3.1 and 3.2.3.2.

3/4.2.4 00ADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribu-tion satisfies the design values used in the power. capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

MILLSTONE - UNIT 3 B 3/4 2-6 Amendment No. / 50

ADMINISTRATIVE CONTROLS-i:

1 4

I SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation.of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

4 A supplemental report containing dose assessments for the previous. year shall.be submitted annually within 90 days after January 1.

j The report shall. include that information delineated in the REM 0DCM.

Any changes to the-REMODCM - shall be submitted in the Semiannual Radioactive Effluent Release Report.

MONTHLY OPERATING REPORTS 5

i 6.9.1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C.

20555, one. copy to - the Regional Administrator Region 1. and one copy to the NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.

I CORE OPERATING LIMITS REPORT l

L 6.9.1.6.a Core operating limits shall be established and. documented in the

- CORE OPERATING.I.IMITS REPORT before each reload cycle or any remaining'part of a

a reload cycle ~ for'the following:

l.

Moderator Temperature Coefficient BOL and. E0L' limits - and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.

Shutdown Rod Insertion Limit for Specification 3/4.1.1.5, j

3.

Control Rod Insertion Limits.for Specification 3/4.1.1.6, 4.

Axial Flux Difference

Limits, target band for Specifications 3/4.2.1.1 and 3/4.2.1.2, i

5.

Heat Flux Hot Channel Factor, K(Z), Power Factor Multiplier for Specifications 3/4.2.2.1 and 3/4.2.2.2.

l; 6.

RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3.

A single submittal may be made for a multiple unit station.

The submittal j

should combine those sections that are common to all units at the station;-

however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material-from each unit.

b MILLSTONE - UNIT 3 6-21 Amendment No.,2ff,,#, 50

t 6.9.1.6 b The analytical methods used to determine the core operating limits shall be those previously reviewed and' approved-by the NRC in:-

i p

1.

WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology,"

3 July 1985 (W Proprietary).:

1 1

2.

WCAP 8385, " Power Distribution Control and Load Following Procedures-

- Topical Report," September,-1981 (W Proprietary).

3.

T. M. Anderson tol K. Kniel (Chief of; Core Performance Branch,. NRC)

~ January 31, 1980 -

Attachment:

Operation-and Safety-Analysis-Aspects of an Improved Load Follow Package. -

3 r

l

.4.

NUREG 800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section.4.3,. Nuclear Design,' July 1981' Branch Technical Position CPB a

4.3-1, Westinghouse-Constant Axial Offset Control (CAOC),

i Revision 2, July 1981.

5.

WCAP-9220-P-A, _ Rev.1,. " Westinghouse ECCS Evaluation Model - 1981 Version,". February 1982 (W Proprietary).

6.-

-WCAP-11946, "SafetyL Evaluation Supporting

a. More Negative EOL-Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station' Unit 3

September l 1988,- (W Proprietary).

l 6.9.1.6.c The core operating limits shall. be determined so that all-applicable limits (e.g. fuel thermal-mechanica1L11mits, core thermal;-hydraulic 4

limits,-ECCS limits, nuclear limits such,as shutdown margin, and transient' and accident ' analysis limits) of the safety; analysis are met.

6.9.1.6 d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions l-

- 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.

1

[

L 1

\\

MILLSTONE - UNIT 3 6-21a Amendment No. 50-w

-,,.,,.. - =..

.=

ww e.

ADMIN 11TRATIVE CONTROL 1 EpttiAL Rfp0 RTE i

6.g.2 Commission, Document Control Desk, Washington, D.C.Special reports shall b 20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, within the time period specified for each report.

6.10 Att0RD RETENT10N 6.10.1 in addition to the a plicable record retention requirements of Title 10, Code of Federal Re ulations, the following records shall be retained for at least the minimum per od indicated.

6.10.2 The following records shall be retained for at least 5 years:

{

Records and logs of unit operation covering time interval at each a.

power level; b.

Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; c.

All REPORTABLE EVENTS; d.

Records of surveillance activities, inspections, and calibrations required by these Technical. Specifications; Records of changes made to the procedures required by e.

Specification 6.8.1; 4

f.

Records of radioactive shipments; g.

Records of sealed source and fission detector leak tests and results; and h.

Records of annual physical inventory of all sealed source material of record.

6.10.3 The ~following records shall be retained for the duration of the unit I

Operating License:

Records and drawing changes reflecting unit design modifications a.

made to systems and equipment described in the Final Safety Analysis Reports b.

Records of new and irradiated fuel inventory, fuel transfers, and

. assembly burnup historiest Records of radiation exposure for all individuals entering c.

radiation control areas; MILLSTONE UNIT 3 6-22 Amendment No. 2a, 50

_

ML20043H722

Text

Attachment:

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