ML20085E106

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Proposed Corrections to Tech Spec Bases Page B 2-7 Re Thermal Margin/Low Pressure & Various Tech Spec Sections & Bases to Correct Editorial Errors & Typos
ML20085E106
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/09/1991
From:
NORTHEAST UTILITIES SERVICE CO.
To:
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ML20085E105 List:
References
NUDOCS 9110180038
Download: ML20085E106 (20)
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Text

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Docket No. 50-333 B13903 Attachment L Millstone Nuclear Power Station, Unit No. 2 Proposed Change to Technical Specifications Non-Intent Changes to Correct Editorial and Typographical Errors October 1991 L

I 9110180038 911009 l PDR ADOCK.05000336'--

l-- P PDR

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INDEX DEFINITIONS PAGE SECTION Encl osure Building Integri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 Reactor Trip System Response Time........................... 1-5 Engineered Safety Feature Response Time..................... 1-5 Physics Tests............................................... 16 Unrodded Integrated Radial Peaking Factor - F . . . . . . . . . . . . . . 1-6 r

Source Check................................................ 1-6 Radiological Effluent Monitoring and Offsite Dose Cal cul ation Manual (REH0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 Radioactive Waste Treatment Systems......................... 16 Purge - Purging.............................................. 16 Venting........ ............................ ............... 1-8' Membe r ( s ) o f t h e Pu bl i c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 Site Boundary............................................... 1-8 Unrestricted Area........................................... 1-8 Storage Pattern........................ .................... 1-8 MILLSTONE - UNIT 2 II Amendment No. 79f, JJJ, JJ7, 0030 Jyp

l l@ll LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION. PAGE 3/4.0 APPLICABillTY ......................................... 3/4 0 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORAT10N CONTROL ................................ 3/4 1-1 Shutdown Margin - T avg 200*F .................... 3/4 1-1 Shutdown Margin - Tavg 200'F .................... 3/4 1-3 Boron Dilution .................................. 3/4 1-4 Moderator Temperature Coefficient (MTC) ......... 3/4 1-5 Minimum Temperature for Criticality . . . . . . . . . . . . . 3/4 1-7

'3/4.1.2 B0 RATION SYSTEMS ................................ 3/4 1-8 Flow Paths - Shutdown ........................... 3/4 1-8 Flow Paths - Operating .......................... 3/4 1-9 l Charging Pump - Shutdown ........................ 3/4 1-12 Charging Pumps - Operating ...................... 3/4 1-13 Boric Acid Pumps - Shutdown ..................... 3/4 1-14 Boric Acid Pumps - Operating .................... 3/4 1-15 Boratod Water Sources - Shutdown ................ 3/4 1-16 Borated Water Sources - Operating ............... 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES ...................... 3/4 1-20 Full Length CEA Group Position .................. 3/4 1-20 Position Indicatt.r Channels ..................... 3/4 1-24 CEA Drop Timc~................................... 3/4 1-26 Shutdown CEA Insertion Limit .................... 3/4 1-27

' Regul ating CEA Insertion Limits . . . . . . . . . . . . . . . . . 3/a 1-28 Control Rod Drive Mechanisms .................... 3/4 1-31 i

MILLSTONE - UNIT 2 IV Amendment No. EE, Jpf, JJf 0031-

~

  • 1 i

lhDEX .

.LJMITING CONDITIONS FOR OPERATION AND SVRVElllANCE RE0VIREMENTS -1 SECTION- PRE i

3/4.4.2 SAFETY VALVES-.................................. 3/44-2 3.4.4.3 RELIEF VALVES .................................. 3/4 4-3 3/4.4.4 PRESSURIZER .................................... 3/4 4-4 .

3/4.4.5 STEAM GENERATORS ............................... 3/4 4-5 3/4.4.6_ REACTOR COOLANT SYSTEM LEAKAGE ................. 3/4 4-8 Leakage Detection Systems ....................... 3/4 4-8 Reactor Cool ant System Leakage . . . . . . . . . . . . . . . . 3/4 4-9 3/4.4.7 C i l % 3'T R Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4+10 J/4.4.8 SPLL'flC ACTIVITY ..............................

3/4 4-13 3/4.4.9 PRESSURE / TEMPERATURE LIMITS .................... 3/4 4-17 Reactor Coolant System ......................... 3/4 4-17 Pressurizer .................................... 3/4 4-21 Overpressure Protection Systems ................ 3/4 4-21a 3/4.4.10 STRUCTURAL INTEGRITY . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-22 3/4.4.11 EEACTOR COOLANT SYSTEM VENTS ................... 3/4 4-23 3/4.5 EMERGEN(J CORE COOLING SYSTEMS (ECCS) 3/4.5.1 -SAFETY INJECTION TANKS ......................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS -_T avg > 300*F ................. 3/4 5-3 3/4.5.3' ECCS SUBSYSTEMS - Tavg < 300'F ................. 3/4 5-7 3/4 5.4 REFUELING WATER STORAGE TANK ................... 3/4 5-8 i

l-l MILLSTONE - UNIT 2 VI Amendment No. ES, //, 19,4-0032

I INDf1 MMillNG CONDITIONS FOR OPERATION ANDEVJ,illANCF RE0VMEMENTS SECTION PARE 3/4.6 CDNTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT .......... .................... 3/4 6-1 Containment Integrity ............................. 3/4 6-1 Containment Leakage .......... ... ................ 3/4 6-2 Containment Air Locks .......... .................. 3/4 6-6 I n te rn al Pre s s u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-8 Air Temperature ........... ....................... 3/4 6-9 Containment Structural Integrity .................. 3/4 6-10 e 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS .............. 3/4 6 12 Containment Spray System ..... .................... 3/4 6-12 Containment Air Recirculati on System .............. 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES ...................... 3/4 6 15 Containment Ventilation System .................... 3/4 6-19 l 3/4.6.4 COMBUSTIBLE GAS CONTROL ........................... 3/4 6-20 Hydrogen Monitors ................................. 3/4 6-20 Electric Hydrogen Recombiners W ................. 3/4 6-21 Hydrogen Purge System ............................. 3/4 6-23 Post-Incident Recirculation Systems ............... 3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT ............................. 3/4 6-25 Enclosure Building Filtration System .............. 3/4 6-25 Enclosure Building Integrity ...................... 3/4 6-28 o

MILLSTONE - UNIT 2 Vil Amendment No. Jpf 0033

- _ - _ - - _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ __~

lhDIX LIMITING _ CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION. EAC3

- Ei,LR(FUfl ING _0PERATIONS 3/4.9,1 BORON CONCENTRATION .............................. 3/4 9-1 3/4.9.2 INSTRUMENTATION .................................. 3/4 9-2 3/4.9.3 DECAY TIME ....................................... 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS ......................... 3/4 9-4 3/4.9.5 COMMUNICATIONS .................................... 3/4 9-5 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING ......... 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING... 3/4 9 3/4.9.8 SHUIDOWN COOLING AND COOLANT CIRCULATION ......... 3/4 9-8 3/4.9.9 CONTAINMENT AND RADIATION MONITORING ............. 3/4 9-9 3/4.9.10 CON 1AINMENT PURGE VALVE ISOLATION SYSTEM ......... 3/4 9-10 3/4.9.11 .WATER LEVEL -_ REACTOR VESSEL ..................... 3/4 9-11 3/4.9.12 STORAGE POOL WATER LEVE;. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9 12 3/4.9.13 STORAGE POOL RADIATION MONITORING . .............. 3/4 9-13 3/4.9.14 STORAGE POOL AREA VENTILATION SYSTEM -

FUEL MOVEMENT .................................... 3/4 9-14

.3/4.9.15. STORAGE POOL AREA VEN11LAT10N S'fSTEM -

FUEL STORAGE ..................................... 3/4 9-16 3/4.9.16 SHIELDED CASK ........... ........................ 3/4 9-19 3/4.9.17 MOVEMENT OF FUEL OVER PEGION 11 RACKS ..... ...... 3/4 9-21 3/4.9.18 SPENT FUEL POOL - REACTIVITY CONDITION ........... 3/4 9-22 3/4.9.19 SPENT FUEL P0OL - STORAGE PATTERN................. 3/4 9-26 i 3/4.9.20 SPENT FUEL P00L -. CONSOLIDATION .................. 3/4 9-27 3/4.10 SPECIAL TESLEXCEPTIONS 3/4.-10.1 SHUTD0'sN MARGIN . . . . . . . ......................... 3/4 10-1 3/4.10.2 GR0lV HEIGHT AND INSERTION LIMITS ................ 3/4 10-2 3/4.10.3 PriSSURE/ TEMPERATURE LIMITATION - REACTOR CRITICALITY ................. .................... 3/4 10-3 MILLSTONE - UNIT 2 IX Amendment No. 59, JSA, Jp,9, JJJ 0034

p. .

A INDEX LIMITING CONDIT10NS'FOR OPERATION AND SVRVElllANCE RE0VIREMENTS SECTION PAGE 3/4.10.4 PHYSICS TESTS ..................-................ 3/4.10 4 1 3/4.10.5 CENTER CEA MISALIGNMENT ......................... 3/4 10-5 l 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1- .IQUID EFFLUENTS ................................ 3/4 11-1 CONCENTRATION ................................... 3/4 11-1 DOSE, LIQUIDS ................................... 3/4 11-2 3/4.11.2 GASE0US EFFLUENTS ............................... 3/4 11-3 DOSE RATE ....................................... 3/4 11-3 DOSE, NOBLE GASES ............................... 3/4 11-4

' DOSE, RADIO 10 DINES, RADIDACTIVE MATERIAL IN-PARTICULATE FORM,-AND RADIONUCLIDES OTHER THAN N0BLE GASES ................................ 3/4 'l-5 -

3/4.11.3 TOTAL DOSE ...................................... 3/4 11-6 l

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L MILLSTONE - UNIT 2 X Amendment No. Jp4, JS9 l 0035-m- _

4. -

l 1

ItLQIl BASES SECTION MGf 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION ............. B 3/4 4-1 3/4.4.2 SAFETY VALVES ........ ............................ B 3/4 4-1 3/4.4.3 REllEF VALVES ..................................... B 3/4 4-2 3/4.4.4 PRESSURIZER ................... ................... B 3/4 4-2 3/4.4.5 STEAM GENERATORS .................................. B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE .................... B 3/4 4-3 3/4.4.7 CHEMISTRY ......................................... B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY ................................. B 3/4 4-4 3/4.4.9 -PRESSURE / TEMPERATURE LIMITS ....................... B 3/4 4-5 3/4.4.10 ST RUCTU RAL INT EGRI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-11 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ...................... B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANXS ............................ B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS ........................ B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK (RWST) ............... B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT ............................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS .............. B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES ...................... B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL ........................... B 3/4 6 4 3/4.6.5 SECONDARY CONTAINMENT ............................. B 3/4 6-5 l

l MILLSTONE - UNIT 2 XII Amendment No. EE, ES, 72, Jpf 0036

.LNpil BASES SECTION A EADI 3/4.9.9 and 3/4.9.10 CONTAINMENT AND RADIATION MONITORING-AND CONTAINMENT PURGE-VALVE ISOLATION SYSTEM ................. B 3/4 9-2

-3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND l STORAGE POOL WATER LEVEL ................................. B 3/4 9-2 l 1

3/4.9.13 STORAGE P0OL RADIATION MONITORING ................... B 3/4 9 l

, 3/4.9.14 and 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM ... 8 3/4 9-3 3/4.9.16 SHIELDED CASK ........................... ........... B 3/4 9-3 3/4.9.17 MOVEMENT OF FUEL OVER REGION 11 RACKS ............... B 3/4 9-3 3/4,9.18 SPENi FUFL POGi - REACTIVITY CONDITION .............. B 3/4 9-3 l 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN ................... B 3/4 9-4 l

-3/4.9.20 SPENT FUEL P0OL - CONSOLIDATION ..................... B 3/4 9-4 1 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN W PGIN .................................. .. B 3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS ................... B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION -

REACTOR CRITICAllTY ............................... B 3/4 10-1 3/4.10.4 PHYSICS TESTS ....................................... B 3/4 10-1 3/4.10.5 CENTER CEA MISALIGNMENT ............................. B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS .................................... B 3/4 11-1 3/4.11,2 GASE0US EFFLUENTS ................................... B 3/4 11-2 3/4.11.3 TOTAL DOSE .......................................... B 3/4 11-4 MILLSTONE - UNIT 2 XIV Amendment No. A9, 7pf, Jpf, JJJ 0037

INDEX 6DHii..STRATIVECONTROLS SECT 10N A E,A,GL 6.1 RESPONSIBillTY ......................................... 6-1 ft2 ORGANIZATION ........................................... 6 Offsite and Onsite Organizations ..................... 6-1 Facility Staff ....................................... 6-1

- 6.3 UNIT STAFF 00ALIFICAT10N1 .............................. 6-la-i 6.4 TRAINING ............................................... 6-5 6.5 REVIEW AND AUDIT 6.5.L PLANT OPERATIONS REVIEW C0KMITTEE (PORC)

Function ............................................. 6-5 Composition .. ....................................... 6-5 Alternates ........................................... 6-5 Meeting Frequency .................................... 6-6 Quorum ............................................ .. 6-6 Responsibilities ..................................... 6-6

. Authority ............................................ 6 Records ....................... ...................... 6-7 6.5.2 SITE OPERATIONS REVIEW COMMITTEE (SORC)

. Function ............................................. 6-7 Composition .......................................... 6-7 Alternates ........................................... 6-8 Meeting Frequency .................................... 6-8

. Quorum ........................ ...................... 6-8 Re s pon s i bi l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 Authority ............................................ 6-9 Records .............................................. 6-9 MILLSTONE - UNIT 2 XVI Amendment No. J0f, Jf/

0038

l

.lHQll

@$NISTRATIVE CONTROLS SECTION PAGE

.E.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS ....................................... 6-17 STARTUP REPORTS ....................................... 6-17 ANNUAL REPORTS ........................................ 6-18 HONTHLY OPERATING REPORT .............................. 6-19 CORE OPERATING LIMITS REPORT .. ....................... 6-19 6.9.2 SPECIAL REPORTS ....................................... 6-19 1119.-RECORD RETENTION ....................................... 6-20 6.11 RADI AT ION PROJE[T ION PROGBAM . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21

_ f.12 HIGH RADIATION AREA .................................... 6-21 6.13 SYSTEMS INTEGRITY ...................................... 6-22

'6.14 10 DINE'HONITORING ...................................... 6-22 6.15 RADIOLOGICAL EFFLUENT MONITORING AND 0FFSITE-DOSE CALCULATION MANUAL (REMODCH) ......................... 6-23 6.16 RADI0 ACTIVE WASTE _lREATMENT ............................ 6-23 5.17 $ECONDARY WATER CHEMISTR1 ... ........................... 6-24 6.181 PASS / SAMPLING AND ANALYSIS OF PLANT EFFLUENTS .......... 6-24 MILLSTONE - UNIT 2 XVIll Amendment No. 79, JE, EJ, EE, Jp)

    • 199,111,199

REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 _ The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits provided in the CORE OPERATING LIMITS-P.EPORT. Regulating CEAs are considered to be fully withdrawn when withdrawn to at least 176 steps. CEA insertion between the Long Term Steady State Insertion Limits and the Transient insertion Limits restricted to the limits provided in the CORE OPERATING LIMITS REPORT.

APPLICABIllTY: MODES 1* and 2*#. o 6CTION:

a, With the regulating CEA groups inserted beyond the Transient Insertion Limits provided in the CORE OPERATING LIMITS REPORT, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:

1. Restore the regulating CEA groups to within the limits, or
2. Reduce THERMAL POWER to that fraction of RATED THERMAL POWER which is allowed by the CEA group position using the above figures,
b. With the regulating CEA groups inserted between the Long Term Steady State Insertion Limits and the Transient Insertion Limits

< specified in the CORE OPERATING LIMITS REPORT for intervals

> 4' hours per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, except during operation pursuant to the provisions of ACTION items c. and d. of Specification 3.1.3.1, operation may proceed provided either:

1. The Short Term Steady State Insertion Limits specified in the CORE OPERATING LIMITS REPORT are not exceeded, or .
2. Any subsequent increase in THERMAL POWER is restricted to 1 5% of RATED THERMAL POWER per hour.
  • See Special Test Exception 3.10.2 and 3.10.5.
  1. With K eff 2 1.0.

4 e

MILLSTONE- UNIT 2 3/4 1-28 Amendment N3. JfE 0040

+

4

, REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS (Continued)

. LIMITING CONDITION FOR OPERATION

c. With the ragulating CEA groups inserted between the Long Term Steady State Insertion Limits and the Transient' Insertion Limits-specified in the CORE OPERATING LIMITS REPORT for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, except during operations pursuant-to the provisions of ACTION items c. and d. of Specification 3.1.3.1, either:
1. Restore the regulating groups to within the Long Term Steady State Insertion Limits nrovided in the CORE OPERATING LIMITS REPORT within two hours, or.
2. Be in HOT STANDBY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.1.3.6 The position of each regulating CEA group shall be determined to be within the Transient insertion Limits provided in the CORE OPERATING LIMITS REPORT:at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the PDll Auctioneer Alarm Circuit is inoperable, then verify the individual CEA ,

. positions at least,once per 4 ttours. The accuniulated times during which the regulatory CEA groups are inserted between the Long Term Steady State

. insertion Limits and the Transient Insertion Limits specified in the CORE OPERATING LIMITS PEPORT shall be determined at letst once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> specified .

MILLSTONE - UNIT 2 3/4 1-29 Amendment No. //E 0041

REACTOR COOLANT SYSTEM-REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 AtJ1 east one reactor coolant system vent path consisting of at least two valves in series capable of being powered from emergency buses shall ce OPERABLE and closed at eae of the following locations:

a. Reactor Vessel heao
b. Pressurizer steam space l

e APPLICABillTY: MODES 1, 2, 3, and 4.

ACTION:

a. With the Pressurizer vent path inoperable, STARTUP and/or POWER OPERATION may continue provided that i) - the inoperable _ vent path is maintained closed with power removed from the valve actuator of . all the valves in the inoperable vent path and li) one power operated relief valve (PORV) and its associated block valve is OPERABLE; otherwise, restore either the inoperable vent path or one PORV and its associated-block valve to-0PERABLE status within 30 days, cr submit a Special Report to the Commission pursuant '.a Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the path to OPERABLF status,
b. With the Reactor Vessel Head vent path inoperable. STARTUP and/or POWER OPERATION may continue provided that the inoperable . vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the Reactor Vessel Head vent path to l OPERABLE status within 30- dr.ys or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause' of the malfunction and the plans for restoring the path to OPERABLE status.

SURVEILLANCE RE0VIREMENTS 4.4 11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by.

! 1. Verifying all manual isolation valves in -each. vent path are l locked in the open position.

2. Cycling each valve in the vent path through ai least once complete cycle of full travel from the control _ room during COLD E SHUTDOWN or REFUE'ING.
3. Verifying flow through the reactor coolant vent system - vent l paths during venting during COLD SHU100WN or REFUELING.

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. /p, 72, J/p, cost jy I

+-

RffVEllNG OPERATIONS SPENT FUEL P00L1- REACTIVITY CONDIT10N LIMITING CONDITION FOR OPERATION _

3.9.18 The Reactivity Condition of the spent fuel pool shall be such that K*77 l is less than or equal to 0.95 at all times.

APPllCABILITY: Whenever fuel is in the spent fuel pool.

ACTIQN:

Borate until a K,7f f .95 is reached.

SURVEllLANCE RE0VIREMENT 4.9.18.1 Ensure that all fuel assemblies to be placed in Region II (as shown in Figure 3.9-2) of the spent fuel pool are within the enrichment and burn-up limits of figure 3.9.1 by checking the assembly's design and burn-up documen-tation.

4.9.18.2 Ensure that the contents of each consolidated fuel storage box to be placed in Region II (as shown in figure 3.9-2) of the spent fuel pool are within the enrichment - and burn-up limits of Figure 3.9-3 by checking the design and burn-up docuraentation for storage box contents.

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L MILLSTONE - UNIT 2 3/4 9-22 Amers ient No. Jp9. JJ/

0043

REFUELING OPERATIONi SPENT FUEL-POOL - STORAGE PATTERN LIMITING CONDITION FOR OPERATION l 3.9.19 Each STORAGE PATTERN of the Region !! spent fuel pool racks shall require either.that:

(1) A cell' blocking device is installeJ in those cell locations shown in Figure 3.9-2; or  ;

(2) If a celi blocking device has been removed, all cells of the STORAGE PATTERN must have consolidated fuel in them, including the formerly blocked location; or (3) Meet both (a) and (b):

(a) If a cell biocking device has been removed, all cells of the STORAGE PATTERN must have consolidated fuel in them except the formerly blocked location.

(b) The formerly-blocked location is vacant and a consolidated fuel box or cell blocking device is immediately being placed into the formerly blocked cell.

APPLICABILITY: Fuel in the Spent Fuel Pool ACTION:

Take immediate action to comply with either 3.9.19(1), (2), or (3). '

SURVEILLANCE REQUIFEMENTS 4.9.19 Verify' that 3.9.19 is satisfied at the following times.

(1) Prior to removing a cell blocking device

-(2) Prior to removing a consolidated fuel storage box .from its Region II storage location.

MILLSTONE - UNIT 2 3/4 9-26 Amendment No JJ/

0044

REFUEllNG OPERATIQH1 SPENT FUEL POOL - CON 1QLIDATf0N LIMITING CONDITION FOR OPERATION

' 3.9.20 Prior to consolidation of spent fuel assemblies, the candidate fuel assemblies must have decayed for at least 5 years.

APPLICABILITY: During all consolidation operations.

e_G1103:

With the requirements of the above specification not satisfied, replace candidate assembly with an appropriate substitute or suspend all consolidation activities.

SURVEILLANCE REQUIREMENTS 4.9.20 -The decay time of all_ candidate fuel assemblies for consolidation shall be determined' to be greater than or equal to five years within 7 days prior to moving the fuel assembly into the consolidation work station.

4 MILLSTONE - UNIT 2 3/4 9-27 Amendment No. JJ/, J/E 0045

REFUELING OPERATIONS BSES 3/4.9.13- STORAGE P00L RADIATION MONITORING The OPERABILITY of the - storage pool radiation monitors ensures that sufficient radiation monitoring capability is available to detect excessive radiation levels resulting - from 1) the inadvertent lowering of the storage pool water level or 2) the release of activity from an irradiated fuel assembly.

3/4.9.14 & 3/4.9.15 STORAGE P0OL AREA VENTILATION SYSTEM The limitations on the storage pool area ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through'the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

3/4.9.16 SHIELDED CASK The limitations of this specification ensure that-in an event of a cask  ;

tilt accident 1) the doses . from ruptured fuel assemblies will be within the '

assumptions of the safety analyses, 2) K eff will remain s .95.

3/4.9.17 MOVEMENT OF FUEL OVER REGION 11 RACKS The limitations of this specification ensure that, in the event of a fuel assembly or a consolidated fuel storage box drop accident into a Region 11 rack location completing a 4-out-of-4 fuel assembly geometry, Keff will remain i s 0.95. I 3/4.9.18 SPENT FUEL P0OL - REACTIVITY CONDITION The limitations described by figure 3.9-1 ensure that the reactivity of fuel assemblies and consolidated fuel storage boxes, introduced into the Region Il spent fuel racks, are conservatively within the assumptions of the safety analysis.

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MILLSTONE - UNIT 2 8 3/4 9-3 Amendment No. # , J M , JJJ 0046

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4 REFUELING OPERATIDES BASES 3/4.9.19 SPENT FUEL P0OL - STORAGE PATTERN The limitations of this specification ensure that the reactivity conditions of the Region 11 storage racks and spent fuel pool K*ff will remati, less than or equal _to 0.95.

The Cell Blocking Devices in the 4th location of the Region 11 storage racks are designed to prevent inadvertent placement and/or storage of fuel assemblies in the blocked locations. The blocked location remains empty to provide the flux trap to maintain reactivity control for fuel assembly storage in any adjacent locations. Only loaded consolidated fuel storage boxes may be placed and/or stored in the 4th location, completing the STORAGE PATTERN, after all adjacent, and diagonal, locations are occupied by loaded consolidated fuel storage boxes.

3/4.9.20 SPENT FUEL POOL - CONSOLIDATION y The limitations of these specifications ensure that the decay heat rates and radioactive inventory of the candidate fuel assemblies for consolidation are conservatively within the assumptions of the safety analysis.

MILLSTONE - UNIT 2 B 3/4 9-4 Amendment No. JJJ 0047

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LIMITING SAFETY SYSTEM SETTING 1 BASES _

Thermal Marcin/ Low Pressure (Continued)

The trip is initiated whenever the reactor coolant system pressure signal drops below either 1850 psia or a computed value as described below, whichever is higher. The computed value is a function of the higher of AT power or ,

neutron power, reactor inlet temperature, the number-of reactor coolant pumps '

-operating and the AXIAL SHAPE INDEX. The minimum value of reactor coolant

- flow rate, the maximum AZIMUTHAL POWER TILT and the maximum CEA deviation permitted for continuous operation are assumed in the generation of this trip function. In- addition, CEA group sequencing in accordance with Specifications 3.1.3.5 and 3.1.3.6 is assumed. Finally, the maximum insertion of CEA banks which can occur during any anticipated operational occurrence prior to a Power Level High trip is assumed.

Thermal Margin / Low Pressure trip setpoints are derived from the core ,

safety limits through application of appropriate allowances for equipment response time measurement uncertainties and processing error. A safety margin is provided which includes: an allowance of 5% of RATED THERMAL POWER to compensate for potential power measurement error; an allowance of 2*F to compensate for potential temperature measurement uncertainty; and a further-allowance of 74 psi to compensate for pressure measurement error, trip system l processing error, and time delay associated with providing effective termina-tion of the occurrence that exhibits the most rapid decrease in margin to the safety-lim;t. The 74 psi allowance is made up of a 5 psi bias, a 19 psi pressure measurement allowance and a 50 psi time delay allowance.

Loss of Turbin2 A Loss of Turbine trip causes a direct reactor trip when operating above 15% of RATED THERMAL POWER. This trip provides turbine protection, reduces the severity of the ensuring transient and helps avoid the lifting _of the main steam line safety valves during the ensuing transient, thus extending the service life of these values. No credit was taken in the accident analyses for operation of this trip. Its functional capability at the specified trip setting is required to enhance the overall reliability of the Reactor Protec-tion System.

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l MILLSTONE - UNIT 2 B 2-7 Amendment No. J.8, EJ, JJ9 0048 I-i'

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