ML20210C609
ML20210C609 | |
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Site: | Millstone ![]() |
Issue date: | 07/16/1999 |
From: | NORTHEAST NUCLEAR ENERGY CO. |
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NUDOCS 9907260105 | |
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Docket No. 50-336 B17772 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Relocation of Selected Technical Specifications Related to Refueling Operations to the Technical Requirements Manual Marked Up Pages July 1999 9907260105 990716 PDR ADOCK 05000336 P
INDEX 11MITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PJE 3/4'.9 REFUELING OPERATIONS 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 i
3/4.9.5 NICATIONS........................................
3 9-5 3/4.9 CRANE OPERABI Y
CONTAINMENT B ING...............
3/4 9-6 ga
,3/.9.7 CRANE T
- SPENT FUEL ST E POOL BUILDING....
3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION................
3/4 9-8 3/4.9.9 CONTAINMENT RADIATION MONITORING........................
3/4 9-9 3/4.9.10 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................
3/4 9-10 l
3/4.9.11 WATER LEVEL - REACTOR VESSEL............................
3/4 9-11 l
3/4.9.12 STORAGE POOL WATER LEVEL................................
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 VENTILATION SYSTEM - FUEL STORAGE.....
3/4 9-16 3/4.9.16. SHIELDED CASK...........................................
3/4 9-19 3/4.9.17 MOVEMENT OF FUlt. IN SPENT FUEL POOL......................
3/4'9-21 3/4.9.18 ' SPENT FUEL POOL - REACTIVITY CONDITION..................
3/4 9-22 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN.......................
3/4 9-26 3/4.9.20 SPENT FUEL POOL - CONSOLIDATION.........................
3/4 9-27 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN........................................
3/4 10-1 l
3/.4.10.2 GROUP HEIGHT AND INSERTION LIMITS......................
3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY..
3/4 10-3 i
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MILLSTONE - UNIT 2 IX Amendment No. ES, Jell,. JE9, 117,in.114 t
INDEX Nc'/emb~ 3,1005
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v sAStS SECTION PA_qE A
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.....................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION B 3;8 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SERVICf. WATER SYSTEM B 3/4 7-4 3/4.7.5 Floor, LEVEL......................
B 3/4 7-4 3/4.7.6 CONir.0L ROOM EMERGENCY VENTILATION SYSTEM B 3/4 7 4 3/4.7.7 5EALED SOURCE CONTAMINATION B 3/4 7-5 3/4.7.B SNUBBERS B 3/4 7-5 3/4.7.9 DELETED........................
B 3/4 7-6 3/4.7.10 DELETED........................
B 3/4 7-7 3/4.7.11 ULTIMATE HEAT SINK B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEV4 B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................
B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT PENET TI 5
B 3/4 9-1 3/4.9.5 C0tt;UNICdTIONS DEWD.
B 3/4 9-1 3/4.9.6 C41ANE opera 0!LITY CONTAIM"ENT CUIL B 3/4 9-2 3/4.9.7 EPANE Tra"EL--SPENT TUEL STORAGE BUIL8ENG D..B 3/4 9-2 3/4.9.B SHUTDOWN COOLING AND COOLING RECIRCULATION B 3/4 9-2 i
MILLSTONE - UNIT 2 KIII Amendment No. 7). 77 J7 77. JPF.
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REEUEOIid OPERATIONS SPENT FUEL POOL. TEMPERATURE j
LIMITING CONDITION FOR OPE ION 3.9.3.2 The spent fue pool bulk temperature sh be maintained at less th
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cr equal to 140*F.
APPLICABILITY: W never irradiated fuel is tored'in the spent fuel po ACTION:
With the bove conditions not'sa fied; Immediate initiate ctions to restore the spen fuel pool tempera-ture to less tha or equal to 140*F, and
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b.
Within one r, suspend all fuel.movem in the spent fuel pool, and c.
Withi n-
' u., isolate the spe fuel pool cleanup demineral' and rs, d.
t least once pe.- 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ecord the spent fuel pool b tempera-ture.
SU ILLANCE REQUIREMENTS h.3.2 The spent fuel bulk temperature shall be than or equal to 140*F least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
erified to be less W
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.HILLST0fiE - UNIT 2 3/4 9-3a Amendment No. JJf,/hf
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REFUEllHG OPERATIONS
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DECAY TIME l
LIMITING CONDITI0t OR OPERATIO:t
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3.9.3.3 e reactor shall be maintained i DE 5 or 6 until the most recen 1/3 cor offload
- in the spent fuel pool as decayed for greater than 504 hour0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from subcriticality.
/ APPLICABILITY: MODES 5 and 6 th the most recent 1/3 core offl d*
decayed les than 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from subtriticali ACTION:
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- With the above nditions not satisfied, iranediat,. initiate actions to restore the actor to FDDE 5 or 6.
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SU ILLANCE REOUIR$1E!TS
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j 4.9.3.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pri to entry into MODE 4. verify th the most recent 1/3 core offload
- h decayed for greater than 504 ho s from sub-criticality.
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- For the purposes this specification, the most r ent 1/3 core offload
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is defined as e fuel '"-iles discharged at tha end of the most recent fuel cycle, his specification does not appl to partial mid-cy.cle discharge resulting f rom defective or dam,,ed fuel if the total decay
. beat lo on the spent fuel pool coolin ystem resulting from such disc r9e is less than the total deca neat load of the spent fue pool at 04 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter subtriticality the most recent 1/3 core load.
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(+L44" MILLSTOME - UNIT 2 3/4 9-3b Amendment No.
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REFUELING OPERATIONS COMMUNICATIONS.*-
- / -
LIMITING CONDI ONFOROPERATION
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3.9.5 rect 'comunications
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room d personnel at the r 11 be maintained be the control wit n the reactor pressur eling station durin fuel or CEA movement vessel.
PLICABILITY: MODE 6
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ACTION:
When direct c nications between e 'ontrol room and sonnel at the refueling st ion cannot be maint ned, suspend all oper ions i'nvolving c
feel or C movement within the eactor pressure vesse.
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SURVEILLANC QUIREMENTS I
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4.9.5 Direct comunications s._
efueling station shall tween the control r and personnel at the rt of and at least onc e demonstrated with' one hour prior to the s
ithin the reactor pres per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during ~ uel or CEA moieinent re vessel.
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MILLSTONE - UNIT 2
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REFUEL-ING OPERATIONS-
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CRANE OPERABILITY - CONTA ENT BUILDING 2
LIMITING CONDIT10lkFOR OPERATION
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3.9.6 T containment building cra (refuelingmachine) sed for moveme of fuel assemblies shall OPERABLE with:
a.
A minimum capacit f 1600 pounds "in th uel only" region, b.
An overload off limit < 1700 po s "in the fuel only"
- region, c.
A mi um capacity of 2900 nds'"in the fuel plus st" re on, and d.
An overload cut off ' it < 3000 pounds "in e fuel plus hoist" region.
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PLICABILITY: 00 RING
'DiENT OF FUEL ASSEMB S.
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ACTION:
With the requ ements of the above ification not satisf d, suspend all crane o rations involving t of fuel assembli SURVEILLANCE REQU ENTS
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4.9.6 T
containment building c es used for moveme of fuel assem-blies all be demonstrated OPE LE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> rior to the start of ving fuel assemblies by rfonning applicable ad tests of at 1
st 1600 and 2900 pounds nd demonstrating appUcable automatic load cut offs when the crane ads exceed 1700 and 0 pounds.
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MILLSTONE - UNry 7 3/4 9-6 XX
x 4.
REFUELING OPERATIONS
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CRANE TRAVEL - SPENT FUEL ORAGE POOL BUILDING 1
LIMITING CONDITION R OPERATION
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3 3.9.7 Loa in excess of 1800 pounds, wi the exception of the conso dated fuel sto ge box, shall be prohibited f assemb es in the storage pool.
a travel over irradiated fu 1
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PLICABILITY: DURING ALL C
~ OPERATION.
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AGTION:
With the require s of the above specificati not satisfied, place load in a safe condi on.
SU EILLANCE REQUIREMENTS
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4.9.7 Crane interloc with loads in exces and/or physical stops whic revent crane travel be demonstrated of 1800 pounds over irradia fuel assemblies sh fuel handling RABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior o initiation of irra 'ated fuel hand 11 erations and at least once 7 days during irrad' ted operations.
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s MILLSTONE - UNIT 2 3/4 9-7 AmendmentNo.g//
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3/4.9 REFUELING OPERATIONS C
5 98 BASES Jun 25 -1998 3/4.9.14 BORON CONCENTRA, TION 21 the reactor will remain subtritical during CORE ALTER 1
water volume having direct access to the reactor vessel. suffic consistent with the initial conditions assumed for the baron in the accident analyses access to the reactor vessel is achieved by determining boron the refueling canal.. The refueling canal is defined as the entire length o pool stretching from refuel pool through transfer canal to spent fuel pool of the water volumes in the steam generators and con low as 1300 ppa. _ During REFUELING an'd/or mix with the water in the reactor vessel.
connecting piping), g, shutdown cooling system (including reactcr vesse and connecting pipin and refueling pool shall be maintained greater than 1950 ppm.
the shutdown cooling system with the water volumes f
)
connecting piping.
This analysis demonstrates that, in the unlikely event in and which all of the water in the steam generators and connecting piping
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boron concentration will remain greater than the req s em concentration.
(
The surveillance requirement to verify that the boron concentration in steam generators is greater than 1300 ppm prior to entering MODE 6 i with the assumptions of the boron dilution calculation.
only located on the cold leg side of the steam generators.The sample points are are representative of the water volumes in the steam generators (both hot an cold legs) and their connecting piping, based on the fact that uniform these water volumes at a boron concentration of approximately 1320 pp ot. curred prior to shutting off the reactor coolant pumps.
boron concentration greater.then or equal to 1320 ppm. rea In March 1996, the of the water'in the steam generators and connecting piping is greater than 1300 ppm.
3/4.9.2' INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures tha redundant monitoring capability is available to datect changes in the'reactiv-ity condition of the core.
3/4.9.3 DECAY TIME The minimu, requirement for reactor subtriticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the radioac tive decay of the short-lived fission products.
with the assumptions used in the accident analyses.This decay time is consistent MILLSTONE - UNIT 2 0300 B 3/4 9-1 Amendment No. 77, J y, pp, 7pJ, Revined by NitC let t es dated Novesnber 24, 1998
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h BAIES (continu,ed)
The requir ent that the ent fuel pool b temperature be aintained below 140*F en res that hig water temperatur will not degrade esin in the spent fuel p 1 deminerali rs and that the perature and h dity above the Pool are e patible with ersonnel comfort nd safety requi nts. Addition all, the equirement e ures that the d ign temperature the fuel pool c o ing ystem, liner uilding structu s, and racks are ot exceeded.
he requirem for the react to remain in 5 or 6 until t most re nt 1/3 core fload has deca d 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> ensur s that alternat cooling available d ing this time cool the spent f 1 pool should a ailure ccur in the pent fuel pool olin system. Th shutdown coolin (SDC) i system is igh capacity s tem; t at is, on train is suffic nt to cool i
both the re and the s>e fuel pool shoul a failure occur n the spent fuel i
pool co ing system wit n 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from eactor shutdown 3/4.9.4 CONTAINMENT PENETRATIONS i
The requirements on containment penetration closure and OPERABILITY l
ensure that a release of radioactive material within containment will be restricted from leakage to th6 environment. The OPERABILITY and closure I
restriction: are sufficient to restrict radioactive material. release from a fuel element rupture based upon the lack of containment pressurization poten-tial while in the REFUELING MODE.
3/4.9.5 CC';^JEttdO"'
The quirement for communications capab ity ensures tha refueling station ersonnel can promptly informed significant ch ges in the
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facili status or c e reactivity condit n during fuel or EA movement thin the r actor pressur vessel.
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{IgLSTONE-UNIT 2 8 3/4 9-la Amendment No. 77 7 #. #9. M
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kusy d,}995 REFUELING OPERATIONS BASES letch 3/4.9.6 Ca" E 0"E",'"ILI"l - 00'.%',i""En E MING The OPE I ITY require ts of the cranes sed for moveme of fuel as m-blies ensur that:
1 ea crane has suffi ent load capaci to lift a uel -
- elcment,
- 2) the co)renternals and p sure vessel are otected fr exces-sive lif ng force in t event they are advertently en edtIuring
^ ting cperat ns.
3/4.9.7 CP."ME T"* VEL EPE.'" FUEL NO"'Or %'IL0lbrkCUh The res iction on 50 ment of loads in cess of the nom dal weight o a g/
fuel asse y and CEA o irradiated fuel ssemblies ensur that no mor than f
the con ts of one f assembly will ruptured in the vent of'a f hand- /
ling cident. Spe fic analysis has en performed fo the drop of consoli-dat fuel storag box on an intact uel assembly.
s assumptio is consistent the activify release assume n the accident alyses.
w 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation at
{
2 1000 gpm ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, (2) sufficient coolant circulation is maintained through the reactor core to minimize the efftets of a boron dilution j
incident and prevent. boron stratification, and D) is consistent with boron l
i dilution analysis assumptions.
i The requirement to have two shutdown cooling loops OPERABLE when the refuel pool is unavailable as a heat sink ensures that a single failure of the operating l
shutdown cooling loop will not result in a complete loss of decay heat removal j
capability.
With the reactor vessel water level at or above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is readily available for core cooling.
Adequate time is thus available to initiate emergency procedures to provide core cooling in the event of a failure of the operating shutdown cooling loop.
3/4.9.9 and 3 /4.9.10 CONTAINMENT RADIATION MONITORING ANL CONTAINMENT VALVE ISOLATION SYSTEM The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OFERABItITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the environment, MILLSTONE - UNIT 2 B 3/4 9-2 A:nendment No. 77, 7J. JJ7./M 0117
Docket No. 50-336 B17772 i
J Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Relocation of Selected Technical Specifications Related to Refueling Operations to the Technical Requirements Manual Retyped Pages i
6
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July 1999 l
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INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION ggg 3/4.9 REFUELING OPERATIONS 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 DELETED......................... 3/4 9-5 3/4.9.6 DELETED........................
3/4 9-6 3/4.9.7 DELETED........................
3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION.......
3/4 9-8 3/4.9.9 CONTAINMENT RADIATION MONITORING 3/4 9-9 3/4.9.10 CONTAINMENT 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 P0OL WATER LEVEL 3/4 9 - 12 3/4.9.13 STORAGE P00L RADIATION MONITORING...........
3/4 9-13 3/4.9.14 STORAGE P00L AREA VENTILATION SYSTEM - FUEL MOVEMENT 3/4 9-14 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM - FUEL STORAGE..
3/4 9-16 3/4.9.16 SHI ELDED CASK.....................
3/4 9-19 3/4.9.17 MOVEMENT OF FUEL IN SPENT FUEL P0OL..........
3/4 9-21 3/4.9.18 SPENT FUEL P0OL - REACTIVITY CONDITION 3/4 9-22 3/4.9.19 SPENT FUEL P0OL - STORAGE PATTERN...........
3/4 9-26 3/4.9.20 SPENT FUEL P0OL - CONSOLIDATION 3/4 9 - 2 7 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN 3 / 4 10 - 1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS 3/4 10 - 2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY,. 3/410-3 l
MILLSTONE - UNIT 2 IX Amendment No. 77, Jpf, 197, 0475
(([e [ffe [fke 1
4
INDEX BASES SECTION pgg 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.....................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PCESSURE/ TEMPERATURE LIMITATION B 3/4 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-4 3/4.7.5 FLOOD LEVEL......................
B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM B 3/4 7-4 3/4.7.7 SEALED SOURCE CONTAMINATION B 3/4 7-5 3/4.7.8 SNUBBERS B 3/4 7-5 3/4.7.9 DELETED........................
B 3/4 7-6 3/4.7.10 DELETED........................
B 3/4 7-7 3/4.7.11 ULTIMATE HEAT SINK B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................
B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS B 3/4 9-1 3/4.9.5 DELETED........................
B 3/4 9-1 3/4.9.6 DELETED........................
B 3/4 9-2 3/4.9.7 DELETED...............
B 3/4 9-2 l
3/4.9.8 SHUTDOWN COOLING AND COOLING RECIRCliAiiON B 3/4 9-2 MILLSTONE - UNIT 2 XIII Amendment No. M. 77. #. M. 1 #.
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i NI,L,LSTONE - UNIT 2 3/4 9-3a AmendmentNo.JJJ,JJp
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i NILLSTONE - UNIT 2 3/4 9-6 Amendment No.
0478
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THIS PAGE INTENTIONALLY LEFT BLANK NILLSTONE - UNIT 2 3/4 9-7 Amendment No. JJ/,
0478 I
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ntrutLING OPERATIONS Novcober 24, 1998 BASES TSCR '-5-98 3/4.9.1 BORON CONCENTRATION
- 1) the reactor will remain subcritical during CORE ALTER
- 2) sufficient boron concentration is maintained for reactivity control in
, and water volume having direct access to the reactor vessel.
consistent with the initial conditions assumed for the bo e
in the accident analyses.
access to the reactor vessel is achieved by determining bar the refueling canal. The refueling canal is defined as the entire leng pool stretching from refuel pool through transfer canal to spent fuel of of the water volumes in the steam generators and low as 1300 ppm.
on During REFUELING an'd/or CORE ALTERATIONS, the water volum in the steam generators and ' connecting piping are stagnant an mix with the water in the reactor vessel.
and connecting piping, shutdown cooling system (including reactor ve connecting piping), and refueling pool shall be maintained greater than 195 ppm.
the shutdown coolinA boron dilution analysis has been performed which ac connecting piping. g system with the water volumes from the steam generators and on of This analysis demonstrates that, in the unlikely event in which all of the water in the st the water in the shutdown cooling system, the resulting shutdown coolie boron concentration will remain greater than the required refueling b ng system concentration.
steam generators is greater than 1300 ppm prior to e with the assumptions of the boron dilution calculation.
e only located on the cold leg side of the steam generators.The sample points are ent are representative of the water volumes in the steam generators (both ho cold legs) and their connecting piping, based on the fact that un these water volumes at a baron concentration of approximately 132 occurred prior to shutting off the reactor coolant pumps.
pm had boron concentration greater.than or equal to 1320 ppm In March 1996, the of the water'in the steam generators and connecting piping is greater 1300 ppm.
The boron concentration 3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensure redundant monitoring capability is available to detect changes in the're ity condition of the core.
c v-3/4.9.3 DECAY TIME irradiated fuel ensures that sufficient time has elapsed tive decay of the short-lived fission products.
e radioac-with the assumptions used in the accident analyses.This decay time is consistent MILLSTONE - UNIT 2 0300 B 3/4 9-1 Amendment Ho. 77, Jy, pp. 7pf, Revised by NHC Jet.tcr dated Novesnber 24, 1998 i
j
e b
BASES (continued)
I l
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization poten-tial while in the REFUELING MODE.
3/4.9.5 DELETED NILLSTONE - UNIT 2 B 3/4 9-la Amendment No. 77, JJJ, JJP, 0479 h8
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REFUELING OPERATIONS BASES 3/4.9.6 DELETED i
l 3/4.9.7 DELETED i
3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation at
- t 1000 gpm ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, (2) sufficient coolant circulation is ma;ntained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification, and (3) is consistent with baron dilution analysis assumptions.
The requirement to have two shutdown cooling loops OPERABLE when the refuel pool is unavailable as a heat sink ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel water level at or above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is readily available for core cooling. Adequate time is thus available to initiate emergency procedures to provide core cooling in the event of a failure of the operating shutdown cooling loop.
3/4.9.9 and 3/4.9.10 CONTAINMENT RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the environment.
NILLSTONE - UNIT 2 B 3/4 9-2 Amendment No. 77, 7/, JJ7, J77, 0479