Text

Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM
	ML20210C609
Person / Time
Site:	Millstone
Issue date:	07/16/1999
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20210C606	List: B17772, Application for Amend to License DPR-65,relocating Selected TS Re Refueling Operations & Associated Bases to Plant TRM; ML20210C609;
References
	NUDOCS 9907260105
	Download: ML20210C609 (21)
	v • d • e

..

'~

Docket No. 50-336 B17772 Attachment 3 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 PDR

' 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 3 9-5 i 3/4.9.5 NICATIONS .. .................... ..................

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 l

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 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

p .,

l MILLSTONE - UNIT 2 IX Amendment No. ES, Jell,. JE9,

"" 117,in.114 t

l INDEX Nc'/emb~ 3,1005

~~ ' v sAStS SECTION A

PA_qE 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 3/4.7.10 DELETED . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-6 3/4.7.11 DELETED . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-7 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 om Amendment No. 7). 77 J7 77. JPF.

J$y.pty

\

l

G mbsr 26, __ R--

REEUEOIid OPERATIONS j

SPENT FUEL POOL. TEMPERATURE LIMITING CONDITION FOR OPE ION 3.9.3.2 The spent fue pool bulk temperature sh

~

cr equal to 140*F. be maintained at less th 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

/

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ture. ecord the spent fuel pool b tempera-SU ,

ILLANCE REQUIREMENTS h.3.2 The spent fuel than or equal to 140*F bulk temperature shall be least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . erified to be less u,- n ., su ,.,

. ~. -n, w w W

A A #

1

)

.HILLST0fiE - UNIT 2 3/4 9-3a Amendment No. JJf,/hf

-Q----

C l REFUEllHG OPERATIONS -^

DECAY TIME l LIMITING CONDITI0t OR OPERATIO:t

/ /

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 0.14 hours 8.333333e-4 weeks 1.91772e-4 months from subcriticality. ,

/ APPLICABILITY: MODES 5 and 6 th the most recent 1/3 core offl d*

decayed les than 504 hours0.00583 days 0.14 hours 8.333333e-4 weeks 1.91772e-4 months from subtriticali .

I ACTION: l

\

With the above nditions not satisfied, iranediat ,. initiate actions to restore the actor to FDDE 5 or 6.

1

. \

SU ILLANCE REOUIR$1E!TS

,s / /

j -

4.9.3.3 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

i l

\ l

For the purposes this specification, the most r ent 1/3 core offload /

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months af ter subtriticality the most recent 1/3 core load.

- e -

(+L44" MILLSTOME - UNIT 2 3/4 9-3b Amendment No. M

. REFUELING OPERATIONS COMMUNICATIONS.*- :/ -

LIMITING CONDI ONFOROPERATION

/

3.9.5 room rect 'comunications 11 be maintained be

?

d personnel at the r the control wit n the reactor pressur vessel. eling station durin fuel or CEA movement PLICABILITY: MODE 6

/

ACTION: .

When direct c nications between c e 'ontrol room and sonnel at the refueling feel or C st ion cannot be maint ned, suspend all oper ions i'nvolving movement within the eactor pressure vesse .

/ .

SURVEILLANC I QUIREMENTS

/

4.9.5 s._ '

the Direct comunications tween the control r and personnel at efueling station shall rt of and at least onc per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during ~with' e demonstrated one hour prior to the s -;

, ithin the reactor pres re vessel. uel or CEA moieinent

/

, d y.ep t win

Th i s pay inhdio*#, ler t- dan C'

.P -

E h

h MILLSTONE - UNIT 2 .n 3/49-5 h

s b

N

/

4 o

REFUEL-ING OPERATIONS-

^

CRANE OPERABILITY - CONTA ENT BUILDING 2

LIMITING CONDIT10lkFOR OPERATION /

/ /

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. ~

, PLICABILITY: 00 RING 'DiENT t OF FUEL ASSEMB S.

/

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

- /

4.9.6 T containment building c es used for moveme blies of fuel assem-all be demonstrated OPE LE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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.

S

^ g'

)

I u

p -

- Y c e k <.

w;g An. '

FS p.~4, & k s

)

MILLSTONE - UNry 7 3/4 9-6 XX

x 4.

REFUELING OPERATIONS

)

CRANE TRAVEL - SPENT FUEL ORAGE POOL BUILDING '

. . . . . . 1 LIMITING CONDITION R OPERATION

/

3 3.9.7 Loa in excess of 1800 pounds, wi fuel sto ge box, shall be prohibited f the exception of the conso dated a travel over irradiated fu 1

assemb es in the storage pool. l

(

/ PLICABILITY: DURING ALL C ~ OPERATION.

AGTION:

With the require s of the above specificati in a safe condi on. not satisfied, place load SU EILLANCE REQUIREMENTS

/

4.9.7 Crane interloc and/or physical stops whic with loads in exces of 1800 pounds over irradia revent crane travel be demonstrated fuel assemblies sh fuel handling RABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior o initiation of irra 'ated fuel hand 11 erations operations.

and at least once 7 days during irrad' ted t

V ye pte. &k Tus pay. c3e %% ff5 WA bM "

.A . f s

MILLSTONE - UNIT 2 3/4 9-7 AmendmentNo.g//

I

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 i 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 C mix with the water and connecting pipin in the reactor vessel.

connecting piping), g, shutdown cooling system (including reactcr vessel ppm. and refueling pool shall be maintained greater than 1950

/

) the shutdown connecting piping. cooling system with the water volumes and fr This analysis demonstrates that, in the unlikely event in

>. which all of the water in the steam generators and connecting piping m boron concentration will remain greater than concentration.

s em the req

(

The surveillance requirement to verify that the boron concentration in steam generatorsofisthe with the assumptions greater than 1300 boron dilution ppm prior to entering MODE 6 i 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. In March 1996, the boron concentration greater .then or equal to 1320 ppm. rea of 1300the water'in the steam generators and connecting piping is greater than ppm.

3/4.9.2' INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures tha redundant ity condition monitoring of the core. capability is available to datect changes in the'reactiv-3/4.9.3 DECAY TIME The minimu, requirement for reactor subtriticality prior to movement of irradiated tive decay offuel ensures that the short-lived sufficient fission products.time has elapsed to allow the radioac 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

~

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 0.14 hours 8.333333e-4 weeks 1.91772e-4 months 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 0.14 hours 8.333333e-4 weeks 1.91772e-4 months 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 l 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 facili promptly informed significant ch ges in the status or c e reactivity condit n during fuel or EA movement thin [

the r actor pressur vessel.

l t

1 l

p '

{IgLSTONE-UNIT 2 8 3/4 9-la Amendment No. 77 7 #. #9. M

i.

kusy d,}995 REFUELING OPERATIONS BASES 3/4.9.6 Ca" E 0"E",'"ILI"l - 00'.%',i""En E MING letch The OPE I ITY require ts of the cranes sed for moveme of fuel as blies ensur that: 1 ea crane has suffi ent load capaci to lift a uel -

m-elcment, 2) the co)renternals and p sure vessel are otected fr exces-sive lif ng force in t event they are advertently en cperat ns. edtIuring ^ ting 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 fuel asse y and CEA o irradiated fuel ssemblies ensur g/

the con ts of one f assembly will that no mor than f ling cident. Spe fic analysis ruptured in the vent of'a f hand- /

has en performed fo the drop of dat fuel storag box on an intact uel assembly. consoli-w the activify release assume n the accident alyses. s assumptio is consistent 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 j maintained through the reactor core to minimize the efftets of a boron dilution i incident and prevent. boron stratification, and D) is consistent with boron dilution analysis assumptions. l i

The requirement to have two shutdown cooling loops OPERABLE when the refuel l

pool is unavailable as a heat sink ensures that a single failure of the operating j 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 SYSTEM VALVE ISOLATION /4.9.10 CONTAINMENT RADIATION MONITORING ANL CONTAINMENT 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 0117 B 3/4 9-2 A:nendment No. 77, 7J. JJ7./M

Docket No. 50-336 B17772 i I

J Attachment 4 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 l

i 6

)

July 1999 l

s

.~ .. ..

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 l

MILLSTONE - UNIT 2 IX Amendment No. 77, Jpf, 197, l 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 #.

un 1# 1H.

1 i

THIS PAGE INTENTIONALLY LEFT BLANK i

i l

i 3/4 9-3a AmendmentNo.JJJ,JJp NI,L,LSTONE

, - UNIT 2

THIS PAGE INTENTIONALLY LEFT BLANK i

l i

t l

l l

l 3/49-3b Amendment No. fff, NigLSTONE-UNIT 2

l THIS PAGE INTENTIONALLY LEFT BLANK l

i NILLSTON:: - UNIT 2 3/4 9-5 Amendment No.

o47s l

l

e ,

i l

THIS PAGE INTENTIONALLY LEFT BLANK 1

i NILLSTONE - UNIT 2 3/4 9-6 Amendment No.

0478

~ .

THIS PAGE INTENTIONALLY LEFT BLANK NILLSTONE - UNIT 2 3/4 9-7 Amendment No. JJ/,

0478 I

l

c ,,

o . :,

ntrutLING OPERATIONS Novcober 24, 1998 BASES TSCR '-5-98 3/4.9.1 BORON CONCENTRATION

1) the reactor will remain subcritical during , and CORE ALTER

2) sufficient water borondirect volume having concentration access to the is maintained reactor vessel. for reactivitye control in consistent with the initial conditions assumed for the bo 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 canalofto spent fuel .

of the water volumes in the steam generators low as 1300 ppm. on and During REFUELING an'd/or CORE ALTERATIONS, the water volum in the mix withsteam the water generators in the reactorand ' connecting piping are stagnant an 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 on of which ac connecting piping. g system with the water volumes from the steam generators and which all of the water Thisinanalysis the st demonstrates that, in the unlikely event in the water in the shutdown cooling system, the resulting shutdown coolie ng system boron concentration will remain greater than the required concentration. refueling b steam generators is greater than 1300 ppm eprior to e with the assumptions of the boron dilution calculation. ent 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 ho cold legs) and their connecting piping, based on the fact that uni these water volumes at a baron concentration of approximately 132 pm had occurred prior to shutting off the reactor coolant pumps. In March 1996, the boron concentration greater .than or equal to 1320 ppm.

of 1300the ppm.water'in the steam generators and connecting The boron concentration piping is greater 3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensure redundant ity condition of monitoring the core. capability is available to detect changes c v-in the're 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 0300 - UNIT 2 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 l

I

, NILLSTONE - UNIT 2 B 3/4 9-la Amendment No. 77, JJJ, JJP, 0479 h8

~

j REFUELING OPERATIONS BASES l

3/4.9.6 DELETED i I

1 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 *

ML20210C609

Text

Navigation menu

Search