Text

Ltr to All Operating PWRs Requesting Amend to Tech Specs Re Decay Heat Removal Capability.Amend Is Necessary to Provide Permanent long-term Assurance That Redundancy Will Be Maintained
	ML20126D835
Person / Time
Site:	05000000
Issue date:	06/11/1980
From:	Eisenhut D; Office of Nuclear Reactor Regulation
To:	; AFFILIATION NOT ASSIGNED
Shared Package
ML19320D046	List: ML20126D835;
References
	GL-80-53, TAC-42092, TAC-42112, TAC-42126, TAC-48832, NUDOCS 8007180479
	Download: ML20126D835 (1)
	v • d • e

o O a o

. s* * ' a ve

.* .'s. UNITto sTATts

! 3, ,, , g 7 NUCLEAR REGULATORY COMMISSION

, ; q#/ ! WASHINGTON, O. C. 20$58 is,M vF./f /

'"** June 11,1980 TO ALL CPE?AT!NG PRESSURIZED WATER REACTORS (PWR'S)

Gentlemen:

This letter transmits the request that you amend the Technical Specifications (TSs) for your facility with respect to reactor decay heat removal capability.

The basis for our reouest is founded in a number of events that have occurred at coerating PWR facilities where decay heat removal capability has been seriously degracea due to inadequate administrative controls utilized wnen the plants were in shutdewn modes of operation. One of these events occurred at the Davis-Besse, Unit No.1 plant on Acril 19, 1930, which was described in !! Information tiotice 80-20 dated May S.1980. In IE Bulletin 80-12 dated May 9,1980, you were requested to imediately implement administrative con-trols which would ensure that prcper means are available to provide redundant cetnods of decay heat removal. While the function of the bulletin was to effect immediate action with regard to this problem, we consider it necessary that sn amencment of your license be made to provide for pemanent long tem assurance that redundancy in decay heat removal capability will be maintained.

You are requested to propose TS changes for your facility that provide for c redundancy in decay heat removal capability for your plant (s) in all modes of coaration. To assist you in preparing your submittal, we have enclosed a c::y of Model tSs whien would provide an acceptable resolution of our c:ncarn. Your re:esal should use the enclosure as a guide and should ine'ude an a:prcorf ate Safety Analysis as a basis.

It is requested that you submit your proposed TSs with the basis within 120 days of receipt of this letter. If you have any questions about this matter, please c:ntact your Project Manager.

Sincerely,

=

Carrell G. E! :e.nn ., /r Division of L'icensing

Enclosure:

Model TSs c:ncerning Cocay Heat .

Rem: val Ca: ability fod719W7Y

L .

3/4.a REACTOR COOLANT SYSTEM 3/4.4.1 C00LAliT LOOPS AND COOLANT CIRCULATION

"~ '

~

STARTUP AND 70'JER OPERATION L!MITING CONDITICN FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.. .

AP'LICA8!LITY: MODES I and 2*.

ACTION:

With one reactor coolant pump not in operation, STARTUP and PCWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than ( ): of RATED THERMAL POWER and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the setpoints for the following trips have been reduced to the values specified in specification 2.2.1 for operation with three reactor coolant pumps operating: !

1. NuclearOverpower). .

2. Nuclear overoower based on RCS flow and AX:AL POWIR IMSALANCE).

3. Nuclear Overpower based on pump monit:rs).

e a .

SURVE!LLANCE RE0VIR!MENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2 The Reactor Protective Instrumentalian channels specified in the applicable ACTION statement acove snall be verified to have had their trip setpoints changed to the values s:ecified in Specificatien 2.2.1 for the applicable number of reactor coolant pumps operating either: ,

a. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after switching to a different pump ccchination if.

the switch is made while operating, or

b. Price to reactor criticality if the switch is made while shutdewn. ,

s

'See Special Test Exception 3.10.4

!&W-STS -

i . <

-3/a.a R!aCTCt C00LANT SYSTEM HOT 57AN05Y 4 LIM!T!NG CON 017!CN FOR CP!tA7!ON 3.4.1.2 a. The reactor coolant loops Itsted below shall be CPEM8LE:

i

1. Reactor Ceolant Loop (A) and at least one associated reactor '

coolant pump.* .

2. Reactor Coolant Loop (B) and at least one associated reactor coolant pump.

b. At least one of the above Reactor Coolant Loops shall be in operation'.

i APeLICAl!LITY: MODE 3 ACTION:

a. With less than the above required reactor coolant loops OPERA 8LE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN '

within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . (

I

b. With no reactor coolant loop in operation, suspend a11 operations involving a riduction in boron concentration of the Reactor Coolant c System coolant,and icop to imediately operation. initiate action to. rpturn the retuired SUR'.'!ILLANC! *!?J12!*EN75 .

4.4.1.2.1 At least tne above required reactor coolant pumps, if not in operation, shall be detemined to be CP!M3LE once per 7 days by verifying c:rrect breaker alignments and indicated pcwer ava' lability.

4.4.1.2.2 At least eqe cooling loop shall be verified to be in operation and circulating reactor toelant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3 ,

%i reac::r ecolant pum:s may be da-energi:ed for up to 1 h:ur provided ,(1{ no operati:ns are semitted that would cause dilutjen of the reacter coolant system tiron c:ncentration, and f,2) core cutlet tamneraturt is maintained at lets: 17F telcw satu ation temperature.

339-573 ,

4

, ..t

& lt

. 3/ .4 RIAC;RhCLANTSYSTIM ,

/ ,(

.EN ,

LIMITING Cor:0! TION FOR OPftAT10*:

=.

3.4.1.3 a. . At. least two of the coolant loops listed below shall be OPEAABLE:

~ /

1. Aesctor Coolant Loop (A) and its associated steam generator

'e and at leest one associated reactor coolant pump,.

.g ,

2. Reactor Cootart Loop (I) and its associated steam generator and at lear,te one associated reactor coolant pumo,

.3. Decay Heat Aemoval' Loop (A),' .

,4 Decay Heat Removal Loop (8),'

b.- At least one of the above coolant loops shall .be in operstion.** i i

< App'.!CAI!L!TY: M00t$ 4 and 5 ACT!CN:

a. With less than the above required coolant loops CPEFABLE. imediately 4 initiate corrective action to return the required coolant locos to OPERA 8LI status as soon as possible; be in COL 3 5HUTDOWN within <

20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no coolant locp in operation, suspend all coerations involving

' a redaction in boren concentration of the Reactor Coolant System and immtdiately initiate corrective action to return the recuired

- "~E361nt loop to ' operation." ~~ "

i SURVEILLaflCIEEqu!2[MENTS 4.4.1.3'.1 it.e' required decay heat remval loop (s) shall be determined OPERA 8L!

per Specification,4.0.5.

4.A.1.3.2 The requird reacter coolant puro(s), if noi: in operation, shall be determined to be OPERA 5LE.once per1 days by verifying correct breaker alignments I

, and i,ndicated power availability.

4.4.1.3.3 ' The required, stes.n generator (s) shall be deter:nined OPERABLE by verifying' locandary side level to be greater than or squal to ( )S.

4.4;1.3.A At least one ecolant loco sha'11 he verified to be in oceration and circulating reestor ecolant at least once ter 12 heurs. ,

Ln wiev nornai or emergency ;cwer source may be incoerable in M00! 5. .

l c'

- A11'rvsetor ccolant pumes and deca / heat removal pumos may be de-energi:ed fer, up to 1-hour provided (1) no coerations are cermitted that would em M1ution cf the reactor coolant s/ stem boran concentration, and (2) core cutlet temoerature is maintained at luast 10 0F below saturstion temperature.

L . , ' 31a.'.575 .,

[ \

a 4 ,

3 RE**.E'.:'.2 2;E M i!CNS LO '.TE8 LEVEL Li,Y! ING CON 0! TION FOR CPEUTION ,

3.9.3.2 Two independent CHR Icops shall be OPERABLE.*

AP7LICA3fLITY: .* 00E 6 when the water level above the top of the irradiated fuel assablies seated within the reactor pressure vessel '

is less than 23 feet.

l ACTICN:

a. '4f th less than the required OHR f oops OPEMBLE, imediately initiate

' ccrrective action to return the required loops to CPERAELE status as soon as possible.

b. ~he provisiens of Specification 3.0.3 are not applicable.

c

,!U:'!E :'.L :N:E ?!!U!*ES'ENTS 4.7.3.2 The required DHR loops shall be deter:nined OPEM3LE :er Scecification 4.0.5.

' ..a r.:r al er e.argency ;cwer source may be inc;erable f:r a.h CHR loop.

!W.!TS

4 *

,3/a.4 #EACTOR COOLANT SYSTEM 5?SES 3/A.A.1 COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops in c;eration, and maintain,CNBR above (1.32/1.30) during all normal operations and antici;ated transients. With one reactor coolant pump not in operation in one ~ loop , THERMAL POWER is restricted by the Nuclear Overpewer Based on RCS Flow and AXIAL POWER IMBALANCE and the Nuclear Overpcwer Based en Pump M:nitors trip, ensuring that the CNBR will be maintained above (1.32/1.30) at the maximum possible THERMAL POWER for the number of reactor coolant ;;mps in operation or the local quality at the point of minimum CNBR equal to (22/15)i, whichever is more restrictive.

In MODE 3, a single reactor coolant icop provides sufficient heat remeval capability for removing decay heat; hcwever, single failure considerations require that two loops be OPERABLE.

~

In MODES 4 and 5, a single reactor coolant loop or CHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two locps be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two OHR Icops to be CPERASLE.

The cperation of one Reactor Coolant Pump or cne CHR pump provides adequate flow to ensure mixing, prevent stratification and prcduce gradual reactivity changes curing boron concentration reductions in the Reactor Ccolant System.

The reactivity change rate associated with boren reduction will, therefore, be within the capabiitty of Operator recognition and c:ntrol.

i 30,-5TS

i 4 .

J l

)

l REFUELING CpERATIONS

??SES 3/4.9.8 DECAY HEAT RE OVAL AND COOLANT CIRCULATION The requirement that at least one DHR loop be in operation 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, and (2) sufficient coolant circula:fon is maintained through the reacter c:re to minimi:e the effect of a bcron dilution incident and prevent boren strati-ficatien.

The recuirement to have two CHR icces OPERASLE when there is less than 23-feet of water abcve the c re ensures that a single failure of the operating DMR lecp will not result in a ccmplete icss of decay heat rer. oval capability. With -

the reacter vessel head renoved and 23 feet of water above the core, a large heat sink is avafiable for core ccoling. Thus, in the event of a failure of the ccerating ORF. Icop, adequate time is provided to initiate emergency procecures to c:ci the c:re.

C e

E Dl-STS

r

. s '

REFUELING OPERATIONS 3/4.9.8 DECAY MEAT REMOVAL AND COOLANT RECIRCULATION ,'

ALL '4ATER LEVELS LIMITING CONDITION FOR OPERATION 3.9.3.1 At least one decay heat renoval (DHR) loop shall be in operation.

APo'. ICABILITY: MODE 6.

AC !CN:

a. With less than one DHR loop in operation, except as provided in b below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment pene-trations providing direct access from the containment atmosphere to the outside at:nosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. The DHR loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per S hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel (hot) legs.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RECUIRESENTS s.9.3.1 At least one DHR loop shall be verified to be in operation and circulating reactor

colant at a flow rate of greater than or equal to (2800) gpm at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l E L'-575

.9 e .

OEFINITION OF GABCOCX d'WILC01 PWR OPE?ATIONAL MODES RUCTIVITY % OF MTED AVERAGE C00LM OPEPATIONAL . MODE CONDITION, X.ff THEPM 1 POWER

TEw.PEPATURE

1. POWER OPE?aTION > 0.99 >5 > (305)CF

2. S ARTUP > 0.99 15 >(205)CF

3. HOT STAN05Y 5 0.99 0 > (305)CF

'. HOT SHUTDOWN

. < 0.99 0 (305)CF > Tavg > 2000F E. COLD SHLC OWN < 0.99 0 1 200CF

5. REFUELING" 1 0.95 0 1 140CF m

' 6 :!ucin; :ecay heat.

" React:r vessel head unbelted or removed and fuel in the vessel.

e 9

4 3/a.a REACTOR COOLANT SYSTEM-3/a.4.1 CCOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LDtITING CCNDITION FOR OPERATION 3 . 4.1.' I Both reactor coolant loops and both reactor coolant pumps in each loop

- shall be in operation. c ...

APCI. ICA3 t L !TY : I and 2.*

ACTION: .

- With less than the above required reactor coolant pumps in operation, be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . .

SUR'!!!LLANCE RECU!REMENTS a.4.1.1 The above required reactor coolant loops shall be verified to be in cperation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

$ee 5:e: ai Tes- Exception 3.10.3.

CE-STS

REACTOR CCCLANT SYSTEM HOT STANOBY LIMITING CCNDIT*CN FCR OPERATION 3.~4.1.2 a. The reactor coolant loops l'isted below shall be OPERASLE:

~

1. Reactor Coolant loop (A) and at least one associated reactor coolant pump.

'2. Reactor Coolant Loop (3) and at least one associated reactor coolant pump.

b. At least one of the above Reactor Coolant loops shall be in operation *.

AFDLICABILITY: MODE 3

-ACTION:

a. With less than the above required reactor coolant loops operable, restore the required loops to GPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTCOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c

b. With no reactor coolant loop in operation, suspend all operations involving _a.r_ eduction. in. boren concen.tration of the Reactor Coolant System and i= mediately initiate corrective acticn to return the required loop to operati,on.

SL'R"E

L'_ANCE . REOUIREMENTS 4.4.1.2.1. At least the above required reactor coolant pumps, if not in cperation, shall be determined to be OPERASLE once per 7 days by verify-ing correct breaker align =ents and indicated power availability.

.4.4.1.2.2 At least.one cooling loop shall be verified to be in operation and circulating rea'ctor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

'Ali reactor cooian pumps may be de-energized for up to I hour provicled (1) no operatiens are ;e'mitted r : hat would :ause dilution of the reactor c:oiant system bgran concentratien, and (2) core outlet te.m perature is maintained it least 10 F below saturation temperature.

CE-STS

e l

.REACTCD.-COOLANT SYSTEM SHUT 00WN LIMITIN3 CONDITION FOR OPERATION l 3.4.1.3 a. At least two of the c olant loops listed below shall be CPERABLE:

1 Reactor Coolant Loop (A) and its associated steam generator !

and at least one associated reactor coolant pump,

2. Reactor Coolant Leop (B) and its associated steam generator and at least one associated reactor coolant ; ump,

3. Shutdown Cooling Loop (A)#

4 Shutdown Cooling Loop (B)'

b. At'least one of the above :colant loops shall be in operation".

APPLICABILITY: M00ES 4-* and 5** ,

AC710N:

' ~ ~

a. With less than the 'above reqdired coolant loops OPERABLE, immediately initiate corrective action to return the required.

coolant loops't5 OPERABCE status is"soon as possible; be in

COLD SHUTDONN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months . . . . . _

b. suscend all operations involvine With a reduction in bcron concentration lhe Reactor C:ola'nt Sy'sted ~'s no coolant loop in oceration,'of initiate corrective action to return the recuired

~

and immediately~6peFation.

c00Ta'rit' loop to SUR"EILLANCE REOUIREMENTS 4.4.1.3.1 The recuired shutdcwn cooling loop (s) shall be determined OPERABLE per Specification 4.0.5.

4.a.1.3.2 The required react:r coolant pump (s), if not in ::eration, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

'Aii reactor ccoiant pum:s and decay heat removal pumos cay' be de-energi:ed for j uo to I hour provided (1) no oceartions are permitted that would causedilutien ,

of the reactor coolant system boren concentration, and (2) core outlet !

temperature is maintained'at least 10 0F below saturation tem:eratur'e. ~

A react:r coolant pump shall not be started with one or more of the RCS cold .

leg tem:eratures less than or equal to (275)CF unless 1) the pressuri:er water volume '; less than (900) cubic feet or 2) the secondary water tem;erature or eacn s .-m generat:r is less than (*6) F above each of the RCS cold leg tem:eratures.

The normal Or emergency ;cwer scurce =av be 'nc;erable in '<00E 5.

CE-STS

. REACTOR COOLANT SYSTEM REtCTOR CCOLANT LOOPS AND COOLANT CIRCULATION SURVEILLANCE RECUIREMENTS (Continued) 4.4.1.3.2 The required steam generator (s) shall be determined OPERABLE by verifying the secondary side water level to be t at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.3.4 At least'on.

e coolant 1oop shall be verified to be in cperation

~

and. circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

O e

e e

e CE-575

REFUELING Op! RATIONS 3/a.9.8 SHUTDOWN COOL?NG AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CCNDITION FOR OPERATION 3.9.EI At legst one shutdown cooling loop shall be in operation.

APPLICA3*LITY: MODE 6 ACTION:

a. With less than ene shutdown cooling loop in operation,

. except as provided in b. below ' suspend all operations involving an increase in the reactor decay heat load or a reduction in boren concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere ,

to the outside atmospnere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5. The shutdcwn cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

.o

c. The provisions of Specification 3.0.3 are not applicable.

, SUR'/EILLANCE REQUIREMENTS 4.9.2.1 At least one shutdown cooling loop"shall be verified to be in operation

.and circulating reactor. coolant at a flow rate of. greater than er ecual.

to (2000) gpm at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l m

CE-ETS

- 1

~ .

REF'.'ELING OPERATIONS LO'4 WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.3.2. Two independent shutdown cooling loops shall be OPERABLE.*

AFPLICABILITY: MODE 5 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACT10!::

a. -With less than the required shutdown cooling loops OPERABLE,

. immediately ini.tiate_cstrictlye action to return loops to OPERABLE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable. .

e

,51.'R'!E:LL

NCE ;EGL'I REY.E*i 5 a.9.3.2. The recuired shutdown cooling loops shall be determined 0FERA5LE per 5;ecifica:icn 4.0.5.

~

' Ins normal or emergency power source may be inocerable for each shu-down cooling loop.

CE-575

O 3/4.4 REACTCR COOLANT SYSTEM 3ASES 3/4.a.1- REACTOR COOLANT LOCPS AND 00LANT CIRCULATION The plant is des.igned to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNER above 1.30 during all normal operatiens and anticipated transients.

In MODE 3, a single reactor ecolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two leeps be OPERABLE.

. In MODES 4 and 5, a single reactor coolant loop or shutdown cccling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERAELE. Thus, if the reactor coolant loc;s are not OPERAELE, this specification requires two shutdown cooling loc;s to be OPERABLE. .

The operation of one Reacter Coolant Pump Or one s.$utdown cooling pump provides adequate ficw to ensure mixing, prevent stratification and produce gradual reactivity changes during boren Concentration reductions in the Reactor-C:olant_5ystem. The reactivity change rate associated with beren reductions will, therefore, be within the capability of operator recognition and centrol. -e The restrictions on-starting a Reactor Coolant Pumo during M00E5 4 and 5 with one er more RC5 c:id legs less than er equal to (275)CF are pr: viced to prevent RCS pressure transients, caused by energy adcitiens fran the sec:ncary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be ;rctected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the ;ressuri:er and thereby ;roviding a vclume for the primary coolant to expand into or (2) by restricting starting of the RCPs to when the secondary water temperature Of each steam generator is less than (46)CF above each of the RCS cold leg temperatures.

l CE-575

RE:UELING OPERATIONS 3ASES 3/*.9.8 COOLANT CIRCULATION The recuirement that at least one shutdewn cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel belew 1c00F as required during the REFUELING MODE, and (2) sufficient coolant circulatien is maintained through the reactor core to minimize the effects of a boron cilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the core, ensures that a single failure of the :cerating shutdown c:oling loop will not result in a ccm:lete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adecuate time is providec to initiate snergency procedures to cool the core.

4 e

G CE-575

r o

OEFIt.ITION OF COMBUSTION ENGINEERING PVR OPERATIONAL MODES REACTIVITY % OF RATED AVERAGE 000L'J(T THER."AL POWER

TEMPE?ATURE OPERATIOXAL MODE CONDITION. K.ff

1. PO*4ER OPERATION > 0.99 >5 > 3000F

2. STARTUP > 0.99 1:5 > 2000F

~3. HOT STANc3Y < 0.99 0 > 300cF

. 4. HOT SHUT 00WN < 0.99 0 2000F > Tavg > 2000F

5. COLD SHUIDOWN < 0.99 0 < 200cF

5. 0 95 0 1 1400F REFUELING" 1

~#

E. clucing cecay heat.

" React.or vessel head unbolted er removed and fuel in the vessel.

b 0

e i

i

. l

s .

3/4.4 -REACTOR COGLANT SYSTEM 3/4.4.1 REACTCR CCOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATICN LIMITING CONDITION FOR.0PERATION

3.4.1.1 All reactor coolant loops shall be in cperation.

APPLICASILITf: MODES 1 and 2.* ',

ACTICN: .

With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within I hour.

-C SURVEILLANCE REOUTREMENT 4.4.1.1 Tne above required reactor coolant loops shall be verified to be in operation and circul'at.i ng reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

'See 5:ecial Tes- Exception 3.10.4

-STS .'

3-o REACTCR COOLANT SYSTEM HOT STANO3Y LIMITU:G CONDITION FOR OPERATION 3.4.1.2 a. At least de of the reactor coolant loops listed below shall be OPERABLE: , ,

1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant pump,

2. Reactor Coolant Loop (B) and its associated steam generator and reactor coof ant pump, ,

3. Reactor Coolant Loop (C) and its, associated steam generator .

and reactor coolant pump, ,

. 4. Reactor Coolant Loop (D) and its associated steam generator and reactor coolant pump. -

. b. At least one of the above coolant loops shall be in operation.*

APPLICABILITY: MCDE 3 ACTION: ,

a. With less than the above required reactor coolant loops CPERABLE, restore the required loops to OPERABLE status within 72 hcurs or be in HOT SHUTOCWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With no reactor coolant loop in operation, suspend all cperatier.s involving a reduction in baron concentration of the Reactor Coolant

'. System and immediately initiate corrective action to return the required coolant locp to operation.

SURVEILLANCE REOUIREN.ENTS 4.a.1.2.1 At least the above recuired reactor coolant pumps, if not in Operatien, shall be determined to be OPERABLE once per 7 days by verifying correc breaker alignments and indicated power availability.

4.4.1.2.2 t At least one cooling 1 cop shall be verified to be in c;eration

, and circulating reaccer ccolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ,

-All reac:cr ceciant pumps may be de-energized for up to I hcur provided (1) no c;srations are ;ermitted that vccid causa dilution of the reactor c:olant systan bcron concentra icn, and (2) core cutlet tamperature is =aintained at least 100F beicw saturation.temparature. ,

i-STS

.q..e., * ~ * * **

REACTCRC00(ANTSYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4;1.3 a. At least two of the coolant loops . listed below shall be OPERA 3tE:

1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant pump,*

2. Reactor Coolant Loop (B) and its associated steam generator and reactor coolant pump,*

. 3. Reactor Coolant ~ Loop (C) and its associated steam generator and reactor coolant pump,*

4. Reactor Coolant Loop (D) and its associated steam generator ,

and reactor coolant pump,*

5. Residual Heat Removal Loop (A),** .

6. Residual Heat Removal Loop (3).**

b. At least one of the above coolant locps shall be in operation.***

APPLICASILITY: MCOE5 4 and 5 ,

ACT!CN:

a. With less than the above required loops OPERASLE, immediately

- initiate corrective action to return the required loops to

OPERASLE status as soon as possible; be in COLD SHUTDOWN i

within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ..

i I

. b. With no ecolant loop in cperation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate ccrrective action to j-return the required coolant loop to operation.

"A reactor c oiant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to (275)0F unless 1) the pressuri:er water volume is less than cubic feet or 2) the secondary water temperature of each steam generater is less than 0F abcve each of the RCS cold leg temperatures.

"The nor al or amergency power s:urce may be inoperable in MCDE 5. "

"All reacter coolant pumps and decay heat removal pu=ps may be de energized for up to I h ur prsvided 1) no perations are penaitted that wcuid cause dilution of the reacter c:clant system beren : ncentration, and 2) :Ora cutlet temperature is maintained at least 100F belcw saturation tsm;eriture.

i-sTs

O 4

REACTCR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS 4.4.1.3. 1 The required residual heat removal loop (s) shall be determined CPERABLE per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pu=p(s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4. 4*.1. 3 . 3 The reg'uired steam generator (s) shall be determined OPERABLE by verifying secondary side lev ~el to be greater than o: equal to ( )% at least ,

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

~

4.4.1.3.4 At least one coolant loop shall be veriffed to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e 9

d 'e

4 4

REFUELING OPERATIONS

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPEPATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation. -

APPLICABILITY: MODE 6 ACTION: ,

a. With less than one residual heau removal loop in operation, -

except as provided in b below, suspend all operations involving an .

increase in the reactor decay heat load 'or a reduction in boren concentration of the Reactor Coolant System. Close all containment penetrations providing- direct access from the containment atmosphere to the outside at:nosphere within 4. hours, r- .

b. The residual heat removal loop may be removed from operatien for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTE?ATIONS in the vicinity of the reactor pressure vessel (hot) legs.

c. The provisions of Specification 3.0.3 are not applicable.

d SURVEILLANCE REOUIREMENTS 4.9.8.1. At least one residual heat renoval loop shall be verified to 5e in !

cperation and circulating reaccor coolant at a flow rate of greater than or equal to (2300) gpm at least once per a hours.

O

" STS

, ._. . _ . , . ,_ _ . _ . . . . , _ _ - _ = . , _ , --_. __ ,

v

,0~

RE/UELING OPE?.ATIONS LOW k'ATER LEVEL LIMITING CONDITION FOR OPERATION.

3.9.S.2 Two independent Residual Heat Removal (RHR) loops shall be OPERA 5LE.* ,

APPLICABILITY: MODE 6 when the water _ level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACTION:

a. With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RER loops to CPERABLE status as soon as possible. -

b. The provisions of _ Specification 3.0.3 are not applicable.

. 5URVEILL2.NCE RECUIREMENTS 4.9.3.2 The required Residual Heat Removal loops shall be deter nined CPERABLE per Specification 4.0.5.

'ine nor=al or emergency power source may be inoperable for each RHR loop. ,

I

'i-STS .

. . .e .

d~

6 9

3/4.4 REACTOR COOLANT SYSTEM 5ASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is' designed to operate with all reactor ecolant loops in operation, and maintain DN3R above 1.30 during all normal operations and anticipated transients. . In MODES 1 and 2 with one reactor coolant loop not in operation this specification requires that the plant be in at least HOT STANC3Y within

~

1 . hour. .

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure censiderations require that two 1 cops be OPERABLE. .

In MODES 4 and 5, a single reacter coolant loop or RHR loop provides sufficient, heat renoval capability for removing decay heat; but single failure c:nsiderations require that at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two RHR {

loops to be OPERABLE. -

The operation of one Reactor Coolant Pump or one RHR pump provides adecuate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.

The reactivity change rate associated with beren reduction will, therefore, be within ,;he capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump with one er more RCS cold legs 1.ess than or equal to (275)0F are provided to prevent RCS pressure transients,. daused by energy additions from the secondary system, which ceuld exceed the' limits of Appendix G to 10 CFR Part 50. The RCS will

.be protacted against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the prassurizer and thereby providing a volume for the primary coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water te=perature of each steam generator is less than ( )0F above each of the RCS cold leg tempera tures . .

. f,-STS e ,

g .me MWD . .

REFUELI!;G CPERATIONS ,

BASES 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ine requirement t' hat at least one residual heat remo' val (RHR) loop be in operation 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 REPJELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a baron dilution incident and prevent boron stratification. ,

The requirement to have two RHR loops OPERASLE when there is less than .

- 23 feet of water above the core ensures that a single failure of the operating 4 . RHR loop will not result in a complete loss of residual heat removal capability.

With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loo'p, adequate time is provided to initiate emergency -

procedures to cool the core.

d i

l l- ,

. y, .

i l

1-STS l

'. . ~._ _ : .. . ..

. . __

v t e Letter Sequence Other
TAC:42092, (Open) TAC:42112, (Open) TAC:42126, (Approved, Closed) TAC:48832, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML20126D835
MONTHYEAR1983-11-22 [Table View]

ML20126D835

Text

Enclosure:

Navigation menu

Search