ML20084U043

Proposed Tech Spec 3/4.9.4,refueling operations-containment Penetrations

ML20084U043
Person / Time
Site:	Davis Besse
Issue date:	06/07/1995
From:	CENTERIOR ENERGY
To:
Shared Package
ML20084U002	List: ML20084T999 ML20084U009 ML20084U043
References
NUDOCS 9506130074
Download: ML20084U043 (8)

Text

.

LAR 91-0001 PCEe 10 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION FORINiilitiiAliGN GNii 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL H0 DES or other conditions specified for each specification. . .

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION vithin the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 1 place the unit in a HODE in which the Specification does not apply by placing '

l.

it, as applicable, in:

At least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

1. l

2. At least HOT SHUTDOVN vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, .and

3. At least COLD SHUTD0VN vithin the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  !

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications.

3.0.4 Entry into an OPERATIONAL HODE or other specified applicability condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements unless otherwise excepted. This provision shall not prevent passage through OPERATIONAL HODES as required to comply with ACTION statements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it say be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s),

component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of Unless both conditions (1) and (2) are satisfied, within 2 this specification.

hours action shall be initiated to place the unit in a HODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

1. At least 80T STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, l~

8

2. At least HOT SHUTDOVN vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 'and

3. At least COLD SHUTD0VN vithin the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This Specification is not applicable in H0 DES 5 or 6.

Amendment No. W, DAVIS-BESSE, UNIT 1 3/4 0-1 /l/46,163 9506130074 950607 PDR ADOCK 05000346 P PDR

- 1 t.AR 9$-0001 l P:ge 11 I

3/4.6 CONTAlf1 MENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMEHI CONTAINMENT INTEGRITY l

LIMITING CONDITION FOR OPERATION 3.6.1.I Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINHENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next ~6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAINNENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that:

1. All penetrations

• not capable of being closed by OPERABLE .

containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in ,

their positions, except those valves that may be opened under administrative controls per Specification 3.6.3.1, and

2. All equipment hatches are closed and sealed.

b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3 SExcept valves, blind flanges, and deactivated automatic valves which .

are located inside the Shield Building (including the annulus and l containment) and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days.

Amendment No. /lA1,194 DAVIS-BESSE, UNIT 1 3/4 6-1

' j ba 95 $0001 j P ge 12 CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION FORINFORMATION ONLY l

._ i 3.6.1.3 Each containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then . .

at least one air lock door shall be closed, and

b. An overall air lock leakage rate of f 0.002 L, at P,, 38 psig.

APPLICABILITY: H0 DES 1, 2, 3 and 4. -

ACTION:

ca. With one air lock door inoperable in one or more containment air locks, or with the containment air lock interlock mechanisa inoperable in one or more containment air locks: .

1. Verify an OPERABLE door in each affected air lock is closed .

within one hour, and

2. Lock an OPERABLE door closed in each affected air lock within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

3. Operation may then continue provided that an OPERABLE door in ,

each affected air lock is maintained closed and is verified ._

to be locked closed at least once per 31 days, and provided that the containment air lock passes each scheduled performance of SR 4.6.1.3b.

4. Otherwise, be in 110T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD ~

Sil0TDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

cb. With one or more containment air locks inoperable except as a result of an inoperable air lock door or air lock interlock mechanism:

1. Verify at least one door in each affected air lock is closed within one hour, and >

. l

2. Restore air lock (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l

3. Otherwise, be in 110T STANDBY within the next 6. hours and in COLD SliUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ,

Sentry and exit through the OPERABLE docr is permissible if necessary to perform repairs of the affected air lock components. After each entry and exit,'the OPERABLE door must be closed without delay.

DAVIS-BESSE, UNIT 1 3/4 6-6 Amendment No.194 I

e LAR 9S 0001 Page 13

_CONTAINMEllT SYSTEMS m eA,NNE,,A, <ecx THIS PAGE PROVIDED SURVEILLANCE RE0VIREMENTS I 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a. By verifying either no detectabic seal leakage when the volume between the door seals is pressurized to 10 psig, or by verifying a seal leakage rate of s 0.0015 L when the volume between the door seals is pressurized . .

to P,, 38 psig, and the air lock door holddowns are installed: l I. fWithin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening, (in MODES 1, 2, 3 and 4) except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

2.

• Prior to establishing CONTAINMENT INTEGRITY when. maintenance has not been performed on the air lock that could affect the air lock sealing capability. Reperformance of this test is not required prior to entering MODE 4 if the air lock has not been opened since the previous test.

b. By conducting an overall air lock leakage test at P , 38 psig, and by verifying that the overall air lock leakage rate is within its limit:

1. #At least once per 6 months, and

2.

• Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.

c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time. _

I

$ Exemption to Appendix "J" of 10 CFR 50.

7 iThe provisions of Specification 4.0.2 are not applicable.

l DAVIS-8 ESSE, UNIT 1 3/46-6a Amendment No.194

~

IAR 95-0001 Page 14 REFUFLING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bolts,

b. A minimum of one door in gach air lock closedg* 6~dti LiiE^M56tsihiiisfit46Fs5nt)ShiiiOBC OrproVidsatt -

OdEjpeFsonnelEagl66Ddo6 Misc idl6 sed!5hd pndividualfiyyall@jhgigg5_ ,,__iejy(rjjoj}sq _ . Eta close:the'doorgaJd

c. Each^~pE&eti'stion pFoviding direct access from the containment atmo-sphere to the out+4de atmosphere FEsTNT{ofitTifinier3 shall be either:

1. Closed by EiiirniIalFoT[dtomatlB an isolation valve, blind flange, or @'ORQengfif5t!P iMb7 or^

2. Be capable of being closed by an OPERABLE containment purge and exhaust isolation valve.

APPLICABILITY: During CORE ALTERATIONS or movement of irradi6ted fuel wit $1n the containment.

ACTION-

a. With the requirements of the above specification not satisfied. immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions Of Sp0ci'ication 3.0.3 are not applicaMer

b. With the containment purge and exhaust isolation system inoperable, close each of the purge and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

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

SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment penetrations shall be determined to be either in its fe]GJP6d closed /isclated condition or capable of being closed by an OPERABLEcontainmenT$urgeandexhaustvalve,within100hourspriortothestartof and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment, by:

a. Verifying the penetrations are in their B@iET1 isolated condition, or

b. Verifying that with the containment purge and exhaust system in opera-tion and the containment purge and exhaust system noble gas monitor capable of providing a high radiation signal to the control room, that after initiation of the high radiation signal, the coritainment purge and exhaust isolation valves can be closed from the control room, or If using the SFAS area radiation monitors, verifying that on a Contain-ment Purge and Exhaust Isolation test signal each purge and exhaust isolation valve automatically actuates to its isolation position.

DAVIS-BESSE. UNIT 1 3/4 9-4 Amendment No. 286

l

' LAR 65-0001 Page 15 I

3/4.9 REFUELING OPERATIONS MSES 3/4.9.1 BORON CONCENTRATION 1

The limitations on reactivity conditions during REFUELING ensure that: 1

1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a  !

uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analysis. . .

3/4.9.2 INSTRUMENTATION The OPERABILITY of source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactiv-ity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure sessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in l i

the safety analyses.

3/4.9.4 CONTAINMENT PENETRATIONS

,cop,Gfnm_ent NSggmoyenis5E[n@oacttM rob 06taca 5 h3 ths.atg@queggesa me

_ leas $

i@st%EM161siisd Unsig _ .<. j@y@

des 01t[#ffs L J _

n Usthispea LCONTAINME N

~ ~^3(g JC0Y31651M : stGh6 fshf3g

.gpy@fssingga

)g 8 snt )

@MsMa#esu_ _ hutcyte greepu l nequyement ~

Both nsorinhlssihu6 l d6htaf6didnt ~Edud ~ '

20REi4BTERATiONS 6ffinhdistEd ~~fi iFO idsdath ' "~'"sd3i n6dt@n%C013 fe! 9MfB1fs%f iids ~~~

des i %gnhted hjid16$t'6fbT6tyjithB '

~ ide%5Miiheei ~ insi stdQ66sdat Idipbbl R166

ishsofinelfst indses%gi 4 "hl eingpun e MhQ66 Jilbl66Ksditsh fH S C 0 13 ! 9lA ~ ~ sbles?

issin a nifatininiinumf6fA sf s6Eckshh fin Sur!&BisiseT~

tonioffirhad 'ssemtiliW#sehtedMttiinini61FbsEtf6HL a e

( 850inedsfddi assbstily! G s#b]dits6ssssdnfrdsthsWQptufs%6fliiinilbisdIit' tit sEsdhnEliaij sal sf

' _ jutd6@[cs)iMMsilablentdRT6s'ssthd@ff

~

E$,k}@ll_jjiMbss l

)inQllpfenbbilinsila6M i

DAVIS-BESSE, UNIT 1 B 3/4 9-1 Amendment No. I86

3 4

e.

ELAR 95-0001 Page 16 ,

'3/4.9 REFUELING OPERATIONS ,

BASES ~  ;

3/4.9.4 CONTAINMENT PENETRATIONS (Continued) i

) ".I/l.';. . ' :, .U ';,. .C'

.[ [j [Qh' f 'h % fd*g7 h ]

$;N[.['[. !'j.(;%.h'y']-p>;gf(.[^]Q((g [h[g{'{d3:

. .j@,7h[@.-

fj 6;. tg _

.. s .

R . .

MikNbn..h% WWOn ^ Sc!

S c requirement: On COntain ent penetration cl0 urc and OPEP.^3ILI U I' cc:ure that a rc100cc of radic:ctive =terial vdthin contai=cnt .dll bc restricted frc= leck ge to the envirc=cnt. Sc OPEP.^SILIH :nd clesure require .cnts are sufficient to restrict radicactive =terial relcacc fr= 0 fuel element rupture b cd u:On the lack Of contain=nt prc urinticq '

pete@l vhile in the REPJE_ING "00E. -

With the containment purge and exhaust system in operation, a high radiation signal received from the containment purge and exhaust system noble gas monitor will effectively automatically contain the release by~ shutting down the. containment purge system supply and exhaust fans and closing their inlet and outlet dampers. On a valid signal, the control room operator will then manually close the containment purge and exhaust isolation valves.

Therefore, the uncontrolled release of radioactive material from the contain-ment to the environment will be restricted, i I

Likewise, use of the SFAS area radiation monitors proviJe an automatic containment isolation signal on high radiation, restricting the uncontrolled release of radioactive material from the containment to the environment. _

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

DAVIS-BESSE. UNIT 1 B 3/4 9-la Amendment No. 186

+ , - - -w -. , - . . . - , . ,

LAR 95-0001 Page 17 REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 As a minimum, 23 feet of water shall be maintained over the -

top of irradiated fuel assemblies seated within the reactor pressure-vessel.

APPLICABILITY _: During movement of fuel assemblies or control rods within the reactor pressure vessel while in tiODE 6.

ACTION:

With the requirements of the above specification not satisfied, suspend all operation involving movement of fuel assemblies or control rods within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.  ;

l l

SURVEILLANCE REQUIREMENTS  :

4.9.10 The water level shall be detennined 'to be at least its minimum l required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during movement of fuel assemblies or control rods within the reactor pressure vessel.

DAVIS-BESSE, UNIT 1 3/4 9-10