ML20086U505

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Proposed Tech Specs Revising TS SR & Deleting Specific Requirements to Perform Surveillances Prior to Beginning or Resuming Core Alterations or CR Withdrawal Assoc W/Refueling Activities
ML20086U505
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 07/28/1995
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20086U484 List:
References
NUDOCS 9508040120
Download: ML20086U505 (8)
v • d • e


Text

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REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS .

4.9.1.1 The reactor mode switch shall be ShutdownorRefuelpositionasspecified[verifiedtobelockedintheqt Iggst o

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4. 9.1. 2 Each of the above required reacthe mode switch Refuel position ,

interlocks" shall be demonstrated OPERABLE by

. FUNCTIONAL TEST "- C' '-- --'-- '- "r ^^ performance  :" ^' --f of at aleast CHANNEL .

once per 7 days during control rod withdrawal or CORE ALTERATIONS, as applicable.

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  • 4.9.1.3 EachoftheaboverequiredreactormodeswitchRefhlposition. l interlocks
  • that is affected shall be demonstrated OPERABLE.by performance of a '
  • CNANNEL FUNCTIONAL TEST prior to restming control rod withdrawal or CORE J

ALTERATIONS, as applicable, following repair, maintenance or replacement of

  • any component that could affect the Refuel position interlock. l i

"The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test.the switch interlock functions provided that all control .

rods are verified to' remain fully inserted by a second' licensed operator or '

other technically qualified member of the unit technical staff.

LIMERICK - UNIT 1 3/49-2 8 9500040120 950728 2 --- -- -

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REFUELING OPERATIONS .

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LIMITING CONDITION FOR OPERATION -

3.9.3 All control rods shall be inserted.* . -

APPLICABILITY: OPERATIONAL CONDITION 5. during CORE ALTERATIONS.** *

' ACTION: *

  • With all control rods not inserted, suspend all other CORE ALTERATIONS, except that one control rod may be withdrawn under control of the reactor. mode switch.  !

Refuel position one-rod out interlock. l SURVEILLANCE REQUIRENENTS-

  • J 4.9.3 i All control ' rods shall be verified to be inserted, except as above 1 specifiedp q+ ' leert once y W houtT.

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l "Except control rods removed per Specification 3.9.10.1 or 3.9.10.2. .

    • See Special Test Exception 3.10.3.

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LIMERICK - UNIT 1 3/4 9-5 All6 g Ig5 t

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,- REFUELING OPERATIONS - -

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3/4.9.5 COMMUNICATIONS .

LIMITING CONDITION FOR OPERATION 3.9.5 refuelingDirect communication floor personnel. shall be maintained between the control room and

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APPLICABILITY: OPERATIONAL CONDITION S, during CORE ALTERATIONS."

ACTION:

When direct communication between the control room and refueling floor personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*

l d ~ '~d SURVEILLANCE REOUIREMENTS 4.9.5 Direct communication between the control room and refueling floor personnel shall be demonstrated _'th'- 15::: ; i; ;; tr.; :t;.^. ;f ::.: at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.*

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  • Except movement of 'n:::: 'n:trr : ::t': :-f control rods with their normal drive system.

LIMERICK - UNIT 1 3/4 9-7 AUS S I!!!

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RIFUELINGOPERATIONS ,

~" '3/4.9.8 WATER LEVEL - REACTOR VESSEL -

LINITING CONDITION FOR OPERATION J.9.8 At least 22 feet of water'shall be maintained over the top of the .

react'or pressure vessel flange. .

' APPLICABILITY: During handling' of twel assembl.ies or control rods within the reactor pressure vessel while in DPERATIONAL CONDITION 5 when the fuel assemblies being handled are irradiated or,the fuel assemblies seated within the reactor vessel are irradiated.

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.. j ACTION: , ,

With the requirements of the above specification not satisfied, suspend all l operations involving handling of fuel assemblies or control rods within the '

reactor pressure vessel after placing all fuel assemblies and control rods in a safe condition. .- .

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SURVEILLANCE REQUIREMENTS

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4.9.8 The reactor vessel water level shall be detemined to be at least its minism required depth fi'- ! N: :: ;r': '- tt: :^z:1 c' : d et least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during handling of fuel assemblies or control rods within the reactor pressure vessel.

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l LIMERICK - UNIT 1 3/4 9-11 AUS s 1sg5 g

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REFUELING OPERATIONS ,

SURVEILLANCE RCOUIREMENTS ,

4. 9.1.1 The reactor mode switch shall be verified to be locked in the Shutdown or Refuel position as specifie,dd of leert onca fer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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4.9.1.2 Each of the above' required reactor mode switch Refuel position interlocks" shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST d th' *' E x x pr':r 'a th: :^27t :f x2 at least once per 7 days during control rod withdrawal or CORE ALTERATIONS, as applicable.

4.9.1.3 Each of the above required reactor mode switch Refuel position interlocks

  • that is affected shall be demonstrated OPERABLE by performance of a ,

CHANNEL FUNCTIONAL TEST prior to resuming control rod withdrawal or CORE '

ALTERATIONS, as applicable, following repair, maintenance or replacement of any component that could affect the Refuel position interlock. ,

  • The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that all control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

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. l 4 I AU6 2 5 585 LIMERICK - UNIT 2 , 3/4 9-2

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-REFUELING OPERATIONS . . j 3/4.9.3 CONTROL R0D POSITION .

LIMITING CONDITION FOR OPERATION l 3.9.3 All control rods shall be inserted.*

  • l APPLICABILITY: OPERATIONAL CONDITION S, during CORE ALTETATIONS.**

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ACTION. j l

With all control rods not inserted, suspend all other CORE ALTERATIONS, except j

. that one control rod may be withdrawn under control of the reactor mode switch Refuel position one-rod-out interlock.  !

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l SURVEILLANCE REQUIREMENTS - 4.9.3 All control rods shall be verified to be inserted, except as above

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specifiedd at least once [o.e 8L hoorf. .

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  • Except control rods removed per Sp'ecification 3.9.10.1 or 3.9.10.2. ,
    • See Special Test Exception 3.10.3. -

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LIMERICK - UNIT 2 3/4 9-5

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' REFUELING OPERATIONS , ,

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3/4.9.5 COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5- Direct communication shall be maintained between the control room and refueling floor personnel. ,

APPLICABILITY: OPERATIONAL CONDITION 5, during CORE ALTERATIONS.*

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ACTION:

When direct communication between the control room and refueling floor personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*

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SURVEILLANCE REQUIREMENTS 4.9.5 Direct communication between the control room and refueling floor personnel shall be demonstrated citht; 1 5::: ; ':7 t; ti; ;t:rt :? : . at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS."

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normal drive system.

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' LIMERICK - UNIT 2 3/4 9-7 M6 2 5 2 i

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I REFUELING OPERATIONS

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3/4.9.8 WATER LEVEL - REACTOR VESSEL l

LIMITING CONDITION FOR OPERATI0A -

3.9.8 At least 22 feet of water shall be maintained over the top of the reactor pressure vessel flange.

APPLICABILITY: Duringhandlingoffuelassembliesorcontrolrodswithinthe[' i reactor pressure vessel while in OPERATIONAL CONDITION 5 when the fuel assemblies

- being handled are irradiated or the fuel assemblies seated within the reactor

. vessel are irradiated. -

ACTION:

With the requirements of the above specification not satisfied, suspend all operations involving handling of fuel assemblies or control rods within the reactor pressure vessel after placing all fuel assemblies and control rods in

- a safe condition. ,

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I S,URVEILLANCE REQUIREMENTS 4.9.8 The reactor vessel eater level shall be determined to be et least its minimum required depth 6' 5:r : ;r':r t th: :tzt :? 17.f 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 handling of fuel assemblies or control rods within the reactor pressure vessel.

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3/4 9-11

- LIMERICK - UNIT 2 l

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