ML20154Q894

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Proposed Tech Specs Re Addition of Special Test Exception for IST & Hydrostatic Testing
ML20154Q894
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/15/1998
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20154Q883 List:
References
NUDOCS 9810260100
Download: ML20154Q894 (28)
v • d • e


Text

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ATTACHMENT 2 Limerick Generating Station Units 1 and 2 i

Docket Nos. 50-352 l 50-353 l

License Nos. NPF-39 I NPF-85 Technical Specifications Change Request l No. 97-04-0 List of Affected Pages Unit 1 Unit 2 Xvi xvi Xxii Xxii 1-10 1-10 3/4 10-7 3/4 10-9 3/4 10-8 B 3/410-2 B 3/410-1 B 3/410-2 9810260100 981015 PDR ADOCK 05000352 P PM ,

.. -, - _ = - - - . - _ - -- - - . . _ - ~ _ - .. - - -

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE REFUELING OPERATIONS (Continued) 3/4.9.10 CONTROL R00 REMOVAL Single Control Rod Removal............................ 3/4 9-13 Mul tipl e Control Rod Remova1. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-15 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1...................................... 3/4 9-17 Low Water Level....................................... 3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY......................... 3/4 10-1 3/4.10.2 R0D WORTH MINIMIZER................................... 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS........................ 3/4 10-3 3/4.10.4 RECIRCULATION L00PS................................... 3/4 10-4 3/4.10.5 0XYGEN CONCENTRATION.................................. 3/4 10-5 3/4.10.6 TRAINING STARTUPS..................................... 3/4 10-6 3/4.10.7 RESERVED - CURRENTLY NOT USED......................... 3/4 10-7 3/4.10.8 INSERVICE LEAK AWD HYDR 0 STATIC TESTING................ 3/4 10-8 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information from pages 3/411-1 through 3/411-6 has been intentionally omitted. Refer to note on page 3/4 11-1.............. 3/4 11-1 Liquid Holdup Tanks................................... 3/4 11-7 3/4.11.2 GASE0US EFFLUENTS The information from pages 3/4 11-8 through 3/4 11-14 has been intentionally omitted. Refer to note on page 3/4 11-8.............. 3/4 11-8 LIMERICK - UNIT 1 xvi

INDEX BASES SECTION EAG1

REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM............................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L........... B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L........ B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL.............................. B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND C0OLANT CIRCULATION.... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.................... B 3/410-1 3/4.10.2' R0D WORTH MINIMIZER.............................. B 3/410-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS................... B 3/410-1 3/4.10.4 RECIRCULATION L00PS.............................. B 3/410-1 3/4.10.5 OXYGEN CONCENTRATION............................. B 3/410-1 3/4.10.6 TRAINING STARTUPS................................ B 3/410-1 3/4.10.7 RESERVED - CURRENTLY NOT USED.................... B 3/410-1 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING........... B 3/410-2 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information on page B 3/4 11-1 has been intentionally omitted. Refer to note on this page. B 3/411-1 (Deleted)........................................ B 3/411-2 Liquid Holdup Tanks.........,.................... B 3/411-2 3/4.11.2 GASEOUS EFFLUENTS
(Deleted)........................................ B 3/411-2 i

. The information on page B 3/4 11-3 has been intentionally omitted. Refer to note on this page. B 3/411-3 (Deleted)........................................ B 3/411-4 LIMERICK - UNIT 1 xxii

DEFINITIONS TABLE 1.2 OPERATIONAL CONDITIONS )

l MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature 1
2. STARTUP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown # *** > 200*F
4. COLD SHUTDOWN Shutdown # ## *** s 200'F **** l
5. REFUELING
  • Shutdown or Refuel ** # NA l

l 1

  1. The reactor mode !. witch may be placed in the Run or Startu)/ Hot Standby position to test the switch interlock functions provided tlat the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
    1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
  • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
    • See Special Test Exceptions 3.10.1 and 3.10.3.
      • The reactor mode switch may be placed in the Refuel position while a single '

control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.

        • See Special Test Exception 3.10.8. l LIMERICK - UNIT 1 1-10

9

.I J-SPECIAL TEST EXCEPTIONS 5

3/4.10.7 RESERVED-CURRENTLY NOT USED t

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! LIMERICK - UNIT 1 3/4 10-7

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SPECIAL TEST EXCEPTIONS 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING j.IMITING CONDITIONS FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212*F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 Specifications are met:

a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a, 7.c.1, 7.c.2 and 7.d of Table 3.3.2-1;
b. 3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY;
c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES;
e. 3.6.5.2.2 REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES; and
f. 3.6.5.3 STANDBY GAS TREATMENT SYSTEM.

APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200*F and less than or equal to 212*F.

ACTION:

With the requirements of the above Specifications not satisfied:

1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification; or
2. Immediately suspend activities that could increase the average reactor coolant temperatureor3ressureandreducetheaveragereactorcoolanttemperatureto 200 F or less w thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for the Specifications listed in 3.10.8 are met.

LIMERICK - UNIT 1 3/4 10-8 l

_ _ . _ _ . _ - . _ _. _ ._.. _ _ m . . _ . _ _ - . _ _ . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _

3/4.10 SPECIAL TEST EXCEPTIONS

- BASES 3.4.10.1 PRIMARY CONTAINMENT INTEGRITY The requirement for PRIMARY CONTAINMENT INTEGRITY is not ap)licable during the period when open vessel tests are being performed during tie low power PHYSICS TESTS.

3/4.10.2 R0D WORTH MINIMIZER In order to perform the tests required in the technical specifications it is necessary to bypass the sequence restraints on control rod movement. The additional surveillance requirements ensure that the specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these tests are being performed and that individual rod worths do not exceed the values assumed in the safety analysis.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur. These additional restrictions are specified in this LCO.

3/4.10.4 RECIRCULATION LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.5 0XYGEN CONCENTRATION Relief from the oxygen concentration specifications is necessary in order l to provide access to the primary containment during the initial startup and I testing phase of operation. Without this access startup and test program could be restricted and delayed.

3/4.10.6 TRAINING STARTUPS This special test exception permits training startups to be performed with the reactor vessel depressurized at low THERMAL POWER and temperature while controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode in order to minimize contaminated water discharge to the radioactive waste disposal system.

3/4.10.7 RESERVED - CURRENTLY NOT USED l LIMERICK - UNIT 1 B 3/4 10-1

3/4.10 SPECIAL TEST EXCEPTIONS l

BASES l

l 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING l This special test exception permits certain reactor coolant pressure tests to be performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the i reactor pressure vessel (RPV) or plant temperature control capabilities during these I tests require the pressure testing at temperatures greater than 200*F and less than or equal to 212*F (normally corresponding to OPERATIONAL CONDITION 3). The additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event. I Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LC0 3.4.6, Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account I anticipated vessel neutron fluence. With increased reactor fluence over time, the I minimum allowable vessel temperature increases at a given pressure. Periodic updates  ;

to the RCS P/T limit curves are performed as necessary, based upon the results of l analysis of irradiated surveillance specimens removed from the vessel. l LIMERICK - UNIT 1 B 3/4 10-2 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REFUELING OPERATIONS (Continued) 3/4.9.10 CONTROL RCD REMOVAL Si ngl e Control Rod Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-13 Multiple Control Rod Remova1.......................... 3/4 9-15 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION  :

l High Water Leve1...................................... 3/4 9-17  ;

Low Water Level....................................... 3/4 9-18 l

3/4.10 SPECIAL TEST EXCEPTIONS 1 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY......................... 3/4 10-1 3/4.10.2 R00 WORTH MINIMIZER................................... 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS........................ 3/4 10-3 1

3/4.10.4 RECIRCULATION L00PS................................... 3/4 10-4 3/4.10.5 0XYGEN CONCENTRATION.................................. 3/4 10-5 3/4.10.6 TRAINING STARTUPS..................................... 3/4 10-6 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING........ 3/4 10-7 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING................. 3/4 10-9 l 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information from pages 3/4 11-1 through 3/411-6 has been intentionally omitted. Refer to note on page 3/4 11-1.............. 3/4 11-1 Liquid Holdup Tanks................................... 3/4 11-7 3/4.11.2 GASE0US EFFLUENTS The information from pages 3/4 11-8 through 3/4 11-14 has been intentionally omitted. Refer to note on page 3/4 11-8.............. 3/4 11-8 LIMERICK - UNIT 2 xvi

~ - . .. ..~ . .-.- - - _- _ - . - . - - - . . . _ . - - _ -

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INDEX j BASES SECTION A EA_GI REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM............................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L. ......... B 3/4 9-2 l

3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL I AND WATER LEVEL - SPENT FUEL STORAGE P00L........ B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL.............................. B 3/4 9-2 l 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.................... B 3/4 10-1 3/4.10.2 R00 WORTH MINIMIZER.............................. B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS................... B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS............ ................. B 3/4 10-1 3/4.10.5 OXYGEN CONCENTRATION............................. B 3/4 10-1 3/4.10.6 TRAINING STARTUPS................................ B 3/4 10-1 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING.... B 3/4 10-1 l

3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING........... B 3/4 10-2 l 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information on page B 3/4 11-1 has been intentionally omitted. Refer to nate on this page.............................................. B 3/4 11-1

( De l e t e d ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-2 Liquid Holdup Tanks.......... ................... B 3/4 11-2 3/4.11.2 GASE0US EFFLUENTS (Deleted)........................................ B 3/4 11-2 The information on page B 3/4 11-3 has been intentionally omitted. Refer to note on this page............................................. B 3/4 11-3 (Deleted)........................................ B 3/4 11-4 LIMERICK - UNIT 2 xxii

v 1 l

, DEFINITIONS I

TABLE 1.2

OPERATIONAL CONDITIONS l

MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature
2. STARTVP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown # *** > 200*F
4. COLD SHUTDOWN Shutdown # ## *** s 200* F **** l I
5. REFUELING
  • Shutdown or Refuel ** # NA l

l

  1. The reactor mode switch may be placed in the Run or Startu)/ Hot Standby position to test the switch interlock functions provided tlat the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
    1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1. j l
  • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.  ;
    • See Special Test Exceptions 3.10.1 and 3.10.3.
      • The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE. '
        • See Special Test Exception 3.10.8. l LIMERICK - UNIT 2 1-10

SPECIAL TEST EXCEPTIONS 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING LIMITING CONDITION FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212*F, and operation considered not to be in OPERATIONAL CONDIlION 3,  !

to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CntlDITION 3 Specifications are met:

a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a, 7.c.1, 7.c.2 and 7.d of Table 3.3.2-1;
b. 3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY;
c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION I VALVES;
e. 3.6.5.2.2 REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES; and
f. 3.6.5.3 STANDBY GAS TREATMENT SYSTEM.

APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200*F and less than or equal to 212*F.

ACTION:

With the requirements of the above Specifications not satisfied:

1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification; or
2. Immediately suspend activities that could increase the average reactor coolant temperature or 3ressure and reduce the average reactor coolant temperature to 200 F or less w' thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for the Specifications listed in 3.10.8 are met.

LIMERICK - UNIT 2 3/4 10-9 l

3/4.10 SPECIAL TEST EXCEPTIONS BASES l 3/4.10.8 INSERVICE LEAK AND HYDR 0 STATIC TESTING This special test exception permits certain reactor coolant pressure tests to be performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) or plant temperature control capabilities during these tests require the or equal to 212*F (pressure testing at temperatures normally corresponding greater to OPERATIONAL than 200*F CONDITION 3).and Theless than

, additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event.

Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LC0 3.4.6, l

Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account i

anticipated vessel neutron fluence. With increased reactor fluence over time, the I

minimum allowable vessel temperature increases at a given pressure. Periodic updates to the RCS P/T limit curves are performed as necessary, based upon the results of l analysis of irradiated surveillance specimens removed from the vessel. l I

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l LIMERICK - UNIT 2 B 3/4 10-2 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION Pg

' REFUELING OPERATIONS (Continued) 3/4.9.10 CONTROL A00 REMOVAL Single Control Rod Reeova1.............................. 3/4 g-13 Mul tipl e Control Rod Remova1. . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 9-15 3/4.9.H RESIDUAL HEAT. REMOVAL AND COOLANT CIRCUMTION High Water Level........................................ 3/4 9-17 Low Water Level.......'.................................. 3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAI) MENT INTEGRITY. . . . . . . . . . . . . . . . .3/4 . . 10-1 3/4.10.2 R00 WORTH MINIMIZER..................................... 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEleNSTRATIONS. . . . . . . . . . . . .3/4 . . 10-3 3/4.10.4 RECIRCU uTION L00PS..................................... 3/4 10-4 3/4.10.5 OXYGEN CONCENTRATION.................................... 3/4 10-5 3/4.10.6 TRAINING STARTUPS....................................... 3/4 10-6 3/4. H RADI0 ACTIVE EFFLUENTS 3/4.H.1 LIQUIDEFFLUENTS The information from pages 3/4 H-1 through 3/411-6 has been intentionally

-omittad. Refer to note on page 3/4 11-1. . . . . . . . . . . . . . . . 3/4.H-1

} Liquid Holdup Tanks..................................... 3/4 H-7 3/4.H.2 GASEOUS EFFLUENTS The infonnation from pages 3/4 H-8 through 3/4 u-14 has been intentionally omitted. Refer to note on page 3/4 H-8. . . . . . . . . . . . . . . . 3/4 H-8 3[4 3/ 4 10 /

3/4.10.B % service Luk Q hdros4dk Te%g 3/4(08 add LIMERICK - UNIT 1 xvi .

Amenc: rant No.gg8 JAK 021991

1 l l INDEX BASES 1

l SECTION I

PAGE REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0EM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L. . . . . . . . . . . . B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L......... B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL............................... B 3/4 9-2 3/4.9.11 RESIDUAL NEAT RE)CVAL AND COOLANT CIRCULATION..... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 1

3/4.10.1 PRIMARY CONTAI M INTEGRITY..................... B3/4lb-1 3/4.10.2 ROD WORTH MINIMIZER............................... B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.................... B 3/4 10-1 3/4.10.4 RECIRCULATION L00FS............................... B 2/4 10-1 3/4.10.5 OXYGEN CONCENTRATION.............................. B 3/4 10-1 3/4.10.6 TRAINING STARTUPS................................. B 3/4 10-1 H RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS The information on page B 3/4 H-1 has been intentionally omitted. Refer to nota on this page. B 3/4 u-1 (Deleted).......................................... B 3/4 11-2 Li qui d Ho l d up Tan ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-2 3/4. H. 2 GASEOUS EFFLUENTS (Deleted).......................................... B 3/4 11-2 The information on page B 3/4 H-3 has been intentionally omittec. Refer to note on this page. B 3/4 11-3 (Deleted)...... ...................................

B 3/4 11-4 3/4.10,'7 ltser-ud-(unecly kt Usej B 3/410- 1 LIMERICX - UNIT 1 xxii Amen =en: No.g, 48

~3/4.10.6 LSLWKC M ydro d w 'S y 3/4 lo-2.

4 -

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10 PORC DEF!NITIONS 2, 13, 53 TABLE 1.2 OPERATIONAL CONDITIONS HODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature
2. STARTUP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown # *** > 200*F
4. COLD SHUTDOWN Shutdown # ## *** s 200 F E*O
5. REFUELING
  • Shutdown or Refuel ** # NA g
  • The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the cortrol rods are verified to remain fully inse*ted by a second licensed operator or other technically qualified memoer of tne unit technical staff.
    1. The reactor mode switch may be placed in the Refuel position while a single control roc drive is being removed from the reactor pressure vessel per' Specification 3.9.10.1.
  • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
    • Sre Special Test Exceptions 3.10.1 and 3.10.3.
      • The reactor moce switch may be placed in the Refuel position while a sincie control roc is being recoupled provided that the one-rod-out interlock is OPERABLE.

t-u

  • See $pdd %st 64 3,lo,8 l au l LIMER::X - UNIT 1-10 ^rendment 2 55 JAN 31 1995

/

SPECIAL TEST EXCEPTIONS 3 / 4.10.7 RESERVED-CURRENTLY NOT USED

\ i l

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i 5

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i LIMERICK - UNIT i 3/4 10-7

.. . .- __= - - - - - - ... ..

SPECIAL TEST EXCEPTIONS 3 / 4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING LIMITING CONDITION FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 Specifications are met:

'i

a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a.

7.c.1,7.0.2 and 7.d of Table 3.3.2-1;

b. 3.6.5.1.1 REACTOR ENCLOSURE SECONDAPV CONTAINMENT INTEGRITY;
c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES;
e. 3.6.5.2.2 REFUELil,G AREA SECONDARY CONTAINMENT AUTOMATIC l l SOLATION VALVES; and
f. 3.6.5.3 STANDBY GAS TREATMENT SYSTEM.

APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200F and less than or equal to 212F.

ACTION:

With the requirements of the above Specifications not satisfied:

1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification: or
2. Immediately suspend activities that could increase the average reactor coolant j temperature or pressure and reduce the average reactor coolant temperature to l

200F or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

SURVEILLANCE REQUIREMENTS <

4.10.8 Verify applicable OPERATIONAL CONDITION 3 sunteillances for the j

Specifications listed in 3.10.8 are met. '

aa LIMERICK - UNIT 1 3/4 10-8

,. . . . _ - . ~ - -- -.- - - _ - - - - - . - _ . _ _ - - . . - - .

3901000402 3/4.10 SPECIAL TEST EXCEPTIONS .

BASES I 1

t i

t 3/4.10.1 PRIMAR'Y CONTAINMENT INTEGRITY the period when open vessel tests are being performed durin PHYSICS TESTS. ,

l I 1/4.10.2 R00 WORTH MINIMIZER In order to perform the tests required in the technical specifications it is necessary to bypass the sequence restraints on control rod movement. The l additional surveillance requirements ensure that the specifications on heat generation rates and shutdown margin requirements are not exceeded l }

period when these tests are being performed and that individual rod worths doduring the not exceed the values assumed in the safety analysis.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS '

Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur. These additional restrictions are specified in this LCO.

3/4.10.4 RECIRCULATION LOOPS 1 This special test exception permits reactor criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.5 OXYGEN CONCENTRATION Relief from the oxygen concentration specifications is necessary in order to provide access to the primary containment during the initial startuo and testing pnase of operation. Without this access the startup anc test program could be restricted and delayed.

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3/4.10.6 TRAINING STARTUPS I

This special test excection permits training startups to be :erformed with  ;

the reactor vessel depressurized at low THERMAL POWER and temperature while controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode in order to minimize contaminated water discharge to the racioactive waste disposal system.

3/4.lO,7 2 45ReVed C Mer M Ot at LIMERICK - UNIT 1 B 3/4 10-1 QCT 3 01M9 Anenament No. U , 33

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3 / 4,10 SPECIAL TEST EXCEPTIONS BASES 3 / 4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING This special test exception permits certain reactor coolant pressure tests to be performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) or plant temperature control capabilities during these tests require the pressure testing at temperatures greater than 200F and less than or equal to 212F (normally corresponding to OPERATIONAL CONDITION 3). The additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event.

Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (A3ME) Boit.*r and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LCO 3.4.6, Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated vessel neutron fluence. With increased reactor fluence over time, the minimum allowable vessel temperature increases at a given pressure. Periodic updates to the RCS P/T limit curves are performed as necessary, based upon the results of analysis of irradiated surveillance specimens removed from the vessel.

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med u pq pasQ abdkl M4 bluk LIMERICK - UNIT 1 B 3 / 4 10-2

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE i

REFUELING OPERATIONS (Continued) 3/4.9.10 CONTROL ROD REMOVAL Si ngl e Control Rod Remova1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-13 l

Mul tipl e Control Rod Remova1. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-15 3/4.9.H RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1........................................ 3/4 9-17 Low Water Leve1.........................................

3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS i

3/4.10.1 PRIMARY CONTAINMENT INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 . 10-1 3/4.10.2 ROD WORTH MINIMIZER..................................... 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.......................... 3/4 10-3 3/4.10.4 RECIRCULATION L00PS....... ............................. .

3/4 10-4 3/4.10.5 OXYGEN CONCENTRATION.................................... 3/4 10-5 3/4.10.6 TRAINING STARTUPS....................................... 3/4 10-6 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING. . . . . . . . . . 3/4 10-7 3/4. H 1ADI0 ACTIVE EFFLUEETS 3/4. n.1 LIQUID EFFLUENTS The information from pages 3 4 11-1 through 3/4 n-6 has been intentionally omit +ed. Refer to note on page 3/4 u-1. . . . . . . . . . . . . . . . 3/4 U-1 Li qui d Hol dup Ta n ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-7 3/4.H.2 GASEOUS EFFLUENTS The information from pages 3/4 u-8 througn 3/4 H-14 has been intentionally omitted. Refer to note on page 3/4 n-8................ 3/4 11-8 4.10.8 Inserdi<r Aah. M hroMWe,s /4(0-8 LIMERICK - UNIT 2 xvi Amenc:nent No.11 JAN 0 : 'ill

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i INDEX BASES i SECTION

PAGE l REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM................................ B 3/4 9-2
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L. . . . . . . . . B . .3/4

. 9-2 i

i 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL 1

and WATER LEVEL - SPENT FUEL STORAGE P00L. . . . . . . . .B 3/4 9-2 1

3/4.9.10 CONTROL RDO REMOVAL...............................

i B 3/4 9-2 5 3/4.9.H RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS i

3/4.10.1 PRIMARY CONTAIMENT INTEGRITY. . . . . . . . . . . . . . . . . .B. 3/4 . . 10-1

) 3/4.10.2 R00 WORTH MINIMIZER............................... B 3/410-1 i

3/4.10.3 SHUTDOWN MARGIN DEMDNSTRATI0NS. . . . . . . . . . . . .S. .3./4 . .10-1

)

1 3/4.10.4 RECIRCULATION L00PS. . . . . . . . . . . . . . . . . . . . . . . . . . .B. .3/4 . . 10-1 t '

3/4.10.5 OXYGEN CONCENTRATION.............................. B 3/4 10-1 3/4.10.6 TRAINING STARTUPS.................................

i B 3/4 10-1

3/4.10.7 SPECIAL INSTRUNENTATION - INITIAL CORE LOADING....

i B 3/4 10-1 3/4. H RADI0 ACTIVE EFFLUENTS i

3/4.n.1 LIQUIDEFFLUENTS The information on page B 3/4 n-1 has been

!' intentionally omitted.

j. Refer to note on this 1

page.............................................. B 3/4 H-1 i

(Deleted)......................................... B 3/4 E-2 i

Liquid Holduo Tanks...............................

B 3/4 u-2 3/4.n.2 GASEOUS EFFLUENTS (Deleted)......................................... B 3/4 n-2 The information on page B 3/411-3 iias been intentionally omitted. Refer to note on this page.............................................. B 3/4 11-3 coe,etee)......................................... B 3/4 u-4

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e O CU[K d i"? i 10 2 LINERICK - UNIT 2 xxii Amendment No.11 JAM 0 2 M

. DEFINITIONS b b TABLE 1.2 l OPERATIONAL CONDITIONS

) o s to'0 1 # 2. 13. se l MODE SWITCH KIERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temoerature
2. STARTUP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown # =** > 200*F
4. COLD SHUTDOWN Shutdown # ## *** s 200*F EO@
5. REFUEllNG
  • Shutdown or Refuel ** # NA M l
  1. The reactor mooe switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
    1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
  • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
    • See Special Test Exceptions 3.10.1 and 3.10.3.
      • The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is

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! l!MERICK - UNIT 2 1-10 4neni em 2 . 5: JAN 3 1 1995

SPECIAL TEST EXCEPTIONS SURVEILLANCE REQUIREMENTS (Continued) 4.10.7 (Continued)

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3. The RPS " shorting links" are removed.
4. The reactor mode switch is locked in the REFUEL position.
b. Performance of a EHANNEL FUNCTIONAL TEST within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start and at least once per 7 days dur.ing CORE ALTERATIONS.
c. Verifying for at least one SRM channel that the' count rate is at least 0.7 cps *:
1. Immediately following the loading o'f the first 15 fuel bundles.
2. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter during CORE ALTERATIONS.

$dr n 3/4.10. b l

  • Provided signal-to-noisa is > 2 (for initial startup only). Otherwise, 3 eps.

LIMERICK - UNIT 2 ,

3/4 10-8 AUG 2 51983

SPECIAL TEST EXCEPTIONS 314.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING LIMITING CONDITION FOR OPERATION 3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 Specifications are met:

a. 3.3.2 ISOLATION ACTUATION INSTRUMENTATION, Functions 7.a.

7.c.1,7.0.2 and 7.d of Table 3.3.2-1;

b. 3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY;
c. 3.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY;
d. 3.6.5.2.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES;
e. 3.6.5.2.2 REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES; and
f. 3.6.5.3 STANDBY GAS TREATMENT SYSTEM.

APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature greater than 200F and less than or equal to 212F.

ACTIONj With the requirements of the above Specifications not satisfied:

.1. Immediately enter the applicable (OPERATIONAL CONDITION 3) action for the affected Specification; or

2. Immediately suspend activities that could increase the average reactor coolant temperature or pressure, and reduce the average reactor coolant temperature to 200F or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 SURVEILLANCE REQUIREMENTS 4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for the Specifications listed in 3.10.8 are met.

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3 / 4.10 SPECIAL TEST EXCEPTIONS BASES l

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l 3 I4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING f

This special test exception permits certain reactor coolant pressure tests to be -

1 performed in OPERATIONAL CONDITION 4 when the metallurgical characteristics of the reactor pressure vassel (RPV) or plant temperature control capabilities during these tests require the pressure testing at temperatures greater than 200F and less than or equal to 212F (normally corresponding to OPERATIONAL CONDITION 3). The additionally imposed OPERATIONAL CONDITION 3 requirements for SECONDARY CONTAINMENT INTEGRITY provide conservatism in response to an operational event.

Inservice hydrostatic testing and inservice leak pressure tests required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are performed prior to the reactor going critical after a refueling outage. The minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (PU) limits required by LCO 3.4.6, Reactor Coolant System Pressure / Temperature Limits. These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated i vessel neutron fluence. With increased reactor fluence over time, the minimum '

l allowable vessel temperature increases at a given pressure. Periodic updates to the RCS P/T limit curves are performed as necessary, based upon the results of analysis of irradiated surveillance specimens removed from the vessel.

kAd LIMERICK - UNIT 2 83/410-2

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