ML20078S903
ML20078S903 | |
Person / Time | |
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Site: | Point Beach ![]() |
Issue date: | 12/22/1994 |
From: | WISCONSIN ELECTRIC POWER CO. |
To: | |
Shared Package | |
ML20078S896 | List: |
References | |
NUDOCS 9412290284 | |
Download: ML20078S903 (11) | |
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Attachment 4 Edited Technical Specification Pages l 15.3.3-6 15.3.4-2a Table 15.3.5-3 page 2 of 2 15.3.7-1,2,3,4,8 Table 15.3.14-1 Table 15.4.1-1 page 2 of 6 i
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9412290284 941222 PDR ADOCK 05000266 P PDR -
- a. Four service water pumps are operable.*
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- b. All necessary valves, interlocks and piping required for the l functioning of the Service Water System during accident conditions are also operable.
- 2. During power operation, the requirements of 15.3.3.D-1 may be modified l
to allow one of the following components to be inoperable at any one time. If the system is not restored to meet the conditions of 15.3.3.0-1 within the time period specified, both reactors will be placed in the hot shutdown condition. If the requirements of 15.3.3.0-1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, both reactors shall be placed in the cold shutdown condition.
- a. One of the four required service water pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. One of the two 104 aaders may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A valve or other passive component may be out of service provided repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
l l Basis l
The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature, by running the reactor coolant pumps.
The reactor is then made critical by withdrawing control rods and/or diluting boron in the coolant.N With this mode of start-up, the energy stored in the reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore to be conservative most engineered l
safety system components and auxiliary cooling systems, shall be fully operable.
l During low temperature physics tests there is a negligible amount of stored energy in the reactor coolant, therefore an accident comparable in severity to the Design Basis Accident is not possible, and the engineered safety systems are not required.
j DuringtheUnitle199y4refuelingoutage,onetrainfBservicewaterpump i
operating with power supplied by the Alternate Shutdown System, B08/B09 480
! Unit 1 - Amendment No. 15.3.3-6 Unit 2 - Amendment No.
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- 2. Single Unit Operation - One of the three operable auxiliary feedwater pumps associated with a unit may be out-of-service for the below specified times. The turbine driven auxiliary feedwater pump may be l
out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the turbine driven auxiliary l feedwater pump cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time j period, the reactor shall be in hot shutdown within the next 12 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Either one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days.* If the motor driven j auxiliary feedwater pump cannot be restored to service within that 7 4 day period the operating unit shall be in hot shutdown within the I
! next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. The main steam stop valves (MS-2017 and MS-2018) and the non-return check !
valves (MS-2017A and MS-2018A) chall be operable. If one main steam stop
- valve or non-return check valve is inoperable but open, power operation may 1
continue provided the inoperable valve is restored to operable status j within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise the reactor shall be placed in a hot shutdown
! condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. With one or more main steam stop valves or non-return check valves inoperable, subsequent operation in the hot shutdown condition may proceed provided the inoperable valve or valves are maintained closed. An inoperable main steam stop valve or non-return check valve may however, be opened in the hot shutdown condition to cool down the affected unit and to perform ter. ting to confirm operability.
E. The crossover steam dump system shall be operable. If the crossover steam i
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dump system is determined to be inoperable, reduce power to less than 480 )
MWe (gross) within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
i F. During power operation, at least one of the turbine overspeed protection 1
systems that trip the turbine stop valves or shut the turbine governor i valves shall be operable. If all three systems are determined to be inoperable, isolate the turbine from the steam supply within the next six hours.
During the "r.it 21000 refueling : t:g:, P30S, the Tr:in S =t:r driv:n
- :=ili ry f :d=ter p=p, =y b; : t of ::rvie: for up t: 12 d:y:. ;
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Unit 1 - Amendment No.
Unit 2 - Amendment No. 15.3.4-2a
TABLE 15.3.5-3 (continued) '
ENGINEERED SAFETY FEATURES ,
1 2 3 4 NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS ML FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET
- b. Start Turbine-Driven Pump -
- i. Undervoltage on 4KV Buses (A01 & A02) 2/each 1/each 1/each Be in hot. shutdown in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />' bus bus bus ii. Low Low Steam Gen.
Water Level 3/SG 2/each 2/SG" Be in hot shutdown in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 4. SAFETY-RELATED ELECTRICAL LOADS
- a. 4.16KV Buses (A05, A06) *"
- i. Degraded Voltage 3/ bus 2/ bus 2/ bus" 11- L,jgs of Koltage,_ 2/ bus _ 1/ bus 1/ bus ,
_,]
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480V Buses (B03[lB04) O M S L a ?I k w _L?/ bus;a c c _a u _ z i _ a 2 .;--
b.
- i. Loss of Voltage 3/ bus 2/ bus 2/ bus" Be in hot shutdown in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching hot shutdown, the unit shall be in cold shutdown within
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48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the event causing the unit shutdown.
If a channel is determined to be inoperable, resulting in one less than the total number of channels being operable, power operation may continue if the following conditions are met:
- 1. The minimum number of operable channels is still satisfied.
- 2. The affected channel is placed in trip within I hour.
Declare the associated sisil6j emergency dit:::1 ;;;;r:ter jiii yntujijily inoperable for the affected bus. The applicable Limiting Condition for Operation (LCO) shall be entered. Separate LCOs may be entered for the Degraded Voltage and Loss '
of Voltage functions.
Both switches must be activated simultaneousl N Mnitemtect EE M /6E Wsp@ElfRIS M M sjAl@![ l@fi[@]@lMMM$11
@ l @y. hM[W[Mi@@lMRWi[M itsMi Unit 1 - Amendment No. Page 2 of 2 Unit 2 - Amendment No.
15.3.7 AUXILIARY ELECTRICAL SYSTEMS
! Acolicability Applies to the availability of off-site and on-site electrical power for plant power operation and for the operation of plant auxiliaries.
, Ob.iective To define those conditions of electrical power availability necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing )
availability of engineered safeguards. l 1
l Specification i i 1 A.1 Under normal conditions neither one nor both reactors shall be made l l
l critical unless the following conditions are met:
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- a. At least two 345 KV transmission lines are in service.
- b. The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers
. associated with the reactor (s) to be taken critical are in service; or one 345/13.8 KV station auxiliary transformer and the associated 13.8/4.16 KV station auxiliary transformer (s) are in service with the gas turbine operating.
- c. 4160 Volt unit supply buses A03 and A04 for the unit to be taken critical are energized from their normal supply. I
- d. Sth urit;' A05/A05 be; ti: bre:ker: r r: = :d frc;;; their : biele:.
- p. Both units' B03/B04 bus tie-breakers are open with control power removed,
- s. A fuel supply of 11,000 gallons is available in each tank which j is being relied upon to supply any operable emergency diesel I
generator (s).
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- f. Four of the five safety-related station batteries and all four of the main DC distribution systems are operable.
- j. Four battery chargers are operable with one charger carrying the DC loads on each main DC distribution bus: D01, D02, 003 and D04. i
- h. 120 VAC Vital Instrument Buses YO1, YO2, YO3, YO4, Y101, Y102, Y103, and Y104 for the unit (s) to be taken critical are energized from a safety-related inverter.
Unit 1 - Amendment No. 15.3.7-1 Unit 2 - Amendment No.
J. For both units to be made critical, the normal power supply and a
, standby emergency power supply to all the 4160/480 Volt safeguards buses shall be operable and the buses are energized from their normal supply.
). For Unit I to be made critical, the normal power _ supply and a standby emergency power supply to the 4160/480 Volt safeguards buses Unit 1 A05/B03, Unit 1 A06/B04, and Unit 2 A06/B04 shall be operable and the buses are energized from their normal supply.
[. For Unit 2 to be made critical, the normal power supply and a standby emergency power supply to the 4160/480 Volt safeguards buses Unit 2 A05/B03, Unit 2 A06/B04, and Unit 1 A05/B03 shall be operable and the buses are energized from their normal supply.
B.1 During power operation of one or both reactors, the requirements of 15.3.7.A.1 may be modified to allow the following arrangements of systems and components:
- a. If the 345 KV lines are reduced to only one, any operating reactor (s) must-be promptly reduced to, and limited to, 50% power. If all 345 KV lines are lost, any operating reactor (s) will be reduced to supplying its auxiliary load, until one or more 345 KV transmission i lines are again available.
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- b. If both 345/13.8 KV auxiliary transformers are out of service and only the gas turbine is operating, only one reactor will remain -
operating and it will be limited to 50% power. The second reactor will be placed in the hot shutdown condition.
- c. If the 13.8/4.16 KV auxiliary transformers are reduced to only one, the reactor associated with the out of service transformer must be placed in the hot shutdown condition.
- d. With a unit in cold or refueling shutdown or defueled, ::: p;ir ;f W :::, A05 :nd AOS cr B03 and 804, for that shutdown unit, may be '
tied together through their common tie breaker for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the required redundant decay heat removal in the shutdown unit and the required redundant shared engineered safety features for the other unit are operable. If the tie breaker cannot be opened or -
the conditions of 15.3.7.B.I.e met within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the operating unit shall be placed in the hot shut-down condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 />.
Unit 1 - Amendment No. 15.3.7-2 Unit 2 - Amendment No.
- e. With a unit defueled, :r.: pir Of be::: f r th: d:ft:1:d er,it,
^^" - ' ^^' - "03 and B04, NgMitM(d6iiiiiiiii}M may be tied together through their common tie-breaker in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided:
- 1) An evaluation is performed to show that the loads that remain or can be energized by the buses will not cause a potential overload of the associated diesel generator. The applicable Limiting Conditions for Operation of the equipment removed from service shall be entered for the operating unit.
- 2) A single train of spent fuel cooling is adequate to cool the spent fuel pool. ,
- 3) The required redundant shared engineered safety features for the other unit are operable,
- f. The normal power supply or standby emergency power supply to Unit 1 A05/B03 or Unit 2 A06/B04 may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the. required redundant' standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into l this LCO and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter. If the normal power supply is out of service, an operable emergency diesel generator is supplying the affected 4160/480 Volt buses. After 7 days, both units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />,
- g. The normal power supply or standby emergency power supply to Unit 1 A06/B04 or Unit 2 A05/B03 or both may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LCO and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter. If the normal power supply is out of service, an operable emergency diesel generator is supplying the affected 4160/480 Volt buses. After 7 days, the affected unit or units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
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Unit 1 - Amendment No.. 15.3.7-3 Unit 2 - Amendment No.
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! ,h . The normal power supply or standby emergency power supply to Unit 1
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A05/B03 and Unit 2 A05/B03, or Unit 1-A06/B04 and Unit 2 A06/B04 may j be out of service for a period not exceeding 7 days
- provided the required redundant engineered safety features are operable and the l
j- required redundant standby emergency power supplies are started l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LCO and every 72 l hours thereafter. If the normal power supply is 'out of service, an operable emergency diesel generator is supplying the affected
) 4160/480 Volt buses. After 7 days, both units will be placed in hot j shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within i
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 3 l i. One of the four connected safety-related station batteries may be !
! inoperable for a period not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided four battery
)' chargers remain operable with one charger carrying the DC loads of l
{ each main DC distribution bus.
l j. If an operating safety-related inverter is rendered inoperable and I f the associated loads transfer to a non-safety-related power source, )
l the loads shall be transferred back to an operable safety-related j
! inverter within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in hot shutdown within an additional 6 l hours and cold shutdown within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> of inverter inoperability. l
- k. If any safeguards bus is deenergized, the applicable LCOs will be l
! entered for the affected equipment. 1
[ 1. One of the four connected battery chargers may be inoperable for a i period not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If an operable battery charger is not ;;
connected to the affected DC distribution bus within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the i
1 4 operating unit (s) shall be sequentially placed in hot shutdown within l the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> respectively, and placed in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
4 Basis i This two unit plant has four 345 KV transmission line interconnections. A 20 MW ;
j gas turbine generator, two original and two additional diesel generators are j installed at the plant. All of these energy sources will be utilized to provide j j depth and reliability of service to the Engineered Safeguards equipment through
} redundant station auxiliary power supply systems.
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- Ouring the Unit 21000 refueling ::t:g:, :t=dby :=r;=:y par t:
j Unit 1 A05/B0i =d Unit 2 A05/B01 =y bc ::t f : rvie: f r up t:
j 12 d y;.
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i-j Unit 1 - Amendment No. 15.3.7-4 j' Unit 2 - Amendment No.
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-- . . I day tanks which do not require a fuel oil transfer pump for flow to the associated EDG. The fuel. oil transfer system is allowed to be out-of-service for two hours for G-O'3 and G-04 due to a two-hour supply of fuel oil in the day tank. The i transfer system may be out-of-service for longer periods if an appropriate i alternate source of fuel is made available to the diesel generators.
The EDG ventilation system is considered operable when diesel room temperature can be maintained $120*F with the diesel engine operating at full load. Temperature will be maintained s120 *F if 1) all- gravity-operated louvers are operable, and
- 2) both diesel room exhaust fans are operable QB for G-01 and G-02; one diesel room exhaust fan is operable and outside air temperature is $80*FEgfM43i3]EQ@
M921K21EWIMEMMf!GHEIMsiL&fl!EM71Hil!9IfE35A!E!WHE3M Bii!MHErsERNfE3EM!MRBEMillIMEfEREM8IfEME EI8MIEMESNerNN@MM!iE9EFRW8DItir#40 Normal DC control power must energize all DC circuits for the associated EDG to be operable.
The original AEC Safety Evaluation for PBNP states, "0nsite fuel storage capacity ,
is sufficient for a minimum of seven days' operation of the required safety feature loads which is acceptable." Therefore, to satisfy this requirement, at least l 34,500 gallons of fuel oil will be maintained available for the emergency diesel generators at Point Beach at all times when EDG operability is required.
If only one 345 KV transmission line is in service to the plant switchyard, ,
a temporary loss of this line would result in a reactor trip (s) if the reactor (s) l power level were greater than 50%. Therefore, in order to maintain continuity ;
of service and the possibility of self sustaining operations, if only one 345 KV transmission line is in service to any operating reactor (s), the power level of the affected reactor (s) will be limited to 50%.
If both 345/13.8 KV station auxiliary transformers are out of service, only one reactor will be operated. The gas turbine will be supplying power to operate safeguards auxiliaries of the operating reactor and acts as a backup supply for the unit's normal auxiliaries. Therefore, to prevent overloading the gas turbine in l
the event of a reactor trip, the maximum power level for the operating reactor will be limited to jig. These conservative limits are set to improve transmission system reliability only and are not dictated by safety system requiremr.rts.
References FSAR Section 8.
Unit 1 - Amendment No. 15.3.7-8 Unit 2 - Amendment No.
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TABLE 15.3.14-1 1
- SAFE SHUTDOWN AREA FIRE PROTECTION l
AUTOMATIC SUPPRES$10N MANUAL SUPPRESSION WATER GAS SPRIWKLER SUPPRESSION FIRE HOSE FIRE AREA ELEVATION SYSTEM SYSTEM STATION DETECTION
- 1. Auxiliary Building South 8' (X) Partial X 15 ..
- 2. Auxiliary Butiding Center X 13 A. Safety Ir.jetion Pur ps 8' X B. Component Cooling Water Pump X
- 3. Auxiliary Building North 8' (X) Partial X 9
- 4. Auxiliary Building West 8' & Below X 16
- 5. Auxiliary Building Scuth 26' X 3
- 6. Auxiliary Building Center 26* X 17
- 7. Auxiliary Building North 26' X 7
- 8. Auxiliary Building Center 46* X 6
- 9. Auxiliary Feedwater Pump Room 8' X X 11
- 10. Vital Switchgear & Battery Room 8' X X 8
- 11. G01 Diesel Generator Room 8' X X 4
- 12. G02 Diesel Generator Room 8' X X 4
- 13. Cable Spreading Room 26' X
- X 17
- 14. Circulating Water Pumphouse X 15 A. Service Water Pumps 8' X
- 15. G03 Diesel Generator Room 28' X X* 3
- 16. G04 Diesel Generator Room 28' X X* 3
- 17. G03 Vital Switchgear Room 28' X* 2
- 18. G04 Vital Switchgear Room 28' X* 2
- 19. G03 Fuel Oil Day Tank Room 28' X X* 1
- 20. G04 Fuel Oil Day Tank Room 28' X X* 1 if??W60'fMMi?0iffiNMEPdG IM i lie f
- Diesel Generator Building fire hose stations are located in Mechanical Equipment Room.
Unit 1 - Amendment No.
Unit 2 - Amendment No.
_ ._._ _ .. _ ._ _ . _ _ _ _ . _ _ _ . _ _ _ ._ _. _ . _ _ . _ _ _ _ . ._ .,_ .. _ _ _ .m TABLE 15.4.1-1 (continued)
PLANT CONDITIONS E CHANNEL DESCRIPTION CHECK CALIBRATE IISI WHEN REQUIRED
- 9. Steam Generator Flow Mismatch S(22) R Q(1) ALL
- 10. Steam Generator Pressure S(16) R Q(1) ALL j
.11. 4KV Bus Undervoltage (A01 & A02)
-AFW pump actuation -
-R M(1) ALL
-Reactor Protection actuation -
R M(1,2) ALL ,
- 12. 4KV Bus Underfrequency (A01 & A02)
-to Reactor Coolant Pump trip -
R -
ALL 1
- 13. Safeguards Bus Voltage
-Loss of 4KV S R MHt ALL
-Degraded 4KV S R M61 ALL l
-Loss of 480V S R MH} ALL j
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- 14. 120 Vac Instrument Buses W(6)
ALL *
- 15. Reactor Trip Signal From Turbine
-Turbine Autostop - -
M(1) ALL
-Turbine Stop Valve - -
M(1) ALL ;
, 16. Reactor Trip Signal From SI - -
M(1) ALL ,
-MFP Trip on Safety Injection - -
R ALL
-MFRV Shutting on Safety Injection - -
R ALL 1
- 18. Accumulator Level and Pressure S R -
ALL
- 19. Analog Rod Position S(8,22) R -
ALL
-with step counters S(22) - -
ALL
-Monitoring by On-Line Computer (18) - -
PWR, HOT S/D I
i Unit 1 - Amendment No. Page 2 of 6 Unit 2 - Amendment No.
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