ML18052A136
| ML18052A136 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/28/1985 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18052A134 | List: |
| References | |
| NUDOCS 8511010064 | |
| Download: ML18052A136 (10) | |
Text
ATTACHMENT Consumers Power Company Palisades Plant
~
Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES October 28, 1985
.8511010064 851028
':'l
- PDR, A DOCK. 05000255. ~ 11 '.
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PDR 9 Pages IC1085-0308A-NL04
3.3 EMERGENCY CORE COOLING SYSTEM (Contd) condition to. pro_v:ld_~_ for re4.u~~iqn of tl:!~ decay heci~ _from_ tl~e fuel _
and consequent reduction of cooling requirements after a postulated loss-of-coolant accident.
This will also permit improved access for repairs in some cases.
After a limited time in hot shutdown, if the malfuction(s) is not corrected, the reactor will be placed in the cold shutdown condition utilizing normal shutdown and cooldown procedures.
In the cold shutdown condition, release of fission products or damage of the fuel elements is not considered possible.
The plant operating procedures will require immediate action to effect repairs of an inoperable component and, therefore, in most cases, repairs will be completed in less than the specified allowable repair times.
The limiting times to repair are intended to:
(1) Assure that operability of the component will be restored promptly and yet, (2) allow sufficient time to effect repairs using safe and proper procedures.
The requirement for core cooling in case of a postulated loss-of-coolant accident while in the hot shutdown condition is significantly reduced below the requirements for a postulated loss-of-coolant accident during power operation.
Putting the reactor in the hot shutdown condition reduces the consequences of a loss-of-coolant accident and also allows more free access to some of the engineered safeguards components in order to effect repairs.
Failure to complete repairs within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of going to the hot shutdown condition is considered indicative of a requirement for major maintenance and, therefore, in such a case, the reactor is to be put into the cold shutdown condition.
With respect to the core cooling function, there is functional redundancy over most of the range of break sizes. (2).
Adequate core cooling for the break spectrum up to and including the 42-inch double-ended break is assured with the minimum safety injection which is defined as follows:
For the system of four passive safety injection tanks, the entire contents of one tank are assumed to be unavailable for emergency core cooling.
In addition, of the two high-pressure safety injection pumps and the two low-pressure safety injection pumps, only one of each type is assumed to operate; and also Proposed 3-32 TSP0885-0268-NL04
3.5 STEM1,AND FEEDWATER SYSTEMS
_____________ Ap_plicabilit¥ __
3.5.1 Applies to the operating status of the Steam and Feedwater Systems.
Objective To define certain conditions of the Steam and Feedwater System necessary to assure adequate decay heat removal capability.
Spec if ica t ions The primary coolant shall not be heated above 325°F.unless the following conditions are met:
- a.
Both electric driven Auxiliary Feedwater Pumps and one fire protection pump shall be operable.
The steam driven pump shall be operable prior to making the reactor critical.
- b.
The Auxiliary Feedwater System Instrumentation shall meet the minimum operability requirements addressed in Technical Specification 3.17.
- c.
All flow control valves associated with the Auxiliary Feedwater System shall be operable.
- d.
All valves, interlocks and piping associated with the above components required to function during accident conditions shall be operable.
- e.
A_minimum of 100,000 gallons of water in the condensate storage and primary coolant system makeup tanks combined.
- f.
The main steam stop valves shall be operable and capable of closing in five seconds or less under no-flow conditions.
-Proposed 3-38 TSP0885-0268-NL04
3.5 STEAM AND FEEDWATER SYSTEMS (Cont'd)
.... l.5.. 2 Wi_th th~. fr:i.ma]'."y Co_o_l_an,t System at a temperature greater than 325°F, the requirements of Specification 3:*5. l may-be modified -to permit the -
following conditions to exist.
If the system is not restored to meet the requirements of Specification 3.5.1 within the time period specified below, refer to Specification 3.5.3.
3.5.3 3.5.4
- a.
One auxiliary feedwater pump may be inoperable as follows:
- 1)
Auxiliary Feedwater Pump P-8A or P-8B for a period of 7 days or
- 2)
Auxiliary Feedwater Pump P-8C for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- b.
Two auxiliary feedwater pumps may be placed in manual, for testing, for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- c.
The fire water makeup to the Auxiliary Feedwater Pump Suction (P-8A and P-8B) may be inoperable for a period of 7 days provided the pump service water makeup to P-8C, pump P-8C, and its corresponding flow control valves are operable.
- d.
The service water makeup to the Auxiliary Feedwater Pump Suction (P-8C) may be inoperable for a period of 7 days provided the fire water makeup to P-8A & P-8B, pumps P-8A & P-8B and their corresponding flow control valves are operable.
- e.
One flow control valve on each train may be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the corresponding redundant flow control valve and a pump in the other pipe train are operable.
With the Primary Coolant System at a temperature greater than 325°F and if the system does not satisfy the requirements of Specification 3.5.1 or the conditions of Specification 3.5.2 except as noted in Specification 3.5.4, the reactor shall be placed in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 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 in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With all Auxiliary Feedwater Pumps inoperable immediately initiate corrective action to restore at least one Auxiliary Feedwater Pump to OPERABLE status as soon as possible and reduce power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the lowest stable power level.consistent with reliable Main Feedwater System operation.
3-38a Proposed TSP0885-0268-NL04
- 3.5 STEAM AND FEEDWATER SYSTEMS (Cont'd)
BASIS The Steam and Power Conversion System is designed to receive steam from the NSSS and convert the steam thermal energy into electrical energy.
A closed regenerative cycle condenses the steam from the main turbine and returns the condensate as heated f eedwater to the steam generators.
Normally, the capability to supply feedwater to the steam generators is provided by operation of the turbine-driven main feedwater pumps.
A reactor shutdown from power requires removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condenser, or by steam discharge to the atmosphere via the main steam safety valves or power operated relief valves.
(1,2)
If the main feedwater pumps are not operating, any one auxiliary feedwater pump can supply sufficient feedwater for removal of decay heat from the Plant.
The Plant is provided with two motor driven auxiliary f eedwater pumps (P-8A, P-8C) and one turbine driven auxiliary feedwater -pump (P-8B).
The Auxiliary Feedwater System is designed so that an automatic start signal is generated to the auxiliary feedwater pumps upon low secondary side steam generator level.
Upon low secondary side steam generator level, auxiliary feedwater pump P-8A would be the first auxiliary feedwater pump to receive an automatic start signal. If pump P-8A failed to start or establish flow within a specified period of time, auxiliary feedwater pump P-8C would receive an automatic start signal. If both pump P-8A and pump P-8C failed to start or establish flow within each pump's specified period of time, auxiliary feedwater pump P-8B would receive an automatic start signal. All three auxiliary feedwater pumps normally take suction from the condensate storage tank.
The minimum amount of water in the condensate storage tank and primary coolant system makeup tanks combined is the amount needed for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of auxiliary feedwater pump operation.
If the outage is more than 8_ hours, Lake Michigan water can be used, by utilizing a fire pump to supply water to the auxiliary feedwater pumps P-8A and P-8B, or by utilizing a service water pump to supply water to auxiliary feedwater pump P-8C.
Three fire pumps are provided, one motor driven and two diesel driven, each capable of delivering 1500 gpm at 125 psig.
Three service water pumps are provided, all of which are motor driven, each capable of
. delivering 8000 gpm at 60 psig.
A closure* time of 5 seconds for the main steam stop valves is considered adequate and was selected as being consistent with expected response time for instrumentation as detailed in the steam line break incident analysis. (3)
REFERENCES (1)
FSAR, Section 4.3.4 (2)
FSAR, Section 14.13.1 (3)
FSAR, Section 14.14 TSP0885-0268-NL04 Proposed 3-39
- 8.
- 9.
- 10.
Valve
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
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No Functional Unit Pressurizer Water Level (LI-0102)
Pressurizer Code Safety Relief Valves Position Indication (Acoustic Monitor or Temperature Indication)
Power Operated Relief Valves (Acoustic Monitor or Temperature Indication)
PORV Isolation Valves Position Indication Subcooling Margin Monitor Auxiliary Feed Flow Rate Indication Auxiliary Feedwater Actuation System Sensor Channels Auxiliary Feedwater Actuation System Actuation Channels Excore Detector Table 3.17.4 Minimum Operable Channels 2
1 per Valve 1 per Valve 1 per Valve 1
Minimum Degree of Redundancy 1
None None None None 1 per flow (h) None Control Valve 2 (e) 1 2 (f) 1 1 (g)
None Permissable Bypass Conditions Not required in Cold or Refuel-ing Shutdown Not Required Below 325°F Not required When PORV Isolation Is Closed and its Indication System is Operable Not required When Reactor is Depressurized and Vented Through a Vent '1:1. 3_ sq in Not Required Below 515°F Not required below 325°F Not required below 325°F Not required below 325°F (e)
Auxiliary Feedwater System Actuation System Sensor Channels contain pump auto initiation circuitry.
If two sensor channels are inoperable, one of the steam generator low level bistable modules in the one of the inoperable channels must be in the tripped condition.
(f)
With one Auxiliary Feedwater Actuation System Actuation Channel inoperable, in lieu of the requirement of 3.17.2; provide a second licensed operator in the control room within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump.
3-8la Proposed TSP0885-0268-NL04
Table 3.17.4 (Cont'd)
(g)
Calculate the Quadrant Power Tilt using the excore readings at
.. -least-once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s_ when __ the_ excor.e detector.s d~vi~tion ala:nn.s _
are operable.
(h)
With two flow rate indicators inoperable for a given control valve the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.
3.18 Secondary Water Monitoring Requirements 3.18.1 3.18.2 3.18.3 3.18.4 3.18.5 Applicability:
Applies to the secondary water requirements of the steam generator blowdown during power operation (generator synchronized).
Objective:
To minimize potential steam generator tube degradation caused by contamination of the secondary coolant.
Specification:
Steam generator water requirements shall be maintained in accordance with Table 3.18.1 except as specified below.
The limits for pH and sodium specified in Table 3.18.1 shall be achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of synchronization of the unit.
If these limits are not established within this *time, the reactor shall be brought to hot standby condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
During operation, other than that specified in 3.18.2, the limits for pH and sodium may exceed those specified in Table 3.18.1 for a period of up to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If these limits are not restored, the reactor shall be placed in hot standby within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The transient limit for specific conductivity specified in Table 3.18.1 shall be achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of synchronization of the unit.
If this limit is not established within this time period, then the reactor shall be brought to the hot standby condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
During operation, the steady-state limit for specific conductivity specified in Table 3.18.1 may be exceeded for a period of up to 7 days.
If this limit is not restored *within this time, the reactor shall be placed in hot standby within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Proposed 3-82 TSP0885-0268-NL04
TABLE 4.1.3 (Contd)
I Minimum Frequencies for Checks, Calibrations arid Testing of Miscellaneous Instrumentation and Controlsi Surveillance Channel Descri_Etion Function Freg,uencl Surveillance Method I
- 15.
Auxiliary Feed Pump
- a.
Calibrate R
- a.
Known Differential Pressure Applied to; Flow Indication Sensors
- 16.
Auxiliary Feed Pump
- a.
Test M (3) (5)
- a.
Switch Start
- b.
Calibrate R
- b.
Known Differential Pressure Applied to Sensors
- 17.
Power Operated Relief Valves and Pressurizer Code Safety Relief Valves Position Indication
- a.
Temperature
- a.
Calibrate R
- a.
Known Resistance Substitute for RTD
- b.
Check s
- b.
Comparison of Channels b *. Acoustic Monitor
- a.
Calibrate R
- a.
Inject Calibrated Test Signal
- 18.
Subcooling Margin
- a.
Check s
- a.
Comparison of Channels Monitor
- b.
Calibrate R
- b.
Known Resistance Substituted for RTD Coincident With Known Pressure Input (4)
(3)Test method to be alternated to include starting auxiliary feedwater pump from the control room ha~d switch, from the breaker (or alt.ernate steam supply) and from the pump test-key switch in a three month period.
(4)In conjunction with item 4(b), Table 4.1.1.
(5)It is not necessary to perform the specified testing during the c.old shutdown condition.
Proposed.
4-lla TSP0885-0268-NL04 e
e
4.. 6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4.6.1 4.6.2 4.6.3 Applicability Applies to the safety injection system, the containment spray.
system, chemical injection system and the containment cooling system tests.
Objective To verify that the subject systems will respond promptly and perform their intended functions, if required.
Specifications Safety Injection System
- a.
System tests shall be performed at each reactor refueling interval.
A test safety injection signal will be applied to initiate operation of the system.
The safety injection and shutdown cooling system pump motors may be de-energized for this test.
- b.
The system will be considered satisfactory if ~ontrol board indication and visual observations indicate that all components have received the safety injection signal in the proper sequence and timing (ie, the appropriate pump breakers shall have opened and closed, and all valves shall have completed their travel.)
- c.
All high pressure safety injection pumps except those otherwise required to be operable shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the PCS cold legs is ~250°F and the vessel head is not removed by verifying that the control system fuses and their fuse holders for the HPSI pumps (P66A, P66B) have been removed from the circuit.
Containment Spray System
- a.
System test shall be performed at each reactor refueling interval.
This test shall be performed with the isolation valves in the spray supply lines at the containment blocked closed.
Operation of the system is initiated by tripping the normal actuation instrumentation.
- b.
At least every five years the spray nozzles shall be verified to be open.
- c.
The test will be considered satisfactory if visual observations indicate all components have operated satisfactorily.
Pumps
- a.
The safety injection pumps, shutdown cooling*pumps, and containment spray pumps shall be started at intervals not to exceed three months.
Alternate manual starting between control room console and the local breaker shall be practiced in the test program.
4-39 Proposed TSP0885-0268-NL04
iil
)
4.9 AUXILIARY FEE~ER SYSTEM Applicability Applies to periodic testing requirements of the turbine-driven and motor-driven Auxiliary Feedwater Pumps.
Object-i-ve-To verify the operability of the Auxiliary Feedwater System and its ability to respond properly when required.
Specifications Demonstrate the operability of each auxiliary feedwater pump:
- a.
At least once per 31 days:
- 1.
The operability of each motor-driven pump shall be confirmed as required by Specification 4.3.c. and Table 4.1.3 Item 16a.
- 2.
The operability of the steam-driven pump shall be confirmed as required by Specification 4.3.c. and Table 4.1.3 Item 16a.
The provisions of Specification 3.0.4 are not applicable for entry into Hot Standby.
- 3.
Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b.
At least once per 18 months by:
BASIS
- 1.
Verifying that each Automatic Valve (CV-0736A, CV-0737A, CV-0727 and CV-0749) actuates to its correct position (or that specified flow is established) upon receipt of a simulated auxiliary feedwater pump start signal.
- 2.
Verifying that each pump starts automatically upon receipt of an auxiliary feedwater actuation test signal.
The periodic testing of Section 4.9.a will verify auxiliary feedwater pump operability by recirculating water to the condensate tank and monitoring pump performance as specified in Section 4.3.c.
The operability testing of Section 4.9.b will verify auto initiation
- of the auxiliary feedwater system by simulating a low steam generator level and observation of pump start.
To automatically start the "C" pump requires placing the "A" pump in manual.
To automatically start the "Bi' pump requires placing the "A & C" pumps in manual.
These tests may be performed during plant operations.
Operability of the flow control valves (CV-0736A, CV-0737A, CV-0727 and CV-0749) will be verified through simulation of an auxil~ary feedwater pump start signal and observing valve actuation to its correct position or by auxiliary feedwater system flow as monitored by installed instrumentation.
REFERENCE FSAR, Section 9.7 Proposed 4-45 TSP0885-0268-NL04