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| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| page count = 13
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Latest revision as of 07:06, 13 December 2021

Proposed Tech Spec Changes,Adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R
ML20137V989
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/30/1985
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20137V948 List:
References
NUDOCS 8510040187
Download: ML20137V989 (13)


Text

-

ATTACHMENT 1 Consumers Power Company Big P.ock Point Plant Docket 50-155 '

l PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES September 30, 1985 i

  1. 8**

8510040187 850930 PDR ADOCK 05000155

'P PDR IC0985-0289-NLO4

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j i

j Limiting Conditions for Operation Surveillance Requirements i

j 11.3.5.3 EMERGENCY POWER SOURCES (Contd) 11.4.5.3 EMERGENCY POWER SOURCES (Contd)

{

! 3. The diesel generator fuel supply (4) Overspeed tripping.

l shall be adequate for three-day

! operation. (5) Battery undervoltage alarm.

4 l 4. If Specifications A.2 or A.3 are not (c) Verify the automatic transfer met, a normal orderly shutdown shall of station power from the be initiated within one (1). hour and 138 kV line to the 46 kV line.

l the reactor shall be shut down as

described in Section 1.2.5(a) with- (d) Verify the automatic transfer of i

in twelve (12) hours and shut down power sources for the lY and 2Y i

as described in Section 1.2.5(a) instrument and control panels.

I and (b) within the following

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During refueling opera- (e) Verify the cells, cell plates, and
tions cease all changes which could battery racks'show no visual i affect reactivity. indication of physical damage or abnormal deterioration for the S. The station battery system and the station battery, the RDS l

. alternate shutdown battery system batteries and the alternate shall be ope'rable under all conditions shutdown battery.

l except during cold shutdown. If the station battery or the alternate (f) Verify the cell-to-cell and shutdown battery is operable, no actions terminal connections are clear j shall be taken which result in a tight, free of corrosion and j reactivity addition, except cooldown, coated with anti-corrosion j or which might result in the primary material for the station battery,

! coolant _ system drained. the RDS batteries and the alternate shutdown battery.

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6. If Specification A.5 is not met a normal
orderly shutdown of the reactor shall be (g) Verify that the battery charger initiated within one (1) hour and the for the station battery and the reactor shall be shut down as described RDS batteries will supply at least 5 in Section 1.2.5(a) within twelve 30 amperes at a minimum of

! (12) hours and shut down as described 135 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

in Section 1.2.5(a) and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

147  ?

Proposed l!

! _TSB0985-0289A-NLO4 4

Limiting Conditions for Operation Surveillance Requirements i

i 11.3.5.3 EMERGENCY POWER SOURCES 11.4.5.3 ' EMERGENCY POWER SOURCES' ,

. lI I Applicability: Applicability:

! Applies to the operational status of the Applies to the periodic testing requirements emergency power sources. for the emergency power sources.

j Objective: Objective:

To assure the capability of the emergency To assure the operability of the emergency .
power sources to provide power required for power sources to provide emergency power in

! emergency equipment in the event of a Loss of the event of a Loss of Coolant Accident.

j Coolant Accident, j Specification:

1 Specification:

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A. The emergency power system surveillance j A. For all reactor operating conditions ex- will be performed as indicated below.

cept cold shutdown, there shall normally In addition, components on which mainte-i be available one 138 kV line, one 46 kV nance has been performed will be tested.

I line, one diesel generator system, one i station battery system, and four RDS un- 1. During each operating cycle -

I terruptible power supplies including l batteries and one alternate shutdown battery (a) Test of automatic initia-j system, except as specified below: tion sensors and load test the emergency diesel to' 180-200 kW

l. Refueling operations and related generator output for at least
testing may be conducted-with the 20 minutes.

i 138 kV line de-energized.

. (b) Test and calibrate the follow-

< 2. The 46 kV line or the diesel generator ing instruments and controls j may be out of service for repair for associated with diesel i periods up to three (3) days during generator:

I reactor operation and for extended l

periods during refueling or shutdown (1) Fuel oil level.

) operations, j (2) Oil Pressure tripping.

l (3) . Water temperature tripping, i 146 l Propose,d j

< TSB0985-0289A-NLO4 i

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l

] Limiting Conditions for Operation Surveillance Requirements l

l 11.3.5.3 EMERGENCY POWER SOURCES (Contd 11.4.5.3- EMERCENCY POWER SOURCES (Contd)

'7. One RDS uninterruptible power supply (h) Verify that the capacity of the including battery may be out of service station battery, the RDS batteries

as described in Section 3.1.5 Action 3. and the alternate shutdown battery l is adequate to supply and maintain 4
8. During reactor power. operation, the in OPERABLE status all.of the i 138 kV line may be out'of service for 'ctual emergency loads for the a

i repair for periods up to three (3) days. design time interval when the

{ battery is subjected to a battery j 9. If Specification A.8 is not met, a normal service test. The design time l orderly shutdown shall be initiated interval for the RDS batteries is i within one (1) hour and the reactor shall one hour, eight hours for the i be shut down as described in Section station battery, and eight hours l.2.5(a) within twelve (12) hours and for the alternate shutdown battery.

shut down as described in Section i 1.2.5(a) and (b) within the following (i) Test and calibrate the 2400 volt' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, bus undervoltage trip control components as follows:

B. During power and refueling operations, 4 . the 2400 volt bus undervoltage components (1) The undervoltage relays shall be operable or placed in the tripped 127-10KY, XZ and YZ will drop condition, except during the monthly out on decreasing voltage of channel functional testing period. no lower than 107.1 volts, 3 . after a delay of 5.6 seconds.

(2) The auxiliary timing relay 162-104 will be actuated after a 10 ! 0.5 second time delay upon receiving a signal from

, all three (3) undervoltage relays.

2. Monthly (a) Test start diesel generator and operate at least the fire pump as a load to 480 V Bus 2B for at

] least 20 minutes.

1 148 l Proposed TSB0985-0289A-NLO4

Limiting Conditions for Operation Surveillance Requirements 11.4.5.3 EMERCENCY POWER SOURCES (Contd)

(b) Verify that the cell voltage is 22.0 volts and specific gravity is 21.2 of each cell of the station battery; and verify that the cell voltage is 26.0 volts and specific gravity is 21.2 on each cell of the RDS batteries; and verify that the cell voltage is 22.1 volts and specific gravity is 21.2 of each cell of the alternate shutdown battery.

(c) Test operate the rod position motor generator set.

(d) Perform a channel functional test of the 2400 volt bus undervoltage trip system.

3. Weekly -

(a) Verify the electrolyte level of each RDS battery pilot cell, the station battery pilot cell and the j alternate shutdown battery pilot

! cell is between the minimum and j maximum level indication marks.

, (b) Verify the pilot cell specific l gravity for RDS, station and

alternate shutdown batteries corrected to (77)*F, is 21.2.

(c) Verify the station battery pilot 1 cell voltage is 22.0 volts. The RDS battery pilot cell voltage is 26.0 volts. The alternate shutdown battery pilot cell

. voltage 22.1 volts. t' i

148a Proposed j TSB0985-0289A-NLO4

Limiting Conditions for Operation Surveillance Requirements

] 11.4.5.3 EMERGENCY POWER S00RCES (Contd) i j (d) Verify the overall battery voltage i is 2125 volts for the station j battery, the RDS batteries and

- the alternate shutdown. battery.

(e) Test start the diesel generator and run for warm-up period.

(f) Verify that the diesel generator

battery electrolyte level above plates and overall battery

) voltage is 224 volts.

, 4. Quarterly - Verify the following:

1 i

(a) That.the specific gravity of the j diesel generator battery is appropriate for continued service.

I

(b) That the diesel generator battery and battery rack show no visual

, indication of physical damage or abnormal deterioration; and j (c) That the diesel generator battery

{ terminal connections are clean,

} , tight, free of corrosion and coated with anticorrosion material.

4 1

1 4

i 148b

] Proposed TSB0985-0289A-NLO4

l Limiting Conditions for Operation Surveillance Requirements 11.4.5.3 EMERGENCY POWER SOURCES (Contd) i

5. Sixty months - At least once per

, 60 months during shutdown, verify that the RDS batteries, the alternate

' shutdown battery and the sta. tion battery l capacity is at least 80% of the j manufacturer's rating when subjected to a performance discharge test. This 4 performance discharge test shall be

' performed subsequent to the satisfactory

' completion of the required battery service test of Part 11.4.5.3.A.1.(h).

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I 148c Proposed TSB0985-0289A-NLO4

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Bases:

Normal station power can be provided by the station turbine, generator, the 138 kV transmission line or the 46 kV line. These sources are adequate to provide emergency a-c power. When none of these sources is available, a single emergency diesel generator rated at 200 kW starts automatically to provide j emergency a-c poser to 480 V Bus 2R. The weekly starting test is based on Manufacturer's Bulletin

! 33743-1 for relubrication protection of moving parts. Diesel generator initiation and output circuit ,

I breaker closure is accomplished by two voltage sensors: -One to detect loss of normal power on Bus 2B; and, the other to provide assurance of generator output prior to automatic closure of the generator l output breaker. Additional breaker interlocks are provided to assure that the normal Buses IA and 2A are

) isolated prior to closing the generator output breaker. This prevents overloading of the generator

! during the switching period. An undervoltage trip at 589.25% of normal voltage isolates the 2400 volt i bus prior to any postulated equipment degradation. '

! n l' The operability of the diesel battery and charger is verified by the weekly starting test of the diesel and by the weekly verification of the electrolyte level and overall battery voltage.

{

m The diesel fuel oil tank is sized for ten-day full-load operation. Three-day supply is considered e adequate to provide fuel makeup. m o

o 4

A single station battery supplies power for normal station services and is sized for emergency uses s

) including valves and controls of Loss of Coolant-Accidents. The. battery can be charged from the @

i emergency diesel generator output if normal station power sources are not available. $

i  %

l The primary core spray valves and the primary containment spray valve are operated and controlled by d j power from the station battery. The backup core spray valves and backup containment spray valve are @

f operated by power from normal station power sources or the emergency diesel generator. o 1 $

i RDS uninterruptible power supplies (UPS) A, B, C, and D (each consisting of a battery, battery charger $-

I and an inverter) supply each division (except division 5) with electrical power. Each UPS has outputs of

) 120 V.a-c, 60 Hz, and 125 V d-c. One of these batteries supplies control power for the emergency diesel i generator. Divi. ions 1 & 2 and 3 & 4 normally receive power from 480 V a-c Buses IA and 2A, j respectively. It she event of loss of power to either or both buses,' provision is included for supplying

input power.from 480 V a-c Bus 2B which is tied to the emergency diesel generator. If all 480 V a-c f power is lost, the RDS UPS is capable of sustaining its outputs for one hour. The station battery had adequate capacity to carry normal loads plus an assumed failure (locked rotor current) of the d-c lube i 149 Amendment No. d2, 43/ 51 1 March 8, 1982 1

TSB0985-0289A-NLO4

4 Bases (Contd) oil pump for 54 minutes without the battery charger and still provide sufficient power for equipment required to operate during a LOCA. If steps are taken to reduce nonessential loads during a loss of off-site power (such as part of the emergency lights), additional time (up to five hours) can be gained from the time of the loss of the charger until the battery would no longer have sufficient power for equipment required to operate during a LOCA. The station battery and the four (4) RDS batteries will be

, considered operable if they are essentially fully charged and the battery charger is in service. '

Additionally, prior to the startup following the 1977 refueling outage, successful completion of service testing and performance discharge testing within each operating cycle and each sixty months, respectively, will further establish battery reliability.

An alternate shutdown battery supplies power to the main steam isolation valve, the emergency condenser l outlet valves and other alternate shutdown equipment. The battery is sized such that loss of the charger does not affect operability of the battery for up to six (6) days at a minimum of 25'F (nine (9) days at a minimum of 40*F) .

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149a I

Proposed I f 4

TSB0985-0289A-NLO4 4

4

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PLANT SYSTEMS 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITIONS FOR OPERATIOM i 3.7.13 The alternate shutdawn system (ASD) equipment shown in Table 3.3.9 shall be operable.

, APPLICABILITY During power operation.

ACTION a .' With any item, other than the #1 control rod drive pump power or the two emergency condenser indicating lights, in Table 3.3.9 inoperable, either restore to operable status within seven days or a normal orderly shutdown shall be initiated within one (1) ' hour and the reactor shall be shutdown as described in Section 1.2.5(a) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shutdown as described in Section 1.2.5(a) and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With the #1 control rod drive pump power or either of the two emergency condenser indicating lights inoperable, either restore to operable status' within sixty days or a normal orderly shutdown shall be initiated within one (1) hour and the reactor shall be shutdown as de' scribed in Section 1.2.5(a) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shutdown as described in Section 1.2.5(a)
and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.13.1 1

1 The ASD monitoring instruments shall be demonstrated OPERABLE by performing a check and a calibration per Table 4.3-9.

4.7.13.2 Each transfer switch, power supply and control circuit shall be demonstrated OPERABLE at least once per 18 months by operating each actuated component from both the control room and the remote location.

J 157 Proposed TSB0985-0289B-NLO4

TABLE 3.3-9 ALTERNATE SHUTDOWN SYSTEM EQUIPMENT INSTRUMENT READOUT LOCATION

1. Steam Drum Level /LI-6819 Panel C31
2. Steam Drum Pressure /PI-6819 Panel C31
3. Emergency Condenser Low Level Panel C31 Alarm Indicating Light /LS-3550
4. Emergency Condenser Firewater Panel C31 Makeup Flow Indicating Light /FS-4947 TRANSFER SWITHCES/ POWER SUPPLIES / CONTROL CIRCUITS SWITCH LOCATION
1. Emergency Condenser Outlet Valve MO-7053 Motor Control MO-7053 Starter
2. Emergency Condenser Outlet Valve M0-7063 Motor Control M0-7063 Starter
3. Main Steam Isolation Valve Control M0-7050 Motor MO-7050 Starter
4. ECS Firewater Makeup Valve Control Panel C31 SV-4947
5. Control Rod Drive Pump No. 1 Power Equipment Lock Proposed 157a TSB0985-0289B-NLO4

. -o TABLE 4.3.-9 ALTERNATE SHUIDOWN SYSTEM INSTRUMENT SURVEILLANCE REQUIREMENTS t

INSTRUMENT SURVEILLANCE FREQUENCY METHOD

1. Steam. Drum Level, A. Check, Quarterly compare to known level LI-6819 B. Calibration Every'18 apply known differential months pressures to transmitters
2. Steam Drum Pressure, A. Check Quarterly compare to known pressure

-PI-6819 B. Calibration Every 18 apply known pressures to months transmitter

3. Emergency Condenser. A. Check Quarterly initiate flow in line Makeup Line Flow Switch Indicating Light B. Calibration Every 18 apply known flow through FS-4947 months flow switch
4. Emergency Condenser Low A. Check Quarterly simulate low level Level Alarm Indicating Light, LS-3550 B. Calibration Every 18 apply known differential (Panel C31) months pressure to switch i

Proposed TSB0985-0289B-NLO4 ,,

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t (SUPPLIED FOR INFORMATION ONLY) d BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION s

l' OPERABILITY.of the fire detection instrumentation ensures that adequate i j warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overal] facility i fire protection program.

In the event that a portion of the fire detection instrumentation is

~~

inoperable, the establishment of frequent fire patrols in the af fected areas j is required to provide detection capability until the inoperable

~

j -instrumentation is restored to OPERABILITY.

l 3/4.7.11 FIRE SUPPRESSION SYSTEMS

-l l

The OPERABILITY of the fire supprestion systems ensures that adequate fire '

suppression capability is available to confine and extinguish fires occurring l in any portion of the facility where safety related. equipment is located. The

fire suppression system consists of the water system, spray and/or sprinklers, j :and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In_the event that portions of the fire suppression systems are inoperable, '

alternate backup fire fighting equipment is required to be made available in j the affected areas until the inoperable equipment is restored to service.  !

i

In the event the fire suppression water system becomes inoperable, immediate j corrective measures must be taken since this system provides the major fire j j suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability
of the corrective measures to provide adequate fire suppression capability for j the continued protection of the nuclear plant.

3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires

- will be confined or. adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire

~

a rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.  ;

i During periods of time when the barriers are not functional, routine fire watch patrols in conjunction with OPERABLE fire detection instrumentation or a continuous fire watch are required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status, i

Amendment No. 17

157c March 6, 1978 s

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TSB0985-0289B-NLO4

- - - - - _ - - - _ . . - - - - - - - - - - - , - - . - _ - - - - , - - - _ - - - - _ , - - - - - - - , - - - - , , m:

BASES (Contd) 3/4.7.13 ALTERNATI SHUTDOWN SYSTEM t

The requirements for the Alternate Shutdown System provide assurance that shutdown and cooldown to approximately 212*F can be achieved in the event of major fire in critical areas of the plant. This capability is in accordance with the criteria of Appendix R to 10 CFR 50.

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l Proposed 157d 1

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TSB0985-0289B-NLO4