ML20203F652

Proposed Tech Specs Re Operability & Surveillance Requirements for Alternate Shutdown Sys,Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg

ML20203F652
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/21/1986
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20203F640	List: ML20203F634 ML20203F646 ML20203F652
References
NUDOCS 8604250207
Download: ML20203F652 (17)

Text

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J ATTACHMENT Consumers Power _ Company Big Rock Point Plant l Docket 50-155 L-i-

I PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES I

j. April 21, 1986 i.

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8604250207 860421 l PDR ADOCK 05000155 P

PDR 31 16 Pages i-L IC0486-0075-NLO4 i

. a CONTENTS (Contd)

Page No 8.0 Research and Development Program (Deleted) ..... .. . 79 -

91 9.0 Inservice Inspection and Testing . . .... ....... 92 - 102 9.1 Applicability . . . . . . ... ....... . .. 92 9.2 Objective . .. . . . . . . ... . ... .. . .. . 92 9.3 Specifications . . . . . . ....... ... . .. 92 9.4 Basis . . . . . . . . . . . . ..... ....... 92 10.0 (Section 6.0) Administrative Controls . . ....... . . 103 - 126 6.1 Responsibility .. . . . . . .. .... .. .... 103 6.2 Organization . . . . . . . . . .. ...... .. . 103 - 106 6.3 Plant Staff Qualifications . .. . ......... 107 6.4 Training .. . .. . . . . ... .... ... .. . 107 6.5 Review and Audit . . . . . . . .. .. .... . .. 107 - 113 6.6 Deleted . . . . .. . . . . .. ..... ... ... 113 6.7 Safety Limit Violation . . . ... ....... .. 113 E.8 Procedures . . . . . . . . ... ....... ... 113 - 114 6.9 Reporting Requirements . . . . .... . ... ... 114 - 120 6.10 Record Retention . . . . . . .. ... ....... 120 - 122 6.11 Radiation Protection Program ..... .... .. . 122 6.12 High Radiation Area . . . .. .... .. .. ... 123 - 123a 6.13 Environmental Qualification . .. . ... ... ... 124 6.14 Process Control Program . . . . ..... .... . . 125 6.15 Offsite Dose Calculation Manual (ODCM) .. ... . . 125 11.0 (Section 3.1.4/4.1.4) Emergency Core Cooling System . ... 130 - 135 (Section 3.1.5/4.1.5) Reactor Depressurization System . . . 136 - 142 (Section 3.3.4/4.3.4) Containment Spray System ... . .. 143 - 145 (Section 3.5.3/4.5.3) Emergency Power Sources . .... .. 146 - 149 12.0 Fire Protection Program . . . . ... . .. ..... .. 150 - 157d (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation . 150 - 151 (Section 3.7.11.1/4.7.11.1) Fire Suppression Water System . 152 - 153 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems . 154 ,

(Section 3.7.11.5/4.7.11.5) Fire Hose Stations . .. . .. 155 i (Section 3.7.12/4.7.12) Penetration Fire Barriers . . ... 156 (Section 3.7.13/4.7.1.3) Alternate Shutdown System . .. . 157 - 157b )

Bases . . . . . ... . . . . . . .. .. ... . . .. .. 157c - 157d j 1

13.0 Radiological Effluent Technical Specifications .... .. 158 - 186 13.1 Radiological Effluent Releases . ... .. ..... 158 - 173 13.2 Radiological Environmental Monitoring . .... ... 174 - 186 11 Proposed TSB0985-0289B-NLO4

Limitina Conditions for Operation Surveillance Requirements 11.3.5.3 EMERGENCY POWER SOURCES 11.4.5.3 EMERGENCY POWER SOURCES

( Applicability:

Applicability:

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

Objective: Objective:

To assure the capability of the emergency To assure the operability of the emergency i

power sources to provide power required for power sources to provide emergency power in emergency equipment in the event of a Loss of Coolant Accident. the event of a Loss of Coolant Accident.

Specification:

Specification:

A. The emergency power system surveillance 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.

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

terruptible power supplies including batteries and one alternate shutdown battery (a) Test of automatic initia-system, except as specified below:

tion sensors and load test the emergency diesel to 180-200 kW

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

138 kV line de-energized.

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

reactor operation and for extended periods during refueling or shutdown (1) Fuel oil level.

operations.

(2) Oil Pressure tripping.

(3) Water temperature tripping.

146 Proposed TSB0985-0289A-NLO4

'l

.. j Limiting Conditions for Operation Surveillance Requirements 11.3.5.3 ENERGEWCY POWER SOURCES (Contd) 11.4.5.3 EMERGENCY POWER SOURCES (Contd)

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

shall be adequate for three-day operation. (5) Battery undervoltage alarm.

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.

the reactor shall be shut down as described in Section 1.2.5(a) with- (d) Verify the automatic transfer of in twelve (12) hours and shut down power sources for the lY and 2Y as described in Section 1.2.5(a) instrument and control panels.

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 affect reactivity. indication of physical damage or abnormal deterioration for the

5. The station battery system and the station battery, the RDS alternate shutdown battery system batteries and the alternate shall be operable under all conditions shutdown battery, except during cold shutdown. If the station battery or the alternate (f) Verify the cell-to-cell and shutdown battery is inoperable, no terminal connections are clean, actions shall be taken which result in tight, free of corrosion and a reactivity addition, except cooldown, coated with anti-corrosion or which might result in the primary material for the station battery, coolant system draiced. . the RDS batteries and the alternate shutdown battery.

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 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 TSB0985-0289A-NLO4

Limiting Conditions for Operation Su rveillance Requirements 11.3.5.3 EMERGENCY POWER SOURCES (Contd) 11.4.5.3 EMERGENCY POWER SOURCES (Contd)

7. One RDS uninterruptible power supply (h) Verify

• hat the capacity of the including battery may be out of service statiu- tiery, the RDS batteries as described in Section 3.1.5 Action 3. and the alternate shutdown battery is adequate to supply and maintain

8. During reactor power operation, the in OPERABLE status all of the 138 kV line may be out of service for actual emergency loads for the repair for periods up to three (3) days. design time interval when the battery is subjected to a battery

9. If Specification A.8 is not met, a normal service test. The design time orderly shutdown shall be initiated interval for the RDS batteries is within one (1) hour and the reactor shall one hour, eight hours for the be shut down as described in Section station battery, and eight hours 1.2.5(a) within twelve (12) hours and for the alternate shutdown battery.

shut down as described in Section 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, the 2400 volt bus ondervoltage components (1) The undervoltage relays shall be operable or placed in the tripped 127-10XY, 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, after a delay of 5.6 seconds.

(2) The auxiliary timing relay 162-104 will be actuated after a 10 1 0.5 second time delay upon receiving a signal from all three (3) undervoltage relays.

2. Montbly -

(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.

148 Proposed TSB0985-0289A-NLO4

Limiting Conditions for Operation Surveillance Requirements ,

11.4.5.3 EMERGENCY 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. j (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 alternate shutdown battery pilot cell is between the minimum and maximum level indic ation marks.

(b) Verify the pilot cell specific gravity for RDS, station and alternate shutdown batteries corrected to 77*F, is 21.2.

(c) Verify the station battery pilot cell voltage is 22.0 volts, the RDS battery pilot cell voltage is 26.0 volts and the alternate shutdown battery pilot cell

, voltage 22.1 volts.

148a Proposed TSB0985-0289A-NLO4

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

(d) Verify the overall battery voltage is 2125 volts for the station 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:

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

(b) That the diesel generator battery and battery rack show no visual indication of physical damage or abnormal deterioration; and (c) That the diesel generator battery terminal connections are clean, tight, free of corrosion and coated with anticorrosion material.

148b Proposed TSB0985-0289A-NLO4

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

5. Sixty months - At least once per 60 months during shutdown, verify that the RDS batteries, the alternate shutdown battery and the, station battery capacity is at least 801,of the manufacturer's rating when subjected to a performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test of Part ll .4.5.3. A. I. (h).

148c TSB0985-0289A-NLO4 Proposed

e 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 emergency a-c power to 480 V Bus 28. The weekly starting test is based on Manufacturer's Bulletin 33743-1 for relubrication protection of moving parts. Diesel generator initiation and output circuit breaker closure is accomplished by two voltage sensors: One to detect loss of normal power on Bus {B; and, the other to provide assurance of generator output prior to automatic closure of the generator 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 bus prior to any postulated equipment degradation.

The operability of the diesel battery and charger is verified by the weekly starting test of the diesel TA and by the weekly verification of the electrolyte level and overall battery voltage. Ei U

The diesel fuel oil tank is sized for ten-day full-load operation. Three-day supply is considered I.I adequate to provide fuel makeup. U a

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

• including valves and controls of Loss of Coolant Accidents. The battery can be charged from the emergency diesel generator output if normal station power sources are not available. [_]

o D

The primary core spray valves and the primary containment spray valve are operated and controlled by I!

power from the station battery. The backup core spray valves and backup containment spray valve are operated by power from normal station power sources or the emergency diesel generator.

y

]  ;

RDS uninterruptible power supplies (UPS) A, B, C, and D (each consisting of a battery, battery charger Q 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 generator.

respectively.

Divisions 1 & 2 and 3 & 4 normally receive power from 480 V a-c Buses IA and 2A, In the 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 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 149 Amendment No. A2, #3, 51 March 8, 1982 TSB0985-0289A-NLO4

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 i

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 1

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 charter 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.

l An alternate shutdown battery supplies power to the main steam isolation valve, the emergency condenser 4

4 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 1

a minimum of 40*F). ,

i I

4 i

1

)t i 149a Proposed TSB0985-0289A-NLO4 4

TABLE 3.3-8 FIRE DETECTION INSTRUMENTS Minimun Instruments Total Operable Instrument Location Instruments Heat Smoke 1._ Electrical Equipment Room Zone 1 Elevation 614' 5 -

3 Zone 2 Elevation 603' 2 -

1 Zone 3 Elevation 599' 4 -

2

2. Exterior Cable Penetration Room Zone 1 Elevation 614' 5 -

3

3. Interior Cable Penetration Room Zone 1 Elevation 614' 6 -

4

4. Emergency Diesel Generator Room 2 1 ' -

5. Screenwell and Pump House 4 2 -

6. Control Room Zone 1 Elevation 627'-9" 2 -

1 Zone 1 Elevation 626'-0" 3 -

2

7. Core Spray Pump Room 2 -

1

8. Computer Room 2 -

1

9. Condensate Pump Room 2 -

1

10. Control Rod Drive Accumulator Room Zone 1 Elevation 599' 2 -

1

11. Shutdown Heat Exchanger Room 2 -

1

12. Recirculation Pump Room 3 2 -

13. Alternate Shutdown Building 2 -

1 i

l Proposed l 151 i TSB0985-0289B-NLO4 l i

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PLANT SYSTEMS e

3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.12 All penetration fire barriers including fire doors and fire dampers protecting safety-related areas shall be functional.

APPLICABILITY: At all times ACTION:

a. With one or more of the above required penetration fire barriers non-functional and with the area of the affected barrier (s) monitored by OPERABLE (pursuant to Specification 3.3.3.8) fire detection instrumen-tation, within I hour establish a fire watch patrol and inspect the affected area (s) at least one per hour.

. b. With one or more of the above required penetration fire barriers non-functional and with the area of the affected barrier (s) not monitored by OPERABLE (pursuant to Specification 3.3.8) fire detection instrumentation, establish a continuous fire watch on at least one side of the affected penetration within I hour.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection;

a. At least one per 18 months, and

b. Prior to declaring a penetration fire barrier functional following repairs or maintenance.

1 4

156 Proposed TSB0985-0289B-NLO4

_ , _ . _._. __,_.u__..___,_,-_-__-,___ -. _ . .. _ ._ _., _ - - . ..,. _ _..._ _ . ,_._. _ ._

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PLANT SYSTEMS 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.13 The alternate shutdown 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, its associated ASD power source or the two emergency condenser indicating lights, in Table 3.3.9 inoperable, either restore to OPERABLE etatus within 7 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, its associated ASD power source or either of the two emergency condenser indicating lights inoperable, either restore to OPERABLE status within 60 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 />.

SURVEILLANCE REQUIREMENTS 4.7.13.1 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 each major refueling shutdown

• by operating each actuated component from both the control room and the remote location.

]

4.7.13.3 At each major refueling shutdown

• perform a verification to insure that equipment (alternate power sources) needed to achieve and i maintain cold shutdown is available.

• But no less than once every 18 months.

157 Proposed TSB0985-0289B-NLO4

- at u o TABLE 3.3-9 ALTERNATE SHUTDOWN SYSTEM EQUIPMENT l

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 SWITCHES / POWER SUPPLIES / CONTROL CIRCUITS SWITCH LOCATION

1. Emergency Condenser-Outlet Valve ASD MO-7053 Motor Control MO-7053* Starter OR Emergency Condenser Outlet Valve ASD M0-7063 Motor 1 Control MO-7063* Starter f

l 2. Main Steam Isolation Valve Control MO-7050 Motor j MO-7050 Starter

3. Emergency Condenser Firewater Makeup Panel C31

' Valve Control SV-4947

4. Control Rod Drive Pump No. I and Equipment Lock associated ASD Power Source

• Section 3.7.13(a) applies only if the alternate shutdown controls for both emergency condenser outlet valves, MO-7053 and MO-7063, are inoperable at the same time.

Proposed 157a TSB0985-0289B-NLO4

TABLE 4.3.-9 ALTERNATE SHUTDOWN SYSTEM INSTRUMENT SURVEILLANCE REQUIREMENTS 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 FS-4947

4. Emergency Condenser Low A. Check Quarterly simulate low level Level Alara Indicating Light, LS-3550 B. Calibration Every 18 apply known differential (Panel C31) months pressure to switch Proposed 157b TSB0985-0289B-NLO4

p- >

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BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION l

OPERABILITY of the fire detection instrumentation ensures that adequate 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 overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring 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, 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.

l l In the event that portions of the fire suppression systems are inoperable, i alternate backup fire fighting equipment is required to be made available in the affected areas until the inoa*-able equipment is restored to service.

In the event the fire suppress er system becomes inoperable, immediate corrective measures must be taken o ce this system provides the major fire suppression capability of the plan 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 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 rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers include active and passive elements in the facility fire protection program which are subject to periodic inspections.

During periods of time when the barriers are not functional, routine fire watch pa*.rols 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.

157c Proposed TSB0985-0289B-NLO4 w__-__-____-

we. *>

BASES (Contd) 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM 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.

V l

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l Proposed 157d TSB0985-02898-NLO4

,