Text

Corrected TS Pages to Amend 86 to License NPF-30,correcting Typos on Pages 3/4 3-26,3-52,3-53 & 11-2
	ML20073D861
Person / Time
Site:	Callaway
Issue date:	09/21/1994
From:	; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20073D865	List: ML20073D861; ML20073E743;
References
	NUDOCS 9409280103
	Download: ML20073D861 (11)
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.T_A_B_L_E_3. 3-4 ( Con t i nued )_

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E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SCTP0lNTS M

E SENSOR hE TOTAL ERROR TRIP ALLOWABLE 30 FUNCTIONAL UNIT ALLOWANCE _(_TAl Z

(SJ_

SETPOINT VALUE 04 E

o'Q 6.

Auxiliary Feedwater (Continued) 84

d. Steam Generator Water Level mg Low-Low (Continued)

2) Start Turbine-Driven Pump (Continued)

c. Vessel AT Equivalent

> 20% RTP

,s Coincident with DI Steam Generator Water 20.2 17.58 2.0

> 20.2% of Narrow

> 18.4% of Narrow Level Low-Low (Adverse Range Instrument Range Instrument 3

Containment Environment)

Span Span and Containment Pressure -

2.8 0.71 2.0 3"

Environmental Allowance

-< l.5 psig

-< 2.0 psig

{

Modifier a

j OR 5

Steam Generator Water 14.8 12.18 2.0

> 14.8% of Narrow

> 13.0% of Narrow Level Low-Low (Normal Range Instrument Range Instrument O

Containment Environment)

Span Span

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR TRIP ALLOWABLE i

e FUNCTIONAL UNIT All0WANCE fTA)

Z ERROR fS) SETPOINT' VALUE 6.

Auxiliary Feedwater (Continued)

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e.

Safety Injection-Start Motor-Driven Pumps See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

f.

Loss-of-Offsite Power-l Start Turbine-Driven Pump N.A.

N.A.

g.

Trip of All Main Feedwater Pumps-R Start Notor-Driven Pumps N.A.

N.A.

b h.

Auxiliary Feedwater Pump Suction Pressure-Low (Transfer to ESW)

N.A.

221.71 psia 120.64 psia 7.

Automatic Switchover to l

Containment Sump a.

Automatic Actuation Logic and Actuation Q

Relays (SSPS)

N.A.

M.A.

,=

%E b.

RWST Level-Low-Low-

. 3.4 1.21 2.0 236%

->35.2%

CE Coincident with E[

Safety Injection See Item 1. above for Safety Injection Trip Setpoints and Allowable Values.

PQ (m

8.

Loss of Power e.]

a.

4 kV Undervoltage

-Loss of Voltage N.A N.A.

N.A.

83V (120V Bus) 83+0,-8.3V (120V Bus)

+

R w/ls delay w/l+0.2,-0.5s delay y

O.

..___._,-._m._.-.-._..,_m.__.__

._m_

___.___.__.____m_______._-_____________

l TABLE 4.3-6 RLMG7L SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

RCS Pressure - Wide Range M

R 2.

Reactor Coolant Temperature - Cold Leg M

R 3.

Source Range, Neutron Flux #

M R

4.

Reactor Trip Breaker Indication M

N.A.

5.

Reactor Coolant Temperature - Hot Leg M

R 6.

Reactor Coolant Pump Breakers N.A.

N.A.

7.

Pressurizer Pressure M

R 8.

Pressurizer Level M

R 9.

Steam Generator Pressure M

R 10.

Steam Generator Level M

R 11.

Auxiliary Feedwater Flow Rate M

R

12. Auxiliary feedwater Pump Suction Pressure M

R

Not required OPERABLE in MODE 1 or MODE 2 about P-6 setpoint.

CALLAWAY - UNIT 1 3/4 3-51

INSTRUMENTATION

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ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: Modes 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the number of OPERABLE accident monitoring instrumentation channels, except the containment radiation level monitors and the unit vent - high range noble gas monitor, less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT l

SHUTDOWN withie %he following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With the number of OPERABLE channels for the containment radiation level monitors or the unit vent - high range noble gas monitor less than the Minimum Channels OPERABLE requirements of Table 3.3-10, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and either restore the inoperable channel to OPERABLE status withi1.7 days, or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days that provides actions taken, cause of the inoperability and plans and schedule for restoring the channels to OPERABLE status.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-7.

CALLAWAY - UNIT 1 3/4 3-52 Amendment No.86 Correction Letter of 9/21/94

TABLE 3.3-10 9p ACCIDENT MONITORING INSTRUMENTATION E

TOTAL MINIMUM NO. OF CHANNELS CHANNELS OPERABLE E

w I

INSTRUMENT i

1.

Containment Pressure

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a.

Normal Range 2

1 b.

Extended Range 2

1 2.

Reactor Coolant Outlet Temperature - T (Wide Range) 2 1

3.

Reactor Coolant Inlet Temperature - Tmo (Wide Range) 2 1

4.

Reactor Coolant Pressure - Wide Range 2

1 5.

Pressurizer Water level 2

1 6.

Steam Line Pressure 2/ steam generator 1/ steam generator 5

7.

Steam Generator Water level - Narrow Range 1/ steam generator 1/ steam generator 8.

Steam Generator Water Level - Wide Range 1/ steam generator 1/ steam generator 9.

Refueling Water Storage Tank Water level 2

1

10. Containment Hydrogen Concentration Level 2

1

11. Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator 12.

PORV Position Indicator

1/ Valve 1/ Valve 13.

PORY Block Valve Position Indicator **

1/ Valve 1/ Valve

14. Safety Valve Position Indicator 1/ Valve 1/ Valve j

$3E

15. Containment Normal Sump Water Level 2

1 l

=co g

{g

16. Containment Radiation Level (High Range, GT-RIC-59,-60)

N.A.

I gg

17. Thermocouple / Core Cooling Detection System 4/ core quadrant 2/ core quadrant h

18. Unit Vent - High Range Noble Gas Monitor (GT-RIC-21B)

N.A.

1

-4s i

TABLE 3.3-10 (Continued)

TABLE NOTATIONS

Not applicable if the associated block valve is in the closed position.

- Not applicable if the block valve is verified in the closed position and power is removed.

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CALLAWAY - UNIT 1 3/4 3-54

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RADIOACTIVE EFFLUENTS s

LIfUID HOLDUP TANKS j

o MITING CONDITION FOR OPERATION U

3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal j

to 150 Curies, excluding tritium and dissolved or entrained noble gases:

a.

Reactor Makeup Water Storage Tank, b.

Refueling Water Storage Tank, c.

Condensate Storage Tank, and

d. Outside temporary tanks, excluding demineralizer vessels and the liner being used to solidify radioactive waste.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, inusediately suspend all additions of radioactive material to the tank, within 4E, hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive l

Effluent Release Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the l

above listed tanks shall be determined to be within the above limit by i

analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.

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CALLAWAY - UNIT 1 3/4 11-1 Amendment No. E f>.89 l

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RADI0 ACTIVE EFFLUENTS f

' EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION i

3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 3% by volume whenever the hydrogen concentra-3 tion exceeds 4% by volume.

l APPLICABILITY: At a: 1 timas.

l ACTION:

a.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 3% by volume but less than or equal to 4% by volume, l

reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to l 4% by volume, then take ACTION a. above.

c.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE RE0VIREMENTS

(

4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP l

SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Specification 3.3.3.10.

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9 CALLAWAY - UNIT 1 3/4 11-2 AmendmentNo.A7,)p,86 Correction Letter of 9/21/94 l

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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Manager, Callaway Plant, shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the control room, I

a designated individual) shall be responsible for the control room command function. A management directive to this effect, signed by the Senior Vice l

President-Nuclear shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 Onsite and Offsite Organization An onsite and offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

1 a.

Lines of authority, responsibility and comunication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization l

positions. These relationships shall be documented and updated.

as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, l

and job descriptions for key personnel positions, or equivalent l

foms of documentation. These requirements shall be documented l

in the FSAR and updated in accordance with 10 CFR 50.71(e).

l b.

The Manager, Callaway Plant shall have responsibility for overall i

unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the i

plant.

l c.

The Senior Vice President, Nuclear shall have corporate responsi-l bility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out the health physics and quality assurance functions may report i

to the appropriate onsite manager; however, they shall have l

sufficient organizational freedom to ensure their independence l

from operating pressures.

CALLAWAY - UNIT 1 6-1 Amendment No. 37, 39 i

ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.2 The Unit organization shall be subject to the following:

a.

Each on duty shift shall be composed of at least the minimum shift l

crew composition shown in Table 6.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room; c.

An individual from the Health Physics organization #, qualified in radiation protection procedures, shall be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibil-ities during this operation; e.

A site Fire Brigade of at least five members # shall be maintained onsite at all times. The Fire Brigade shall not include the Shift i

Supervisor, and the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; f.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g.,. licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.

The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12);

and g.

The Superintendent, Operations, Shift Supervisors, and Operating Supervisors shall hold a senior reactor operator license. The Unit Reactor Operator shall hold a reactor operator license or a senior reactor operator license.

May be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

CALLAWAY - UNIT 1 6-2 Amendment No. /1, 86 Correction Letter of 9/21/94 1

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) m.

Review of Unit operations to detect potential hazards to nuclear safety; i

n.

Investigations or analysis of special subjects as requested by the

]

Chaiman of the NSRB; l

o.

Review of Unit Turbine Overspeed Protection Reliability Program and l

revisions thereto; and j

p.

Review of the Fire Protection Program and submitting reconinended changes to the NSRB.

4

6. 5.1. 7 The ORC shall:

a.

Reconenend in writing to the Manager, Callaway Plant approval or i

disapproval of items considered under Specifications 6.5.1.6a j

through e.,

1., J., k., 1., o., and p. above.

b.

Render determinations in writing with regard to whether or not each i

item considered under Specifications 6.5.1.6b. through e., and m.,

above, constitutes an unreviewed safety question; and l

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Senior Vice l

j President-Nuclear and the Nuclear Safety Review Board of disagreement between the ORC and the Manager, Callaway Plant; however, the 4

Manager, Callaway Plant shall have responsibility for resolution of j

such disagreements pursuant to Specification 6.1.1.above.

1 RECORDS

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6. 5.1. 8 The ORC shall maintain written minutes of each ORC meeting thet, at a j

minimum, document the results of all ORC activities perfonned under the responsi-j bility provisions of these Technical Specifications.

Copies shall be provided j

to the Senior Vice President-Nuclear and the Nuclear Safety Review Board.

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6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

FUNCTION i

6.5.2.1 The NSRB shall function to provide independent review and audit of l

designated activities in the areas of:

a.

Nuclear power plant operations.

l b.

Nuclear engineering, i

c.

Chemistry and radiochemistry, j

d.

Metallurgy, l

e.

Instrumentation and control, f.

Radiological, safety, j

g.

Mechanical and electrical engineering, and l

h.

Quality assurance practices.

j The NSRB shall report to and advise the Senior Vice President-Nuclear on those areas of responsibility stated in Specifications 6.5.2.8 and 6.5.2.9.

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CALLAWAY - UNIT 1 6-9 Amendnent No. M,19 OCT 2 71988 1

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ML20073D861

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