Text

Amend 86 to License NPF-30,revising TS to Reflect Editorial & Typograghical Changes for Consistency & Clarity.Changes Include Trip Setpoint Corrections,Description Clarifications,Ref Updates & Title Deletions
	ML20059C503
Person / Time
Site:	Callaway
Issue date:	12/21/1993
From:	Wharton L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059C506	List: ML20059C503; ML20059C508;
References
	NUDOCS 9401050282
	Download: ML20059C503 (15)
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UNITED STATES

[.J'fi (&j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555-0001

%...../

UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. NPF-30 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated August 1, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in-10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

i 9401050282 931221 PDR ADOCK 050004B3 P

PDR

(2) Technical' Soecifications and Environmental' Protection Plaq The Technical Specifications contained in Appendix'A, as revised through Amendment No.

86, and the Environmental-Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance. The Technical Specifications are_ to be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION kM 6

L. Raynard Wharton, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

December 21, 1993 1

4

s

'c ATTACHMENT TO LICENSE AMENDMENT NO. 86 OPERATING LICENSE N0. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.

REMOVE INSERT 3/4 3-26 3/4 3-26 3/4 3-52 3/4 3-52 3/4 3-53 3/4 3-53 3/4 6-31 3/4 6-31 3/4 11-2 3/4 11-2 6-2 6-2 i

1 i

I

...O l'

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS r-E SENSOR

-4 TOTAL ERROR TRIP ALLOWABLE FUNCTIONAL UNIT ALLOWANCE (TA)

Z (S)

SETPOINT VALUE

-i 6.

Auxiliary Feedwater (Continued)

d. Steam Generator Water Level 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

ContainmentEnvironment)

Span Span and Containment Pressure -

2.8 0.71 2.0

< 2.0 psig F

Environmental Allowance

~< 1.5 psig

~

Modifier OR E-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

=

g TABLE 3.3-4 (Continued)

P E

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 22 TOTAL SENSOR TRIP ALLOWABLE FUNCTIONAL UNIT ALLOWANCE (TA)

Z

. ERROR (S)

SETPOINT VALUE c-z 6.

Auxiliary Feedwater (Continued) 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 Start Turbine-Driven Pump N.A.

N.A.

-N.A.

g.

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

N.A.

Y Z

h.

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

N.A.

221.71 psia 220.64 psia p

7.

Automatic Switchover g

Containment Sump

%g a.

Automatic Actuation logic and Actuation to g

Relays (SSPS)

N.A.

8 b.

RWST Level-Low-Low 3.4 1.21 2.0 136%

235.2%

Coincident with Safety Injection See Item 1. above for Safety Injection Trip Setpoints and Allowa'oie hiues.

8.

Loss of Power a.

4 kV Undervoltage

-Loss of Voltage N.A N.A.

N.A.

83V (120V Bus) 83+0,-8.3V (120V Bus) w/1s delay w/l+0.2,-0.Ss delay e'

'S a---.

s-e a-y

3 TABLE 4.3-6 J

REMOTL SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.

CHANNEL

~ CHANNEL INSTRUMENT CHECK CALIBRATION 1.

RCS Pressure - Wide Range M-R l

2.

Reactor Coolant Temperature - Cold Leg M

R i

3.

Source Range, Neutron Flux #

M R

j 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.

i 7.

Pressurizer Pressure M

R i

8.

Pressurizer Level M

R 9.

Steam Generator Pressure M

R 1

10.

Steam Generator Level M

R 3

11.

Auxiliary Feedwater Flow Rate M

R 12.

Auxiliary Feedwater Pump Suction Pressure M

R

-i

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

j q

i 1

3 CALLAWAY - UNIT 1 3/4 3-51

4 INSTRUMENTATION 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:

l a.

With the number of OPERABLE accident monitoring instrumentation i

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 i

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 STANBY 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 .

c.

With the number of OPERABLE channels for the containment radiation level monitors or the unit vent - high range noble gas monitor less I

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 within 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.

1 d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS I -

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

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION 9

TOTAL MINIMUM NO. OF CHANNELS 7

CHANNELS OPERABLE

=Z INSTRUMENT 1.

Containment Pressure 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 - Tao (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 1

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 f

12.

PORY Position Indicator

1/ Valve 1/ Valve A

13.

PORY_ Block Valve Position Indicator **

1/ Valve 1/ Valve Ef

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

15. Containment Normal Sump Level 2

1

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

N.A.

I

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

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

N.A.

1 l

l l

l

p.

TABLE 3.3-10 (Continuod)

TABLE NOTATIONS

.I

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 15 removed.

4 6

b F

b r

.I e

CALLAWAY - UNIT 1 3/4 3-54

'l CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL SYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 ACTION:

a.

With one containment hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6. hours and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.6.4.1 Each containment hydrogen analyzer shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and at least once per 31 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gas containing ten volume percent hydrogen, balance nitrogen.

l CALLAWAY - UNIT I 3/4 6-31 Amendment No.86

CONTAINMENT SYSTEMS HYDROGEN CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.4.2 A Hydrogen Control System shall be OPERABLE with two independent Hydrogen Recombiner Systems.

APPLICABILITY:

MODES 1 and 2 ACTION:

With one of the two independent Hydrogen Recombiner Systems inoperable, restore the inoperable Hydrogen Recombiner System to OPERABLE status within 30 days or 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 .

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE:

At least once per 6 months by verifying, during a Hydrogen Recombiner a.

System functional test, that the heater air temperature increases to greater than or equal to 1150'F within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ; and b.

At least once per 18 months by:

1)

Performing a CHANNEL CALIBRATION of all Hydrogen Recombiner System instrumentation and control circuits, 2)

Verifying through a visual examination that there is no evidence of abnormal conditions within the Hydrogen Recombiner System enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and 3)

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

t CALLAWAY - UNIT 1 3/4 6-32

,o'

.s

.s RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the follcwing unprotected outdoor tanks shall be limited to less than or equal to 159 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, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive 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 above listed tanks shall be determined to be within the above limit by 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.

CALLAWAY - UNIT 1 3/4 ll-T Amendment No. 50 g

L.

RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 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-tion exceeds 4% volume.

APPLICABILITY: At all times 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, 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 on oxygen to less than or equal to 4% by volume, then take ACTION a. above.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE RE0VIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP 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.

l

+

CALLAWAY - UNIT 1 3/4 11-2 Amendment No. 37, E9,86

___._____,__m____

m 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, 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.

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 positions. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or equivalent foms of documentation. These requirements shall be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

The Manager, Callaway Plant shall.have responsibility for overall anit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

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 to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

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

o 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 enmposed of a least the minimum shift 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 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 l

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. 37,85

ML20059C503

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