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Amend 43 to License NPF-30,revising Tech Specs Re Steam Generator Low Low Level Trip Circuitry by Adding Environ Allowance Modifier & Trip Time Delay
	ML20245D075
Person / Time
Site:	Callaway
Issue date:	04/14/1989
From:	Hannon J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20245D076	List: ML20245D075; ML20245D082; ML20245D084;
References
	NUDOCS 8904280099
	Download: ML20245D075 (41)
	v • d • e

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DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-30 1.

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

A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated August 30, 1988, as supplemented by letters dated November 18 (2 letters) and December 28, 1988, and February 7, 10 and 15, 1989 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 Comission; C.

There is reasonable assurance (1) 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 Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

8904280099 890414 DR p

ADOCK O N 3 PNU L

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-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 43, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C/ WA $i '

John N.Hannon, Director

' Project Directorate III-3

/

Division of Reactor Projects - III, p

IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 14, 1989 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 43 OPERATING LICENSE NO. 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. Corresponding overleaf pages are provided to maintain document completeness.

REMOVE INSERT 2-5 2-5 2-5 a 2-5 b 2-5 c 3/4 3-3 3/4 3-3 3/43-3(a) 3/4 3-6 3/4 3-6 3/43-6(a) 3/4 3-6(a) 3/4 3-8 3/4 3-8 3/4 3-10 3/4 3-10 3/4 3-10(a) 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18

-3/43-18(a) 3/4 3-21(a) 3/4 3-25 3/4 3-25 3/4 3-25 3/4 3-25 3/4 3-25 3/4 3-25 d 3/4 3-25 e 3/4 3-25 f 3/4 3-31 3/4 3-31 3/4 3-32(a) 3/43-32(a) 3/4 3-36 3/4 3-36 3/4 3-36(a)

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TABLE NOTATIONS

0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup in accordance with approved procedures.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) The applicable MODES and ACTION statement for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l

for surveillance testing of other channels per Specification 4.3.1.1, and c.

Either, THERMAL POWER is restricted to less than or requal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range hutron Flux interlock)

Setpoint restere the inoperabit channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or b.

Above the P-6 (Intermediate Range Neutron Flux interlock)

Setpoint but be1N 10% of RATED THERMA POWER, restore the i

inoperable channet to OPE 8 TABLE status prior to increasing l'

THERMAL POWER above 10% of RATED THERMAL POWER.

CALLAWAY - UNIT 1 3/4 3-5 Amendment No.17 l

TABLE 3.3-1 (Continued) i ACTION STATEMENTS (Continued)

ACTION 4 - With the number of OPERABLE channels one lese, than the Minimum Channels OPERABLE requirement suspend all operat'ons involving positive reactivity changes.

ACTION 5 - a.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves BG-V178 and BG-V601 are closed and secured in position within the next hour.

b.

With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, and verify valves BG-V178 and BG-V601 2re cfosed and secured in position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured in position every 14 days.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - With an ir. operable delay timer in the Trip Time Delay circuitry, STARTUP and/or POWER OPERATION may proceed provided that the Vessel Delta-T (Power-), Power-2) channels in the affected protection sets are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification

3. 0. 2.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at itast HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing oer Specification 4.3.1.1, provided the other channel is OPERABLE.

I CALLAWAY - UNIT 1 3/4 3-6 Amendment No. J7, 43

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 10 - With the number of OPERABLE channels one less than the Minimum l

Channels OPERABLE requirement, restore the inoperable channel to f

OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 - With one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inop'erab.1,'e, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the affetted breaker inoperable and apply ACTION 9.

The breaker shall not be bypassed while one of the diverse trip features'is inoperable except for the time required for performing maintenance to restore the breaker to.

OPERABLE status.

ACTION 13 - With the number of OPERABLE channels less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that the Containment Pressure-Environmental Allowance Modifier channels in the affected protection rets are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

s CALLAWAY - UNIT 1 3/4 3-6(a) knendment No.19,43

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i FABLE 3.3-3 (Continued) j AC110N STATEMENTS (Continued) b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With less than the Minimum Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator 1

window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE channels one less than the Minimum t

Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable char.nel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve j

inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION required by Specification 3.7.1.2.

ACTION 25 - With the number of OPERABLE channels one les; than the Minimum Channels OPERABLE requirement, declare the afrected diesel generator and oft-site power source inoperable and take the ACTION requittd by Specification 3.8.1.1.

ACTION 26 - With the number of OPERABLE channels one less than the Minimum i

Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or initiate and maintain opera-

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tion of the Control Room Emergency Ventilation System.

AC110N 27 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDSY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

CALLAWAY - UNIT 1 3/4 3-21

i TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION. 27(a) - With an inoperable delay timer in the Trip Time Delay I

circuitry. STARTUP and/or POWER OPERATION may proceed provided that the Vessel AT (Power-1, Power-2) channels in the affected protection set are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 27(b) - With the number of OPERABLE channels less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided that the Containment Pressure-Environmental Allowance Modifier channels in the affected protection sets are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 27(c) - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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ENGINEERED SAFETY FEATURES RESPONSE TIMES J

INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 5.

Containment Pressure-High-3 a.

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< 32(1)/20(2) b.

Phase "B" Isolation 31.5 6.

Containment Pressure-High-2 Steam Line Isolation 5 2(5) 7.

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Steam Generator Water Level-High-High a.

Feedwater Isolation 5 2(5) b.

Turbine Trip 5 2.5 9.

Steam Generator Water Level-Low-Low a.

Start Motor-Driven Auxiliary Feedwater Pumps 5 60 (8) b.

Start Turbine-Driven Auxiliary Feedwater Pump 5 60 (8) 10.

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

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

I 1

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l CALLAWAY - UNIT 1 3/4 3-31 Amendment No. W. 43 1

l i

TABLE NOTATIONS (Continued) l (7)-

Diesel generator starting and sequence loading delays included.

Sequential transfer of charging pump. suction. from the VCT to the RWST (RWST valves open, then VCT valves close) is not included.

Response time 8ssumes only. opening of RWST valves.

(8)~

Does not include Trip Time Delays.. Response times noted above include the transmitters 7300 process protection cabinets, solid state protection cabinets, and actuation devices only. This reflects the response times necessary for THERMAL POWER in excess of 20% RATED THERMAL POWER.

i 1

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LIMITING SAFETY SYSTEM SETTINGS BASES Steam Generator Water Level The Steam Generator Water Level Low-Low trip protects the reactor from loss of heat sink in the event of a sustained steam /feedwater flow mismatch resulting from loss of normal feedwater or a feedwater system pipe break, inside or outside of containment. This function also provides input to the steam generator level control system, therefore, the actuation logic must be able to withstand both an input failure to the control system (which may then require the protective function actuation) and a single failure in tne remaining channels providing the protection function actuation. This results in a 2/4 actuation logic. With the transmitters (d/p cells) located inside containment and thus possibly experiencing adverse environmental conditions (due to a feedline break),

the Environmental Allowance Modifier (EAM) was devised. The EAM function (Containment Pressure with a setpoint of < l.5 psig) senses the presence of adverse containment conditions (elevated pressure) and enables the Steam Generator Water Level - Low-Low trip setpoint (Adverse) which reflects the increased transmitter uncertainties due to this environment. The EAM allows the use of a lower Steam Generator Water Level - Low-Low trip setpoint (Normal) when these conditions are not present, thus allowing more margin to trip for normal operating conditions. The Trip Time Delay (TTD) creates additional operational margin when the plant needs it most, during early escalation to power, by allowing the operator time to recover level when the primary side load is sufficiently small to allow such action. The TTD is based on the continuous monitoring of primary side power through the use of Vessel AT. Two time delays are possible, based on the primary side power level, the magnitude of the trip delay decreasing with increasing power.

In the event that the EAM or TTD functions do not meet the minimum channels operable requirements, it is l

acceptable to place the inoperable channels in the Tripped Condition and continue operation.

Placing the inoperable channels in this mode will result in the enabling of the Steam Generator Water Level - Low-Low (Adverse) function, for the EAM, or in the removal of the trip delay, for the TTD.

In the event that the Steam Generator Water Level - Low-Low (Normal) function does not meet the minimum channels operable requirement, it is acceptable to place the associated EAM channe., in the Tripped Condition and continue operation. Performing this action will result in the enabling of the Steam Generator Water Level - Low-Low (Adverse) function which has a more conservative (higher level) trip setpoint.

At this time it would also be acceptable to place the inoperable Steam Generator Water Level - Low-Low channels in the Bypassed Condition to prevent an inadvertent Reactor Trip or ESFAS actuation.

Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide core protection against DNB as a result of complete loss of forced coolant flow.

The specified Setpoints assure a Reactor trip signal is gen.erated before the Low Flow Trip Setpoint is reached. Time delays are incorporated in the Underfrequency and Undervoltage trips to prevent spurious Reactor trips from monientary electrical power transients.

For undervoltage, the delay is set so that the time required I

CALLAWAY - UNIT 1 B 2-7 Amendment No. 43

LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltage and Underfrequency - Reactor Coolant Pump Busses (Continued) l 1

i for a signal to reach the Reactor trip breakers following the simultaneous trip l

of two or more reactor coolant pump bus circuit breakers shall not exceed 1.2 seconds.

For underfrequency, the delay is set so that the time required for a signal to reach the Reactor trip breakers after the Underfrequency Trip Setpoint is reached shall not exceed 0.3 second. On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of. approximately 10% of RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10% of full power equivalent); and on increasing power, reinstate:d automatically by P-7.

Turbine Trip A Turbine trip initiates a Reactor trip. On decreasing power the Reactor.

trip from the Turbine trip is automatically blocked by P-9 (a power level of approximately 50% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.

Safety Injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip'upon any signal which initiates a Safety Injection. The ESF instrumentation channels which initiate a Safety Injection signal are shown in Tabl e 3. 3-3.

CALLAWAY - UNIT 1 B 2-7(a)

Amendment No. 43

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LIMITING SAFETY SYSTEM SETTINGS BASE 5_

Reactor Trip System Interlocks lhe Reactor Trip System interlocks perform the following functions:

P-6 On increasing power, P-6 allows the manual block of the Source Range trip si.e., prevents premature block of Source Range trip), provides a backup block for Source Range Neutron Flux doubling, and allows deenergization of the high voltage to the detectors. On decreasing power, Source Range Level trips are automatically reactivated and high voltage restored.

P-7 On increasing power, P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, reactor coolant pump bus undervoltage and underfrequency, pressurizer low pressure and pres-surizer high level. On decreasing power, the above listed trips are automatically blocked.

P-8 On increasing power, P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops. On decreasing power, the P-8 automatically blocks the single loop Low Flow trip.

P-9 On increasing power, P-9 automatically enables Reactor trip on Turbine trip. On decreasing power, P-9 automatically blocks Reactor trip on Turbine trip.

P-10 On increasing power, P-10 allows the. manual block of the Intermediate Range trip and the Low setpoint Power Range trip; and automatically blocks the Source Range trip and de energizes the Source Range high voltage power. On decreasing power, the Intermediate Range trip and the Low Setpoint Power Range trip are automatically reactivated.

Provides input to P-7.

P-13 Provides input to P-7.

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CALLAWAY - UNIT 1 8 2-8

ML20245D075

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