Text

Amend to License DPR-50 Revising Plant TS to Modify Operational Safety Instrumentation Requirements to Specify Completion Time Which Allows for Performance of Maint
	ML20071L234
Person / Time
Site:	Crane
Issue date:	07/25/1994
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp
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ML20071L237	List: ML20071L234; ML20071L238;
References
	DPR-50-A-189 NUDOCS 9408030033
	Download: ML20071L234 (14)
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k UNITED STATES

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^j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 2055h 301 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LICHT COMPANY

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PENNSYLVANIA ELECTRIC COMPANY I

GPU NUCLEAR CORPORATION QOCKET N0. 50-289 j

THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE l

Amendment No. 189 License No. DPR-50 1.

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

A.

The application for amendment by GPU Nuclear Corporation, et al.

(the licensee), dated March 2,1994, 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 i

Chapter I; B.

The facility will operate in conformity with the application, the j

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 i

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 l

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, e

9400030033 940725 PDR ADOCK 05000289 P

PDR

- 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.

DPR-50 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.189, are hereby incorporated in the license.

GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f fV John F.

olz, Directo Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 25, 1994

i i

ATTACHMENT TO LICENSE AMENDMENT NO.189 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET N0. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Insert 3-27 3-27 3-27a 3-27a 3-29 3-29 3-30 3-30 3-30a 3-31 3-31 3-32 3-32 3-32a 3-32a 3-32b 3-32b 3-32c 4-5 4-5 O

3.5 INSTRUMENTATION SYSTEMS 3.5.1 OPERATIONAL SAFETY INSTRUMENTATION Applicability Applies to unit instrumentation and control systems.

Obiective i

To delineate the conditions of the unit instrumentation and safety circuits necessary to assure reactor safety.

Specifications 3.5.1.1 The reactor shall not be in a startup mode or in a critical state l

unless the requirements of Table 3.5-1, Column "A" and "B" are met, except as provided in Table 3.5-1, Column "C".

Specification 3.0.1 1

applies.

3.5.1.2 The key operated channel bypass switch associated with each reactor protection channel may be used to lock the reactor trip module in-the untripped state as indicated by a light. Only one channel shall be locked in this untripped state at any one time. Unit operation at rated power shall be permitted to continue with Table 3.5-1, Column "A".

Only one channel bypass key shall be kept in the control room.

3.5.1.3 In the event the number of protection channels operable falls below l

the limit given under Table 3.5-1, Column "A", operation shall be limited as specified in Column "C".

Specification 3.0.1 applies.

i 1

3.5.1.4 The key operated shutdown bypass switch associated with each reactor protection channel shall not be used during reactor power 1

operation (except for required maintenance or testing).

3.5.1.5 During START-UP when the intermediate range instruments come on scale, the overlap between the intermediate range and the source range instrumentation shall not be less than one decade.

3.5.1.6 During START-UP, HOT STANDBY or POWER OPERATION, in the event that a control rod drive trip breaker is inoperaWe, within one hour place the breaker in trip.

Specification 3.0.1 applies.

3.5.1.7 During START-UP, HOT STANDBY or POWER OPERATION, in the event that one of the control rod drive trip breaker diverse trip features (shunt trip or undervoltage trip attachment) is inoperable:

a.

Restore to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or b.

Within one additional hour place the breaker in trip.

Specification 3.0.1 applies.

27 Amendmiint No. %2, PS, J27,189

3.5.1.7.1 Power may be restored through the breaker with the failed trip feature for up to two hours for surveillance testing per T.S.

4.1.1.

3.5.1.8 During STARTUP, HOT STANDBY or POWER OPERATION, in the event that one of the two regulating control rod power SCR electronic trips is i

inoperable, within one hour:

a.

Place the inoperable SCR electronic trip in the tripped condition or b.

Remove the power supplied to the associated SCRs.

Specification 3.0.1 applies.

3.5.1.8.1 Power may be restored through the SCRs with the failed electronic trip for up to two hours for surveillance testing per T.S. 4.1.1.

3.5.1.9 The reactor shall not be in the Startup mode or in a critical state unless both HSPS actuation logic trains associated with the Functional units listed in Table 3.5-1 are operable except as provided in Table 3.5-1,D.

3.5.1.9.1 With one HSPS actuation logic train inoperable, restore the train to OPERABLE or place the inoperable device in an actuated state within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With both HSPS actuation logic trains inoperable, restore one train to OPERABLE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Bases Every reasonable effort will be made to maintain all safety instrumentation in operation.

The reactor trip, on loss of feedwater may be bypassed below 7%

reactor power. The bypass is automatically removed when reactor power is raised above 7%. The reactor trip, on turbine trip, may be bypassed below 45%

reactor power (Reference 1). The safety feature actuation system must have two analog channels functioning correctly prior to startup.

The anticipatory reactor trips on loss of feedwater pumps and turbine trip have been added to reduce the number of challenges to the safety valves and power operated relief valve but have not been credited in the safety analyses.

Operation at rated power is permitted as long as the systems have at least the redundancy requirements of Column "B" (Table 3.5-1).

This is in agreement with redundancy and single failure criteria of IEEE 279 as described in FSAR Section 7.

There are four reactor protection channels. Normal trip logic is two out of four. Minimum required trip logic is one out of'two.

3-27a Amendment No. J77, J7(, JJ), J57,189 T

b

TABLE 3.5-1 j[

o INSTRUMENTS OPERATING CONDITIONS En Ei Functional Unit (A)

(B)

(C) s Minimum Operable Minimum Degree Operator Action if Conditions

.?!

Channels of Redundancy of Column A and B Cannot be Het j$

A.

Reactor Protection System

((

l.

Manual pushbutton 1

0 (a) 2.

Power range instrument channel 2

1 (a) 3.

Intermediate range instrument 1

0 (a) (b) channels 4.

Source range instrument channels 1

0 (a) (c) 5.

Reactor coolant temperature 2

I (a) instrument channels b$

6.

(Deleted) 7 Flux / imbalance / flow 2

1 (a) 8.

Reactor coolant pressure a.

High reactor coolant pressure 2

1 (a) instrument channels b.

Low reactor coolant' pressure 2

(a) instrument channels

y TABLE 3.5-1 (Cont'd) g gt INSTRUMENTS OPERATING CONDITIONS e

!?

Functional Unit (A)

(B)

(C) i Minimum Operable Minimum Degree Operator Action if Conditions Channels of Redundancy of Column A and B Cannot Be Met 3

A.

Reactor Protection System (cont'd) 9.

Power / number of pumps 2

1 (a) instrument channels k$

10. High reactor building 2

1 (a) pressure channels e

(a) Restore the conditions of Column (A) and Column (B) within one hour or place the unit in HOT SHUTDOWN within an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

[3 (b) When 2 of 4 power range instrument channels are greater than 10 percent full power, intermediate range instrumentation is not required.

c' (c) When 1 of 2 -intermediate range instrument channels is greater than 10- amps, or 2 of 4 power range instrument channels are greater than 10 percent full power, source range instrumentation is not required.

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2 TABLE 3.5-1 (Cont'd)

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INSTRUMENTS OPERATING CONDITIONS a

=

P functional Unit (A)

(B)

(C)

_, i Minimum Operable Minimum Degree Operator Action if Conditions og Channels of Redundancy of Column A and B Cannot Be Met B.

Other Reactor Trips l

1.

Loss of Feedwater (c) 2 1

(a) 2.

Turbine Trip (c) 2 1

(b) l (a) Restore the conditions of Column (A) and Column (B) within one hour or reduce indicated reactor power to less than 7% within an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(b) Restore the conditions of Column (A) and Column (B) within one hour or reduce indicated reactor power to less than 45% within an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

u, E,

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(c) Trip may be defeated during low power physics tests.

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jf TABLE 3.5-1 (Cont'd) g 8t INSTRUMENTS OPERATING CONDITIONS g

i co y

Functional Unit (A)

(B)

(C)

Minimum Operable Minimum Degree Operator Action if Conditions Channels of Redundancy of Column A and 8 Cannot Be Met l

g:

5; C.

Engineered Safety Features e

1.

Makeup and Purification System (high pressure injection mode) a.

Reactor Coolant Pressure 2

1(b)

(a) l Instrument Channels b.

Reactor Building 4 psig 2

1(b)

(a)

)

Instrument Channels c.

Manual Pushbutton-2 N/A (g)

(also actuates Low Pressure Y'

Injection)

M 2.

Decay Heat System (low pressure injection mode) a.

Reactor Coolant Pressure 2

1(b)

(a)

Instrument Channels b.

Reactor Building 4 psig 2

1(b)

(a)

J Instrument Channels' c.

Reactor Coolant Pressure 1

0 Open circuit breaker at MCC D.H. Valve Interlock for DH-VI or DH-V2 with the affected valve in the closed Bistable position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or

\\

maintain R.C. pressure less than 350 psig.

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TABtE 3.5-1 (Cont'd) g

[

INSTRUMENTS OPERATING CONDITIONS a

E Functional Unit (A)

(B)

(C)

8 Minimum Operable Minimum Degree Operator Action if Conditions y

Channels of Redundancy of Column A and B Cannot Be Met l

[

C.

Engineered Safety Features (cont'd)

U 3.

Reactor Building Isolation and

?

Cooling System a.

Reactor Bldg. 4 psig 2

1(b)

(a) i Instrument Channel b.

Manual Pushbuttons 1.

4 psig feature 2

N/A (g)

11. 30 psig feature 2

N/A (g) c.

RPS Trip 2

1(b)

(a)

Y d.

Reactor Building 30 psig 2

1 (c)

M pressure switches e.

RCS Pressure less than 1600 psig 2

1(b)

(a) f.

Reactor Building Purge Line 1

0 (f)

Isolation (AHV-1A and i

AHV-10) High Radiation 4.

Reactor Building Spray System a.

Reactor Building 30 psig 2

1 (d) pressure switches b.

Spray Pump Manual Switches 2

N/A (g) 5.

4.16KV ES Bus Undervoltage, Relays a.

Degraded Grid Voltage Relays 2

I (e) b.

Loss of Voltage Relay 2

1 (e)

s

[

TABLE 3.5-1 (Cont'd) 3 INSTRUMENTS OPERATING CONDITIONS C.

Engineered Safety Features (cont'd)

(a) Restore the conditions of Column (A) and Column (B) within one hour or place the reactor in HOT SHUTDOWN I

E within an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i M

(b) The minimum degree of redundancy may be reduced to 0 up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for surveillance testing.

E (c) The Operability requirement is two out of three pressure switches in each train, with a minimum degree of redundancy of one, in each train.

1.

If the minimum conditions are not met on one train, restore the function to OPERABLE within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or place the reactor in HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

If the minimum conditions are not met on either train, then place the reactor in HOT SHUTDOWN in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(d) The Operability requirement is two out of three pressure switches in each train, with a minimum degree of redundancy of one, in.each train.

w w

E 1.

If the minimum conditions are not met on one train, restore the function to OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or i

place the reactor in HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

If the minimum conditions are not met on either train, then place the reactor in HOT SHUTDOWN in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(e) If a relay fails in the untripped state, it shall be placed in a tripped state within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to obtain a degree of redundancy of 1.

The relay may be removed from the tripped state for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for functional testing pursuant to Table 4.1-1.

(f) Discontinue Reactor Bui1 ding purging and close AHV-1A, IB, IC, and 10 within eight hours.

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TABLE 3.5-1 (Cont'd) a g

INSTRUMENTS OPERATING CONDITIONS a

C.

Engineered Safety Features (cont'd) 2 (g) The Operability requirement is for the manual actuation switch for the specified feature on each train to be 8

OPERABLE.

1.

If the manual actuation switch on one train is inoperable, restore the switch to OPERABLE status within 3

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SilUIDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

If both manual actuation switches for that feature are inoperable, then place the reactor in HOT SHUTDOWN in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

my s

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I

L jr TABLE 3.5-1 (Cont'd) g INSTRUMENTS OPERATING CONDITIONS g

?.

8f Functional Unit (A)

(B)

(C)

I Minimum Operable Minimum Degree Operator Action if Conditions Channels of Redundancy of Column A and B Cannot Be Met l

D.

Heat Sink Protection System 1.

EFW Auto Initiation a.

Loss of both Feedwater pumps N/A(b)

N/A(b)

(a) b.

Loss of all RC Pumps N/A(b)

N/A(b)

(a) c.

OTSG A low Level 2

1 (a) d.

OTSG B Low Level 2

1 (a) e.

High Reactor Building Pressure 2

1 (a) i 2.

MFW Isolation a.

OTSG A low Pressure 2

1 (a) b.

OTSG B Low Pressure 2

1 (a) 3.

EFW Level Control a.

OTSG A Level Control N/A(b)

N/A(b)

(a) i w

2, b.

OTSG B Level Control N/A(b)

N/A(b)

(a) 1 W

(a) Restore the conditions of Column (A) and Column (B) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or place the unit in HOT SHUTDOWN within f

the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(b) Operability requirements are specified in Section 3.5.1.9.

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TABLE 4.1-1 (Cont'd)

CHANNEL DESCRIPTION CHECK TEST CALIBRATE, REMARKS 5 19. Reactor Building Emergency g

Cooling and Isolation i

System Analog Channels 2

a. Reactor Building S(l)

M(1)

F (1) When CONTAINMENT INTEGRITY is required.

g 4 psig Channels

b. RCS Pressure 1600 psig S(l)

M(1)

NA (1) When RCS Pressure > 1800 psig.

g

c. RPS Trip S(l)

M(1)

NA (1) When CONTAINMENT INTEGRITY is required.

y

d. Reactor Bldg. 30 psig S(l)

M(1)

F (1) When CONTAINMENT INTEGRITY is required.

pressure switches l

,c

e. Reactor Bldg. Purge W(1)

M(1)

F (1) When CONTAINMENT INTEGRITY is required.

Line High Radiation q

(AH-V-1A/D) y

f. Line Break Isolation W(1)

M(1)

R (1) When CONTAINMENT INTEGRITY is required.

Signal (ICCW & NSCCW)

20. Reactor Building Spray NA Q

NA l

System Logic Channel

, 21. Reactor Building Spray NA M

F 30 psig pressure switches 22.. Pressurizer Temperature S

NA R

Channels

23. Control Rod Absolute Position S(l)

NA R

(1) Check with Relative Position Indicator.

24. Control Rod Relative Position S(l)

NA R

(1) Check with Absolute Position Indicator.

25. Core Flooding Tanks

a. Pressure Channels S(l)

NA F

(1) When Reactor Coolant system pressure is greater than 700 psig.

b. Level Channels S(l)

NA F

26. Pressurizer Level Channels 5

NA R

-

ML20071L234

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