ML20046B353

Amend 161 to License DPR-61,revising TS to Reflect Mods Made to Modernize SG Feedwater Control Sys

ML20046B353
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/14/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20046B351	List: ML20046B350 ML20046B353 ML20046B358 ML20046B361
References
NUDOCS 9308040107
Download: ML20046B353 (13)

Text

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UNITED STATES ig, TI NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D.C. 20555-0001 i

CONNECTICVT YANKEE ATOMIC POWER COMPANY i

DOCKET NO. 50-213 HADDAM NECK PLANT l

AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 161 License No. DPR-61 1.

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

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated January 29, 1993, as supplemented April 30, 1993, 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 protisions 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; i

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.

9308040107 930714 PDR ADOCK 05000213 P

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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-61 is hereby amended to read as follows:

(2) Technical Specifications

{

The Technical Specifications contained in Appendix A, as revised l

through Amendment No.161, are hereby incorporated in the license.

l The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

f FOR THE NUCLEAR REGULATORY COMMISSION

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a a

F. Stolz, Directo

[' Pro,j ect Directorate I/4 Whision of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment-I Changes to the Technical l

Specifications Date of Issuance: July 14, 1993 1

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ATTACHMENT TO LICENSE AMENDMENT NO. 161 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 3-3 3/4 3-3 3/4 3-6 3/4 3-6 3/4 3-10 3/4 3-10 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 i

3/4 3-20 3/4 3-20 3/4 3-22 3/4 3-22 B3/4 3-1 B3/4 3-1 B3/4 3-la i

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TABLE 3.3-1 (Continued) jg REACTOR TRIP SYSTEM INSTRUMENTATION

=

- ca 5"

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE ll FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION n

8.

Steam Flow-High 4 (1/ steam line) 2 1/ steam line 1, 2 9#

9.

Steam Generator Water 3/SGlevel 2/SG level 2/SG level 1, 2 6#

Level-Low and coincident and Coincident With with Steam /Feedwater Flow 2/ steam / feed-1/ steam / feed-1/ steam / feed-Mismatch water flow water flow water flow mismatch in mismatch mismatch each SG in same loop in each SG

10. Undervoltage - Reactar 2 (1/ bus) 1 2 (1/ bus) 1( )

8 4g Coolant Pumps a

y>

11. Safety Injection 2

1 2

1, 2 12 w

a 3o t:?

rn m-m

.m

...m v-.,s

4 TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 4:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes and restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or open/ verify open the Reactor Trip System breakers within the next hour.

ACTION 5:

Action has been deleted.

ACTION 6:

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 nours; however, the inoperable channel may be bypassed up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, reduce THERMAL POWER to below 74% of RATED THERMAL POWER (P-8) within I hour and place the inoperable channel in the trip position within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

ACTION 8:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirerent, reduce THERMAL POWER to below 10% of RATC9 THERMAL POWER (P-7) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 9:

With the number of OPERABLE channels one less than the Mirn>ww Channels OPERABLE requirement, STARTUP and/or POWER OPERATION may pre'.eed until performance of the next required ANALOG CHANNEL OPERATIONAL. TEST provided that the inoperable channel is placed in the tripped condition within I hour.

i HADDAM NECK 3/4 3-6 Amendment No. JJJ,161, 0003

JABLE 4.3-1 (Continued)

REACTOR TRIP SISTEM INSTRUNENTATION SURVEILLANCE REQUIRENENTS

'M TRIP ANALOG ACTUATING MODES FOR E

CHANNEL DEVICE WHICH E

CHANNEL CHANNEL OPERATIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION IEST TEST IS REQUIRED 8.

Steam Flow--High S

R(5)

SW N.A.

1, 2 l

9.

Steam Generator Water Level--Low Coincident with Steam /Feedwater Flow Mismatch S

R SW N.A.

1, 2 l

10. Undervoltage - Reactor Coolant Pumps N.A.

R N.A.

R 1(*)

{ 11.

Safety Injection N.A.

N.A.

N.A.

R 1, 2 Y 12.

Reactor Coolant Pump I ")

I 5

Breaker Position Trip N.A.

N.A.

N.A.

R

13. Main Steam Line Trip Valve Closure N.A.

N.A.

N.A.

R 1(,)

14. Turbine Trip N. A.

N.A.

N.A.

R 1(a)

{i n

M Y

TABLE 3.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

~

5 MINIMUM 08 TOTAL NO.

CHANNELS CHANNELS APPLICABLE E

FUNCTIONAL UNIT OF CHANNELS TO ACTUATE OPERABLE MODES ACTION

=y 3.

Auxiliary Feedwater a.

Wide Range Stm. Gen. Water Level--Low 1)

Four Loops 8

2 Channels 8

1(a)(b)(d) 21 Operating in any one train 2)

Three Loops 6

2 channels 6

1(a)(b)(d)#

26 Operating in any one train w

b.

Trip of All Main 1/ pump 1 from each 1/ pump 1(a) 26 1

Feedwater Pumps pump w

d-c.

DC powered hydraulic pump 1/ pump 1/ pump 1/ pump 1, 2, 3 27 autostart 4.

Emergency Bus Undervoltage E

a.

4.16 kV Bus Under-3/ bus 2/ bus 2/ bus 1, 2, 3, 4 24

{

voltage-Level 1 s

E b.

4.16 kV Bus Undervoltage-

[

Level 2 3/ bus 2/ bus 2/ bus 1, 2, 3, 4 24 o

c.

4.16 kV Bus Undervoltage-Level 3 3/ bus 2/ bus 2/ bus 1, 2 24 Three loop operation is not allowed for Cycle 17.

a t

TABLE 3.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

.B

=

"8 MINIMUM 2

TOTAL NO.

CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO ACTUATE OPERABLE MODES ACTION 9

5.

Containmert Isolation (Containment Air Recirculation System, Feedwater Isolation, Safety Injection) a.

Containment Pressure-High 4

2 3

1, 2, 3, 4 20, 24 b.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

g 6.

Feedwater Isolation Y

a.

Narrow Range Steam Generator 3/sta. gen.

2/stm. gen.

2/stm. gen.

I 24 E

Water Level--High in each in any in each operating operating operating loop loop loop f

a 2a

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TABLE 3.3-2 (Continued)

TABLE NOTATIONS

• Trip function may be bypassed in this MODE when RCS pressure is less than 1800 psig.

• • The channel (s) associated with the protective functions derived from the out-of-service reactor coolant loop shall be placed in the tripped mode.

(a) THERMAL POWER greater than 10% of RATED THERMAL POWER.

(b) For Surveillance Testing, at most only one train may be taken out of service at a time.

7 (c) Not used.

(d) For surveillance testing purposes, (item 3.a of Table 4.3-2) the minimum channels OPERABLE may be less than those specified in Table 3.3-2 for items 3.a.1 and 3.a.2.

ACTION STATEMENTS f

ACTION 20 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 21 With the number of OPERABLE c'.annels one less than the Minimum Channels OPERABLE requirement, startup and/or power operation may proceed until performance of the next required ANALOG CHANNE'. OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 22 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 23 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

HADDAM NECK 3/4 3-17 AmendmentNo.J7E,ffJ, c211

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v TABLE 3.3-3 (Continued) g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS m

E FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE x

R^

4.

Emergency Bus Undervoltage a.

4.16 kV Bus Undervoltage -

22870** volts 22784** volts Level I b.

4.16 kV Bus Undervoltage -

23684 volts 23664 volts Level 2 with a 9 second with a 8 second time delay, to 10 second time delay.

c.

4.16 kV Bus Undervoltage -

24019 volts with 23999 volts wich a level 3 a 9 second time 8 second to 10 delay.

second time delay.

w1 5.

Containment Isolation w

A, (Containment Air Recirculation System, Feedwater Isolation, Safety Injection) o a.

Containment Pressure - High 14.7 psig 55.0 psig b.

Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and allowable values.

g 6.

Feedwater Isolation E

Steam Generator Water Level--High 174% of narr9w-range 580% of narrow-range l

a.

l instrument span instrument span e

?

Rated Thennal Power Setpoint is by tap position. Time delay of device is inverse function of voltage. Device must change state within 0.95 - 1.05 seconds when the input voltage to the device goes from normal to 50% of the trip yg setting voltage instantaneously.

.i -

TABLE 4.3-2 (Continued)

E E!LQJNEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS l

g TRIP 1

ANALOG ACTUATING MODES FOR x

g CHANNEL DEVICE WHICH l

X CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK fallBRATION TEST TEST IS RE0VIRED 4.

Emergency Bus Undervoltage a.

4.16 kV Bus N.A.

R NA.

M*

1, 2, 3, 4 Undervoltage -

Level I b.

4.16 kV Bus N.A.

R N.A.

M*

1, 2, 3, 4 Undervoltage -

Level 2 c.

4.16 kV Bus N.A.

R N.A.

M*

1, 2 Undervoltage -

m A,

level 3 m

5.

Containment Isolation (Containment Air Recirculation System, Feedwater Isolation, Safety Injection) a.

Containment Pressure D

R SW H.A.

1, 2, 3, 4

--High b.

Safety Injection See Item 1. above for,all Safety Injection Surveillance Requirements.

g f6.

Feedwater Isolation E

Steam Generator Water S

R SW R

1 l

a.

M Level--High w(*

Trip actuating device operational test is defined as a test of each individual channel. A complete logic test g

will be perfonned on a refueling outage basis. On a monthly basis, en undervoltage condition will be initiated at the sensing device to verify the operability of the trip actuating device and verify that the associated alarm relays operate.

P i

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and Engineered Safety Features Actuation System instrumentation and interlocks ensure that: (1) the asso-ciated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out-of-service for testing or mainte-nance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reli-ability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assump-tions used in the safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.

The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The Feedwater Isolation circuit is considered to be OPERABLE p'rovided either the Feedwater Regulating Valve or the Feedwater Isolation MOV is available for automatic closure.

The Engineered Safety Feature Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.

To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Setpoints have been specified in Table 3.3-3.

Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error.

The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensi-tive to combinations indicative of various accidents, events, and tran-sients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break HADDAM NECK B3/4 3-1 Amendment No. JU, 161 essa

i 3

INSTRUMENTATION j

BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION AND ENGINEERED SAFETY FEKTJRES ACTUATION SYSTEM INSTRUMENTATION (continued)-

or loss-of-coolant accident:

(1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3) startup of the emergency diesel

.i generators,(4) containment isolation, (5)

Turbine trip, (6) auxiliary i

feedwater pumps start and automatic valves position, (7) containment l

cooling fans start and automatic valves position, and (8) essential service water pumps start and automatic valves position.

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HADDAM NECK B3/4 3-la Amendment No.161 eest

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