ML20211N801

Amend 14 to License NPF-38,changing Tech Specs by Bypassing nonsafety-related High Steam Generator Level Trip Below 20% of Rated Thermal Power,Adding Reactor Vessel Level Monitoring & Changing Location of Seismic Monitors

ML20211N801
Person / Time
Site:	Waterford
Issue date:	02/18/1987
From:	Joshua Wilson Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211N805	List: ML20211N801 ML20211N826
References
NUDOCS 8703020225
Download: ML20211N801 (20)

Text

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UNITED STATES 8'

'n NUCLEAR REGULATORY COMMISSION f

' E WASHINGTON, D. C. 20655

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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 License No. NPF-38 1.

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

A.

The applications for amendment, dated June 24, July 15, and August 29, 1986, as supplemented by letters dated October 3, November 3, and November 12, 1986 by Louisiana Power and Light Company (licensee),

comply with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the 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; 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-38 is hereby amended to read as follows:

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 14, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.

LP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

Jam s H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: February 18, 1987 l

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February 18, 1987 O

3-ATTACHMENT TO LICENSE AMENDMENT NO. 14 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 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 area of change. Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pages Overleaf Pages 3/4 3-3 3/4 3-4 3/4 3-36 3/4 3-35 3/4 3-37 3/4 3-38 3/4 3-44 3/4 3-43 3/4 3-45 3/4 3-45a 3/4 3-46 B 3/4 3-3 B 3/4 3-3a Pages 3/4 2-1, 3/4 2-2 and 3/4 2-2a are reissued for pagination purposes, and Page B 3/4 3-4 is reissued without change.

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TABLE 3.3-1 k

REACTOR PROTECTIVE INSTRUMENTATION E

2 MINIMUM E

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i

b 1.

Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 1

2 sets of 2 1 set of 2 2 sets of 2 3*, 4*, 5*

8 w

2.

Linear Power Level - High 4

2 3

1, 2 2#, 3#

3.

Logarithmic Power Level-High a.

Startup and Operating 4

2(a)(d) 3 1, 2 2#, 3#

4 2

3 3*, 4*, 5*

8 b.

Shutdown 4

0 2

3, 4, 5 4

4.

Pressurizer Pressure - High 4

2 3

1, 2 2#, 3#

i 5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2#, 3#

wA 6.

Containment Pressure - High 4

2 3

1, 2 2#,.3#

7.

Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

8.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

9.

Local Power Density - High 4

2(c)(d) 3 1, 2 2#, 3#

10. DNER - Low 4

2(c)(d) 3 1, 2 2#, 3#

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#-

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12. Reactor Protection System Logic 4

2 3

1, 2 5

3*, 4*, 5*

8

13. Reactor Trip Breakers 4

2(f) 4 1, 2 5

)

E 3*, 4*, 5*

8

14. Core Protection Calculators 4

2(c)(d) 3 1, 2 2#, 3# and 7

15. CEA Calculators 2

1 2(e) 1, 2 6 and 7 5

16. Reactor Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

7 TABLE 3.3-1 (Continued)

TABLE NOTATION q

With the protective system trip breakers in the closed position, the CEA' drive system capable of CEA withdrawal, and fuel in the reactor vessel.

1. The provisions of Specification 3.0.4 are not applicable.

-4 (a) Trip may be manually bypassed above 10 % of RATED THERMAL POWER; bypass shal1 be automatically removed when THERMAL POWER is less than or '

4 equal to 10 % of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matica11y removed whenever pressurizer pressure is greater than or equal to 500 psia.

-4 (c) Trip may be manually bypassed below 10 % of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than 4

or equal to 10 % of RATED THERMAL POWER.

During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5%

of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.

(d) Trip may be bypassed dering testing pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2.

(f) Each channel shall be comprised of two trip breakers; actual trip 1cgic shall be one-out-of-two taken twice.

(g) High steam generator level trip may be manually bypassed in Modes 1 and 2,

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at 20% power and below.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by 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/or open the protective system trip breakers, j

ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

If the inoperable channel is bypassed, the desirability of maintaining this chanel in the bypassed condition shall be reviewed in accordance with Specification 6.5.1.6k.

The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN.

WATERFORD - UNIT 3 3/4 3-4 AMENDMENT NO. 14

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INSTRUMENTATION SEISMIC' INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant-to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.

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b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event (one or more basemat accelerations of 0.05 g or greater) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days.

Data shall be retrieved from the accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

Each of the above seismic monitoring instruments which is actuated during a seismic event (one or more basemat accelerations of 0.05 g or greater) but is not accessible during power operation shall be restored to OPERABLE status and a~ CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below.

A supplemental report shall then be prepared and submitted to the Commission within 10 days pursuant to Specification 6.9.2 describing the additional data from these instruments.

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'dATERFORD - UNIT 3 3/4 3-35 l~

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TABLE 3.3-7

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SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS IL}TRUMENTSANDSENSORLOCATIONS

-RANGE OPERABLE 1.

riaxial Time-History Accelerograph System a.

Accelerometer (YT-SM 6000) Adjacent to RB -35 ft MSL 0.02-1.0 g 1

b.

Accelerometer (YT-SM 6001) RB +46'ft MSL 0.02-1.0 g 1

c.

Accelerometer (YT-SM 6002) Free Field Yard Area 0.02-1.0 g 1

d.

Starter Unit (YS-SM 6000) Adjacent to RB

-35 ft MSL 0.01-0.02 g 1

e.

Starter Unit (YS-SM 6001) RB +51 ft MSL 0.01-0.02 g 1

f.

Recorder (YR-SM 6000) Control Room RAB +46 ft MSL 0.02-1.0 g 1

g.

Control Unit (YZ-SM 6000) Control Room RAB +46 ft MSL 0.02-1.0 g 1*

h.

Playback Unit (YR-SM 6001) Control Room RAB +46 ft MSL 0.02-1.0 g 1

2.

Triaxial Peak Accelerographs a.

YR-SM 6020 RB +56 ft MSL 0-2 g 1

b.

YR-SM 6021 RB +8'2" MSL 0-2 g 1

c.

YR-SM 6022 RAB +21 ft MSL 0-2 g 1

3.

Triaxial Seismic Switches a.

Seismic Swtich (YS-SM 6060) RB -35 ft MSL 0.1-0.25 g 1

b.

Control Unit (YZ-SM 6060) Control Room RAB +46 ft MSL 0.1-0.25 g 1*

4.

Triaxial Response-Spectrum Recorders a.

YR-SM 6010 RB +10 ft MSL 1-32 Hz, 0-2 g 1

b.

YR-SM 6041 RAB -35 ft MSL 1-32 Hz, 0-2 g 1

c.

YR-SM 6042 RAB +21 ft MSL 1-32 Hz, 0-2 g 1

d.

Peak Shock Annunciator (YR-SM 6045)

RB -35 ft MSL 1-32 Hz, 0-2 g 1

e.

Peak Shock Annunciator Control Unit (YZ-SM 6045) Control Room RAB +46 ft MSL 1-32 Hz, 0-2 g 1

"With reactor control room annunciation.

WATERFORD - UNIT 3 3/4 3-36 AMENDMENT N0.14

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST 1.

Triaxial Time-History Accelerograph System a.

Accelerometer (YT-SM 6000) Adjacent to RB -35 ft MSL N.A.

R SA b.

Accelerometer (YT-SM 6001) RB

+46 ft MSL N. A.

R SA c.

Accelerometer (YT-SM 6002) Free Field Yard Area N.A.

R SA d.

Starter Unit (YS-SM 6000) Adjacent to RB -35 ft MSL M

R SA e.

Starter Unit (YS-SM 6001) RB

+51 f t MSL M

R SA f.

Recorder (YR-SM 6000) Control Room RAB +46 ft MSL M

R SA g.

Control Unit (YZ-SM 6000) Control Room RAB +46 ft MSL M

R SA*

h.

Playback Unit (YR-SM 6001) Control Room RAB +46 ft MSL N.A.

R SA 2.

Triaxial Peak Accelerographs a.

YR-SM 6020 RB +56 ft MSL N.A.

R N.A.

b.

YR-SM 6021 RB +8'2" MSL N.A.

R N.A.

c.

YR-SM 6022 RAB +21 ft MSL N.A.

R N.A.

3.

Triaxial Seismic Switches a.

Seismic Switch YS-SM 6060 RB -35 ft MSL M

R SA b.

Control Unit YZ-SM 6060 Control Room RAB +46 ft MSL M

R SA*

4.

Triaxial Response-Spectrum Recorders a.

YR-SM 6040 RB +10 ft MSL N.A.

R N.A.

b.

YR-SM 6041 RAB -35 ft MSL N.A.

R N.A.

c.

YR-SM 6042 RAB +21 ft MSL N.A.

R N.A.

d.

Peak Shock Annunciator YR-SM 6045 RB -35 ft MSL N.A.

R N.A.

e.

Peak Shock Annunciator Control Unit YZ-SM 6045 Control Room RAB

+46 ft MSL N.A.

R SA

• With reactor control room annunciation.

WATERFORD - UNIT 3 3/4 3-37 AMENDMENT NO.14

INSTRUMENTATION a

METEOROLOGICAL INSTRUMENTATION

' LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2_within the next 10 days outlining the cause of.the malfunction and the plans for restoring the channel (s) to OPERA 3LE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

k WATERFORD - UNIT 3 3/4 3-38

t TABLE 4.3-6 E

g REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL c'

INSTRUMENT CHECK CALIBRATION I

g 1.

Neutron Flux M

R*

~

2.

Reactor Trip Breaker Indication M

N.A.

w 3.

Reactor Coolant Temperature-Cold Leg (TCold)

M R

4.

Reactor Coolant Temperature -

Hot Leg (THot)

M R

5.

Pressurizer Pressure M

R 6.

Pressurizer Level M

R

{

7.

Steam Generator Level M

R w

8.

Steam Generator Pressure M

R 9.

Shutdown Cooling Flow Rate M

R 10.

Emergency Feedwater Flow Rate M

R 11.

Condensate Storage Pool Level M

R

• Neutron detector may be excluded from CHANNEL CALIBRATION.

1 4

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 Table 3.3-10 shall be OPERABLE.The accident monitoring instrumentation cha APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With the number of OPERABLE accident monitoring channels less than a.

the Required Number of Channels shown in Table 3.3-10, take the action identified in Table 3.3-10.

b.

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, take the action identified in Table 3.3-10.

The provisions of Specification 3.0.4 are not applicable.

c.

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

WATERFORD - UNIT 3 3/4 3-44 AMEN 0 MENT N0.14

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5 TABLE 3.3-10 i

g ACCIDENT MONITORING INSTRUMENTATION i

A4 REQUIRED MINIMUM S

NUMBER OF CHANNELS o

INSTRUMENT CHANNELS OPERABLE

' ACTION I

l E

1.

Containment Pressure 2

1 29,30 l

p 2.

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

29,30 l

3.

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

29,30 w

l 4.

Reactor Coolant Pressure - Wide Range 2

1 29,30 5.

Pressurizer Water Level 2

1 29,30 6.

Steam Generator Pressure 2/ steam generator 1/ steam generator 29,30 7.

Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator 29,30 l

8.

Steam Generator Water Level - Wide Range 1/ steam generator **

1/ steam generator ** 29,30 9.

Refueling Water Storage Pool Water Level 2

1 29,30 10.

Emergency Feedwater Flow Rate 1/ steam generator **

1/ steam generator ** 29,30 m

h 11.

Reactor Cooling System Saturation Margin Monitor 2

1

.29,30 l

12.

Safety Valve Position Indicator 1/ valve 1/ valve 29,30 13.

Containment Water Level (Narrow Range) 1***

1***

29,30 14.

Containment Water Level (Wide Range) 2 1

29,30 15.

Core Exit Thermocouples 4/ core quadrant 2/ core quadrant 29,30 16.

Containment Isolation Valve Position. Indicators

• 1/ valve #

1/ valve #

29,30 29,30 17.

Condensate Storage Pool Level 2

1 i

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18.

Reactor Vessel Level Monitoring System 2****

1 31,32 1

E E

g

1. If the containment isolation valve is declared inoperable and the provisions of Specification 3.6.3 are-l complied with, position indicators may be inoperable; otherwise, comply with the provisions of H

g Specification 3.3.3.6.

I h

• Containment isolation valves listed in Table 3.6-2 (Category 1).

1 a

• • These corresponding instruments may be substituted for each other.

• • • 0peration may continue for up to 30 days with less than the Minimum Channels ~0PERABLE requirement.

• • • • A channel is eight sensors in a probe. A channel is operable if four or more sensors, one or more in the upper j

three and three or more in the lower five, are operable.

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TABLE 3.3-10 ACTION STATEMENTS I

ACTION 29 -

With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, i

either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 30 -

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10; either restore the inoperable channel (s) 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 31 -

With the number of OPERABLE accident monitoring channels, less than the Required Number of Channels, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 32 -

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory; 2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 3.

Restore the system to OPERABLE status at the next scheduled refueling.

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l WATERFORD - UNIT 3 3/4 3-45a AMENDMENT NO.14 l

s TABLE 4.3-7 c4 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 98 i

E CHANNEL CHANNEL i

INSTRUMENT CHECK CALIBRATION 1.

Containment Pressure M

R w

2.

Reactor Coolant Outlet Temperature - THot (Wide Range)

M R

3.

Reactor Coolant Inlet Temperature -TCold (Wide Range)

M R

4.

Reactor Coolant Pressure - Wide Range M

R 5.

Pressurizer Water Level M

R 6.

Steam Generator Pressure M

R 7.

Steam Generator Water Level - Narrow Range M

R y

8.

Steam Generator Water Level - Wide Range M

R w

9.

Refueling Water Storage Pool Water Level M

R

]

10.

Emergency Feedwater Flow Rate M

R 11.

Reactor Coolant System Saturation Margin Monitor M

R 12.

Safety Valve Position Indicator M

R 13.

Containment Water Level (Narrow Range)

M R

14.

Containment Water Level (Wide Range)

M R

15.

Core Exit Thermocouples M

R 16.

Containment Isolation Valve Position M

R R

17.

Condensate Storage Pool Level M

R 18.

Reactor Vessel Level Monitoring System M

R m.-.

5

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INSTRUMENTATION BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." Table 3.3-10 includes Regulatory Guide 1.97 Category I key variables.

The remaining Category I variables are included in their respective specifications.

The Subcooled Margin Monitor (SM), the Heated Junction Thermocouple (HJTC),

and the Core Exit Thermocouples (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post TMI-2 3

Action Plan.

The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to existence of, and recovery from ICC.

Additionally, they aid in tracking reactor coolant i

inventory.

These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37.

These are not required by the accident analysis, nor to bring the plant to Celd Shutdown.

In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and reactor vessel head are removed.

It is not feasible to repair a channe!

except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core.

If only one channel is inoperable, it should be restored to OPERABLE status in a refueling outage as soon as reasonably possible.

If both channels are inoperable, at least one channel shall be restored to OPERABLE status in the nearest refueling outage.

l 3/4.3.3.7 CHEMICAL DETECTION SYSTEMS The OPERABILITY of the chemical detection systems ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chemical release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975 aad the recommendations of Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," June 1974.

3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early l

WATERFORD - UNIT 3 8 3/4 3-3 AMEN 0 MENT N0.14

s stages.

Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

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WATERFORD - UNIT 3 8 3/4 3-3a AMENDMENT NO. 14 I

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INSTRUMENTATION BASES 3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the require-ments of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment, or structures.

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WATERFORD - UNIT 3 8 3/4 3-4

3/4.2 POWER DISTRIBUTION LIMITS 3/4 2.1 LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.1 The linear heat rate limit (of Figure 3.2-1) shall be maintained by one of the following methods as applicable:

Maintaining COLSS calculated core power less than or equal to COLSS a.

calculated core power operating limit based on linear heat rate (when COLSS is in service); or b.

Operating within the region of acceptable operation of Figure 3.2-la using any operable CPC channel (when COLSS is out of service).

APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.

ACTION:

With the linear heat rate limit not being maintained as indicated by:

1.

COLSS calculated core power exceeding COLSS calculated core power operating limit based on linear heat rate; or 2.

When COLSS is out of service, operation outside the region of accep-table operation in Figure 3.2-la; within 15 minutes initiate corrective action to reduce the linear heat rate to within the limits and either:

Restore the linear heat rate to within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or a.

b.

Be in at least HOT STAHOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.1.1 The provisions of Specification 4.0.4 are not applicable.

The linear heat rate shall be determined to be within its limits when 4.2.1.2 THERMAL POWER is above 20% of RATED THERMAL POWER by continuously monitoring the core power distribution with the Core Operating Limit Supervisory System (COLSS) or, with the COLSS out of service, by verifying at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> that the linear heat rate, as indicated on any OPERABLE Local Power i

l Density channel, is within the limits shown on Figure 3.2-la.

4.2.1.3 At least once per 31 days, the COLSS Margin Alarm shall be verified to actuate at a THERMAL POWER level less than or equal to the core power operating limit based on kW/ft.

WATERFORD - UNIT 3 3/4 2-1 AMENDMENT NO. 12

J L s

j 13.4 a 557.5'F Kw/FT

,g 13.4 e

UNACCEPTABLE I

OPERATION e

1. 4 13.3 2

e E

cc E

13.1

(

w 0

F 13.1 Kw/FT 6

a 520*F\\

ACCEPTABLE cc 13'2 OPERATION y

i a

6 l

a.

13.0!

l 51C 520 530 540 550 560 i

Tc INITIAL CORE COOLANT INLET TEMPERATURE, 'F.

i i

FIGURE 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc WATERFORD - UNIT 3 3/4 2-2 AMENDMENT NO. 12

D 13.8 a 557.5'F

}

Kw/FT -

g 13.8 0 3 UNACCEPTABLE 3W OPERATION E!

Wi

<o 13.7 h

/

9o O

==

m4 2m 13.6 l

13.5 Kw/FT w2 a 520'F ACCEPTABLE I4 OPERATION m2

<o 13.5 2

a x

b' 13.4 l

510 520 530 540 550 560' i

Tc INITIAL CORE COOLANT INLET TEMPERATURE, 'F.

FIGURE 3.2-la ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT OF SERVICE WATERFORD - UNIT 3 3/4 2-2a AMEN 0 MENT NO. 12 l

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