ML20197F103

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Amends 41 & 22 to Licenses NPF-11 & NPF-18,respectively, Revising Tech Specs to Reflect Low &/Or Degraded Grid Voltage Mods
ML20197F103
Person / Time
Site: LaSalle  
Issue date: 05/09/1986
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20197F107 List:
References
NUDOCS 8605150429
Download: ML20197F103 (14)
v • d • e


Text

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b an 8

UNITED STATES 8

NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20555

'N

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-11 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 13, 1985, as supplemented by letters dated January 3 and March 10, 1986, complies with the 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 application, the provisions of the Act, and the regulations of the Commission; 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 set forth in 10 CFR Chapter 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 1

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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:-

i (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 41 and the Environmental Protection Plan contained in 4

Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

B605150429 860509 PDR ADOCK 05000373 P

PDR

, 3.

This amendment is effective upon startup following the first refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION

't Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing

Enclosure:

Changes to the Technical Specifications Date of Issuance:

May 9,1986 f

e P

I l

ENCLOSURE TO LICENSE AMENDMENT NO. 41 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed paces. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT l

3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-30(a) 3/4 3-34 3/4 3-34 1

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TABLE 3.3.3-1 (Continued)

E m

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION N

l;;

MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL E

TRIP FUNCTION FUNCTION (a)

CONDITIONS ACTION A

C.

DIVISION 3 TRIP SYSTEM g

1.

HPCS SYSTEM a.

Reactor Vessel Water Level - Low, Low, Level 2 4

1, 2, 3, 4*, 5*

35 b.

Drywell Pressure - High 4(c) 1, 2, 3 35.

c..

Reactor Vessel Water Level-High, Level 8 2(d) 1, 2, 3, 4*, 5*

32 d.

Condensat'e Storage Tank Level-Low 2(d) 1, 2, 3, 4*, 5*

36 e.

Suppression Pool Water Level-High 2

1, 2, 3, 4*, 5*

36 f.

Pump Discharge Pressure-High (Bypass) 1 1, 2, 3, 4*, 5*

31 R

g.

HPCS System Flow Rate-Low (Permissive) 1 1, 2, 3, 4*, 5*

31 h.

Manual Initiation

  • 1/ division 1, 2, 3, 4*, 5*

34 w

h D.

LOSS OF POWER MINIMUM APPLICABLE TOTAL NO.

INSTRUMENTS OPERABLE OPERATIONAL OF INSTRUMENTS TO TRIP INSTRUMENTS (a) CONDITIONS ACTION 1.

4.16 kv Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**

37 (Loss of Voltage) 2.

4.16 kv Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**

37 (Degraded Voltage)

(a) A channel instrument may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during periods of required surveillance without placing the trip system / channel / instrument in the tripped condition provided at least one other OPERABLE channel / instrument in the same trip system is monitoring that parameter.

(b) Also actuates the associated division diesel generator.

g (c).Provides. signal to close HPCS pump discharge valve only on 2-out-of-2 logic.

(d) Provides signal to HPCS pump suction valves only.

3 g.

Applicable when the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.

Required when ESF equipment is required to be OPERABLE.

3

<+

Not required to be OPERABLE when reactor steam dome pressure is < 122 psig.

E t

l t

l TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within one hour

  • or declare the i

associated system inoperable.

l b.

With more than one channel inoperable, declare the associated system inoperable.

i ACTION 31 -

With the number of OPERABLE channels less than required by the i

Minimum OPERABLE channels per Trip Function, place the inoperable channel in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 32 -

With the number of OPERABLE channels less than required by 1

the Minimum OPERABLE Channels per Trip Function requirement, I

declare the associated ADS trip system or ECCS inoperable.

ACTION 33 -

With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the i

inoperable channel in the tripped condition within one hour.

ACTION 34 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, 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 declare the associated ADS trip system or ECCS inoperable.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement For one trip system, place that trip system in the tripped a.

1

, condition within one hour

  • or declare the HPCS system 4

inoperable.

b.

For both trip systems. declare the HPCS system inoperable.

i ACTION 36 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at-least one inoperable channel in the tripped condition within i

one hour

ACTION 37 -

With the number of OPERABLE instruments less than the Minimum Operable Instruments, place the inoperable instrument (s)-in the tripped condition within I hour

"The provisions of Specification 3.0.4 are not applicable.

LA SALLE - UNIT 1 3/4 3-27 Amendment No. 41 j

l-

TABLE 3.3.3-2 (Continued) 5 EMERGENCY CORE COOLING. SYSTEM ACTUATION INSTRUMENTATION SETPOINTS 5-f:

ALLOWABLE m

TRIP FUNCTION TRIP SETPOINT VALUE i

ji 2.

4.16 kV Emergency Bus Undervoltage 1

(Degraded Voltage) s a.

4.16 kV Basis i

1) Divisions 1, 2 and 3 3814 1 76 volts with 3814 1 76 volts with g

10 1 1 seconds time 10 1 1 seconds time l

delay with LOCA signal delay with LOCA signal or or 5 1 0.5 minutes time 5 1 0.5 minutes time delay without LOCA delay without LOCA signal signal ti

+

Y.

.8 a

R E

5

^ ^

Tl;BLE 4.3.3.1-1 (Continued) 5 EMERGENCY CORE C00LINC SYSTED ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS F

CHANNEL OPERATIONAL CHAhNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH ji TRIP FUNCTION CHECK _

TEST CALIBRATION SURVEILLANCE REQUIRED 4

C. DIVISION 3 TRIP SYSTEM p.

1. HPCS SYSTEM a.

Reactor Vessel Water Level -

Low Low, Level 2 NA M

R 1, 2, 3, 4*, 5*

b.

Drywell Pressure-High NA M

Q 1, 2, 3 a

c.

Reactor Vessel Water Level-High Level 8 NA M

R 1, 2, 3, 4 *, 5*

d.

Condensate Storage Tank Level -

Low NA M

Q 1, 2, 3, 4*, 5*

R2 e.

Suppression Pool Water Level - High NA M

Q 1, 2, 3, 4*, 5*

i>

. f.

Pump Discharge Pressure-High NA.

M Q

1, 2, 3, 4*, 5*

g.

HPCS System Flow Rate-Low NA M

Q 1, 2, 3, 4*, 5*

h.

Manual Initiation NA R

NA 1, 2, 3, 4*, 5*

D. LOSS OF POWER-1.

4.16 kV Emergency Bus Under-voltage (Loss of Voltage)

NA NA R

1, 2, 3, 4**, 5**

2.

4.16 kV Emergency Bus Under-NA NA R

1, 2, 3, 4**, 5**

l voltage (Degraded Voltage) i

  1. Not required to be OPERABLE when reactor <ceam done pressure is less than or equal to 122 psig.
  • When the system is required to be OPERAPLE after being manually realigned, as applicable, per Specification 3.5.2.

l[

    • Required when ESF equipment is required to be OPERABLE.

EL

      • The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during g

Refuel 1, which is to commence no later than October 27, 1985.

E af f:

UNITED STATES h3 g

NUCLEAR REGULATORY COMMISSION g

j WA$HiNGTON, D. C. 20556

\\*****/

COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-18 1.

The Nuclear Regulatory Comission (the Comission or the NRC) having found that:

A.

The application for amendment filed by the Comonwealth Edison Company (the licensee), dated November 13, 1985, as supplemented by letters dated January 3 and March 10, 1986, complies with the 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 application, thet 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 Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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.

i 2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:

(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 22, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The_ licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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3.

This amendment is effective upon date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

+= c;m Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing

Enclosure:

Changes to the Technical Specifications Date of Issuance:

May 9,1986 b

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i ENCLOSURE TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-18

?

DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-30(a) 3/4 3-34 3/4 3-34

~

e e

L 1

.mmm

g

, TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL b

TRIP FUNCTION FUNCTION (d)

CONDITIONS ACTION

-4 C.

DIVISION 3 TRIP SYSTEM 1.

HPCS SYSTEM

~

Reactor Vessel Water Level - Low, Low, Level 2 4

1, 2, 3, 4*, 5*

35 a.

b.

Drywell Pressure - High 4(c) 1, 2, 3 35 c.

Reactor Vessel Water Level-High, Level 8 2(d) 1, 2, 3, 4*, 5*

32 d.

Condensate Storage Tank Level-Low 2(d) 1, 2, 3, 4*, 5*

36 e.

Suppression Pool Water Level-High 2

1, 2, 3, 4*, 5*

36 w

f.

Pump Discharge Pressure-High (Bypass) 1 1, 2, 3, 4*, 5*

31

.)

' g.

HPCS System Flow Rate-Low (Permissive) 1 1, 2, 3, 4*, 5*

31 w

h.

Manual Initiation 1/ division 1, 2, 3, 4 *, 5

  • 34 D.

LOSS OF POWER MINIMUM TOTAL NO.

INSTRU-OPERABLE APPLICABLE OF INSTRU-MENTS TO INSTRU-OPERATIONAL MENTS TRIP MENTS(a)

CONDITIONS ACTION 1.

4.16 kV Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**

37 (Loss of Voltage) 2.

4.16 kV Emergency Bus Undervoltage 2/b,us 2/ bus 2/ bus 2, 2, 3, 4**, 5**

37 (Degraded Voltage) (Divisions 2 and 3)

TABLE NOTATION (a) A channel / instrument may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during periods of required

{

surveillance without placing the trip system / channel / instrument in the tripped condition provided at least one other OPERABLE channel / instrument in the same trip system is monitoring that parameter.

s(

(b) Also actuates the associated division diesel generator.

(c) Provides signal to close NPCS pump discharge valve only on 2-out-of-2 logic.

=#

(d) Provides signal to HPCS pump suction valves only.

f Applicable when the system is required to.be OPERABLE per Specification 3.5.2 or 3.5.3.

Required when ESF equipment is required to be OPERABLE.

m N

Not required to be OPERABLE when reactor steam dome pressure is < 122 psig.

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within one hour

b.

With more than one channel inoperable, declare the associated system inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function, place the inoperable channel in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS inope.rable.

ACTION 33 -

With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 34 -

With the number of OPERABLE channels less than reouired by the Minimum OPERABLE Channels per Trip Function requirement, 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 declare the associated ADS valva or ECCS inoperable.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement

_ For one trip system, place that trip system in the tripped a.

. condition within one hour

b., For both trip systems, declare the HPCS system inoperable.

ACTION 36 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE-Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour

ACTION 37 -

With the number of OPERABLE instruments less than the Minimum OPERABLE INSTRUMENTS, place the inoperable instrument (s) in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

"The provisions of Specification 3.0.4 are not applicable.

LA SALLE - UNIT 2 3/4 3-27 Amendment No. 22

l g

TABLE 3.3.3-2 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS F

ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE D.

LOSS OF P0sER (Continued)

}

2.

4.16 kV Emergency Bus Undervoltage m

(Degraded Voltage) a.

4.16 kV Basis

1) Divisions 2 and 3 3814 1 76 volts with 3814 1 76 volts with 10 1 1 seconds time 10 i 1 seconds time delay delay with LOCA signal with LOCA signal or or 5 1 0.5 minutes time 5 1 0.5 minutes time delay delay without LOCA without LOCA signal R

signal 4

W I

9 T

I 4

4 F

~

L g

TABLE 4.3.3.1-1 (Continued) s EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS P

rn '

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH E

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Q

C.

DIVISION 3 TRIP SYSTEM w

1.

HPCS SYSTEM

~

Reactor Vessel Water Level -

a.

Low Low, Level 2 NA M

R 1, 2, 3, 4*, 5*

~

b.

Ibrywell Pressure-High NA M

Q 1, 2, 3 c.

Reactor Vessel Water Level-High Level 8 NA M

R 1,2,3,4*,5*

d.

Condensate Storage Tank Level -

Low NA M

Q, 1, 2, 3, 4 *, 5*

w'>

e.

Suppression Pool Water Level - High NA M

Q 1, 2, 3, 4*, 5*

w J,-

f.

Pump Discharge Pressure-High NA M

Q 1, 2, 3, 4*, 5*

g.

HPCS System Flow Rate-Low NA M

Q 1, 2, 3, 4*, 5*

h.

Manual Initiation NA R

NA 1, 2, 3, 4*, 5*

D.

LOSS OF POWER 1.

4.16 kV Emergency Bus Under-NA NA R

1, 2, 3, 4**, 5**

voltage.(Loss of Voltage) i 2.

4.16 kV Emergency Bus Under-NA NA R

1, 2, 3, 4**, 5**

voltage (Degraded Voltage)

(Divisions 2 and 3)

TABLE NOTATIONS I

  1. Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 122 psig.

a k

  • When the system is required to be OPERABLE after being manually realigned, as applicable, per 5

Specification 3.5.2.

    • Required when ESF equipment is required to be OPERABLE.

b

-

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