ML20094C798

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Amends 17 & 2 to Licenses NPF-11 & NPF-18,respectively, Changing Tech Specs Re Main Steamline Temp Difference Trip Setpoints & Allowable Values
ML20094C798
Person / Time
Site: LaSalle  
(NPF-11-A-017, NPF-11-A-17, NPF-18-A-002, NPF-18-A-2)
Issue date: 07/03/1984
From: Schwencer A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20094C799 List:
References
NUDOCS 8408080155
Download: ML20094C798 (8)


Text

,

O COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATI_0N, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment 17 License No. NPF-11 1.

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

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A. - Tiie oppitcatfor, for amendment filed by the Cc:=cnwealth Edisen Company, dated May 25, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the

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Act), and the Comission'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 Comission;

-C.

There is reasonable assurance:

(i)thattheactivitiesauthorized 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 Ccmission's regulations set forth in 10 CFR Chapter I; 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 acccrdance with 10 CFR Part 51 of the Comission's. regulations and all applicable requirements have been satisfied.

k 2.

Accordingly, the license is amended by changes to the Technical I

Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11

'hereby amended to read as follows:

'(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 17, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

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The license shall operate the facility in accordance with the C

Technical Specifications and the Environmental Protection Plan.

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3. -This amendment is effective as of date of issuance, s

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FOR THE NUCLEAR REGULATORY COMMISSION a -

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A. Schwencer, Chief Licensing Branch No. 2 ichiji[,,,,

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-Division of Licensing p' ' '

Enclosure:

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  • Changes-to.the Technical l f,,, : Specifications

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ENCLOSURE TO LICENSE AMENDMENT NO. 17 FACILITY OPERATING LICENSE NO. NPF-11

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DOCKET NO. 50-373 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and

- contain a vertical line indicating the arca of change.

REMOVE INSERT 3/4 3-15 3/4 3-15

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ISOLATION ACTUATION INSTRUMENTATION SETPOINTS i=

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ALLOWABLE m

TRIP FUNCTION TRIP SETPOINT VALUE h.

AUTOMATIC INITIATION h

1.

PRIMARY CONTAINMENT ISOLATION a.

' Reactor Vessel Water Level.

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2)-

Low Low, level 2 I -50 inches *

'~> 11.0 inches

  • 1)

Low, level 3

> 12.5 inches *

> -57 inches

  • b.

Drywell Pressure - High 1 1.69 psig i 1.89 psig c.

Main Steam Line 1)

Radiation - High 1 3.0 x full power background.

1 3.6 x full background 2)

Pressure - Low

> 854 psig

> 834 psig 3)

Flow - High 1 111 psid i 116 psid d.

Main Steam Line Tunnel Temperature - High i 140*F i 146 F w1 e.

Main Steam Line Tunnel m

. A Temperature - High 136 *F

< 42 F l.

4 f.

Condenser Vacuum - Low

> 7 inches Hg vacuum i 5.5 inches Hg vacuum w

2.

SEC0NDARY CONTAINMENT ISOLATION a.

Reactor Building Vent Exhaust Plenum Radiation - High i 10 mr/hr i 15 mr/hr b.

Drywell Pressure - High

'1 1.69 psig i 1.89 psig c.

Reactor Vessel Water Level - Low Low, Level 2

> -50 inches *

> -57 inches

  • d.

Fuel Pool Vent Exhaust Radiation - High 1 10 mr/hr i 15 mr/hr 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION l

a.

AFlow - High i 70 gpm 1 87.5 gpm g.

b.

Heat Exchanger Area Temperature g

- High i 181*F i 187 F c.

Heat Exchanger Area Ventilation g

AT - High 1 85*F 1 91*F d.

Pump Area Temperature - High 1 116 F i 122*F G

e.

Pump Area Ventilation AT - High 1 13*F i 19*F f.

SLCS Initiation NA NA g.

Reactor' Vessel Water Level -

Low Low, Level 2

> -50 inches *

> -57 inches

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COMMONWEALTH EDISON COMPANY

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DOCKET NO. 50-374 r,

LA SALLE COUNTY STATION, UNIT 2 4

AMENDMENT TO FACILITY OPERATING LICENSE Amendment 2 License No. NPF-18

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1.

The Nuclear Regulatory Comission (the Comission or the NRC) having

.found.that:

1g;.5 [150 appl 1 cati ~on for amendment filed by the Comonwealth Edison pg= ~'A..

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' Company, dated May 25, 1984, complies with the standards and

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requirements of the Atomic Energy Act of 1954, as amended (the

Act), and the Comission's regulations set forth in 10 CFR

-Chapter I;.

'B.

'The facility will. operate in confomity with the application, 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

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D and~ safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth

.ini10'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 J.-

The Lissuance of this amendment is in accordance with 10 CFR Part 51

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E of the Comission'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 the Facility Operating License No. NPF-18 t

Lhereby amended to read as follows:

,(2)' Technical Specifications ar.d Environmental Protection Plan

-The Technical Specifications contained in Appendix A, as revised

.through Amendment No. 2, and the Environmental Protection Plan

' contained in Appendix B,. are hereby incorporated in the license.

-The license shall operate the facility in accordance with the

~. Technical Specifications and the Environmental Protection Plan.

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32 This amendment is effective as of.date of issuance.

g FOR THE NUCLEAR REGULATORY COMMISSION Originalsigned by A. Schwencer, Chief Licensing Branch No. 2 o,

Division of Licensing m,.~<,,,_

Enclosure:

Changes.to'the Technical

. Specifications-Date of Issuance: JUL 0 3 24

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fts ENCLOSURE TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following page of the~ Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contain a vertical-line indicating the area of change.

REMOVE INSERT 3/4'3-15 3/4 3-15 m

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TABLE 3.3.2-2 r-

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ISOLATION ACTUATION INSTRUMENTATION SETPOINTS;

. TRIP SETPOINT VALUE ALLOWABLE p

TRIP FUNCTION

'A.

AUTOMATIC INITIATION c-$

1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low, Level 3

> 12.5 inches *

> 11.0 inches

  • 2)

Low Low, Level 2

[-50 inches *

[-57 inches

  • b.

Drywell Pressure - High 5 1.69 psig i 1.89 psig c.

Main Steam 4.ine 1)

Radiation - High 5 3.0 x full power background 5 3.6 x full background 2)

Pressure - Low

> 854 psig

> 834 psig 3)

Flow - High 5 111 psid 5 116 psid d.

Main Steam Line Tunnel Temperature - High 5 140*F 5 146 F e.

Main Steam Line Tunnel w}

A Temperature - Hioh 5 36 F

$ 42 F l

f.

Condenser Vacuum - Low

> 7 inches Hg vacuum

> 5.5 inches Hg vacuum 5

2.

SECO'NDARY CONTAINMENT ISOLATION a.

Reactor Building Vent Exhaust Plenum Radiation - High 5 10 mr/h 5 15 mr/h b.

Drywell Pressure - High

$ 1.69 psig 5 1.89 psig c.

Reactor Vessel Water Level - Low Low, Level 2

> -50 inches

  • d.

Fuel Pool Vent Exhaust

> -57 inches

  • Radiation - High 5 10 mr/h 5 15 mr/h R

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

AFlow - High

-< 70 gpm

-< 87.5 gpm b.

Heat Exchanger Area Temperature 5

- High

~< 181*F

~< 187 F

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c.

Heat Exchanger Area Ventilation AT - High

< 85

< 91*F d.

Pump Area Temperature - High 5116F

{122F e.

Pump Area Ventilation AT - High

$ 13*F

$ 19 F f.

SLCS Initiation N.A.

N'. A.

g.

Reactor Vessel Water Level -

Low Low, Level 2

> -50 inches *

> -57 inches"