ML20078C003

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Amends 85 & 46 to Licenses NPF-39 & NPF-85,respectively, Raising Steam Leakage Detection Sys set-points That Isolate Hpci & RCIC Sys Equipment on High Equipment Room Temp & High Delta Temp
ML20078C003
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/20/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co
Shared Package
ML20078C005 List:
References
NPF-39-A-085, NPF-85-A-046 NUDOCS 9501260138
Download: ML20078C003 (10)


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UNITED STATES a

j NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D.C. 20666 4 001

,o PHILADELPHIA ELECTRIC COMPAt[1 DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. NPF-39 1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated July 20, 1994, as supplemented on September 23, 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 Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be condacted 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; 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.

l 9501260138 950120 PDR ADOCK 05000352 P

PDR

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1 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-39 is hereby amended to read as follows:

Technical Soecifications i

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendmant No.

4 85, are hereby incorporated into this license.

Philadelphia Electric i

Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

4 3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMNISSION i

j

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h F. Stolz, Direc j

ect Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j

Attachment:

Changes to the Technical Specifications 4

Date of Issuance: January 20, 1995 4

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ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 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 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 4

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TABLE 3.3.2-2 (Centinued) r-ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

  • i2 ALLOWABLE y

TRIP FUNCTION TRIP SETPOINT VALUE 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION E

a.

RWCS a Flow - High 5 54.9 gpm 5 65.2 gpm b.

RWCS Area Temperature - High s 135*F or 12' r**

s 145'F or 130*F**

c.

RWCS Area Ventilation

{

a Temperature - High s 32 F

$ 40*F d.

SLCS Initiation N.A.

N.A.

e.

Reactor Vessel Water Level -

Low, Low, - Level 2 2 -38 inches

  • 2 -45 inches l

{

f.

Manual Initiation N.A.

N.A.

4.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.

HPCI Steam Line a Pressure - High 5 343" H,0 s 358" H,0 b.

HPCI Steam Supply Pressure - Low 2 100 psig 2 90 psig c.

HPCI Turbine Exhaust Diaphragm Pressure - High s 10 psig s 20 psig

$*g d.

HPCI Equipment Room Temperature - High 225*F 2 218'F, s 247'F l

e.

HPCI Equipment Room 4 Temperature - High 5 126*F s 130.5*F f.

HPCI Pipe Routing Area Temperature - High 175'F 2 165'F, s 200 F g.

Manual Initiation N.A.

N.A.

h.

HPCI Steam Line a Pressure - Timer 3 5 r s 12.5 seconds 2.5 s r s 13 seconds i

. -..... - - -. -... - -..... - ~. -... - _... - -

TABLE 3.3.2,Z (Centinued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5ig ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE n

5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION Eq a.

RCIC Steam Line a Pressure - High s 213" H,0 s 223" H,0 b.

RCIC Steam Supply Pressure - Low 2 64.5 psig 2 56.5 psig c.

RCIC Turbine Exhaust Diaphragm Pressure - High s 10.0 psig s 20.0 psig d.

RCIC Equipment Room Temperature - high 205'F 2 198'F, s 227*F l

R e.

RCIC Equipment Room a Temperature - High s 109*F s ll3.5"F l

Yg f.

RCIC Pipe Routing Area l

Temperature - High 175'F 2 165'F, s 200*F g.

Manual Initiation N.A.

N.A.

h.

RCIC Steam Line a Pressure Timer 3 s r s 12.5 seconds 2.5 s r s 13 seconds b

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Og UNITED STATES

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20666-0001

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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 i

LIMERICK GENERATING STATION. UNIT 2

{

MENDMENT TO FACILITY OPERATING LICENSE

{

l Amendment No. 46 License No. NPF-85 1.

The Nuclear Regulatory Comission (the Connission) has found that:

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated July 20, 1994, as supplemented on September 23, 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 Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the common l

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 Comission's regulations and all applicable requirements have been satisfied.

.,,...y_m

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l

and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:

Technical Soecificationt The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

46, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COPMISSION f

/,

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f.

Jh F. Stolz, Director j pr ject Directorate I-2/

D vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 20, 1995 I

ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 i

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 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 l

l I

i P

TABLE 3.3.2-2 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

,._g ALLOWABLE g

TRIP FUNCTION TRIP SETPOINT VALUE E

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION g

a.

RWCS A Flow - High s 54.9 gpm 5 65.2 gpa

[

b.

RWCS Area Temperature - High s 135*F or 122*F**

5 145'F or 130*F**

c.

RWCS Area Ventilation a Temperature - High s 32*F 5 40*F d.

SLCS Initiation N.A.

N.A.

e.

Reactor Vessel Water Level -

Low, Low, - Level 2 2 -38 inches

  • 2 -45 inches f.

Nanual Initiation N.A.

N.A.

g y

4.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISit.R[QN a.

HPCI Steam Line a Pressure - High s 343" H,0 s 358" H,0 b.

HPCI Steam Supply Pressure - Low 2 100 psig 2 90 psig c.

HPCI Turbine Exhaust Diaphragm Pressure - High 5 10 psig 5 20 psig d.

HPCI Equipment Room Temperature - High 225'F 2 218'F, s 247 F l

e.

HPCI Equipment Room g

a Temperature - High s 126*F s 130.5*F l

N f.

HPCI Pipe Routing Area y

Temperature - High 175*F 2 165'F, s 200*F g.

Nanual Initiation N.A.

N.A.

h.

HPCI Steam Line a Pressure - Timer 3 5 r s 12.5 seconds 2.5 s r s 13 seconds 1

TABLE 3.3.2-2 (Centinued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS r-2g ALLOWABLE TRIP FUNCTION TRIP.SETPOINT VALUE n

5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION E

q a.

RCIC Steam Line A Pressure - High 5 213" H,0 s 223" F(0 n,

b.

RCIC Steam Supply Pressure - Low 2 64.5 psig 2 56.5 psig c.

RCIC Turbine Exhaust Diaphragm Pressure - High s 10.0 psig s 20.0 psig d.

RCIC Equipment Room Temperature - High 205*F 2 198"F, s 227*F l

4" e.

RCIC Equipment Room i

A Temperature - High s 109*F s 113.5"F 1

Y 2;

f.

RCIC Pipe Routing Area Temperature - High 175*F 2 165*F, s 200'F g.

Manual Initiation N.A.

N.A.

h.

RCIC Steam Line a Pressure Timer 3 s r s 12.5 seconds 2.5 s r s 13 seconds e

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