ML20100F606
| ML20100F606 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/14/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20100F610 | List: |
| References | |
| NPF-39-A-113, NPF-85-A-075 NUDOCS 9602210461 | |
| Download: ML20100F606 (10) | |
Text
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30086 0001
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No.113 1.icense No. NPF-39 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated July 28, 1995, complies with the standards and j
requirements of the f.t::nic Energy Act of 1954, as amended (the Act),
and the Comission'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 (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; D.
The issuance of this amendment will not be inimical to the comon defense and security cr 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.
l 9602210461 960214 PDR ADOCK 05000352 P
' 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 The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 113, 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, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 3
Jo 5 F. Stolz, Direct oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: February 14, 1996
~
j ATTACHMENT TO LICENSE AMENDMENT NO.113 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 3-7 3/4 3-7 3/4 3-8 3/4 3-8 F
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TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIRENENTS k
CHANNEL OPERATIONAL 5
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH E FUNCTIONAL UNIT CHECK TEST CALIBRATIONfa) SURVEILLANCE REQUIRED e
c 1.
Interinedtate Range Monitors:
5 a.
Neutron Flux - High S(b)
W R
2 l
[
S W(j)
R 3,4,5 b.
Inoperative N.A.
W(j)
N.A.
2,3,4,5 2.
Average Power Range Monitor (f):
a.
Neutron Flux -
S(b)
Q SA 2
Upscale, Setdown S
Q(j)
SA 3,5(k) b.
Neutron Flux - Upscale
- 1) Flow Biased S,D(g)
Q W(d)(e),SA 1
l j
- 2) High Flow Clamped S
Q W(d)(e),SA 1
l
{
c.
Inoperative M.A.
Q(j)
N.A.
1,2,3,5(k) d.
Downscale S
Q SA 1
3.
Reactor Vessel Steam Dome Pressure - High
-S Q
R 1,2(h)
F t
g 4.
Reactor Vessel Water Level-g-
Low, level 3 S
Q R
1, 2 a>
N 5.
241n Steam Line Isolation Valve - Closure N.A.
Q R
1 h
6.
DELETED DELETED DELETED DELETED DELETED l
7.
Drywell Pressure - High S
Q R
1, 2 w
8.
Scram Discharge Volume Water level - High 3
l
- a. Level Transmitter S
Q R
1,2,5(i) l
- b. Float Switch N.A.
Q R
1,2,5(1)
TABLE 4.3.1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATIOP SURVEILLANCE REQUIREMENTS
- ii g
CHANNEL OPERATIONAL p;
CHANNEL FUNCTIR1AL CHANNEL CONDITIONS FOR WHICH 3
FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED I
g 9.
Turbine Stop Valve - Closure N.A.
Q R
1 Z
10.
Turbine Control Valve Fast i
Closure, Trip 011 Pressure - Low N.A.
Q R
1 l
11.
Reactor Mode Switch r
Shutdown Position N.A.
R N.A.
1,2,3,4,5 i
12.
Manual Scram N.A.
W N.A.
1,2,3,4,5 l
(a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
}
(b)
The IRM and SRM channels shall be detemined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for a least 1/2 wi decades during each controlled shutdown, if not performed within the previous 7 days.
i (c)
DELETED l
w d.
(d)
This calibration shall consist of the adjustment of the APRM chinnel to confom to the power values calculated by l
a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER 225% of RATED THERMAL POWER. Adjust the APRM l
channel if the absolute difference is greater than 2% of RATED THERMAL POWER.
l (e)
This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
(f)
The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
k (g)
Verify measured core flow (total core flow) to be greater than or equal to established core flow at the existing g
loop flow (APRM % flow). During the startup test program, data shall be recorded for the parameters listed to g
provide a basis for establishing the specified relationships. Comparisons of the actual data in accordance with g
the criteria listed shall commence upon the conclusion of the startup test program.
1 l
(h)
This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification P
3.10.1.
(i)
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
t m
(j)
If the RPS shorting links are required to be removed per Specification 3.9.2, they may be reinstalled for up to 2 l
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> for required surveillance. During this time, CORE ALTERATIONS shall be suspended, and no control rod shall be moved from its existing position.
(k)
Required to be OPERABLE only prior to and during shutdown margin demonstrations as performed per Specification 3.10.3.
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 30668 4 001 l
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 i
LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.75 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated July 28, 1995, 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 (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; 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.
j
. 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-85 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 75
, 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, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 1
Q r
- s
/
/
Joh F. Stolz, Direct P ject Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 14, 1996
ATTACHMENT TO LICENSE AMENDMENT NO. 75 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 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 3-7 3/4 3-7 3/4 3-8 3/4 3-8
4 j
TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATI0t! SURVEILLANCE REOUIREMENTS l
C.
M CHANNEL OPERATIONAL iS CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH R FUNCTIONAL UNIT CHECK-TEST CALIBRATIONfa) SURVEILLANCE REQUIRED h 1.
Intermediate Range Nonitors
~
5 a.
Neutron Flux - High S(b)
W R
2 r
S W(j)
R 3,4,5 b.
Inoperative M.A.
W(j)
N.A.
2,3,4,5
[
2.
Average Power Range Monitor (f):
a.
Neutron Flux -
S(b)
Q SA 2
Upscale, Setdown S
Q(j)
SA 3,5(k)
E b.
Neutron Flux - Upscale l) Flow Biased S,0(g)
Q W(d)(e),SA 1
l 1
R
- 2) High Flow Clamped S
Q W(d)(e),SA l'
l l
y c.
Inoperative N.A.
Q(j)
N.A.
1,2,3,5(k) w i
d.
Downscale S
Q SA 1
3.
Reactor Vessel Steam Dome Pressure - High S
Q R
1,2(h) l C
y Reactor Vessel Water Level-e 4 Low, Level 3 S
Q R
1, 2 m
A 5.
Main Steam Line Isolation g
Valve - Closure N.A.
Q R
1 h 6.
DELETED DELETED DELETID DELETED DELETED N 7.
Drywell Pressure - High S
Q R
1, 2 8.
Scram Discharge Volume Water level - High
- a. Level Transmitter S
Q R
1,2,5(i)
- b. Float Switch N.A.
Q R
1,2,5(1) i
~
+
-i TABLE 4.3.1.1-I.(Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENT 4 i
G i
m E
CHANNEL OPERATIONAL i
E CHANNEL FUNCTIONAL CHAhMEL CONDITIONS FOR WHICH
[
FUNCTIONAL UNIT CHECK TEST CALIBRATIONfa)
SURVEILLANCE REQUIRED l
c 9.
Turbine Stop Valve - Closure N.A.
Q R
1 l
" 10.
Turbine Control Valve Fast Closure, Trip 011 Pressure - Low N.A.
Q R
1 11.
Reactor Mode Switch i
Shutdown Position N.A.
R N.A.
1,2,3,4,5 12.
Manual Scram N.A.
W N.A.
1,2,3,4,5 l
l (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
i t'(b)
The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for a least 1/2
)
decades during each controlled shutdown, if not performed within the previous 7 days.
Y (c)
" (d)
This calibration shall consist of the adjustment of the APRN channel to confom to the power values ca DELETED a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER 225% of RATED THERMAL POWER. Adjust the APRM 2
channel if the absolute difference is greater than 2% of RATED THERMAL POWER.'
E8 (e)
This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow l
signal.
A (f)
The LPRMs shall t,s calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
4 (g)
Verify measured core flow (total core flow) to be greater than or equal to established core flow at the existing w
loop flow (APRM % flow). During the startup test program, data shall be recorded for the parameters listed to provide a basis for establishing the specified relationships. Comparisons of the actual data in accordance with E
the criteria listed shall commence upon the conclusion of the startup test program.
L (h)
This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
(1)
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
l (j)
If the RPS shorting links are required to be removed per specification 3.9.2, they may be reinstalled for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance. During this time, CORE ALTERATIONS shall be suspended, and no control rod shall be moved from its existing position.
(k)
Required to be OPERABLE only prior to and during shutdown margin demonstrations as perfonned per Specification 3.10.3.
. m
.