ML20043F740
| ML20043F740 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/22/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043F741 | List: |
| References | |
| NUDOCS 9006180062 | |
| Download: ML20043F740 (12) | |
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UNITED STATES
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NUCLE AR REGULATORY COMMISSION a
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j PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-39 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by Philadelphia Electric Company (thelicensee)datedNovember 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set j
forth in 10 CFR Chapter I l
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 (i) that the activities authorized by this amendment can be conducted without endangering the health and tafety of the public, and (ii) that such activities will be conducted i
in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense end security or to the health and safety of the public; and j
E.
The issuance of this anendment is in accordance with 10 CFR Part 51 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 Facility Operating License No. NPF-39 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. 39 are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION l
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Walter R. Butler Director.
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Project Directorate I-2 Division of Reactor Projects I/II
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Attachment:
I Changes to the Technical-Specifications Date'of Issuance: May 22, 1990 i
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ff i
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La' Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1990
i ATTACHF.ENT TO LICENSE AMENDMENT NO. 39 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 Amendrent number and contain vertical lines indicating the area of change.
Remove Insert 3/4 1-9 3/419 3/4 1-10 3/4 1 10 i
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REACTIVITY CONTROL SYSTEMS CONTROL R00 SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.1.3.5 All control rod scram accumulators shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and $*.
ACTION:
a.
In OPERATIONAL CONDITION 1 or 2:
1.
With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
a)
Restore the inoperable accumulator to OPERABLE status, or b)
Declare the control rod associated with the inoperable accumulator inoperable.
Otherwise, 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 />.
2.
With more than one control rod scram accumulator inoperable, declare the associated control rods inoperable and:
a)
If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch.
If no control rod drive pump is operating and:
1)
If reactor pressure is 3900 psig, then restart at least one control drive, pump within 20 minutes or place the reactor mode switch in the shutdown position, or 2)
If reactor pressure is (900 psig, then place the l
reactor mode switch in the Shutdown position, b)
Insert the inoperable control rods and disarm the associated control valves either:
1)
Electrically, or L
2)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 5*:
1.
With one withdrawn control rod with its associated scram i
accumulator inoperable, insert the affected control rod and disarm the associated directional control valves within one hour, either:
a)
Electrically, or l-b)
Hydraulically by closing the drive water and exhaust water j
isolation valves.
"At least the accumulator associated with each withdrawn control rod.
Not i
applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
LIMERICK - UNIT 1 3/4 1-9 Amendment No. 39 l
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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 2.
With more than one withdrawn control rod with the associated scram accumulator inoperable or no control red drive pump oper-ating, immediately place the reactor mode switch in the Shutdown
- position, c.
The provisions of Specification 3.0.4 are not applicable.
4.1.3.5 Each control rod scram accumulator shall be determined OPERABLE:
a.
At least once per 7 days by verifying that the indicated pressure is greater than or equal to 955 psig unless the control rod is inserted and disarmed or scrammed, b.
At least once per 18 months by:
1.
Performance of a:
a)
CHANNEL FUNCTIONAL TEST of the leak detectors, and b)
CHANNEL CALIBRATION of the pressure detectors, and verifying an alarm setpoint of equal to or greater than 955 psig on decreasing pressure.
LIMERICK - UNIT 1 3/4 1-10 Amendment No. JI, 39 l
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NUCLEAR REGULATORY COMMISSION
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE 1
l Amendment No. 6 l
License No. NPF-85 1.
The Nuclear Regulatory Commission (the Comission) has found that A.
The application for amendment by Philadelphia Electric Company (thelicensee)datedNovember 17, 1989 complies with the standardsandrequirementsoftheAtomIcEnergyActof1954,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; l
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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications l
asindicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) l 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.
6, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1990 i
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'tib cv Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
i Changes to the Technical Specifications t
Date of Issuance: May 22, 1990 4
l 1
1 ATTACHMENT TO LICENSE AMENDMENT NO.
6 FACILITY OPERATING LICENSE N0. NPF-85 DOCKET NO. 50-353 1
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and 1
contain vertical lines indicating the area of change.
Remove Insert "
3/4 1-9 3/4 1-9 3/4 1-10 3/4 1-10 i
REACTIVfTY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION l
3.1.3.5 All control rod scram accumulators shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and $*.
ACTION:
a.
In OPERATIONAL CONDITION 1 or 2-1.
With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
i a)
Restore the inope sble accumulator to OPERABLE status, or b)
Declare the control rod associated with the inoperable accumulator inoperable.
Otherwise, be in at least HOT SHUTDOWN within the r4xt 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
With more than one control rod scram accumulator inoperable, declare the associated control rods inoperable and:
a)
If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least i
c"o 'ontrol rod drive pump is operating by inserting at ise.sc one withdrawn centrol red at least one notch.
If no control rod drivs pasa is operating and:
1)
If reactor p;stsure is >900 psig, then restart at least one control rod drive pump within 20 minutes or place the reactor mode switch in the shutdown position, or 2)
If reactor pressure is <900 psig, then place the reactor mode switch in the Shutdown position.
b)
Insert the inoperable control rods and disarm the associated control valves either:
1)
Electrically, or i
2)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 5*:
1.
With one withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and disarm the associateo directional control valves within one hour, either' a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
"At least the accumulator associated with each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
LIMERICK - UNIT 2 3/4 1-9 Amendment llo. 6 l
I
'l REACTIVITV CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS i
I 2.
With more than one withdrawn control rod with the associated scram accumulator inoperable or no control rod drive pump oper-ating, immediately place the reactor mode switch in the Shutdown position.
c.
The provisions of Specification 3.0.4 are not applicable, t
4.1.3.5 Each control rod scram accumulator sh611 be determined OPERABLE:
R.
At least once per 7 days by verifying that the indicated pressure is greater than or equal to 955 psig unless the control rod is inserted and disarmed or scrammed, b.
At least once per 18 months by:
1.
Performance of a:
a)
CHANNEL FUNCTIONAL TEST of the leak detectors, and b)
CHANNEL CALIBRATION of the pressure detectors, and verifying an alarm setpoint of equal to or greater than 955 psig on decreasing pressure, i
LIMERICK - UNIT 2 3/4 1-10 Amendment No. 6 g
_ _ _..