ML17164A495
| ML17164A495 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  (NPF-014, NPF-022) |
| Issue date: | 12/20/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17164A496 | List: |
| References | |
| NPF-14-A-136, NPF-22-A-106 NUDOCS 9501050331 | |
| Download: ML17164A495 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 PENNSYLVANIA POWER 8i LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM EL CTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
136 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
B.
The application for the amendment filed. by the Pennsylvania Power 5 Light Company, dated July 19,
- 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
'nd the Commission's regulations set forth in 10 CFR Chapter I; 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:
(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 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 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.
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2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
136 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
PP&L 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 and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Decem><<
2O
>994 Jo n F. Stolz, Direc or P oject Directorate
-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT.NO. 136 F
C ITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 1-19 3/4 1-20 INSERT 3/4 1-19 3/4 1-20
REACTIVITYCONTROL SYSTEMS 3 4.1.5 STANDBY LIQUID CONTROL SYSTEM LIMITINGCONDITION FOR OPERATION 3.1.5 The standby liquid control system shall be OPERABLE.
APPLICABILITY:
ACTION:
OPERATIONALCONDITIONS 1, 2.
aO In OPERATIONALCONDITION 1 or 2:
1.
With one pump and/or one explosive valve inoperable, restore the inoperable pump and/or explosive valve to OPERABLE status within 7 days or 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 the standby liquid control system otherwise inoperable, restore the system 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 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 />.
SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:
ai At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that; 1.
The temperature of the sodium pentaborate solution is within the limits of Figure 3.1.5-1.
2.
The available volume of sodium pentaborate solution is withinthe limits of Figure 3.1.5-2.
3.
The heat tracing circuit is OPERABLE by actuating the test feature and determining that the power available light on the local heat tracing panel energizes.
SUSQUEHANNA - UNIT 1 3/4 1-19 Amendment No. i~6
REACTIVITYCONTROL SYSTEMS SURVEILLANCE REQUIREMENTS Continued b.
At least once per 31 days by; 1.
Verifying the continuity of the explosive charge.
2.
Determining that the available weight of sodium pentaborate is greater than or equal to 5500 Ibs and the concentratioq,of boron in solution is within the limits of Figure 3.1.5-2 by chemical analysis.
3.
Verifyingthat each valve, manual, power operated or automatic, in the flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm at a pressure of greater than or equal to 1190 psig is met.
d.
At least once per 18 months during shutdown by; 1.
Initiating one of the standby liquid control system loops, including an explosive,'alve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel.
The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired. Both injection loops shall be tested in 36 months.
2.
Demonstrating that all heat traced piping is unblocked by pumping from the storage tank to the test tank and then draining and flushing the discharge piping and test tank with demineralized water.
This test shall also be performed anytime water or boron is added to the solution or when the solution temperature drops below the limitof Figure 3.1.5-1.
This test shall also be performed whenever both heat tracing circuits have been found to be inoperable and may be performed by any series of sequential, overlapping or total flow steps such that the entire flow path is included.
SUSQUEHANNA - UNIT 1 3/4 1-20 Amendment No. 1~6
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER 5 LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STA ION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. >O6 License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8I;;
Light Company, dated Duly 19,
- 1994, 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:
(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 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 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 attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 106 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPLL 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 and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR R GULATORY COMMISSION
~
~
~
oh F. Stolz, Dir or Pr ject Directora I-2 ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 20, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 106 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 1-19 3/4 1-20 INSERT 3/4 1-19 3/4 1-20
REACTIVITYCONTROL SYSTEMS 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM LIMITINGCONDITION FOR OPERATION 3.1.5 The standby liquid control system shall be OPERABLE.
APPLICABILITY:
OPERATIONALCONDITIONS 1, 2.
ACTION:
ar In OPERATIONALCONDITION 1 or 2:
1.
With one pump and/or one explosive valve inoperable, restore the inoperable pump and/or explosive valve to OPERABLE status within 7 days or 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 the standby liquid control system otherwise inoperable, restore the system 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 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 />.
SURVEILLANCEREQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:
aO At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that; 1.
The temperature of the sodium pentaborate solution is within the limits of Figure 3.1.5-1
~
2.
The available volume of sodium pentaborate solution is withinthe limits of Figure 3.1.5-2.
3.
The heat tracing circuit is OPERABLE by actuating the test feature and determining that the power available light on the local heat tracing panel energizes.
SUSQUEHANNA - UNIT 2 3/4 1-19 Amendment No. i06
A P
I' 4
I
REACTIVITYCONTROL SYSTEMS SURVEILLANCEREQUIREMENTS Continued b.
At least once per 31 days by; 1.
Verifying the continuity of the explosive charge.
2.
Determining that the available weight of sodium pentaborate is greater than or equal to 5500 Ibs and the concentrationof boron in solution is within the limits of Figure 3.1.5-2 by chemical analysis.
3.
Verifyingthat each valve, manual, power operated or automatic, in the flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm at a pressure of greater than or equal to 1124 psig is met.
d.
At least once per 18 months during shutdown by; Initiating one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel.
The
'eplacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired.
Both injection loops shall be tested in 36 months.
.2.
Demonstrating that all heat traced piping is unblocked by pumping from the storage tank to the test tank and then draining and flushing the discharge piping and test tank with demineralized water.
U This test shall also be performed anytime water or boron is added to the solution or when the solution temperature drops below the limitof Figure 3.1.5-1.
This test shall also be performed whenever both heat tracing circuits have been found to be inoperable and may be performed by any series of sequential, overlapping or total flow steps such that the entire flow path is included.
SUSQUEHANNA - UNIT 2 3/4 1-20 Amendment No. ~O6