ML17157A966
| ML17157A966 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/02/1991 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157A967 | List: |
| References | |
| NUDOCS 9112130178 | |
| Download: ML17157A966 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
114 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power tt Light Company, dated September 4,
1991 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-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.
114 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9112130178 911202 PDR ADOCK 05000387, P
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMHISSION
Attachment:
Changes to the Technical Specifications Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 2,
1991
ATTACHMENT TO LICENSE AMENDMENT NO. ))4 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The overleaf page is provided to maintain document completeness.*
RENOVE 3/4 5-5 3/4 5-5a INSERT 3/4 5-5 3/4 5-5a*
V ntinu 2.
For the HPCI system, verifying that the system develops a flowof at least 5000 gpm against a test line pressure of greater than or equal to 245 psig when steam is being supplied to the turbine at 150 J 15 psig.
3.
Performing a
CHANNEL CALIBRATION of the CSS header 4P instrumentation and verifying the setpoint to be 6 1 psid.
4.
Verifying that the suction for the HPCI system is automatically transferred from the condensate storage tank to the suppression chamber on a condensate storage tank water level - low signal and on a suppression chamber - water level high signal.
5.
Performing a CHANNEL CALIBRATIONof the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be 2 113 psig.
d.
For the ADS:
1.
At least once per 31 days, performing a CHANNELFUNCTIONALTEST of the accumulator backup compressed gas system low pressure alarm system.
2.
At least once per 18 months:
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
b)
Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig and observing that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow.
c)
Performing a CKQ~L CALIBRATIONof the accumulator backup compressed gas system low pressure alarm systems and verifying air alarm setyoint of 2070 J 35 psig on decreasing pressure.
e.
At least every 18 months the following shall be accomplished by any series of sequential, overlapping or total channel steps such that the entire channel is tested:
The provisions of Specification 4.0.4 are not applicable provided the surveillance is
. performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
ADS solenoid energization shall be used alternating between ADS Division 1 and ADS Division 2.
SUSQUEHANNA - UNIT 1 3/4 5-5 Amendment No 114
EMERGENCY 'CORE COOLING SYSTEMS SURVEILLANCE RE UIREMEHTS Continued 1.
A functional test of the interlocks associated with LPCI and CS pump starts in response to an automatic initiation signal in Unit 1 followed by a "False" automatic initiation signal in Unit 2.
2.
A functional test of the interlocks associated with LPCI and CS pump starts in response to an automatic initiation signal in Unit 2 followed by a "False" automatic initiation signal in Unit 1.
3.
A functional test of the interlocks associated with LPCI and CS pump starts in response to simultaneous occurrence of an automatic initiation signal in both Unit 1 and Unit 2 and a Loss-of-Offsite-Power condition affecting both Unit 1 and Unit 2.
SUSQUEHANNA - UNIT 1
>~-, ~F04 3/4 5-Sa Aaen~nt No. 112
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
83 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 Light Company, dated September 4,
1991 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) T~hi 1
S if' d
E i 1 <> For the HPCI system, verifying that the system develops a flowofat least 5000 gpm against a test line pressure of greater than or equal to 245 psig when steam is being supplied to the turbine at 150 J 15 psig.
3.
Performing a CKQ~L CALIBRATION of the CSS header d,P instrumentation and verifying the setpoint to be ~
1 psid.
4, Verifyingthat the suction for the HPCI system is automatically transferred from the condensate storage tank to the suppression chamber on a condensate storage tank water level - low signal and on a suppression chamber - water level high signal.
5.
Performing a CHANNEL CALIBRATIONof the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be 2 113 psig.
d.
For the ADS:
1.
At least once per 31 days, performing a CHANNELFUNCTIONALTEST of the accumulator backup compressed gas system low pressure alarm system.
2.
At least once per 18 months:
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
b)
ManuaHy opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig~ and observing that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow.
The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
ADS solenoid energization shall be used alternating between ADS Division 1 and ADS Division 2.
For the startup following the Third Refueling and Inspection
- Outage, this suveillance shall read as follows:
For the HPCI System, verifying that the system develops a flowof at least 4850 gpm against a test line pressure of 600 psig when steam is being supplied to the turbine at 150+ psig.>>
SUSQUEHANNA - UNIT2 3I4 5-5 Amendment No.
83
EMERGENCY CORE COOlING SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.
c)
Performing a CHANNEL CALIBRATION of the accumulator backup compressed gas system low pressure alarm systems and veri-fying air alarm setpoint of 2070 + 35 psig on decreasing pressure.
At least every 18 months the following shall be accomplished by any series of sequential, overlapping or total channel steps such that the entire channel is tested:
1.
A functional test of the interlocks associated with LPCI and CS pump starts in response to an automatic initiation signal in Unit 1 followed by a "False" automatic initiation signal in Unit 2.
2.
A functional test of the interlocks associated with LPCI and CS, pump starts in response to an automatic initiation signal in Unit 2 followed by a "False" automatic i'nitiation signal in Unit 1.
3.
A functional test of the interlocks associated with LPCI and CS pump starts in response to simultaneous occurrence of an automatic initiation signal in both Unit 1 and Unit 2 and a Loss-of-Offsite-Power condition affecting both Unit 1 and Unit 2.
SUSQUEHANNA -,UNIT 2 3/4 5-6 Amendment No.81 JUN S 7 59