ML17157A744
| ML17157A744 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/27/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157A745 | List: |
| References | |
| NUDOCS 9107180037 | |
| Download: ML17157A744 (14) | |
Text
~gg RE0y 0
j'
)fy*g+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 PENNSYLVANIA POWER le LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET tlO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATItlG LICENSE Amendment No. 112 License No. NPF-14 1.
The Yuclear Regulatory Commission (the Commission or the NRC) having fourd that:
A.
The application for the amendment filed by the Pennsylvania Power lt Light Company, dated July 27, 1990, 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. 112 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9107180037 910b27 PDR ADOCK 05000387 e
~
~
0 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COI1HISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27, 1991 Walter R. Butler, Director Proiect Directorate I-2 Division of Reactor Projects - I/II
ATTACHMENT TO LICENSE AMENDMENT NO. 112 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 pages are identified by Amendment number ard contain vertical lines indicating the area of change.
The overleaf page is provided to maintain document completeness.*
REI<OVE 3/4 5-5 3/4 5-6 INSERT 3/4 5-5 3/4 5-5a 3/4 5-6*
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.
2.
For the HPCI system, verifying that the system develops a flow of at least 5000 gpm against a test line pressure of 210 i 15 psig when steam is being supplied to the turbine at 150 i 15 psig.
- 3.
Performing a
CHANNEL CALIBRATION of the CSS header.
hP instru-mentation and verifying the setpoint to be
< 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 condens'ate storage tank water level - low signal and on a suppression chamber - water level high signal.
5.
Performing a
CHANNEL CALIBRATION of the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be
> 113 psig.
For the ADS:
2.
At least once per 31 days, performing a
CHANNEL FUNCTIONAL TEST of the accumulator backup compressed gas system low pressure alarm system.
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.
e.
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 f1 ow.
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:
"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. 112
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued l.
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 3/4 5-5a Amendment No. 112
EMERGENCY CORE C
NG SYSTEMS 3/4 5.2 ECCS -
SHUTDOWN l
LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following subsystems shall be OPERABLE:
a.
Core spray system (CSS) subsystems with a subsystem comprised of:
2.
Two OPERABLE CSS pumps, and An OPERABLE flow path capable of taking suction from at least one of the following water sources and transferring the water through the spray sparger to the reactor vessel:
a) b)
From the suppression
- chamber, or When the suppression chamber water level is less than the limit or is drained, from the condensate storage tank congaining at least 135,000 available gallons of water, equivalent'o a level of'9K.
b.
Low pressure coolant injection (LPCI) system subsystems with a subsystem comprised of:
1.
At least one OPERABLE LPCI pump, and 2.
An OPERABLE flow path capable of taking suction from the suppression chamber upon being manually realigned and transferring
. the.water to the reactor vessel.
APPLICABILITY:
OPERATIONAL CONDITION 4 and 5".
ACTION a ~
With one of the above required subsystems inoperable, restore at least two subsystems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations with a potential for draining the reactor vessel.
With both of the above required subsystems inoperable, suspend CORE ALTERATIONS and all operations with a potential for draining the reactor vessel.
Restore at least one subsystem to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish SECONDARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
he ECCS
>s not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the spent fuel pool gates are
- removed, and water level is maintained within the limits of Specification 3.9.8 and 3.9.9.
SUSQUEHANNA - UNIT 1 3/4 5-6
'II
~p,g REG(
Wp
+
0 g%
I g
4 0
~
Q
~ ~
I 0
+>>*++
UNITED STATES NUCLEAR REGULATORY COIVIMISSION WASHINGTON. D.c. 20555 PENNSYLVANIA POMFR 8
LIGHT COMPANY ALLEGHENY ELECTRIC CCOPERATIVE INC.
DOCKET NO. 5G-388 SUS UEHAI'NA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATIIIG LICENSE Amendment No. 81 License No. NPF-22 1.
The Nuclear Regulatory CoImission (the Commission or the NPC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 5
Light Company, dated July 27, 1990, complies with the standards and reouirements of the Atom'.c Energy Act of 1954, as amended
!the Act),
and the Commission's regulations set for th in 10 CFR Chapter I; B.
The faci.ity will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(',) 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 dei'ense and security or to the health and safety of the public; and E.
The issuance of this amendment
~s 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.
81 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 Environmertal Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27, 1991 Malter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II
ATTACHMENT TO LICENSE AMENDMENT NO. 81 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 page is identified by Amendment number and contains vertical lines indicating the area of change.
REI10VE 3/4 5-5 3/4 5-6 INSERT 3/4 5-5*
3/4 5-6
SURVEILLANCE RE UIREMENTS Continued d.
2.¹ For the HPCI system, verifying that the system develops a flow of at least 5000 gpm against a test line pressure of 210 + 15 psig when steam is being supplied to the turbine at 150 E 15 psig."
3.
Performing a
CHANNEl. CALIBRATION of the CSS header bP instru-mentation and verifying the setpoint to be ( 1 psid.
4.
Verifying that the suction for the HPCI system is automati'cally 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 CALIBRATION of the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be
> 113 psig, For the ADS:
l.
At least once per 31 days, performing a
CHANNEL FUNCTIONAL TEST 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'he 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.
"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.
I
""ADS solenoid energization shall be used alternating between ADS Division 1 and ADS Division 2.
¹For the startup following the Third Refueling and Inspection Outage, this surveillance shall read as follows:
For the HPCI System, verifying that the system develops a flow of at least 4850 gpm against a test line pressure of 600 psig when steam is being supplied to the turbine at 150 i 15 psig.*
SUS)UEHANNA - UNIT 2 3/4 5" 5 Amendment No. 62 DEC 18 l989
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 initiation signal in Unit l.
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