ML17158C215
| ML17158C215 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/26/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158C216 | List: |
| References | |
| NPF-14-A-166, NPF-22-A-140 NUDOCS 9707100206 | |
| Download: ML17158C215 (13) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 PENNSYLVANIA POWER EE LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANN STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. >66 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 h
Light Company, dated June 10,
- 1996, as supplemented on July 25,
- 1996, 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.
97o7zooooo mosoz PDR ADQCK OM00387 PDR
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)
Tech ical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. >66 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPEL shall oper ate 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:
June 26, 1997 Jo n
. Stolz, Direct P o't Directorate I-D>>sion of Reactor Projects I/II Office of Nuclear Reactor Regulation
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ATTACHMENT TO LICENSE AMENDMENT NO, 166 ACILITY OPERATING LICENSE NO. NPF-14 OCKET 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 3-18 3/4 3-20 NSERT 3/4 3-18 "3/4 3-20
TABLE3.3.2-2 (Continued)
ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS TRIP FUNCTION MAINSTEAM LINE ISOLATION(Continued)
- e. Condenser Vacuum-Low f.
Reactor Building Main Steam Line Tunnel Temperature-High
- g. Reactor Building Main Steam Line Tunnel b, Temperature-High
- h. Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature-High
- 4. REACTORWATER CLEANUP SYSTEM ISOLATION RWCUI Flow-High
- b. RWCU Area Temperature-High
- c. RWCU/Area Ventilation d, Temperature-High
- d. SLCS Initiation
- e. Reactor Vessel Water Level-Low Low, Level 2 f.
RWCU Flow-High
- g. Manual Initiation
- 5. REACTOR CORE ISOLATIONCOOLING SYSTEM ISOLATION
- a. RCIC Steam Line d, Pressure-High
- b. RCIC Steam Supply Pressure-Low
- 5 99oF**
NA 5 197'F'*
c60 gpm 5 147'F or 131'F¹ s 69'F NA a -38 inches*
s 462 gpm NA s 188" HqO a 60 psig s 10.0 psig ALLOWABLEVALUE a 8.8 inches Hg vacuum s 184'F-6 108'F**
5200'F'*
s80 gpm s 154'F or 137'F¹ 720F NA a P5 inches
~472 gpm NA s193" H>O a 53 psig s 20.0 psig
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TRIP FUNCTION TRIP SETPOINT TABLE3.3.2-2 (Continued)
ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS ALLOWABLEVALUE
- h. HPCI Pipe Routing Area d, Temperature-High i.
Manual Initiation j.
Drywell Pressure-High s 89'F¹¹ NA 5 1.72 pslg s 98'F¹¹ s 1.88 psig
- 7. RHR SYSTEM SHUTDOWN COOLING/HEADSPRAY MODE ISOLATION M
CO lO ED
- a. Reactor Vessel Water Level-Low, Level 3
- b. Reactor Vessel (RHR Cut-in Permissive) Pressure-High
- c. RHR Flow-High
- d. Manual Initiation
- e. Drywell Pressure-High See Bases Figure B 3/4 3-1.
a 13.0 inches s 98 psig s 25,000 gpm NA 5 1.72 psig a 11.5 inches s 108 psig s 26,000 gpm NA s 1.88 psig O
Initialvalue. Final value to be determined based on Power Uprate startup testing. Any required change to this value shall be submitted to the Commission within 90 days of test completion.
¹ Lower setpoints forTSH-G33-1N600 E, F.
¹¹ 15 minutes time delay.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE
'INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.>4O 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 June 10,
- 1996, as supplemented on July 25,
- 1996, 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.
140 and the Environmental Protection Plan contained in Appendix B, 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:
June 26, 1997 Jo n
. Stolz, Direct Pr j ct Directorate I Di 'sion of Reactor Projects I/II Office of Nuclear Reactor Regulation
TTACHHENT TO LICENSE AHENDHENT NO. 140 FACILITY OPERATING L CENSE NO. NPF-22 OCKET 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.
REHOVE 3/4 3-18 3/4 3-20 INSERT 3/4 3-18 3/4 3-20
~ 1
TABLE3.3.2-2 (Continued)
ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS TRIP FUNCTION MAINSTEAM LINE ISOLATION(Continued)
- e. Condenser Vacuum-Low f.
Reactor Building Main Steam Line Tunnel Temperature-High
- g. Reactor Building Main Steam Line Tunnel b, Temperature-High
- h. Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature-High
- 4. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. RWCU 6 Flow-High
- b. RWCU Area Temperature-High
- c. RWCU/Area Ventilation b, Temperature-High
- d. SLCS initiation
- e. Reactor Vessel Water Level-Low Low, Level 2 f1. RWCU Flow-High f2. Non-Regenerative Heat Exchanger Discharge Temperature - High
- g. Manual Initiation
- 5. REACTOR CORE ISOLATIONCOOLING SYSTEM ISOLATION
- a. RCIC Steam Line b, Pressure-High
- b. RCIC Steam Supply Pressure-Low
- c. RCIC Turbine Exhaust Diaphragm Pressure-High TRIP SETPOINT a 9.0 inches Hg vacuum 1770F 99oF NA 197oF s60 gpm s 147'F or 131'FC 69oF a -38 inches 5462 gpm s 144'F NA s 138" H20 a 60 psig s 10.0 psig ALLOWABLEVALUE a 8.8 inches Hg vacuum s 184'F s 108'F NA 5 200'F s80 gpm s 154'F or 137'F0 s 72'F a -45 inches 6472 gpm s 150'F z 143" H20 a 53 psig 6 20.0 psig
TABLE3.3.2-2 (Continued)
ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS TRIP FUNCTION
- 7. RHR SYSTEM SHUTDOWN COOLINGIHEADSPRAY MODE ISOLATION TRIP SETPOINT ALLOWABLEVALUE 4)
Ca>
CD
- a. Reactor Vessel Water Level-Low, Level 3
- b. Reactor Vessel (RHR Cut-in Permissive) Pressure-High
- c. RHR Flow-High
- d. Manual Initiation
- e. Drywell Pressure-High See Bases Figure B 3/4 3-1.
z 13.0 inches*
s 98 psig s 25,000 gpm s 1.?2 psig a 11.5 inches s 108 psig s 26,000 gpm NA s 1.88 psig Initial value. Final value to be determined based on Power Uprate startup testing. Any required change to this value shall be submitted to the Commission within 90 days of test completion.
¹ Lower setpoints forTSH-G33-2N600 E, F.
¹¹ 15 minutes time delay.
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