ML20070D264
| ML20070D264 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20070D267 | List: |
| References | |
| DPR-50-A-186 NUDOCS 9407070307 | |
| Download: ML20070D264 (8) | |
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0 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554K11 g
,e METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NVCLEAR CORPORATION DOCKET N0. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPER.ATING LICENSE Amendment No. 186 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated June 12, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
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 Commission's regulations; 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.
l 9407070307 940630 PDR ADOCK 05000289 P
i 6 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.
DPR-50 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 186, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t'12 John F. Sto
, Director Project D ectorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 30, 1994
E e Y,
ATTACHMENT TO LICENSE AMENDMENT N0.186 FACILITY OPERATING LICENSE N0. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3-18d 3-18d 3-18e 3-18e 3-18f 3-18f 3-189 3-18g (new page number) 3-19h (new page number) l 1
3.1.12 Pressurizer Power Operated Relief Valve (PORV) and Block Valve applicability Applies to the settings, and conditions for isolation of the PORV.
Ob.iective To prevent the possibility of inadvertently overpressurizing or depressurizing the Reactor Coolant System.
Soecification 3.1.12.1 When the RCS is below 332 F the PORV shall not be taken out of service, nor shall it be isolated from the system unless one of the following is in effect:
a.
High Pressure Injection Pump breakers are racked out.
b.
MU-V16A/B/C/D are closed with their breakers open, and MU-V217 is closed.
c.
Head of the Reactor Vessel is removed.
3.1.12.2 The PORV settings shall be as follows:
a.
Above 275 F 12 F - Minimum 2425 psig (Nominal 2450 psig).
With the PORV setpoint below the minimum value, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:
1.
restore the setpoint above the minimum value, or 2.
close the associated block valve, or 3.
close the PORV, and remove power from PORV 4.
otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
Below 275 F 12 F - Maximum 510 psig (Nominal 485 psig).
Within the PORV setpoint above the maximum value, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:
1.
restore the setpoint below the maximum value, or 2.
satisfy the requirements of Technical Specification 3.1.12.1 allowing the PORV to be taken out of service.
3-18d Amendment No. 66, 78, 16, 167, 186
t 3.1.12.3 If the reactor vessel head is installed and T.o is$332*F, High Pressure Injection Pump breakers shall not be racked in unless; a.
MU-V16A/B/C/D are closed with their breakers open, and MU-V217 is closed, and 4
b.
Pressurizer level is < 220 inches.
If pressurizer
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level is > 220 inches restore level to f 220 inches within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.1.12.4 The PORV Block Valve shall be OPERABLE during HOT STANDBY, STARTUP, and POWER OPERATION:
a.
With the PORV Block Valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:
1.
restore the PORV Block Valve to OPERABLE status or 2.
close the PORV (verify closed) and remove power from the p0RV l
3.
otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30
- hours, b.
With the PORV block valve inoperable, restore the t
inoperable valve to OPERABLE status prior to startup from the next COLD SHUTOOWN unless the COLD SHUTDOWN occurs within 90 Effective Full Power Days (EFPD) of the end of the fuel cycle.
If a COLD SHUTOOWN occurs within this 90 day period, restore the inoperable valve to OPERABLE status prior to startup for the next fuel cycle.
Bases If the PORV is removed from service while the RCS is below 332*F, sufficient measures are incorporated to prevent severe overpressurization by either eliminating the high pressure sources or flowpaths or assuring that the RCS is open to atmosphere.
The PORV setpoints are specified with tolerances assumed in the bases for Technical Specification 3.1.2.
Above 287'F (275'F + 12*F), the p0RV setpoint has been chosen to limit the potential for inadvertent discharge or cycling of the PORV.
Other action such as removing the power to the PORV has the same effect as raising the setpoint which also sat.isfies this requirement. There is no upper limit on this setpoint as the i
Pressurizer Safety Valves (T.S. 3.1.1.3) provide the required overpressure relief.
Below 263 F (275 F - 12 F), the PORV setpoint is reduced to provide the required low temperature overpressure relief when high pressure sources and flowpaths are in service. There is no lower limit on the pressure 4
actuation specified as lower setpoints also provide this same protection, j
l 3-18e Amendment No. 78, f6, 167, 186
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in both cases, the 275'F i 12*F setting is specified to reflect the nominal value which allows for normal variations in the temperature setpoint while maintaining the tolerances assumed in the bases for T.S. 3.1.2.
Either pressure actuation setpoint is acceptable within the temperature range between 263*F and 287'F.
i With RCS temperatures less than 332*F and the makeup pumps running, the high pressure injection valves are closed and pressurizer level is maintained less than 220 inches to allow time for action to prevent severe overpressurization in the event of any single failure.
The PORV block valve is required to be OPERABLE during the HOT STANDBY, STARTUP, and POWER OPERATION in order to provide isolation of the PORV discharge line to positively control potential RCS depressurization.
For protection from severe overpressurization during HPI testing, refer to Section 4.5.2.1.c.
1 f
3-18f Amendment No.186 4
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i 3.1.13 Reactor Coolant System Vents apolicability Provides the limiting conditions for operation of the Reactor Coolant System Vents.
These limiting conditions for operation (LCO) are applicable only when Reactor is critical.
Ob.iective To ensure that sufficient vent flow paths are operable during the plant operating modes mentioned above.
Specification 3.1.13.1 At least one reactor coolant system vent path consisting of at least two power operated valves in series, powered from emergency buses shall be OPERABLE and closed at each of the following locations:
a.
Reactor vessel head * (RC-V42 & RC-V43) b.
Pressurizer steam space (RC-V28 & RC-V44) c.
Reactor coolant system high point (either RC-V40A and 41A) or (RC-40B and 41B) as.119B 3.1.13.2 a.
With one of the above reactor coolant system vent paths inoperable, the inoperable vent path shall be maintained closed, with power removed from the valse actuators in the inoperable vent path. The inoperable vent path shall be restored to OPERABLE status within 30 days, or the plant shall be in HOT SHUTDOWN within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With two or more of the above reactor coolant system vent paths inoperable, maintain the inoperable vent path closed, with power removed from the valve actu-ators in the inoperable vent paths, and restore at least two of the vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
This specification becomes binding after installation and initially being declared operable.
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Amendment No. (f. 186
e IL41u The safety function enhanced by this venting capability is core cooling.
For events beyond the present design basis, this venting capability will substantially increase the plants ability to deal with large quantitles of noncondensible gas which could interfere with natural circulation (i.e.,
core cooling).
The reactor vessel head vent (RC-V42 & RC-V43 in series) provides the capability of venting noncondensible gases from the majority of the reactor vessel head as well as the Reactor Coolant hot legs (to the elevation of the top of the outlet nozzles) and cold legs (through vessel internals leakage paths, to the elevation of the top of the inlet nozzles).
This vent is routed to containment atmosphere.
Venting for the pressurizer steam space (RC-V28 and RC-V44 in series) has been provided to assure that the pressurizer is available for Reactor Coolant System pressure and volume control.
This vent is routed to the Reactor Coolant Drain Tank.
Additional venting capability has been provided for the Reactor Coolant hot leg high points (RC-V40A, B, RC-41A, B), which normally cannot be vented through the Reactor vessel head vent or pressurizer steam-space vent. These vents relieve to containment atmosphere through a rupture disk (set at low pressure).
The above vent systems are seismically designed and environmentally qualified in accordance with the May 23, 1980 Commission Order and Memorandum per NUREG-0737, Item II.B.l.
The high point vents do not fall within the scope of 10 CFR 50.49, since the vents are not relied upon during or following any design basis event (Reference 1). The pcwer operated valves (2 in series in each flow path) which are powered from emergency buses fail closed on loss of power. All vent valves for the reactor vessel head vent, pressurizer vent and loop B high point vent are powered from the class IE "B" bus.
The vent valves for the loop A high point vent are powered from the class lE "A" bus.
The power operated valves are controlled in the Control Room.
The individual vent path lines are sized so that an inadvertent valve opening will not constitute a LOCA as defined in 10 CFR 50.46(c)(1).
These design features provide a high degree of assurance that these vent paths will be available when needed, and that inadvertent operation or failures will not significantly hamper the safe operation of the plant (Reference 2).
REFERENCES (1) UFSAR, Section 4.2.3.9
" Reactor Coolant System Venting" (2) UFSAR, Section 7.3.2.2.c (16)
" Reactor Coolant System Venting" 3-18h Amendment No. #/, IW, M,186