ML20092P425
| ML20092P425 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/21/1984 |
| 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 | |
| ML20092P426 | List: |
| References | |
| DPR-50-A-097 NUDOCS 8407060285 | |
| Download: ML20092P425 (8) | |
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A ne0 UNITED STATES l'
o,i NUCLEAR REGULATORY COMMISSION
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 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 licensees) dated February 9,1984, 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; B. 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.
MO7C60285 840621 PDR ADOCK 05000289 p
2.
Accordingly, Facility Operating License No. DPR-50 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Revise paragraph 2.c.(2) to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.97,are hereby incorporated in the license. The GPU Nuclear Cor) oration shall operate the facility in accordance wit) the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bn to z, Chi f erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 21, 1984 i
ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACI!.ITY OPERATING LICENSE NO. DPR-50 s
DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert 11 11 iv iv 3-18f 3-18g 4-54 4-54
i TABLE OF CONTENTS Section Pace 2
SAFETY LIMITS APO LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 Safety Limits, Reactor Core 2-1 2.2 Safety Limits, Reactor System Pressure 2-4
'2.3 Limiting Safety System Settinos, Protection Instrumentation 2-5 3.0 LIMITING COOITICNS FOR OPERATIO4 3-1 3.1 Reactor Coolant System 3-1 3.1.1 Operational Components 3-1 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1. 3 Mirtimun Conditions for Criticality 3-6 3.1.4 Reactor Coolant System Activity 3-8 3.1.5 Chemistry 3-10 3.1.6 Leakage 3-12 3.1.7 Moderator Temperature Coefficient of Reactivity 3-16 3.1.8 Single Loop Restrictions 3-17 3.1.9 Low Power Physics Testing Restrictions 3-18 3.1.10 Control Rod Operation 3-18a 3.1.11 Reactor Internal Vent Valves 3-18b 3.1.12 Pressurizer Power Operated Relief Valve (PORV) 3-18c and Block Valve 3.1.13 Reactor Coolant System Vents 3-18f 3.2 Makeup and Purification and Chemical Addition Systems 3-19 3.3 Emergency Core Cooling, Reactor Buildino Emeroency Cooling, 3-21 and Reactor Buildinc Soray Systems 3.4 Decay Heat Removal - TurDine Cycle 3-25 3.5 Instrumentation Systems 3-27 3.5.1 Operational Safety Instrumentation 3-27 3.5.2 Control Rod Group and Power Distribution Limits 3-33 3.5.3 Engineered Safeguards Protection System Actuation Setpoints 3-37 3.5.4 Incore Instrunentation 3-38 3.5.5 Accident Monitoring Instrumentation-3-40a 3.6 Reactor Buildino 3-41 3.7 Unit Electrical Power System 3-42 3.8 Fuel Loading and Refueling 3 3.9 Radioactive Materials 3-46 3.10 Miscellaneous Radioactive Materials Sources 3-46
.3.11 Handlino of Irradiated Fuel 3 3.12 Reactor Buildino Polar Crane 3-57 3.13 Secondary System Activity 3-58 3.14 Flood 3-59 3.14.1 W lodic Inspection of the Dikes Around TMI 3-59 3.14.2 Flood Condition for Placing the Unit in Hot Standby 3-60 3.15 Air Treatment Systems 3-61 3.15.1 Emergency Control Room Air Treatment System 3-61 3.15.2 Reactor Building Purge Air Treatment System 3-62a i
3.15.3 Auxiliary and Fuel Handling Exhaust Air Treatment System 3-62:
i Amendment No. J), 77, 73, 97 II i
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TABLE OF CONTENTS Section Pace 4.7 Reactor Control Rod System Tests 4-48 4.7.1 Control Rod Drive System Functional Tests 4-48 4.7.2 Control Rod Program Verification 4-50 i
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4.8 Main Steam Isolation Valves 4-51 1
4.9 Emeroency Feedwater System Periodic Testina 4-52 I
4.9.1 Test 4-52 4.9.2 Acceptance Criteria 4-52a 4.10 Reactivity Anomalies 4-53 4.11 Reactor Coolant System Vents 4-54 l
I 4.12 Air Treatment Systems 4-55 4.12.1 Emergency Control Room Air Treatment System 4-55 4.12.2 Reactor Building Purge Air Treatment System 4-55b i
4.12.3 Auxiliary and Fuel Handling Exhaust Air Treatment System 4-55d i
4.13 Radioactive Materials Sources Surveillance 4-56 4.14 Reactor Buildino Purce Exhaust System 4-57 l
4.15 Main Steam System Inservice Inspection 4-58 4.16 Reactor Internals Vent Valves Surveillance 4-59 4.17 Snock Suoaressors (Snubbers) 4-60 4.18 Fire Protection Systems 4-72 4.18.1 Fire Protection Instruments 4-72 4.18.2 Fire Suppression Water System 4-73 1
4.18.3 Deluge / Sprinkler System 4-74 1
4.18.4 CO2 System 4-74 j
4.18.5 Halon Systems 4-75 4.18.6 Hose Stations 4-76 4.19 OTSG Tube Inservice Inspection 4-77 4.19.1 Steam Generator Sample Selection and Inspection Methods 4-77 4.19.2 Steam Generator Ttbe Sample Selection and Inspection 4-77 4
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4.19.3 Inspection Frequencies
.4-79 4.19.4 Acceptance Criteria 4-80 4.19.5 Reports 4-81 4.20 Reactor Buildino Air Temperature
'4-86 4.21.1 Radioactive Liquid Effluent Instrumentation.
4-87 l
4.21.2 Radioactive Gaseous Process and Efflue-f. Monitoring 4-90 j
Liquid EfflJents 4-97 Instrumrntation 4.22.1.1 1
4.22.1.2 Dose 4-102 4.22.1.3_ Liquid Waste Treatment 4-103 4.22.1.4 Liquid HoL1up Tanks 4-104
'4.22.2.1 Dose Rate 4-105 4.22.2.2 Dose, Noble Gas 4-110 4.22.2.3 Dose, Radiciodines, Radioactive' Material in Particulate 4-111 Form and Radionuclides Other Than Ncble Gases' l
4.22.2.4 Gaseous Radwaste Treatment 4-112 4.22.2.5 Explosive Gas Mixture 4-113 4
4.22.2.6 Gas Storage Tanks 4-114 1
4.22.3.1 Solid Radioactive Waste 4-115 l
4.22.4 Total Dose 4-116 4.23.1 Monitoring Program 4-117 4.23.2 Land Use Census 4-121 4.23.3 Interlaboratory Comparison Program 4-122 Amendment No.~ JJ, 28, g AI, A7, 55, 72, 75,75, iv l
a 3.1.13 Reactor Coolant System, Vents Acolicability 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.
Objective To ensure that sufficient vent flow paths are operable during the plant operating modes mentioned above.
Soecification 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-V408 and 418)
Action 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 valve 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 actuators in the inoperable vent paths, and restore at least two of the vent paths to GPERABLE 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 SHUT 00WN 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.
Amendment No. 97 3-18f
F Bases The safety ftnction enhanced by t is venting capability is core cooling. For l-events beyond the present design basis, this venting capability will substantially increase the plants ability to deal with large quantities of noncondensible gas which could interfeze with natural circulation (i.e., core 4
cooling).
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The reactor vessel head vent (RC-V42 & RC-V43 in series) provides the capability of venting noncondensible gases from the majority of the reactor
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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 contairsnent atmosphere.
I Venting for the pressurizer steam space (RC-Y28 and RC-V44 in series) has been i
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, b
Additional venting capability has been provided for the Reactor Coolant hot j
leg high points (RC-VACA,B, RC-V41A,B), which normally cannot be vented i
through the Reactor vessel head vent or pressurizer steam-space vent. These i
vents relieve to containment atmosphere through a rupture disk (set at low t
f pressure).
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I The above vent systems are seismically designed, environmentally qualified and 3
the power 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 lE "B" bus. The vent valves for the loop A high point
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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 inadvertant 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 ooeration or failures will not significantly hamper the safe operation of the
- plant, i
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i Amendment No. 97 3-18g t
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4.11 REACTOR COOLANT SYSTEM VENTS Acolicability Apolies to Reactor Coolant Syste:7. Vents.
Objective To ensure that Reactor Coolant System vents are able to perform their de function.
SCE ification 4.11.1 Each zeactor crolant sytta vent path shall be demonstrated OPERABLE once per refelirg intervC by cycling ecch power operated valve in the vent rath thrtugh at lerat,one complete cycle of full travel
.from the control ro(n ckring COLD SHUTDOWN or REFUELING.
BASES Reactor Coolant System Vents will perform thcir functions.
advisable to perform these tests during Plqnt ? wer Gperation, or when there It is not is significant orcssu"a in the Reactor Collant System.
to be performed during either Cold Shutdom or htfueling. Tests are, therefore, 1
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Amendment No. U, 97
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