ML20080K493
| ML20080K493 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/09/1984 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20080K476 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM GL-83-37, NUDOCS 8402160029 | |
| Download: ML20080K493 (7) | |
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TECHNICAL SPECIFICATION CHANGE REQUEST NO.137 I.
Technical Specification Change Request No.137 The Licensee requests that attached revised pages replace the following pages of the existing Technical Specifications.
Replace:
11, iv, 4-54, and insert new pages: 3-18f, 3-18g.
II.
Reasons for Change In accordance with the NRC staff request (Generic letter 83-37) dated
' November 1,1983 we are providing technical specifications for the Reactor Coolant System vents. The NRC sample technical specifications were used as a basis for this technical specification change request.
The vent paths which have been included in this change request are:
- 1) Reactor Vessel Head Vent
- 2) Reactor Coolant High Point Vent
- 3) Pressurizer Steam Space Vent Provisions have been made, in the attached technical specification pages, for the fact that the reactor vessel head vent is not currently fully operational.
III. -Safety Evaluation and Justification of Change Persuant to the NRC TMI-2 Lessons Learned Action Plan (NUREG-0737 Item II.B.1) TMI-1 has installed Reactor Cnolant System vents. The NRC staff requested by Generic Letter 83-37 (and also NUREG-0737) that these modifications be included in the plant technical specifications. These
. specifications will help ensure that the Reactor Coolant System vents will be'able to perform their intended function, by requiring that they be operable during plant operation 2nd that periodic testing be performed.
IV.
No Significant Hazard Considerations Operation of TMI-l in accordance with this Technical Specification Change Request adds surveillance and operability requirements beyond the scope of the current-Technical Specification and does not:
- 1) involve a significant increase in the probability or consequences of an accident previously evaluated since this change is administrative in nature;
- 2) create the possibility of a new or different kind of accident fran any accident previously evaluated; it provides additional assurance that the plant (i.e. Reactor Coolant Vents) will respond to an accident as designed; 8402160029 840209 PDR ADOCK 05000289 P
- 3) involve.a significant reduction in a margin of safety since it increases the margin of safety by providing additional assurance of operability of the Reactor Coolant System Vents.
' V.
.Lnplementation It is requested that the implementation of this amendment be six weeks after issuance.
.VI.
Amendment Classification (10 TR 170.22)
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i This change request is administrative in nature and is, therefore,
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considered a class II' amendment. A check for $1,200.00 is enclosed.
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E TABLE OF CONTENTS Section Pace 2-SAFETY LIMITS AND 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 Settings, Protection Instrumentation 2-5 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.1 Reactor Coolant System 3-1 3.1.1 Operatioral Components 3-1
.3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1.3 Minimum Conoitions 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 Building Emergency Cooling, 3-21 and Reactor Building Spray Systems 3.4 Decay Heat Removal - Turbine 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 Instrumentation 3-38 3.5.5 Accident Monitoring Instrumentation 3-40a 3.6 Reactor Building 3-41
' 3. 7 Unit Electrical Power System 3-42 3.8 Fuel Loading and Ref ueling 3-44 3 *. 9 Radioactive Materials
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3-46 3.10 Miscellaneous Radioactive Materials Sources 3-46 3.11 Handling of Irradiated Fuel 3-55 3.12 Reactor Building Polar Crane 3-57 3.13 Secondary System Activity 3-58
- 3.14 Flood 3-59 3.14.1 Periodic Inspection of the Dikes Around TMI 3-59 3.14.2
. lood Condition for Placing the Unit in Hot Standby 3-60 F
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 3.15.3 Auxiliary and Fuel Handling Exhaust Air Treatment System 3-62c li
TABLE OF CONTENTS
- Section Page
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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 4.8 Main Steam Isolation Valves 4-51 4.9 Emergency Feedwater System Periodic Testing 4-52 4
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
4.12' Air Treatment Systems 4-55
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4.12.1 Emergency Control Room Air Treatment System 4-55 4.12.2 Reactor Building Purge Air Treatment System 4-55b 4'.12.3 Auxiliary and Fuel Handling Exhuast Air Treatment System 4-55d
- 4.13 Radioactive Materials Sources Surveillance 4-56 4.14 Reactor Building Purge Exhaust System 4-57
- 4.15 Main Steam System Inservice Inspection 4-58 4.16 Reactor Internals Vent Valves Surveillance 4-59
.4.17 Shock Suppressors (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 4.18.3 Deluge / Sprinkler System 4-74 4.18.4' Ch System 4-74 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 4.19.3 Inspection Frequencies 4-79 4.19.4 Acceptance Criteria 4-80 4.19.5 Reports 4-81 4.20 Reactor Building Air Temperature 4-86
~4.21.1 Radioactive Liquid Effluent Instrumentation 4-87 4.21.2 Radioactive Gaseous Process and Effluent Monitoring 4-90 Instrumentation 4.22.1.1 Liquid Effluents 4-97 4.22.1.2 Dose 4-102
'4.22.1.3 Liquid Waste Treatment 4-103 4.22.1.4 Liquid Holdup 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 4.22.2.4 Gaseous Radwaste Treatment 4-112 4.22.2.5 Explosive Gas Mixture 4-113 4.22.2.6 Gas Storage Tanks 4-114 4.22.3.1 Solid Radioactive Waste 4-115 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 l.
IV
3.1.13 Reactor Coolant System Vents Applicability 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.
Specification 3.1.13.1 At least one reactor coolant system vent path consisting of at least
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two power operated valves in series, powered from emergency busses 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-V40B and 418)
Action 3.1.13.2 a.
With one of the above reactor coolant system vent paths f -
inoperable, the inoperable vent path shall be maintained closed, with power removed from tre 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 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.
3-18f
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Bases The. safety function enhanced by this venting capability is core cooling. For events beyond the present design basis, this ventirg capability will substantially increase the plants ability to deal with large quantities 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) ano 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-V4GA,B, RC-V41A,B), which normally can not 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, environmentally qualified and
.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 locp B high point vent are powered from the class lE "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 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 operation or failures will not significantly hamper the safe operation of the plant.
3-18g
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. 4.11-REACTOR COOLANT SYSTEM VENTS Applicability Applies to Reactor Coolant System Vents.
Objective To ensure that Reactor Coolant System vents are able to perform their design function.-
Specification 4.11.1 Each reactor coolant cystem vent path shall be demonstrated OPERABLE once per refueling interval by cycling each power operated valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.
BASES Frequency of tests specified above are necessary to ensure that the individual Reactor Coolant System Vents will perform their functions.
It is not advisabia to perform these tests during Plant Power Operation, or when there is significant pressure in the Reactor Coolant System.
Tests are, therefore, to be performed during either Cold Shutdown or Refueling.
e 4-54