ML20154Q627
| ML20154Q627 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 10/19/1998 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20154Q625 | List: |
| References | |
| RTR-NUREG-1430 NUDOCS 9810260035 | |
| Download: ML20154Q627 (11) | |
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Proposed Technical Specification Revised Pages I
i 9810260035 981019 yDR ADOCK 05000289 l PDR
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TABLE OF CONTENTS Sggion Eagg 1 2 SAEhTflJMES AND LIMTIINDJAFETY SLSTEM SETTIb'G..S 2-1 2.1 - Safety Limits. Reactor Core ' 21
.2.2 Safety Lirni.ls_,. Reactor System Pressurs 24 2.3 - . Limiting Safety System Settings. Protection Instrumentation 2-5 3 LIMITING CONDITIONS FOR OPERATION 31 !
3.0 Ogne_ra! Action Reauirements 3-1 3.1 ' Reactor Coolant System 3-la l 3.1.1 Operational Components 3-la 3.1.2 Pressurization, Heatup and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality ' 3-6 3.1.4 Reactor Coolant System Actisity 3-8 3.1.5 Chemistry 3-10 3.1.6 Leakage .
3 12
'3.1.7 Moderator Temperature Coeflicient of Reacthity 3 16 3.1.8 SingleImop Restrictions 3-17 3.1.9 Low Power Physics Testing Restrictions 3-18 .
3.1.10 ControlRod Operation 3-18a ;
3.1.11 ReactorInternal Vent Valves 3-18e 3.1.12 Pressurizer Poner Operated Relief Vaive (PORV) l and Block Vahr 3-18d
.3.1.13 Reactor Coolant System Vents 3-18f ;
3.2 DSkted 3-19 1 3.3 Emergency Core Cooling. Reactor Building Emergency L90li llg and Reactor BuildingSpmy Systems 3-21 3.4 Decay Heat Removal Canability 3-25 3.4.1 Reactor Coolant System Temperature Greater than 250 F 3-25 l'
3.4.2 Reactor Crolant System Temperature 250 F or Less 3 26 3.5 . Instrumer.tatign.Sy.tems s 3-27 ,
3.5.1 Operati<.,nal Safety Instnunentation 3-27 l 3.5.2 Control Rod Group and Power Diuribution Limits 3-33 J 3.5.3 : Engineered Safeguards Protection System Actuation Setpoints 3-37 3.5.4 Incore Instnmientation 3 38 -
3.5.5 Accident Monitoring Instrumentation 3-40a ,
3.5.6 Deleted 340f I 3.5.7 Remote Shutdown System 340g 3.6 '
l Reactor Building _ 3-41 3.7 Unit Electrical Power System 3-42 3.8 FugLIgxxiingand Refueling 344
' 3.9 Deleted 3-46 '
3.10 Miscellaneous Radioactive Materials Sources 346 3.11 Handling ofIrradiated Fuel 3 55 l
. 3.12 Rgactor Buildingfolar_Grane 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 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 3.15.3 Auxiliary and Fuel Handling Building Air Treatment System 3-62c 3.15.4 Fuel Handling Building ESF Air Treatment System 3-62e ii Amendment No. 59r72r78c97r98r419,-122r1%rl49eM77 482r196
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, LIST OF TABLES l TABLE TITLE PAGE
't.2 Frequency Notation I-8 2.3-1 Reactor Pn>tection S3 stem Trip Setting Limits 2-9 3.1.6.1 Pressure Isolation Check Valves Between the 3-15a Primary Coolant System and LPIS 3.5-1 Instruments Operating Conditions 3-29 3.5-1A DELETED 3.5-2 Accident MonitoringInstruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d 3.5-4 Remote Shutdown System Instrumentation and Control 3-40i l 3.21-1 DELETED 3.21-2 DELETED 3.23-1 DELETED 3.23-2 DELETED 4.1-1 Instrument Sunciliance Requirements 4-3 4.1-2 Minimum Equipment Test Frequency 4-8 4.1-3 Minimum Sampling Frequency 4-9 4.1-4 Post Accident Monitoring Instrumentation 4-10a 4.19-1 Minimum Number of Steam Generators to be 4-84 Inspected During Insenice Inspection 4.19-2 Steam Generator Tube Inspection 4-85 4.21-1 DELETED 4.21-2 DELETED 4.22-1 DELETED 4.22-2 DELETED 4.23-1 DELETED l 51 l
l Amendment No.59c72rloo r 106cil8r137rl42rl47r154rl73r197 I
3.5.7 REMOTE SHUTDOWN SYSTEM Applicability l Applies to the operability requirements for the Remote Shutdown System Panel"B" Functions l in Table 3.5-4 during STARTUP, POWER OPERATION AND HOT STANDBY.
Objectives j 1
To assure operability of the instrumentation and controls necessary to place and maintain the unit in HOT SHUTDOWN from a location other than the control room.
Specification 1
The minimum number of functions identified in Table 3.5-4 shall be OPERABLE. With the l number of functions less than the minimum required, restore the required function to OPERABLE status within 30 days or 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 HOT SHUTDOWN within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Bases The Remote Shutdown System provides the control room operator with suflicient instmmentation and controls to place and maintain the unit in a safe shutdown condition from locations other than the control room. This capability is necessary to protect against the possibility that the control room becomes inaccessible. A safe shutdown condition is defined as HOT SHUTDOWN.
In the event that the control room becomes inaccessible, the operators can establish control at the remote shutdown panel and place and maintain the unit in HOT SHUTDOWN. Not all controls and necessary transfer switches are located at the remote shutdown panel. Some controls and transfer switches will have to be operated locally at the switchgear, motor control panels, or other local stations. The unit automatically reaches HOT SHUTDOWN following a unit shutdown and can be maintained safely in HOT SHUTDOWN for an extended period of time.
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I 3-40g Amendment No.
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l The OPERABILITY of the Remote Shutdown System control and instrumentation Functions ensures that there is sufficient information available on selected unit parameters to place and maintain the unit in HOT SHUTDOWN should the control room become inaccessible. l The Remote Shutdown System is required to provide equipment at appropriate locations
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outside the control room with a capability to promptly shut down and maintain the unit in a '
safe condition in HOT SHUTDOWN.
l The criteria governing the design and the specific system requirements of the Remote
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Shutdown System are located in 10 CFR 50, Appendix A, GDC 19,
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The controls, instrumentation, and transfer switches are those required for: Reactor Coolant Inventory Control, Reactor Coolant System Pressure and Temperature Control, Decay Heat Removal, Reactivity Monitoring, OTSG Level and Pressure Control, Reactor Coolant Flow
! Control, and Electrical Power.
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The Remote Shutdown System instruments and control circuits covered by this specification do not need to be energized to be considered OPERABLE. This specification is intended to l ensure the Remote Shutdown System instmments and control circuits will be OPERABLE if unit conditions require that the Remote Shutdown System be placed in operation. The operability ofcomponents and equipment are determined by their respective Technical
- l. Specification requirements. Ifa component required for safe shutdown is placed in its fail-safe l condition, as permitted by Technical Specifications, then the safety function has been assured and the remote shutdown panel function is considered operable.-
Entry into an applicable REACTOR OPERATING CONDITION while relying on the l specification actions is allowed even though the specification actions may eventually require a l unit shutdown. This is acceptable due to the low probability of an event requiring these instmments. ,
The conditions of the specification may be entered independently for each Function listed on Table 3.5-4 and completion times ofinoperable Functions will be tracked separately for each Function.
3-40h i Amendment No.
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TABLE 3.5-4 (Sheet 1 of 2)
REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS i
l Function / Instrument Required Number ;
or Control Parameter ofFunctions i
- 1. ' Reactor Coolant Coolant Temperature 1 !
Inlet Temperature 1 !
Coolant Pressure 1 Pressurizer Level 1 RC-V 1 -
RC-V-3 1
- 2. EmergencyFeedwaterControls EFW AFlowIndicator 1 EFW B Flow Indicator 1 OTSG A Level 1 OTSG B Level 1 EF-V-30B 1 EF-V-30D 1 1
- 3. OTSG"B" Pressure Control l Outlet Pressure 1 MS-V-4B 1 MS-V-8B 1 l MS-V-8A 1 l
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!- 3-40i Amendment No.
TABLE 3.5-4 (Sheet 2 of 2) !
l Function /Instmment Required Number orControl Parameter ofFunctips
- 4. Decay Heat Removal ;
Cooler Outlet Temperature 1 Pump Inlet Temperature 1 Flow I ,
i S. ReactorNeutronPower Source Range Flux 1 i
- 6. Makeup Controland Status l MU-P-1B 1 MU-P-lC 1 MU-P-3B 1 MU-P-3C 1 MU-V-2A 1 MU-V-2B 1 MU-V-8 1 MU-V-14B i MU-V-16C 1 ,
MU-V-16D 1 I MU-V-18 1
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MU-V-20 1 l MU-V-32 Indicator 1 MU-V-37 1 DH-T-1 BWST Level 1 Makeup Tank Level 1
- 7. Decay Heat Closed Cycle Cooling Water DC-P-1B (Auxiliary"B" Panel) 1
- 8. DieselGenerator EG-Y-1B 1 3-40j Amendment No.
4.1 OPERATIONAL SAFETY REVIEW
> . 1 Applicability 1
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, Applies to items directly related to safety limits and limiting conditions for operation.
Ob_iective i To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
Specification 4.1.1 The minimum frequency and type of surveillance required for reactor protection system, engineered safety feature protection system, and heat sink protection
! system instrumentation when the reactor is critical shall be as stated in Table l 4.1-1.
4.1.2 Equipment and sampling test shall be performed as detailed in Tables 4.1-2 and i 4.1-3. l 4.1.3 Each post-accident monitoring instrumentation channel shall be demonstrated l OPERABLE by the performance of the check, test and calibration at the frequencies shown in Table 4.1-4.
4.1.4 Each remote shutdown system function shown in Table 3.5-4 shall be demonstrated OPERABLE by the performance of the following check, test, and calibration:
a) Perform CHANNEL CHECK for each required instrumentation channel l that is normally energized every 31 days.
b) Verify each required control circuit and transfer switch is capable of performing the intended function every refueling interval.
c) Perform CHANNEL CALIBRATION for each required instrumentation channel every refueling interval (excludes source range flux).
Baser Check Failures such as blown instmment fuses, defective indicators, or faulted amplifiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instmment or system. Funhermore, such failures are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state ofindependent channels measuring the same variable supplements this type i of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated i is deemed adequate for reactor system instrumentation.
4-2 Amendment No. -78,123, 98,-+56,157,158 ,181
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l L B_ases (Cont'd) l 1 .
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- l The 600 ppmb limit in item 4, Table 4 -3 is used to meet the requirements of Section l 5.4. Under other circumstances the minimum acceptable boron concentration would I
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, ave been zero ppmb.
i Calibration Calibration shall be performed to assure the presentation and acquisition of accurate information. The nuclear flux (power range) channels amplifiers shall be checked and
! calibrated if necessary, every shift against a heat balance standard. The frequency of heat balance checks will assure that the difTerence between the out-of-core l instrumentation and the heat balance remains less than 4%.
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Channels subject only to " drift" errors induced within the instmmentation itself can tolerate longer intervals between calibrations. Process system instmmentation errors induced by drift can be expected to remain within acceptance tolerances if recalibration is performed at ;
l the intervals ofeach refueling period. 1 Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.
Thus, minimum calibration frequencies set forth are considered acceptable.
1 Lesting ,
On-line testing of reactor protection channels is required monthly on a rotational basis. The rotation scheme is designed to reduce the probability of an undetected failure existing within the system and to minimize the likelihood of the same systematic test errors bemg l introduced into each redundant channel (Reference 1). )
The rotation schedule for the reactor protection channels is as follows:
a) Deleted b) Monthly with one channel being tested per week on a continuous sequential rotation.
The reactor protection system instrumentation test cycle is continued with one channel's instmmentation tested each week. Upon detection of a failure that prevents trip action in a channel, the instrumentation associated with the protection parameter failure will be tested in the remaining channels. If actuation of a safety channel occurs, assurance will be required that actuation was within the limiting safety system setting.
The protection channels coincidence logic, the control rod drive trip breakers and the regulating control rod power SCRs electronic trips, are trip tested monthly. The trip test checks all logic combinations and is to be performed on a rotational basis.
Discovery of a failure that prevents trip action requires the testing of the instmmentation associated with the protection parameter failure in the remaining channels.
1 For purposes of surveillance, reactor trip on loss of feedwater and reactor trip on turbine trip are considered reactor protection system channels.
4-2a Amendment No. 78;457;481-200
ENCLOSURE 2 Certificate of Service for TMI-I Technical Specification Change Request No. 248 l
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 1
IN THE MATTER OF DOCKET NO. 50-289 !
GPU NUCLEAR INC. LICENSE NO. DPR CERTIFICATE OF SERVICE i
This is to certify that a copy ofTechnical Specification Change Request No. 248 to Appendix A of the i Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been l filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, )
Pennsylvania; and the Pennsylvania Department ofEnvironmental Resources, Bureau of Radiation ' I Protection, by deposit in the United States mail, addressed as follows: )
Mr. Darryl LeHew, Chairman Ms. Sally Klein, Chairman Board of Supervisors of Board ofCounty Commissioners ;
Londondeny Township ofDauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown,PA 17057 Front & Market Streets Hanisburg,PA 17101 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources Rachael Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 ATTN: Mr. Stan Maingi i
GPU NUCLEAR INC.
BY: '
84 4 o ice President and rector, TMI DATE: / /1!96
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