ML20093J978
| ML20093J978 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/01/1984 |
| 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 | |
| ML20093J980 | List: |
| References | |
| TASK-2.F.1, TASK-TM, DPR-50-A-100 NUDOCS 8410170118 | |
| Download: ML20093J978 (11) | |
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UNITED STATES
,3 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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l METROPOLITAN EDIS0N 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
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Amendment No. 100 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by GPU Nuclear Corporation, et al (the licensees) da.ted January 5, 1983, as revised June 13, 1984, complies with the standards and requirements of the Atomic Energy -
Act of -1954, as amended (the Act), and the Comission'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 Comission; 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) tiiat s0ch activities will be conducted in compliance with 'the Comission's regulations; D. The issuance of this amendment will not be inimical to the 1on defense and security or to the health and safety of the pt 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.
841017011e 841001 PDR ADOCK 05000289 P
(7 2-2.
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:
- Technical Specificatiens The Technical Specifications contained it, Appendix A, as revised through Amendment No.100, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment becomes effective 45 days after its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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J in F. Stolz, Chief erating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications
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Date of Issuance: October 1, l984 eaa.pw t
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ATTACHMENT TO LICENSE AMENDMENT NO.100 FACILITY OPERA'lING LICENSE N0. DPR-50 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 area of change.
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Remove Insert.
vi vi 3-40a 3-40a 3-40b 3-40b 3-40d 3-40e 4-1 e.
4-1 4-Sa 4-Sa 4-10a e
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LIST OF TABLES TABLE TITLE PAGE j
1.2 Frequency Notation' 1-8 2.3-1 Reactor Protection System Trip-Setting Limits 2-9 3.5-1 Instruments Operating conditions 3-29 3.5-2 Accident Penitoring Instruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d 3.16-1 Safety Related Shock Suppressors (Snubbers) 3-65 3.18-1 Fire Detection Instruments 3-87 3.21-1 Radioactive Liquid Effluent Monitoring Instrumentation 3-97 3.21-2 R:4dioactive Liquid Effluent Monitoring Instrumentation 3-101-3.23-1 Radiological Environmental Monitoring Program 3-122 3.23-2 Reporting Levels for Radioactivity Concentration 3-126 in Environmental Samples 4.1-1 Instrument Surveillance 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 l
4.2-2 Surveillance Capsules Insertion and Withdrawal Schedule 4-27a 4.19-1 Minimum Number of Steam Generators to be 4-84 Inspected During Inservice Inspection 4.19-2 Steam Generator Tube Inspection 4-85 4.21-1 Radioactive Liquid Effluent Monitoring '
4-88 Instrumentation Surveillance Requirements 4.21-2 Radioactive Gaseous Effluent Monitoring 4-91 Instrumentation Surveillance Requirements 4.22-1 Radioactive Liquid Waste Sampling & Analysis Program 4-98 4.22-2 Radioactive Gaseous Waste Sampling & Analysis Program 4-106 4.23-1 Maximum Valves for the Lower Limits of Dectection (LLD).
4-118 Amendment $$,U,100 v1 m
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3.5.5 ACCIDENT MONITORING INSTRUMENTATION Acolicability.
Applies to the operability requirements for the instruments identified in' Table 3.5-2 and Taole 3.5-3 during STARTUP, POWER OPERATION and l
HOT STArOBY..
-Objectives To assure operability of key instrumentation useful in diagnosing situations which could represent or lead to inadequate core cooling -
or evaluate and predict the course of accidents beyond the design basis.
Specification 3.5.5.1 The minimum nurrber of channels identified for the instruments in l
Table 3.5-2, shall be OPERABLE. With the number of instrumentation channels less than the minimum required, restore the inoperable l
channel (s) to OPERABLE status within seven (7) days (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for i
pressurizer level) dr be in at least HOT SHUTDOWN within the next six 1
(6) hours and in COLD SHUTDOWN within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Prior to starttp following a COLD SHUTDOWN, the minimum nurrber of channels.
shown in Table 3.5-2 shall be operable.
3.5.5.2 The channels identified for the instruments specified in Table 3.5-3 shall be OPERABLE. With the number of instrumentation channels less 1
than required, restore the inoperable channel (s) to OPERABLE in accordance with the action specified in Taole 3.5-3.
~ Bases
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The saturation Margin Monitor provides a guid< and reliable means for j
determination of saturation temperature margins. Hand calculation of saturation pressure and saturation temperature margins can be easily and quickly performed as an alternate indication for the Saturation Margin Monitors.
Discharge flow from the two (2) pressurizer code safety valves and the PORV is mcasured by differential pr' essure transmitters connected across elbow taps downstream of each valve. A delta-pressure indication from each pressure transmitter is availaole in the control room to indicate code safety or relief valve line flow. An alarm is also provided in the control room to indicate that discharge from a pressurizer code safety or relief valve is occurring. In addition, an acoustic monitor is provided to detect flow in the PORV discharge line. An alarm is provided in the control room for the acoustic monitor.
3-40a Amendment'No. 7E, 100
7 The Emergency'F6edwater System is providid with two channels of flow Linstrumentation on each of tne two, discharge lines. Local flow indication is also available for' the. emergency feedwater system.
l Although the pressurizer has multiple level indications, the separate
' indications are selectable via a switch for display on a single display.
- Pressurizer level, however, can also be determined via the patch panel and the
- computer log..-In addition, a second channel of pressurizer level indication is available independent of the NNI..
Although the instruments identified in Table 3.5-2 are significant in diagnosing situations which could lead to inadequate core cooling, loss of any one of the instruments in Table 3.5-2 would not prevent continued, safe, reactor operation. Therefore, operation is justified for up to 7 days (48
~ hours for pressurizer level). Alternate indications are available for Saturation Margin Manitors using hand calculations, the PORV/ Safety Valve position monitors using discharge line thermocouple and Reactor Coolant Drain Tank indications, and for EFW flow using Steam Generator level and EFW pump discharge pressure. Pressurizer level has two channels, one channel from NNI
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(3 D/P instrument strings through a single indicator) and one channel
. independent of the NNI. Operati6n with the aoove pressurizer level channels l
out of service is permitteo for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Alternate indication would be
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available through the plant computer.
Manitors for containment pressure, containment water level,.. containment hydrogen level and various high range radiation monitors are useful to evaluate and predict tne course of accidents which go beyond the plant design basis (See Table 3.5-3).
.These instruments should be maintained for that purpose.
eksy.a 3-40b Amendment No. 75,100
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!E TADLE 3.5-3 8
SI Pnet Accident Monitoring In s t rumenta tion FUNCIIDN IN ST RUHEN T S REQUIRED NUMBER HINIMUM NUMBER AC T I ON OF CilANNEL S OF CllANNELS
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1.
High Range Noble Gas Ef fluent
[
a.
Condenser Vacuum Pump Exhaust 1
1 A
( Ril-A 5-li i )
b.
Condenser Vacuum Pump Exhaust 1
1 A
(llH-G2 5 )
e I
c.
Auxiliary and Fuel llendling 1
1 A
Building Exhaust (RM-A8-ili) i d.
Reactor Building Purge Exhaust 1
1 A
( h M-A9-Ill )
e.
Reactor Du11 ding Purge Exhaust 1
1 A
l
(
c)
(RH-C24)
EL f.
Main Steam Lines Radiation 1
1 A
each OTSG each UtSG
( R H-G26 /it H-G 2 7 )
2.
Containment Iligh Range Radiation 2
2 A
(RM-G22/23) 3.
Containment Pressure 2
1 a
4.
C6ntainment water Level 2
1 0
5.
Containment fly dr o g e n 2
1 0
TABLE 3.5-3 (Continued)
ACTIONS A.
With the nunber of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements:
1.
either restore the inoperable. channel (s) to OPERA 3LE status within 7 days of the event, or 2.
prepare and submit a Special Report within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring tne system to OPERABLE status.
l B.
1.
With the number of OPERABLE accident monitoring instrumentation channels less than the. Required Channels OPERABLE requirements, restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
With the number of OPERABLE accident monitoring instrumentation channels less _than the Minimum Channels OPERABLE requirements, restore the inoperable channel (s).to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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3-40e Amendment No.100
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' A'.;
, SURVEILLANCE STANDARDS Specified. intervals may be adjusted plus or minus 25 percent to accommodate normal test schedules..
4.1 OPERATIONAL SAFETY REVIEW Applicability Applies to items directly related to safety limits and limiting conditions for operation.
' Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
Specification 4.'l.1 The minimum frequency and type of surveillance required for reactor protection system and engineered safety feature protection system instrumentation when the reactor is critical shall oe as stated in Table 4.1-1.
4.1.2 Equipment and sampling test shall be performed as detailed in Tables 4.1-2 and 4.1-3.
4.1.3 Each post' accident monitoring intrumentation channil shall be demonstrated OPERABLE by the performance of the check, test and calibration at th.e frequencies shown in Table 4.1-4.
Bases Check Failures such as blown instrument fuses, defective indicators, or faulted amplifiers which result in " upscale" or "downscale" ir:dication can be easily recognized by sinple' observation of the functioning of an. tastrument or system. Furthermore,' sucn failures are, in many cases, revealed by alarm or annuciator action. Comparison of output and/or state of independent channels measuring the same variable stpplements this type of built-in surveillance.
Based.on experience in operation o when the unit is in operation, tfief Loth conventio'nal and nuclear systems, minimum checking frequency stated is deemed adequate for reactor system instrumentation.
Calibration Calibration shall be performed to assure tne 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 calance checks will assure that the difference between the out-of-core instrumentation and the heat balance remains less than 4%.
4-1 Amendment No.
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Radiation llonitarleig Systems
- W(1)(3)
H(3)
Q(2)
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Using Llie installed check cource.whose. I hockground is less than twice the e xpec teel increuse in cpm whicle would result from cf the check mource alone. 'Dackground readings greater than this value are sufficient in Lliensolvos tu aliow tli s t the:
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monitor is functioning.
(2)
Except eres gamma radiation monitors o'
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IBM-C6, RH-C7, and NH-CU,'which are located in liigh radiation areas of the lleactor Dullding.
These monituru will be coliterutud quarterly or ut tho seout s clic elu l o d reactor sleutdown following tiisi j
quarter in which calibration would normally be due, if a shutdown during the di quarter does not occur.
(3)
Surveillances are required to be l
per formed only when containment integrity la required.
Ihle applies to monitors which In!Llate containment isolation only.
29.
Bligh.end Ldw P ressure NA NA R
Injection Systems:. flow Channels.
N,
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_ Dues not include the monitore covered under specification 3.5.5.2 and 4.1.3 9
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