ML20234C339
| ML20234C339 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1987 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20234C141 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8709210252 | |
| Download: ML20234C339 (4) | |
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s METROPOLITAN EDIS0N COMPANY
' JERSEY' CENTRAL POWER & LIGHT. COMPANY AND PENNSYLVANIA ELECTRIC COMPANY-THREE MILE ISLAND NUCLEAR STATION, UNIT.1 Operating License No. DPR-50 Docket No.:50-289 Technical. Specification Change Request No.175 This Technical Specification Change Request is submitted in support of Licensee's' request to change Appendix ~A to Operating License No. DPR-50 for Three Mile.
Island Nuclear.' Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION BY:
Yf te Pr(sitent & Director, TMI-l Sworn and Subscribed to before mp thJs /b' day of Jf nL abfv,1987.
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)otary PubJTc snARctt r,810W1 fiOTARY PU3UC Nf 0D' TOW?4 0020, DAUPHIN COUNTY J
KY C0mt; WON EIPIRES JUNE 12.1933 m, Perugwaia Assxbtlea of fjatr.rIn 8709210252 870915 PDR ADOCK 05000289c P
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I.
TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR)'NO. 175 GPUN requests.that the following changed replacement pages be inserted into the existing Technical Specification:
Revised pages: 3-40b, 3-40d, 4-10a L
These pages are attached to this change request.
II.
REASON FOR CHANGE In accordance with commitments outlined in GPUN letters dated October 1 and November 9,1984 and NRC ' Order dated _ July 18,1985, TMI-1 will have q
installed the post-accident monitoring instrumentation to satisfy
?
Regulatory Guide 1.97, Revision 3, Category I indication requirements for the following variables' prior to startup following refueling i
outage 7:
1.
Wide Range Neutron Flux 2.
RCS Cold Leg Water Temperature 3.
RCS Hot Leg Water Temperature i
4.
RCS Pressure 5.
Core Exit Temperature 6.
Coolant Inventory 7.
Degrees of Subcooling 8.
Containment Sump Water Level 9.
Containment Pressure 10.
Containment Isolation Valve Position 11.
Containment Area Radiation - High Range 12.
Containment Hydrogen Concentration 13.
LPI/ Decay Heat Removal System Flow 14.
Flow in.HPI System (Makeup Flow-in) 15.
Refueling Water Storage Tank Level (BWST) 16.
Steam Generator Level 17.
Steam Generator Pressure 18.
Auxiliary or Emergency Feedwater Flow 19.
Condensate Storage Tank Water Level III.
SAFETY EVALUATION JUSTIFYING CHANGE I
The proposed amendment incorporates appropriate surveillance and operability requirements to ensure operability of instrumentation associated with Wide Range Neutron Flux, RCS Cold Leg Water Temperature, RCS Hot Leg Water Temperature, RCS Pressure, Steam Generator Pressure and Condensate Storage Tank Water Level variables. The proposed i
surveillance and operability requirements are commensurate with those requirements currently specified in TMI-1 Technical Specification l
Sections 3.5.5 and 4.1 for existing Accident Monitoring Instrumentation.
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Existing TMI-1 Technical Specification Table 3.5-2 provides adequate surveillance and operability requirements to ensure operability of post-accident monitoring instrumentation associated with Core Exit Temperature, Degrees of Subcooling, and Auxiliary or Emergency Feedwater
)
Flow variables.
Existing TMI-1 Technical Specification Table 3.5-3 l
provides adequate surveillance and operability requirements to ensure operability of post-accident monitoring instrumentation associated with Containment Sump Water Level, Containment Pressure, Containment' Area Radiation-High Range, and Containment Hydrogen Concentration variables.
Existing TMI-1 Technical Specification Table 4.1-1 'provides adequate i
surveillance and operability requirements to ensure operability of j
post-accident monitoring instrumentation associated with LPI/ Decay Heat Removal System Flow, Flow in HPI System (Makeup Flow-in), Refueling Water Storage Tank Level (BWST), and Steam Generator Level variables.
IV.
NO SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this Technical Specification Change Request poses no significant hazards as defined by NRC in 10 CFR 50.92.
1.
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
The design basis events related to this change are those accidents evaluated in TMI-l FSAR Chapter 14. The proposed amendment ensures operability of instrumentation installed to monitor selected plant variables and systems during and following the postulated accidents analyzed in Chapter 14 of the TMI-1 FSAR, and has no affect on the probability of occurrence or consequences of these previously evaluated accidents.
2.
Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The design basis events related to this change are those accidents evaluated in THI-1 FSAR Chapter 14. The proposed amendment has no affect on the possibility of creating a new or different kind of accident from any accident previously evaluated.
The proposed amendment ensures operability of instrumentation installed to monitor selected plant variables and systems during and following the postulated accidents analyzed in Chapter 14 of the TMI-l FSAR and is unrelated to the possibility of creating a new or different kind of accident.
3.
Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
The proposed amendment constitutes an additional control not presently included in the Technical Specifications. Therefore, the overall margin of safety for the plant is increased.
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- The Commission has.provided. guidelines pertaining to the.
application of, the three standards by listing specific. examples in 48 FR 14870.:' The proposed amendment is' considered to be in the same) category as. example (ii) of amendments that are considered not' likely to involve significant hazards consideration in that the proposed change constitutes an additional control not presently.
. included.in the. technical specifications..Thus, ' operation of the facility in 'accordance with the proposed amendment involves no
'significant hazards considerations.
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.V.
' IMPLEMENTATION It is requested-that the amendment authorizing this change become effective. upon startup following Cycle 7 refueling. outage.
AMENDMENT FEE (10 CFR 170.21,)
VI.. :
Pursuant.to the provisions of.10 CFR 170.21, attached is a check for
$150.00.
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