ML20247N246
| ML20247N246 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 07/26/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20247N242 | List: |
| References | |
| NUDOCS 8908020341 | |
| Download: ML20247N246 (4) | |
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. OPR-50 Docket No. 50-289 Technical Specification Change Request No. 192 This Technical Specification Change Request is tubmitted 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:
Vi~ce President & Director, TMI-1 Sworn and Subscribed to before me this c2le4 day of G alc.
, 1989.
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. TECHNICAL SPEC 1FICAT10N CHANGE REQUEST (TSCR) NO. 192 GPUN requests that the attached revised pages replace page 4-2, 4-5 and 4-Sa'of the TMI-1 Technical Specifications.
II. REASON FOR CHANGE Four changes are incorporated in this TSCR:
A.
The first item pertains to revision of the Reactor Protection System channel testing schedule making the number of performances per channel more equitabic. Performing tests in accordance with the present schedule accrues significantly different numbers of monthly tests per channel over time. Since the rotation always begins with channel A, operating cycles containing several plant shutdowns and start-ups result in channel A accruing the greatest number of test performances with B, C and D decreasing respectively. Unnecessary degradation or wear of components having the greatest number of test cycles may result over the life of the plant. This change only alters the order of test performance previously delineated.
B.
The second item involves table 4.1-1.28(2). Area gamma radiation monitor, RM-G21 is included for exemption from quarterly calibration when purging is not permitted. This is in keeping with testing of similar Radiation Monitoring System channels and is based on ALARA considerations.
C.
Item three changes the list of monitors in the note on page 4-Sa to exclude those monitors specifically identified, thereby resolving conflicts between table 4.1-1 item 28 and tables 4.21-1 and 4.21-2.
D.
The. last item corrects an error in table 4.1-1.23. It replaces the word " Absolute" in the Channel Description with the word " Relative" on page 4-5.
III. SAFETY EVALUATION JUSTIFYING THE CHANGE The items comprising the change were evaluated and found to have no adverse effect upon nuclear safety.
Revising the rotation schedule of the Reactor Protection System channel testing will increase confidence in the operability of those channels that j
had a fewer number of tests. At the same time, it will reduce the wear on 1
those components having the greatest number of test cycles.
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l Inclusion of RM-G21 for exemption from quarterly calibration continties the precedent for testing similar Radiation Monitoring System channels located in the Reactor Building.
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1 Radiation chr.nnel RM-G21 provides monitoring of activity for containment isolation.
It monitors the Reactor Buildirig sump and alarms and isolates the sump by closing WDL-V534 and WDL-Vb35 on detection of radioactivity at or above the setpoint. 1 l
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I-III. SAFETY EVALUATION JtJSTIFYING THE CHANGE (CONT'D.)
Decreasing the calibration frequency will have no affect on the nuclear safety or safe plant operation since:
a.
the safety function is required infrequently; the sump isolation valves are normally closed (open only for draining the sump).
b.
changing isolation valve positions to oper, requires manual action.
It is not automatic.
Closure cf WDL-V535 is autoinatic on low sump level.
c.
conservatism exists in the independent alert setpoint.
d.
administrative controls require operator action in response to excessive radiation levels indicated by sustained or unexpected alert or high alarm from radiation monitors reading out in the control room.
Given the above, any drift resulting from the lenger calibration frequency should not impact the aM11ty to isolate the sump.
The benefit of the change which will result from the decrease in calibration frequency is a reduction in personnel expoture which offsets any decrease in reliability which might result from the increase in calibration frequency.
Revising the note to exclude the monitors identified by the specified TS sections, 3.21 ( Radioactive Liquid Effluent Instrumentation ) and 4.21 ( Radioactive Gaseous Process and Effluent Monitoring Instrumentation ), eliminates possible ambiguity in the Radiation Monitoring System channel being described.
The final proposed change is administrative in nature and has no adverse effect upon nuclear safety. TS 4.3-1.23 has been changed to correct a clerical error since " Absolute" has been specified instead of " Relative".
IV. NO SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this lechnical Specification Change Request poses no significant hazards as defined by the NRC in 10 CFR 50.92. It does not involve significant hazards as evaluated below.
1.
Operation of Three Mile Island Nuclear $tation, Unit-1, in accordance with this change would not involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed Technical Specification does not modify or create an accident initiating condition.
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IV. - NO SIGNIFICANT HAZARDS CONSIDERATIONS (CONT'D.)
2.
Operation of Three Mile. Island Nuclear Station, Unit-1, in accordance with this change would not create the possibilit; of a new or different kind of accident from any accident previously evaluated because the proposed Technical Specification does not modify or create an accident initiating condition.
3.
Operation of Three Mile Island Nuclear Station, Unit-1, in accordance with this che.nge would not involve a significant reduction in a margin of safety since all Updated Final Safety Analysis Report (UFSAR) assumptions remain unchanged.
V.
IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon issuance and shall be implemented within thirty days of receipt.
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