ML20137X047
| ML20137X047 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1985 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20137X035 | List: |
| References | |
| NUDOCS 8510040448 | |
| Download: ML20137X047 (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. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 143, Rev. 1 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
' Directo'r, THI-1 Sworn and Subscribed day of Aintt.rn%js.86 to.beforp mp,th
, 1985.
/ I AW f
Notary.P M ic g*We 'a#*h' a
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 GPU NUCLEAR C'ORPORATION This is to certify that a copy of Technical Specification Change Request No. 143, Rev. 1 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Fred Rice, Chairman Bo'ard of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Mit'dletown, PA 17057 Harrisburg, PA 17120 Mr. Thomas Gerusky, Director PA.' Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATIO BY 51 rector', TMI-1 DATE: September 30, 1985 L
I.
Technical Specification Change Request No.143, Rev.1 It is requested that the attached revised pages replace the following pages of the existing Technical Specifications:
Replace pages 3-27, 3-28, 4-2, 4-3 Add new pages 3-27a, 3-28a This request supersedes the previous Request No. 143-in its entirety.
II.
Reason for Change On February 1, 1985, Tech. Spec. Change Request 143 was submitted to provide clarification that the regulating control rod power silicon controlled rectifier (SCR) electronic trips are trip tested monthly, and prior to startup when the reactor has been shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Tech. Spec. Change Request 143 is being revised to also provide conditions for operability for control rod drive trip breakers and diverse trip devices, and the regulating control rod power SCR electronic trips.
III. Safety Evaluation Justifying Change TMI-1 Technical Specification Table 4.1-1, Item 2, requires that the control rod drive trip breakers be trip tested monthly and prior to
'startup when the reactor has been shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The language of the Specification is broad enough to cover the SCR portion of the trip function, however, for clarity, the Specification is being changed to specifically identify the SCR portion of the trip.
function. TMI-1 Surveillance Procedure 1303-4.1 requires confirmation
.of the SCR trip function by verifying the reduction in current from the affected power supply on a monthly basis. This Tech. Spec. change is an administrative change for clarification only; the testing requirement remains the same.
The existing Specification 3.5.1.6 has' been expanded to provide limiting conditions for operation for specific components of the reactor trip system, i.e, control rod drive trip breakers, the diverse trip features and the regulating control rod power SCR electronic trips, in accordance with the guidance provided in Generic Letter 85-10. The addition of conditions for the diverse trip features, due to the addition of the shunt trip. attachment, and the SCR electronic trips will assure the reliability of the reactor trip system is not reduced due to the
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inoperability of one of these components. Thus, these conditions will
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constitute an additional control and not reduce the margin of safety.
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IV.
No Significant Hazards Consideration The proposed change provides a clarification to a surveillance and the clarification and addition of limiting conditions for operation for components of the reactor trip system consistent with the guidance provided in Generic Letter 85-10 and:
l 1.
does not adversely affect plant design or operation, and therefore l
would not involve a significant increase in the probability or consequences cf an accident previously evaluated; l
2.
does not involve modification to existing plant equipment, and therefore would not create the possibility of a new or different kind of accident from any accident previously evaluated; 3.
does not involve changes which would affect the safety analysis of the plant, and therefore would not involve a significant reduction in a margin of safety.
The proposed amendment is in the same category as Example (11) of amendments that are considered not likely to involve significant hazards consideration (48 FR 14870) in that the change constitutes an additional control not presently included in the Technical Specifications.
I V.
Implementation It is requested tht. this amendment become effective upon issuance.
VI.
Amendment Fee (l's TP(170.21)
Pursuant to the provisions v? 10 CFh 170.21, a check for $150.00 was provided on February 12, 1985,s payment for Tech. Spec. Change Request 143.
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