ML20041D353
| ML20041D353 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/25/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20041D337 | List: |
| References | |
| NUDOCS 8203050254 | |
| Download: ML20041D353 (4) | |
Text
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METROPOLITAN EDISON COMPAhT 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.lli 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 thir request, proposed replacement pages for Appendix A are also inclEded.
GPU NUCLEAR CORPORATION By Director, TMI-l Svornandsubscribedtomethis,76 dayofOY LC M / 1982.
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W Notaj Pflic FAMELA JOY LUE.!CHT, Natary Public Mdd,ttown, Dauphin County, Pa.
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8203050254 820225 PDR ADOCK 05000289 P
F UNITED STA1ES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No.lli to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Donald Hoover, Chairman Mr. John E. Minnich, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION By )
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Director, TMI-l Dated:
February 25, 1982
l I
TECHNICAL SPECIFICATION CHANGE REQUEST NO. 111 The Licensee requests the attached changed pages replace the following pages of the existing Technical Specifications:
Appendix A Replace pages 3-61, 3-62a, 3-62c,l4-55d II.
REASONS FOR CHANGE REQUEST At the present time, Technical Specifications reauire the Control Building Emergency Ventilation System (CBEVS), the Reactor Building Purge Exhaust System (RBPE), and the Auxiliary and Fuel Handling Building Ventilation System to have a > 90% radioactive methyl iodine decontamination efficiency during irradiated fuel handling. During our planned inspection of the Reactor Coolant System, ventilation operability would be required. This change request is being submitted to modify the existing Technical Specif-ications to establish ventilation operability without requiring the specified laboratory carbon sample analysis.
Further, it has been determined as a result of recent performance testing and balancing of the auxiliary and fuel handling building ventilation system (A&FHV).that the-original design. flow.through the building of 118,810 CFM (i 10%) cannot be achieved. Actual measured flow is 103,210 CFM. This is not considered important for our planned fuel movement, since if a fuel accident were to occur, the A&FHV system supply fans would trip and the exhaust ~ fans would draw a negative pressure on the auxiliary fuel handling buildings.
Current operating flow will be 103,000 CFM i 10%.
Relief from this requirement is still necessary.
III.
SAFETY ANALYSIS JUSTIFYING CHANGE Movement of irradiated fuel would require ventilation operability as defined in Section 3.15 of the TMI-1 Technical Specifications. However, due to the extended period of time since fuel assemblies were last irradiated and the relatively short half-lif e of 1 31 and its associated isotopes, 1
virtually no radioiodine remains.
Since the Reactor is to remain shutdown, no new Il31 or its associated isotopes will be generated. Therefore, since virtually no radioiodine exists the potential for release to the atmosphere would be less than that due to a fuel handling accident with freshly irradiated fuel with the charcoal filters operable. On this basis, the charcoal adsorbers of the Ventilation Systems need not be operable. The charcoal adsorbers will be replaced prior to Restart.
The purpose of the A&FHV system is to maintain a negative pressure (to prevent the spread of contamination) and to provide adequate ventilation flow for equipment cooling needs. Major safety related equipment do not rely upon the A&FHV system for cooling. Additionally, during the planned RCS inspection, the major ECCS components will not be required to be operable.
Prior to Cycle 5 operation our re-evaluation of the current ventilation needs of the auxilary and fuel handling building will be completed and a revision of Sections 3.15.3 will be submitted with a detailed safety evaluation.
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i The dampers which have been installed in the A&FHV system to protect the Unit 1 Auxilary Building from contamint. tion during Unit 1 Operations, in the event of the Submerged Deminerizer Eystem failure, will not be used during the fuel handling evolutions prior to Restart. This will' assure that the A&FHV will not be intentpted and that releases if any.
will be monitored by the normal release paths.
Since TMI-1 will not be operating, safe operations cannot be affected.
Conclusion In conclusion, with regard to Reactor Building Purge Exhaust System and the Auxilary & Fuel Handling Building Ventilation System and Control Building Emergency Ventilation System and associated Technical Specifications:
(1) The probability or consequences of accidents previously evaluated have not increased.
(2) No accidents, other than those previously considered, will be introduced.
(3) No safety margins have been reduced.
6 IV.
AMENDMENT CULSSIFICATION (10 CFR 170.22)
This change request involves a single safety issue and is therefort, considered a class III license amendment. A check is the amount of
$4,000.00 is enclosed.
V.
IMPLEMENTATION In order to f acilitate the reactor coolant inspection, we request that the Amendment be effective as of the date of issuance.
VI.
REFERENCES 1.
Technical Specification Change Request No.102, Letter Llt 113, Dated 4-24-81.
2.
FSAR Chapter 9, Sections ;9.8.25, 9.8.3.3, 9.8.4e, and Figure 9.20 a