ML20036B972
| ML20036B972 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/26/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036B971 | List: |
| References | |
| NUDOCS 9306070415 | |
| Download: ML20036B972 (2) | |
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO FACILITY OPERATING LICENSE NO. DPR-73 GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 2 DOCKET NO. 50-320 l
1.0 INTRODUCTION
By letter dated March 17, 1992, GPU Nuclear Corporation (GPUN or the licensee) requested the approval of a change to the Three Mile Island Nuclear Station, Unit No. 2 (TMI-2) Appendix A and Appendix B Technical Specifications (A-TS and B-TS respectively).
Included in this request to change the license was a request to change the TMI-2 Recovery Operations Plan (ROP). The R0P is a separate document that contains the surveillance requirements for TMI-2.
The surveillance requirements were removed from the TMI-2 Appendix A technical specifications by NRC Order dated February 13, 1980.
They have been maintained since that date as a separate document amendable by letter authorization by the NRC staff.
The purpose of the current R0P amendment request and the associated R0P is to relocate the TMI-2 Technical Specifications related to radiological effluents to the Offsite Dose Calculation Manual (0DCM) in accordance with the guidance in NRC staff Generic Letter 89-01 dated January 31, 1989.
A copy of the proposed ODCM was enclosed for NRC staff review in the March 17, 1992 submittal.
On June 18, 1992, the licensee submitted Revision 1 to their amendment request.
Revision 1 provided an updated copy of the TMI Site ODCM.
The updated copy of the ODCM was identified as Revision 2.
On December 23, 1992, the licensee submitted Revision 2 to their amendment and R0P change request.
The December 23, 1993 revision requested that the TMI-2 Technical Specifications reporting requirements related to quarterly-dose assessment and radioactive effluents be changed cc.isistent with the provisions of 10 CFR 50.36a(a)(2).
Neither the March 17, 1992 nor the December 23, 1992 submittals revised the licensee's proposed changes to the R0P originally submitted by letter dated March 17, 1992.
2.0 DISCUSSION AND EVALUATION The licensee's request for changes to the TMI-2 Appendix A and Appendix B i
Technical Specifications and their Revision 2 to the ODCM are approved in a separate letter issued concurrently with this change to the TMI-2 R0P.
1 Section 4.3.3.1, " Radiation Monitoring Instrumentation", of the TMI-2 R0P refers to Table 4.3-3 which lists and defines operability for each required station radiation monitor.
The licensee proposes removing Section 4.3.3.1 and I
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the corresponding Table 4.3-3 from the R0P and relocating the remaining applicable requirements to the ODCM Part II, Section 3.3 and Table 2.3-1.
The current R0P requirement specifies monitoring at a number of locations in the facility at specific facility modes. The licensee is currently in Mode 3 and is physically unable to reenter Modes I or 2.
The licensee, in R0P change 46, requested that monitoring requirements defined for only Modes I and 2, and therefore no longer applicable to TMI-2, be deleted from the original Table 4.3-3.
These are the vent monitor for the Containment Air Control Envelope (Mode 1 only), Fuel Handling Building Exhaust Monitors (Modes 1 and 2 only), Submerged Demineralizer System (SDS) monitors (SDS is no longer operating and has been dismantled), Fuel Transfer Canal (Modes 1 and 2 only),
Fuel Pool "A" (Modes 1 and 2 only), Fuel Handling Building Truck Bay (Modes )
and 2 only), and Reactor Building End Fitting Storage Area (Mode _1 only).
The remaining monitoring requirements for the Containment and the. Waste Handling and Packaging Facility are to be transferred to the ODCM. The staff finds the proposed relocation of the remaining operable requirements to the ODCM acceptable and consistent with NRC staff Generic Letter 89-01.
The licensee also requested that Section 4.3.3.1, " Radiation Monitoring Instrumentation", in the text of the R0P, that refers to the requirements in Table 4.3-3 also be deleted. Since the table would no longer be part of the R0P there is no need to retain an operability statement in the text. The licensee also proposes updating the index (table of contents) to the R0P to reflect the deletion of Section 4.3.3.1.
The staff finds these administrative changes acceptable.
3.0 CONCLUSION
The proposed changes are consistent with the guidance in NRC staff Generic Letter 89-01 and will not adversely affect the health and safety of the public.
These changes do not constitute an unreviewed safety question, nor do they involve a significant hazard or an environmental impact.
Since the licensee is eliminating requirements in the R0P that are no longer applicable and relocating the remaining requirements to the ODCM, and making some minor administrative changes, the staff finds the changes acceptable.
Principal Contributor: Michael T. Masnik Date:
May 26, 1993 t