ML20078Q706
| ML20078Q706 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/13/1994 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9412230037 | |
| Download: ML20078Q706 (3) | |
Text
Ctation Support Department c==-
PECO ENERGY 5imf=""Lo,,
965 Chesterbrook Boulevard Wayne, PA 19087-5691 December 13,1994 Docket Nos. 50-352 50-353 License Nos. NPF 39 NPF-85 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Units 1 and 2 Technical Specifications Change Request No. 93-18-0 MSIV Leakage Control System Gentlemen:
By letter dated January 14,1994. PECO Energy Company (PECO Energy) submitted a Limerick Generating Station (LGS), Unit 1 and Unit 2, Technical Specifications (TS) Change Request (i.e.,
93-18-0) that proposed to increase the allowab's leak rate for the main steam isolation valves (MSIVs) and to delete the MSIV Leakage Control System (LCS). The Change Request utilized the General Electric, BNing Water Reactor Owners' Group (BWROG) seismic analysis methodology (NEDC 31858P). The Changa Request was sir.dlar to plant Hatch's request, which was subsequently approved by the NRC, and met the intent of 10CFR Part 100, Appendix A.
The NRC requested additional information pertaining to this methodology, and it was provided by PECO Energy letters dated August 1,1994 and October 25,1994.
On December 9,1994, a telephone conversation between the NRC and PECO Energy was established to clarify selsmic structural Issues pertaining to the methodology used in the subject LGS Change Request. During the December 9,1994, telephone conversation the NRC and PECO agreed that in order to completely resolve the issues, a one-time (i.e., will not be part of the licensing basis) seismic pipe analysis, in accordance with a NRC previously approved methodology, for the non-Category I portion of the proposed alternate drain pathway (LGS Line EBD-208), would be necessary to confirm the previously submitted analysis. Therefore, the
- following are the results of this confirmatory analysis, which corroborate our January 14,1994 TS Change Request. This information is being submitted under affirmation, and the associated affidavit is enclosed.
In order to provide this additional confirmation of the BWROG seismic methodology (NEDC 31858P), a preliminary seismic analysis has been performed, which will be finalized in a few days, for pipe line EBD-208, assuming LGS Safe Shutdown Earthquake (SSE) loads and using Bechtel computer code ME-101. The Bechtel code has been reviewed and found acceptable by the NRC and documented in the LGS Updated Final Safety Analysis Report (UFSAR) Section 1 9.1.2.6.1.
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4 December 13,1994 Page 2 The preliminary results showed the following. The EBD-208 line stresses were calculated assuming the SSE conditions and compared against the code allowable 2.4 S and found to be h
within the allowable limits. Supports were evaluated and found to be within the allowable limits with a majctity of expansion anchors having a safety factor of 4 and a few supports having a safety factor of 3.
The ME 101 analysis results corroborate the results of the NEDC 31858P seismic methodology, provided in the January 14,1994, change request submittal, which demonstrated that the proposed alternate pathway will be capable of performing its function during and after an SSE.
Consistent with the guidance in 10CFR Part 100, which provides the NRC criteria for evaluating the vitab8lty of seismic designs, the alternate pathway will remain functional during and following a Safe Shutdown Earthquake; thus meeting 10CFR Part 100, Appendix A. This design is based on equivalent static load analysis, a preliminary dynamic load analysis and actual demonstrations of the survivability of condensers in actual power plants that have experienced earthquakes.
If you have any questions, please do not hesitate to contact us.
Very truly yours, s
G. A. Hunger, Jr.,
Director-Licensing Attachments Enclosure cc:
T. T. Martin, Administrator, Region I, USNRC (w/ attachments and enclosure)
N. S. Perry, USNRC Senior Resident inspector, LGS (w/ attachments and enclosure)
R. R. Janati, PA Bureau of Radiological Protection (w/ attachments and enclosure)
,a COMMONWEALTH OF PENNSYLVANIA u.
COUNTY OF CHESTER D. R. Helwig, being first duly sworn, deposes and says: That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the enclosed information supporting Technical Specifications Change Request No. 9318-0 " Increase the Allowable Leak Rate for the Main Steam isolation Valves and Delete the MSIV Leakage Control System,' lor Limerick Generating Station, Unit I and Unit 2, Facility Operating License Nos. NPF-39 and NPF-85, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
Vice President Subscribed and sw to before rae this Ib day of 1994.
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