ML20198K529
| ML20198K529 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/08/1998 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEIN-97-077, IEIN-97-77, NUDOCS 9801150027 | |
| Download: ML20198K529 (5) | |
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_7 PECO NUCLEAR n
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' A Unit of PECO Energy UMO$rY,o January 8,1998 Docket No. 50-352 50-353 License Nos. NPF-39 NPF-85 j
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Limerick Generating Station, Units 1 and 2 Technical Specifications Change Request No. 96-06-0 Company Name Change Supploraent i
Dear NRC Officials:
By letter dated February 25,1997, PECO Energy submitted Technical Specifications (TS) Change Request No. 96-06-0 for Limerick Generating Station (LGS), Units 1 and 2, requesting a change to the LGS Facility Operating License, and Appendix A and Appendix B of tha license, reflecting a corporate name change, removal of obsolete information, and correction of typographical errors.
PECO Energy is withdrawing a portion of the TS change request. On October 10, 1997, the NRC issued NRC Information Notice 97-77, " Exemptions From the Requirements of Section 70.24 of Title 10 of the Code of Federal Regulations." The Information Notice, which is related to NRC Policy issue, SECY-97-155 (issued on July 21,1997), informed licensees about actions the staff plans to take regarding the need to retain an exemption for 10 CFR 70.24, " Criticality Accidert Requirements." PECO
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Energy's TS change request indicated that the refererice to the exemption and the r$bsolete material license (SNM-1977) containing the exemption would be deleted from the LGS Unit 2 Facility Operating License, Section 2.D. In light of SECY 97-155 and Information Notice 97-77, the removal of the exemption reference and traceability to the NRC Authorization of the exemption through SNM-1977 would not be correct.
. Therefore, PECO Energy is withdrawing its request to remove the reference noted as change number 29 in our February 25,1997 request.
This supplement does not change the information supporting the Finding of No Significant Hazards Consideration Section, contained in our February 25,1997 request letter, Attachment 1 to this letter contains the marked up Unit 2 FOL page 5, reflecting this partial withdrawal. - This information is being submitted under affirmation, and the If I required affidavit is enclosed.-
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January 8,1998 t
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If you have any questions or require additional information, please do not hesitate to contact us.
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Very truly yours, Y Y $ l/=og G. A. Hunger, Jr.
. Director-Licensing Attachments Enclosure r
. cc:
. H. J. Miller, Administrator, Region I, USNRC (w/ attachments, enclosure)
A. L. Burritt, USNRC Senior Resident inspector, LGS (w/ attachments, enclosure)
R. R. Jsnati, Director, PA Bureau of Radiological Protection (w/ attachments, enclosure) i f
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COMMpNWEALTH 0F. PENNSYLVANIA.
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5 COONTY OF PHILADELPHIA 1
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1 LJ. B. Cotton, being first d'uly sworn, deposes and says: 'that he is Vice President of i
PECO Energy Company, the Applicant herein; that he has read the enclosed
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supplement and withdrawal for a portion of Technical Specifications Change Request
- ; No._96-06-0, " Company Name Change," for Limerick Generating Station, Unit 1 andl:
F thereof; Tand that the statements and matters set forth therein are trun and correct to
' the best of his knowledge, information and belief..
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Vi6e President 4
' Subscribed and sworn to ibefore'me this f day
- of J 1998.
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-l ATTACHMENT 1
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-s LIMERICK GENERATING STATION
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UNITS 1 AND 2.
- Docket Nos. 50-352 50-353 License Nos.- NPF-39 NPF-85 C
4 TECHNICAL SPECIFICATIONS CHANGE REQUEST No. 96-06-0 Supplement AFFECTED PAGE m
Unit 2 1
- FOL,
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3893262360
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the local leak rate testing of the Traversing Incore Probe Shear from the schedule requirements of 10 CFR 50.33(k()(1) related to availability of funds for decomissioning the facility (Section 22.1, SSER 8)'~and (e) exemption 4 rom the requirement ofA0 CFR Pa (W.44, the,fnerting'of contain' ment sf(months'after iffitiaf
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criticality (Section_6.2.5'of SSERAO.4the special circumstances regarding exemptions (a), (b) and (c) are identified in Sections 6.2.6.1 of the SER and SSER 3.
1.n exemption from the criticality monitoring requirements of 10 CFR 70.24 was prevfously granted with NRC materials license No. SNM-1977 issued November 22, 1988. The licensee is hereby exempted from the requirements of 10 CFR 70.24 insofar as this requirement applies to the handling and storage of fuel assemblies held under this ifcense.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items a, b, c, d, and e above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and reguistions of the Comission.
E.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial r.otification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Ccater via the Emergency Notification System with written followup within thirty days in accordancewiththeproceduresdescribedin10CFR50.73(b),(c),
and (e).
F.
The licer.sce shc11 have and maintain financial protection of such type and in such amounts as the Consnission shall require in
.accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
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