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| | document type = Letter type:JAFP, License-Application for (Amend/Renewal/New) for DKT 30, 40, 70 | | | document type = Letter type:JAFP, License-Application for (Amend/Renewal/New) for DKT 30, 40, 70 |
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| =Text= | | =Text= |
| {{#Wiki_filter:Entergy Nuclear NortheastEntergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 | | {{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. |
| | | James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Kevin Bronson Site Vice President - JAF JAFP-11-0003 January 13, 2011 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 |
| JAFP-11-0003 | |
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| January 13, 2011 | |
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| United States Nuclear Regulatory Commission | |
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| Attn: Document Control Desk | |
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| Washington, D.C. 20555 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 | | Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
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| Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) hereby requests an | | Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) hereby requests an amendment to the Facility Operating License (FOL) for the James A. FitzPatrick Nuclear Power Plant (JAF). |
| | This license amendment submittal requests the deletion of specific references to Safety Evaluation Reports (SER), Technical Specification Amendments, and Exemptions in condition 2.C(3), Fire Protection, of the FOL. The deleted text will be replaced with the words as supplemented. |
| | The proposed FOL change is non-technical in nature and thus does not involve a significant increase in the probability or consequences of an accident previously evaluated. This change has no effect on any previously submitted amendments currently under review by the NRC. provides a description and evaluation of the proposed FOL changes. provides the proposed FOL changes as marked up pages. provides the proposed FOL changes in final typed format with change bars. |
| | Entergy requests NRC approval of the proposed FOL amendment by January 13, 2012, with the amendment being implemented within 60 days from approval. |
| | In accordance with 10 CFR 50.91, a copy of this application, with the associated attachments, is being provided to the designated New York State official. |
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| amendment to the Facility Operating License (FOL) for the James A. FitzPatrick Nuclear Power
| | JAFP-11-0003 Page 2 of 2 There is no new commitment made in this letter. |
| | Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing Manager, at (315) 349-6766. |
| | I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on January 13, 2011. |
| | 7Z~ |
| | Kevin Bronson KB/JP/jo Attachments: 1. Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection, Description and Evaluation |
| | : 2. Proposed Facility Operating License Change (Marked up) |
| | : 3. Proposed Facility Operating License Change (Final Typed) cc: |
| | Regional Administrator, Region I Mr. Paul Eddy U. S. Nuclear Regulatory Commission New York State Department of Public 475 Allendale Road Service King of Prussia, PA 19406-1415 3 Empire State Plaza, 10th Floor Albany, NY 12223 Resident Inspector's Office U.S. Nuclear Regulatory Commission Mr. Francis Murray, President James A. FitzPatrick Nuclear Power Plant NYSERDA Lycoming, NY 13093 17 Columbia Circle Albany, NY 12203-6399 Mr. Bhalchandra Vaidya, Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Document Components: |
| | 001 Transmittal Letter, JAFP-11-0003; with attachments |
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| Plant (JAF).
| | JAFP-11-0003 Attachment 1 Application for Amendment to Modify the Facility Operating License Section 2.C(3), Fire Protection Description and Evaluation Page 1 of 4 |
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| This license amendment submittal requests the deletion of specific references to Safety
| | JAFP-11-0003 Attachment 1 |
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| Evaluation Reports (SER), Technical Specification Amendments, and Exemptions in condition
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| 2.C(3), Fire Protection, of the FOL. The deleted text will be replaced with the words as
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| supplemented.
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| The proposed FOL change is non-technical in nature and thus does not involve a significant
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| increase in the probability or consequences of an accident previously evaluated. This change
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| has no effect on any previously submitted amendments currently under review by the NRC.
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| provides a description and evaluation of the proposed FOL changes.
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| provides the proposed FOL changes as marked up pages.
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| provides the proposed FOL changes in final typed format with change bars.
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| Entergy requests NRC approval of the proposed FOL amendment by January 13, 2012, with the
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| amendment being implemented within 60 days from approval.
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| In accordance with 10 CFR 50.91, a copy of this application, with the associated attachments, is
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| being provided to the designated New York State official. Kevin Bronson Site Vice President - JAF JAFP-11-0003 Page 2 of 2 There is no new commitment made in this letter.Questions concerning this request may be addressed to Mr.Joseph Pechacek, Licensing Manager, at (315)349-6766.I declare under penalty of perjury that the foregoing is true and correct.Executed on January 13, 2011.Kevin Bronson KB/JP/jo Attachments:
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| 1.Applicationfor Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection, Description and Evaluation 2.Proposed Facility Operating License Change (Marked up)3.Proposed Facility Operating License Change (Final Typed)cc: Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office U.S.Nuclear Regulatory Commission James A.FitzPatrick Nuclear Power Plant Lycoming, NY 13093 Mr.Bhalchandra Vaidya, Project Manager Division of Operating Reactor Licensing U.S.Nuclear Regulatory Commission Washington, DC 20555-0001 Mr.Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10 th Floor Albany, NY 12223 Mr.Francis Murray, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399 Document Components:
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| 001 Transmittal Letter, JAFP-11-0003; with attachments Page 1 of 4
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| JAFP-11-0003
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| Application for Amendment to Modify the Facility Operating License Section 2.C(3), Fire Protection Description and Evaluation
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| JAFP-11-0003 Page 2 of 4
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| ==1.0 DESCRIPTION== | | ==1.0 DESCRIPTION== |
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| The proposed amendment would modify the Facility Operating License (FOL) by | | The proposed amendment would modify the Facility Operating License (FOL) by deleting references to specific Safety Evaluation Reports (SER), Technical Specification (TS) Amendments, and Exemptions from license condition 2.C(3), Fire Protection, and replacing them with the words as supplemented. This is an administrative amendment to the FOL. |
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| deleting references to specific Safety Evaluation Reports (SER), Technical Specification (TS) Amendments, and Exemptions from license condition 2.C(3), Fire Protection, and | |
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| replacing them with the words as supplemented. This is an administrative amendment | |
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| to the FOL. | |
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| ==2.0 PROPOSED CHANGE== | | ==2.0 PROPOSED CHANGE== |
| S Currently, FOL condition 2.C(3) states in part: | | S Currently, FOL condition 2.C(3) states in part: |
| | | the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), |
| the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 | |
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| dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated | |
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| October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated | |
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| February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), | |
| 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), | | 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), |
| 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated | | 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 The proposed change is to delete the preceding text and replace it with the words as supplemented. This change would facilitate record keeping by allowing the SERs, TS Amendments, and Exemptions to be tracked in the Fire Protection Program. |
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| January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated | |
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| April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and | |
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| September 10, 1992 | |
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| The proposed change is to delete the preceding text and replace it with the words as | |
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| supplemented. This change would facilitate record keeping by allowing the SERs, TS | |
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| Amendments, and Exemptions to be tracked in the Fire Protection Program. | |
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| ==3.0 BACKGROUND== | | ==3.0 BACKGROUND== |
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| In addition to the requirements of 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part | | In addition to the requirements of 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, the FOL contains additional conditions to which the James A. FitzPatrick Nuclear Power Plant (JAF) is subject to. Specifically, condition 2.C(3) requires JAF to maintain a Fire Protection Program as described in the Updated Final Safety Analysis (UFSAR) report and applicable supplements, amendments, and exemptions. |
| | | During the course of a fire protection triennial inspection, it was noted by the NRC that not all fire protection SERs were included in the fire protection condition of the JAF license. Further review and discussion by Entergy and the NRC concluded that there is no regulatory requirement to explicitly reference specific SERs in a plants license condition and that it would be appropriate to remove the specific SER references to be consistent with other plants. |
| 70, the FOL contains additional conditions to which the James A. FitzPatrick Nuclear | | In its current form, the FOL lists the original SER as well as supplemental SERs, NRC letters, Exemptions, and TS Amendments from 1972 through 1994. Fire protection SERs, NRC letters, Exemptions, and TS Amendments approved after 1994 have not been incorporated into the FOL conditions. They are tracked separately within the Fire Protection Program. |
| | | Page 2 of 4 |
| Power Plant (JAF) is subject to. Specifically, condition 2.C(3) requires JAF to maintain a | |
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| Fire Protection Program as described in the Updated Final Safety Analysis (UFSAR) | |
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| report and applicable supplements, amendments, and exemptions. | |
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| During the course of a fire protection triennial inspection, it was noted by the NRC that | |
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| not all fire protection SERs were included in the fire protection condition of the JAF | |
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| license. Further review and discussion by Entergy and the NRC concluded that there is | |
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| no regulatory requirement to explicitly reference specific SERs in a plants license | |
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| condition and that it would be appropriate to remove the specific SER references to be | |
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| consistent with other plants. | |
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| In its current form, the FOL lists the original SER as well as supplemental SERs, NRC | |
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| letters, Exemptions, and TS Amendments from 1972 through 1994. Fire protection | |
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| SERs, NRC letters, Exemptions, and TS Amendments approved after 1994 have not | |
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| been incorporated into the FOL conditions. They are tracked separately within the Fire
| | JAFP-11-0003 Attachment 1 |
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| Protection Program.
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| JAFP-11-0003 Page 3 of 4 | |
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| ==4.0 TECHNICAL ANALYSIS== | | ==4.0 TECHNICAL ANALYSIS== |
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| There is no technical change being requested. The proposed change is administrative | | There is no technical change being requested. The proposed change is administrative in order to facilitate record keeping of approved 10 CFR 50 Appendix R exemptions. |
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| in order to facilitate record keeping of approved 10 CFR 50 Appendix R exemptions. | |
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| 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration | | 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration |
| : 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously | | : 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? |
| | | Response: No. |
| evaluated? | | The proposed FOL change is administrative and does not involve a plant or design function change. It has no effect on reactor operation or accident analyses, and thus, the proposed FOL change does not increase the probability or consequence of an accident previously evaluated. |
| | | : 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? |
| Response: No. | | Response: No. |
| The proposed FOL change is administrative and does not involve a plant or design function change. It has no effect on reactor operation or accident analyses, and thus, the proposed FOL change does not increase the probability or consequence of an | | The proposed FOL change is administrative and does not involve a plant or design function change. Because the proposed amendment would not change the design, configuration, or method of operation of the plant, it would not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | | : 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety? |
| accident previously evaluated. | | Response: No. |
| : 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously | | The proposed FOL change is administrative and does not involve a plant or design function change. No design or safety margin is involved. Therefore, the proposed change does not involve a reduction in any margin of safety. |
| | | 5.2 Applicable Regulatory Requirements / Criteria 10 CFR 50.90 provides the criteria for license amendments. Whenever a holder of a license, including a construction permit and operating license under this part, and an early site permit, combined license, and manufacturing license under part 52 of this chapter, desires to amend the license or permit, application for an amendment must be filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications. |
| evaluated? | | Page 3 of 4 |
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| Response: No. | |
| The proposed FOL change is administrative and does not involve a plant or design | |
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| function change. Because the proposed amendment would not change the design, configuration, or method of operation of the plant, it would not create the possibility of a | |
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| new or different kind of accident from any accident previously evaluated. | |
| : 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety? | |
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| Response: No. | |
| The proposed FOL change is administrative and does not involve a plant or design | |
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| function change. No design or safety margin is involved. Therefore, the proposed | |
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| change does not involve a reduction in any margin of safety. | |
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| 5.2 Applicable Regulatory Requirements / Criteria 10 CFR 50.90 provides the criteria for license amendments. Whenever a holder of a | |
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| license, including a construction permit and operating license under this part, and an | |
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| early site permit, combined license, and manufacturing license under part 52 of this | |
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| chapter, desires to amend the license or permit, application for an amendment must be | |
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| filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form | |
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| prescribed for original applications. | |
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| JAFP-11-0003 Page 4 of 4
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| 5.3 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable
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| assurance that the health and safety of the public will not be endangered by operation in
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| the proposed manner; (2) such activities will be conducted in compliance with the
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| Commissions regulations; and (3) the approval of the proposed change will not be
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| inimical to the common defense and security or to the health and safety of the public.
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| 6.0 ENVIRONMENTAL ASSESSMENT A review has determined that the proposed changes would not change a requirement
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| with respect to installation or use of a facility component located within the restricted
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| area, as defined in 10 CFR 20, and does not change any inspection or surveillance
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| requirement. Therefore, the proposed change does not involve: (i) a significant hazards
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| consideration; (ii) a significant change in the types or significant increase in the amounts
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| of any effluents that may be released offsite; or (iii) a significant increase in individual or
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| cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental
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| assessment need be prepared in connection with the proposed changes.
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| 7.0 REFERENCE 1 USNRC, Code of Federal Regulations, Section 10 CFR 50.90 Application for amendment of license, construction permit, or early permit
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| JAFP-11-0003
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| Proposed Facility Operating License Change (Marked up)
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| Facility Operating License Page 3
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| A m e n d m e n t 2 9 9
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| (4) E N O p u r s u a n t t o t h e A c t a n d 1 0 C F R P a r t s 3 0 , 4 0 , a n d 7 0 t o r e c e i v e , p o s s e s s , a n d u s e , a t a n y t i m e , a n y b y p r o d u c t , s o u r c e a n d s p e c i a l n u c l e a r m a t e r i a l w i t h o u t r e s t r i c t i o n t o c h e m i c a l o r p h y s i c a l f o r m , f o r s a m p l e a n a l y s i s o r i n s t r u m e n t c a l i b r a t i o n; o r a s s o c i a t e d w i t h r a d i o a c t i v e a p p a r a t u s , c o m p o n e n t s o r t o o l s..
| | JAFP-11-0003 Attachment 1 5.3 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commissions regulations; and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public. |
| (5) P u r s u a n t t o t h e A c t a n d 1 0 C F R P a r t s 3 0 a n d 7 0 , t o p o s s e s s , b u t n o t s e p a r a t e , s u c h b y p r o d u c t a n d s p e c i a l n u c l e a r m a t e r i a l s a s m a y b e p r o d u c e d b y t h e o p e r a t i o n o f t h e f a c i l i t y. | | 6.0 ENVIRONMENTAL ASSESSMENT A review has determined that the proposed changes would not change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and does not change any inspection or surveillance requirement. Therefore, the proposed change does not involve: (i) a significant hazards consideration; (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed changes. |
| C. T h i s r e n e w e d o p e r a t i n g l i c e n s e s h a l l b e d e e m e d t o c o n t a i n a n d i s s u b j e c t t o t h e c o n d i t i o n s s p e c i f i e d i n t h e f o l l o w i n g C o m m i s s i o n r e g u l a t i o n s i n 1 0 C F R C h a p t e r I: P a r t 2 0 , S e c t i o n 3 0.3 4 o f P a r t 3 0 , S e c t i o n 4 0.4 1 o f P a r t 4 0 , S e c t i o n s 5 0.5 4 a n d 5 0.5 9 o f P a r t 5 0 , a n d S e c t i o n 7 0.3 2 o f P a r t 7 0; a n d i s s u b j e c t t o a l l a p p l i c a b l e p r o v i s i o n s o f t h e A c t a n d t o t h e r u l e s , r e g u l a t i o n s , a n d o r d e r s o f t h e C o m m i s s i o n n o w o r h e r e a f t e r i n e f f e c t; a n d i s s u b j e c t t o t h e a d d i t i o n a l c o n d i t i o n s s p e c i f i e d o r i n c o r p o r a t e d b e l o w:
| | 7.0 REFERENCE 1 USNRC, Code of Federal Regulations, Section 10 CFR 50.90 Application for amendment of license, construction permit, or early permit Page 4 of 4 |
| (1) M a x i m u m P o w e r L e v e l E N O i s a u t h o r i z e d t o o p e r a t e t h e f a c i l i t y a t s t e a d y s t a t e r e a c t o r c o r e p o w e r l e v e l s n o t i n e x c e s s o f 2 5 3 6 m e g a w a t t s (t h e r m a l). | |
| (2) T e c h n i c a l S p e c i f i c a t i o n s T h e T e c h n i c a l S p e c i f i c a t i o n s c o n t a i n e d i n A p p e n d i x A , a s r e v i s e d t h r o u g h A m e n d m e n t N o. 2 9 9 a r e h e r e b y i n c o r p o r a t e d i n t h e r e n e w e d o p e r a t i n g l i c e n s e. T h e l i c e n s e e s h a l l o p e r a t e t h e f a c i l i t y i n a c c o r d a n c e w i t h t h e T e c h n i c a l S p e c i f i c a t i o n s. (3) F i r e P r o t e c t i o n E N O s h a l l i m p l e m e n t a n d m a i n t a i n i n e f f e c t a l l p r o v i s i o n s o f t h e a p p r o v e d f i r e p r o t e c t i o n s p r o g r a m a s d e s c r i b e d i n t h e F i n a l S a f e t y A n a l y s i s R e p o r t f o r t h e f a c i l i t y a n d a s a p p r o v e d i n t h e S E R d a t e d N o v e m b e r 2 0 , 1 9 7 2; t h e S E R S u p p l e m e n t N o. 1 d a t e d F e b r u a r y 1 , 1 9 7 3; t h e S E R S u p p l e m e n t N o. 2 d a t e d O c t o b e r 4 , 1 9 7 4; t h e S E R d a t e d A u g u s t 1 , 1 9 7 9; t h e S E R S u p p l e m e n t d a t e d O c t o b e r 3 , 1 9 8 0; t h e S E R S u p p l e m e n t d a t e d F e b r u a r y 1 3 , 1 9 8 1; t h e N R C L e t t e r d a t e d F e b r u a r y 2 4 , 1 9 8 1; T e c h n i c a l S p e c i f i c a t i o n A m e n d m e n t s 3 4 (d a t e d J a n u a r y 3 1 , 1 9 7 8), 8 0 (d a t e d M a y 2 2 , 1 9 8 4), 1 3 4 (d a t e d J u l y 1 9 , 1 9 8 9), 1 3 5 (d a t e d S e p t e m b e r 5 , 1 9 8 9), 1 4 2 (d a t e d O c t o b e r 2 3 , 1 9 8 9), 1 6 4 (d a t e d A u g u s t 1 0 , 1 9 9 0), 1 7 6 (d a t e d J a n u a r y 1 6 , 1 9 9 2), 1 7 7 (d a t e d F e b r u a r y 1 0 , 1 9 9 2), 1 8 6 (d a t e d F e b r u a r y 1 9 , 1 9 9 3), 1 9 0 (d a t e d J u n e 2 9 , 1 9 9 3), 1 9 1 (d a t e d J u l y 7 , 1 9 9 3), 2 0 6 (d a t e d F e b r u a r y 2 8 , 1 9 9 4) a n d 2 1 4 (d a t e d J u n e 2 7 , 1 9 9 4); a n d N R C E x e m p t i o n s a n d a s s o c i a t e d s a f e t y e v a l u a t i o n s d a t e d A p r i l 2 6 , 1 9 8 3 , J u l y 1 , 1 9 8 3 , J a n u a r y 1 1 , 1 9 8 5 , A p r i l 3 0 , 1 9 8 6 , S e p t e m b e r 1 5 , 1 9 8 6 a n d S e p t e m b e r 1 0 , 1 9 9 2 a s s u p p l e m e n t e d , s u b j e c t t o t h e f o l l o w i n g p r o v i s i o n:
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| JAFP-11-0003
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| Proposed Facility Operating License Change (Final Typed) | | JAFP-11-0003 Attachment 2 Proposed Facility Operating License Change (Marked up) |
| | Facility Operating License Page 3 |
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| Facility Operating License Page 3
| | (4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.. |
| | (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| | C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| | (1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal). |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 299 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. |
| | (3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), |
| | 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 as supplemented, subject to the following provision: |
| | Amendment 299 |
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| A m e n d m e n t
| | JAFP-11-0003 Attachment 3 Proposed Facility Operating License Change (Final Typed) |
| | Facility Operating License Page 3 |
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| (4) E N O p u r s u a n t t o t h e A c t a n d 1 0 C F R P a r t s 3 0 , 4 0 , a n d 7 0 t o r e c e i v e , p o s s e s s , a n d u s e , a t a n y t i m e , a n y b y p r o d u c t , s o u r c e a n d s p e c i a l n u c l e a r m a t e r i a l w i t h o u t r e s t r i c t i o n t o c h e m i c a l o r p h y s i c a l f o r m , f o r s a m p l e a n a l y s i s o r i n s t r u m e n t c a l i b r a t i o n; o r a s s o c i a t e d w i t h r a d i o a c t i v e a p p a r a t u s , c o m p o n e n t s o r t o o l s.. | | (4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.. |
| (5) P u r s u a n t t o t h e A c t a n d 1 0 C F R P a r t s 3 0 a n d 7 0 , t o p o s s e s s , b u t n o t s e p a r a t e , s u c h b y p r o d u c t a n d s p e c i a l n u c l e a r m a t e r i a l s a s m a y b e p r o d u c e d b y t h e o p e r a t i o n o f t h e f a c i l i t y. | | (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| C. T h i s r e n e w e d o p e r a t i n g l i c e n s e s h a l l b e d e e m e d t o c o n t a i n a n d i s s u b j e c t t o t h e c o n d i t i o n s s p e c i f i e d i n t h e f o l l o w i n g C o m m i s s i o n r e g u l a t i o n s i n 1 0 C F R C h a p t e r I: P a r t 2 0 , S e c t i o n 3 0.3 4 o f P a r t 3 0 , S e c t i o n 4 0.4 1 o f P a r t 4 0 , S e c t i o n s 5 0.5 4 a n d 5 0.5 9 o f P a r t 5 0 , a n d S e c t i o n 7 0.3 2 o f P a r t 7 0; a n d i s s u b j e c t t o a l l a p p l i c a b l e p r o v i s i o n s o f t h e A c t a n d t o t h e r u l e s , r e g u l a t i o n s , a n d o r d e r s o f t h e C o m m i s s i o n n o w o r h e r e a f t e r i n e f f e c t; a n d i s s u b j e c t t o t h e a d d i t i o n a l c o n d i t i o n s s p e c i f i e d o r i n c o r p o r a t e d b e l o w: | | C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| (1) M a x i m u m P o w e r L e v e l E N O i s a u t h o r i z e d t o o p e r a t e t h e f a c i l i t y a t s t e a d y s t a t e r e a c t o r c o r e p o w e r l e v e l s n o t i n e x c e s s o f 2 5 3 6 m e g a w a t t s (t h e r m a l). | | (1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal). |
| (2) T e c h n i c a l S p e c i f i c a t i o n s T h e T e c h n i c a l S p e c i f i c a t i o n s c o n t a i n e d i n A p p e n d i x A , a s r e v i s e d t h r o u g h A m e n d m e n t N o. , a r e h e r e b y i n c o r p o r a t e d i n t h e r e n e w e d o p e r a t i n g l i c e n s e. T h e l i c e n s e e s h a l l o p e r a t e t h e f a c i l i t y i n a c c o r d a n c e w i t h t h e T e c h n i c a l S p e c i f i c a t i o n s. (3) F i r e P r o t e c t i o n E N O s h a l l i m p l e m e n t a n d m a i n t a i n i n e f f e c t a l l p r o v i s i o n s o f t h e a p p r o v e d f i r e p r o t e c t i o n s p r o g r a m a s d e s c r i b e d i n t h e F i n a l S a f e t y A n a l y s i s R e p o r t f o r t h e f a c i l i t y a n d a s a p p r o v e d i n t h e S E R d a t e d N o v e m b e r 2 0 , 1 9 7 2 a s s u p p l e m e n t e d , s u b j e c t t o t h e f o l l o w i n g p r o v i s i o n:}} | | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. |
| | (3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972 as supplemented, subject to the following provision: |
| | Amendment}} |
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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
[Table view] Category:License-Application for (Amend/Renewal/New) for DKT 30
MONTHYEARRS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications JAFP-11-0003, Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection2011-01-13013 January 2011 Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)2005-05-31031 May 2005 Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-01-0246, Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004)2002-01-0909 January 2002 Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004) 2021-06-30
[Table view] Category:40
MONTHYEARRS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21054A1322021-04-14014 April 2021 U.S. NRC Analysis of Entergy Nuclear Operations, Inc'S Initial and Updated Decommissioning Funding Plans for the Big Rock Point, Indian Point, Pilgrim, Palisades, Fitzpatrick, and Vermont Yankee Independent Spent Fuel Storage Installations RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-19-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-04-0101 April 2019 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-18-145, Report on the Status of Decommissioning Funding for James Fitzpatrick Nuclear Power Plant Independent Spent Fuel Storage Installation2018-12-10010 December 2018 Report on the Status of Decommissioning Funding for James Fitzpatrick Nuclear Power Plant Independent Spent Fuel Storage Installation CNRO-2016-00010, Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2016-03-30030 March 2016 Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) ENOC-15-00005, Decommissioning Funding Status Report Entergy Nuclear Operations, Inc2015-03-30030 March 2015 Decommissioning Funding Status Report Entergy Nuclear Operations, Inc ENOC-13-00007, Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc ENOC-12-00039, ISFSI Decommissioning Funding Plans (10 CFR 72.30)2012-12-13013 December 2012 ISFSI Decommissioning Funding Plans (10 CFR 72.30) CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications JAFP-11-0003, Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection2011-01-13013 January 2011 Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection ENOC-10-00010, Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 20092010-03-31031 March 2010 Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 2009 ENOC-09-00007, Status Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2008 - 10 CFR 50.75(f)(1)2009-03-30030 March 2009 Status Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2008 - 10 CFR 50.75(f)(1) ENOC-08-00028, J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report2008-05-0808 May 2008 J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report ENOC-07-00007, Status of Decommissioning Funding for Year Ending December 31. 2006 - 10 CFR 50.75(f)(1)2007-03-29029 March 2007 Status of Decommissioning Funding for Year Ending December 31. 2006 - 10 CFR 50.75(f)(1) JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)2005-05-31031 May 2005 Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-01-0246, Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004)2002-01-0909 January 2002 Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004) 2023-03-23
[Table view] Category:70
MONTHYEARRS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21054A1322021-04-14014 April 2021 U.S. NRC Analysis of Entergy Nuclear Operations, Inc'S Initial and Updated Decommissioning Funding Plans for the Big Rock Point, Indian Point, Pilgrim, Palisades, Fitzpatrick, and Vermont Yankee Independent Spent Fuel Storage Installations RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-19-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-04-0101 April 2019 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-18-145, Report on the Status of Decommissioning Funding for James Fitzpatrick Nuclear Power Plant Independent Spent Fuel Storage Installation2018-12-10010 December 2018 Report on the Status of Decommissioning Funding for James Fitzpatrick Nuclear Power Plant Independent Spent Fuel Storage Installation CNRO-2016-00010, Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2016-03-30030 March 2016 Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) ENOC-15-00005, Decommissioning Funding Status Report Entergy Nuclear Operations, Inc2015-03-30030 March 2015 Decommissioning Funding Status Report Entergy Nuclear Operations, Inc ENOC-13-00007, Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc ENOC-12-00039, ISFSI Decommissioning Funding Plans (10 CFR 72.30)2012-12-13013 December 2012 ISFSI Decommissioning Funding Plans (10 CFR 72.30) CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications JAFP-11-0003, Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection2011-01-13013 January 2011 Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection ENOC-10-00010, Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 20092010-03-31031 March 2010 Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 2009 ENOC-09-00007, Status Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2008 - 10 CFR 50.75(f)(1)2009-03-30030 March 2009 Status Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2008 - 10 CFR 50.75(f)(1) ENOC-08-00028, J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report2008-05-0808 May 2008 J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report ENOC-07-00007, Status of Decommissioning Funding for Year Ending December 31. 2006 - 10 CFR 50.75(f)(1)2007-03-29029 March 2007 Status of Decommissioning Funding for Year Ending December 31. 2006 - 10 CFR 50.75(f)(1) JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)2005-05-31031 May 2005 Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-01-0246, Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004)2002-01-0909 January 2002 Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage (JPTS-01-004) 2023-03-23
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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Kevin Bronson Site Vice President - JAF JAFP-11-0003 January 13, 2011 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) hereby requests an amendment to the Facility Operating License (FOL) for the James A. FitzPatrick Nuclear Power Plant (JAF).
This license amendment submittal requests the deletion of specific references to Safety Evaluation Reports (SER), Technical Specification Amendments, and Exemptions in condition 2.C(3), Fire Protection, of the FOL. The deleted text will be replaced with the words as supplemented.
The proposed FOL change is non-technical in nature and thus does not involve a significant increase in the probability or consequences of an accident previously evaluated. This change has no effect on any previously submitted amendments currently under review by the NRC. provides a description and evaluation of the proposed FOL changes. provides the proposed FOL changes as marked up pages. provides the proposed FOL changes in final typed format with change bars.
Entergy requests NRC approval of the proposed FOL amendment by January 13, 2012, with the amendment being implemented within 60 days from approval.
In accordance with 10 CFR 50.91, a copy of this application, with the associated attachments, is being provided to the designated New York State official.
JAFP-11-0003 Page 2 of 2 There is no new commitment made in this letter.
Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing Manager, at (315) 349-6766.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 13, 2011.
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Kevin Bronson KB/JP/jo Attachments: 1. Application for Amendment to Modify the Facility Operating License Condition 2.C(3), Fire Protection, Description and Evaluation
- 2. Proposed Facility Operating License Change (Marked up)
- 3. Proposed Facility Operating License Change (Final Typed) cc:
Regional Administrator, Region I Mr. Paul Eddy U. S. Nuclear Regulatory Commission New York State Department of Public 475 Allendale Road Service King of Prussia, PA 19406-1415 3 Empire State Plaza, 10th Floor Albany, NY 12223 Resident Inspector's Office U.S. Nuclear Regulatory Commission Mr. Francis Murray, President James A. FitzPatrick Nuclear Power Plant NYSERDA Lycoming, NY 13093 17 Columbia Circle Albany, NY 12203-6399 Mr. Bhalchandra Vaidya, Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Document Components:
001 Transmittal Letter, JAFP-11-0003; with attachments
JAFP-11-0003 Attachment 1 Application for Amendment to Modify the Facility Operating License Section 2.C(3), Fire Protection Description and Evaluation Page 1 of 4
JAFP-11-0003 Attachment 1
1.0 DESCRIPTION
The proposed amendment would modify the Facility Operating License (FOL) by deleting references to specific Safety Evaluation Reports (SER), Technical Specification (TS) Amendments, and Exemptions from license condition 2.C(3), Fire Protection, and replacing them with the words as supplemented. This is an administrative amendment to the FOL.
2.0 PROPOSED CHANGE
S Currently, FOL condition 2.C(3) states in part:
the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),
80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989),
142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 The proposed change is to delete the preceding text and replace it with the words as supplemented. This change would facilitate record keeping by allowing the SERs, TS Amendments, and Exemptions to be tracked in the Fire Protection Program.
3.0 BACKGROUND
In addition to the requirements of 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, the FOL contains additional conditions to which the James A. FitzPatrick Nuclear Power Plant (JAF) is subject to. Specifically, condition 2.C(3) requires JAF to maintain a Fire Protection Program as described in the Updated Final Safety Analysis (UFSAR) report and applicable supplements, amendments, and exemptions.
During the course of a fire protection triennial inspection, it was noted by the NRC that not all fire protection SERs were included in the fire protection condition of the JAF license. Further review and discussion by Entergy and the NRC concluded that there is no regulatory requirement to explicitly reference specific SERs in a plants license condition and that it would be appropriate to remove the specific SER references to be consistent with other plants.
In its current form, the FOL lists the original SER as well as supplemental SERs, NRC letters, Exemptions, and TS Amendments from 1972 through 1994. Fire protection SERs, NRC letters, Exemptions, and TS Amendments approved after 1994 have not been incorporated into the FOL conditions. They are tracked separately within the Fire Protection Program.
Page 2 of 4
JAFP-11-0003 Attachment 1
4.0 TECHNICAL ANALYSIS
There is no technical change being requested. The proposed change is administrative in order to facilitate record keeping of approved 10 CFR 50 Appendix R exemptions.
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration
- 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed FOL change is administrative and does not involve a plant or design function change. It has no effect on reactor operation or accident analyses, and thus, the proposed FOL change does not increase the probability or consequence of an accident previously evaluated.
- 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed FOL change is administrative and does not involve a plant or design function change. Because the proposed amendment would not change the design, configuration, or method of operation of the plant, it would not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed FOL change is administrative and does not involve a plant or design function change. No design or safety margin is involved. Therefore, the proposed change does not involve a reduction in any margin of safety.
5.2 Applicable Regulatory Requirements / Criteria 10 CFR 50.90 provides the criteria for license amendments. Whenever a holder of a license, including a construction permit and operating license under this part, and an early site permit, combined license, and manufacturing license under part 52 of this chapter, desires to amend the license or permit, application for an amendment must be filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.
Page 3 of 4
JAFP-11-0003 Attachment 1 5.3 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commissions regulations; and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ENVIRONMENTAL ASSESSMENT A review has determined that the proposed changes would not change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and does not change any inspection or surveillance requirement. Therefore, the proposed change does not involve: (i) a significant hazards consideration; (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed changes.
7.0 REFERENCE 1 USNRC, Code of Federal Regulations, Section 10 CFR 50.90 Application for amendment of license, construction permit, or early permit Page 4 of 4
JAFP-11-0003 Attachment 2 Proposed Facility Operating License Change (Marked up)
Facility Operating License Page 3
(4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools..
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 299 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993),
190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 as supplemented, subject to the following provision:
Amendment 299
JAFP-11-0003 Attachment 3 Proposed Facility Operating License Change (Final Typed)
Facility Operating License Page 3
(4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools..
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972 as supplemented, subject to the following provision:
Amendment