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{{#Wiki_filter: | {{#Wiki_filter:Exelon Nuclear www.exeloncorp.com Exelon. | ||
200 Exelon Way Nucea-Kennett Square, PA 19348 10CFR50.71 (e)(4) | |||
August 14, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Peach Bottom Atomic Power Station, Unit 1 Facility Operating License No. DPR-12 NRC Docket No. 50-171 | |||
==Subject:== | ==Subject:== | ||
Peach Bottom Atomic Power Station, Unit 1 Updated Final Safety Analysis Report, Revision 5 In accordance with | Peach Bottom Atomic Power Station, Unit 1 Updated Final Safety Analysis Report, Revision 5 In accordance with 10CFR50.71 (e)(4) and 10CFR50.4(b)(6), this letter submits Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1. | ||
As required by 1 OCFR50.71 (e)(5), each replacement page contains a bold vertical line in the margin adjacent to each area changed along with the date of the change. Two (2)Engineering Change Requests (ECRs) were incorporated in Revision 5 of the PBAPS, Unit 1, UFSAR (ECRs 09-00023 and 08-00414). | The attached copy is being provided to the NRC with page revision listings that identify the latest revision date of all current pages in accordance with 10CFR50.71 (e)(1). Page replacement instructions for incorporating Revision 5 into the UFSAR are also included in the Attachment. As required by 1 OCFR50.71 (e)(5), each replacement page contains a bold vertical line in the margin adjacent to each area changed along with the date of the change. Two (2) | ||
As required by | Engineering Change Requests (ECRs) were incorporated in Revision 5 of the PBAPS, Unit 1, UFSAR (ECRs 09-00023 and 08-00414). | ||
Updated Final Safety Analysis Report, Revision 5 August 14, 2009 Page 2 | As required by 10CFR50.71 (e)(2)(i), I certify that to the best of my knowledge, Revision 5 to the PBAPS Unit 1 UFSAR accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. In addition, as required by 10CFR50.71 (e)(2)(ii), no changes under the provisions of 1 OCFR50.59, but not previously submitted to the NRC, have been made. | ||
If you have any questions or require further information, please contact Tom Loomis at (610) 765-5510. | |||
Very truly yours, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC /i---- | |||
Updated Final Safety Analysis Report, Revision 5 August 14, 2009 Page 2 | |||
==Attachment:== | ==Attachment:== | ||
Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland L. Kauffman, USNRC, Region I | |||
PBAPS PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REPLACEMENT INSTRUCTIONS Revision 5, August 14, 2009 Remove Page Insert Page | |||
[Revisions indicated by revision bar at right margin] | |||
Page Revision Listing (page 1 & 2) Page Revision Listing (pages 1 & 2) | |||
Page 14 Page 14 Page 68 Page 68 | |||
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT Page Revision Listing TITLE REVISION DATE Updated Final Safety Analysis Report Title Page 4 8/27/03 Note Page 3/27/98 Table of Contents 3/27/98 Pages 1 - 13 3/27/98 Page 14 5 8/14/09 Pages 15 - 35 3/27/98 Pages 36 - 39 2 11/15/99 Page 40 3/27/98 Pages 41 - 44 2 11/15/99 Page 45 3/27/98 Page 46 3 8/27/01 Page 47 2 11/15/99 Page 48 3 8/27/01 Pages 49 - 50 2 11/15/99 Page 51 3 8/27/01 Pages 52 - 53 3/27/98 Pages 54 - 56 2 11/15/99 Pages 57 - 58 3/27/98 Pages 59 - 61 2 11/15/99 Pages 62 - 63 3/27/98 Pages 64 - 66 2 11/15/99 Page 67 3 8/27/01 Page 68 5 8/14/09 Pages 69-79 3/27/98 Appendix 1 Licensing Documents 4 8/27/03 License Reference Letters November 24, 1975 Letter to NRC 3/27/98 March 4,1987 Letter to NRC 3/27/98 December 16, 1988 Letter to NRC 3/27/98 July 12, 1989 Letter to NRC 3/27/98 August 23, 1989 Letter to NRC 3/27/98 License/Technical Specifications Amendment No. 11 to License No. DPR-12 4 8/27/03 Technical Specifications (4 pages) | |||
Page 1 3 8/27/01 Page 2 4 8/27/03 Page 3 4 8/27/03 Page 4 4 8/27/03 AUG 14 2009 I Revision 5 I | |||
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REVISION LISTING (Continued) | |||
NRC SERs Safety Evaluation Supporting Amendment No. 7 3/27/98 Safety Evaluation Supporting Amendment No. 8 3/27/98 Safety Evaluation Supporting Amendment No. 9 1 10/27/98 Safety Evaluation Supporting Amendment No. 10 3 8/27/01 Safety Evaluation Supporting Amendment No. 11 4 8/27/03 AUG 14 2009 Revision 5 i | |||
water is required to prevent overheating of the delay beds. Therefore, the emergency cooling system for the water cooled delay beds will be removed from service soon after reactor shutdown to permit decommissioning work on this system early in the schedule. | |||
3.4.7 All piping connections which penetrate the contain-ment will be severed, capped and welded outside the containment, except for the containment vacuum breaker assembly and associated penetration. | |||
Electrical penetrations will be left as is. The ventilation supply and exhaust ducts will be severed and welded shut outside the containment. | Electrical penetrations will be left as is. The ventilation supply and exhaust ducts will be severed and welded shut outside the containment. | ||
A six inch pressure equalization line equipped with a replaceable absolute filter will be installed on the containment to prevent a pressure differential from developing between the inside and outside of the containment. | A six inch pressure equalization line equipped with a replaceable absolute filter will be installed on the containment to prevent a pressure differential from developing between the inside and outside of the containment. In addition, the containment vacuum breaker assembly was left as-is per NCR 95-00043. | ||
In addition, the containment vacuum breaker assembly was left as-is per NCR 95-00043.3.4.8 The outer door of the emergency air lock and the equipment door on Elevation 116' will be welded closed. The inner doors of the personnel air lock on Elevation 116' and the access lock on Elevation 176'-6" will be welded in the open position. | 3.4.8 The outer door of the emergency air lock and the equipment door on Elevation 116' will be welded closed. The inner doors of the personnel air lock on Elevation 116' and the access lock on Elevation 176'-6" will be welded in the open position. The interlock mechanisms in these two latter locks will be disabled and the outer door on each lock will be secured with a heavy duty padlock. | ||
The interlock mechanisms in these two latter locks will be disabled and the outer door on each lock will be secured with a heavy duty padlock.3.4.9 Flammable materials other than electrical cables and solid graphite left in the sealed reactor vessel will be removed from the containment. | 3.4.9 Flammable materials other than electrical cables and solid graphite left in the sealed reactor vessel will be removed from the containment. | ||
AUG 14 2009 Revision 5 Other possible radiological hazards could occur in the event of a fire, flooding, or severe local storm damage. Since all readily flammable material has been removed as appropriate from the SAFSTOR facility, the chance of fire has been reduced considerably. | AUG 14 2009 Revision 5 Other possible radiological hazards could occur in the event of a fire, flooding, or severe local storm damage. Since all readily flammable material has been removed as appropriate from the SAFSTOR facility, the chance of fire has been reduced considerably. | ||
Flooding has been discussed in Section 4.2.Since this SAFSTOR facility is in the immediate vicinity of Units 2-3, which are operating, any local condition which may require emergency action will be apparent to the Unit 2-3 operating staff so that they can take appropriate, timely action.4.4.7 Processing of Unit 1 Liquid Radwaste Any liquid waste created or found at Unit 1 will be designated as Unit 1 waste and appropriately reported to the NRC in accordance with Technical Specifications. | Flooding has been discussed in Section 4.2. | ||
This waste will be transferred to the PBAPS radwaste facility located between Units 2 and 3 for processing. | Since this SAFSTOR facility is in the immediate vicinity of Units 2-3, which are operating, any local condition which may require emergency action will be apparent to the Unit 2-3 operating staff so that they can take appropriate, timely action. | ||
This waste will be clearly designated as belonging to the Unit 1 facility. | 4.4.7 Processing of Unit 1 Liquid Radwaste Any liquid waste created or found at Unit 1 will be designated as Unit 1 waste and appropriately reported to the NRC in accordance with Technical Specifications. This waste will be transferred to the PBAPS radwaste facility located between Units 2 and 3 for processing. This waste will be clearly designated as belonging to the Unit 1 facility. This process will be controlled by written procedures. | ||
This process will be controlled by written procedures. | AUG 14 2009 Revision 5 | ||
AUG 14 2009 Revision 5 | }} | ||
Latest revision as of 09:39, 12 March 2020
| ML092330043 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/14/2009 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML092330043 (7) | |
Text
Exelon Nuclear www.exeloncorp.com Exelon.
200 Exelon Way Nucea-Kennett Square, PA 19348 10CFR50.71 (e)(4)
August 14, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Peach Bottom Atomic Power Station, Unit 1 Facility Operating License No. DPR-12 NRC Docket No. 50-171
Subject:
Peach Bottom Atomic Power Station, Unit 1 Updated Final Safety Analysis Report, Revision 5 In accordance with 10CFR50.71 (e)(4) and 10CFR50.4(b)(6), this letter submits Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1.
The attached copy is being provided to the NRC with page revision listings that identify the latest revision date of all current pages in accordance with 10CFR50.71 (e)(1). Page replacement instructions for incorporating Revision 5 into the UFSAR are also included in the Attachment. As required by 1 OCFR50.71 (e)(5), each replacement page contains a bold vertical line in the margin adjacent to each area changed along with the date of the change. Two (2)
Engineering Change Requests (ECRs) were incorporated in Revision 5 of the PBAPS, Unit 1, UFSAR (ECRs 09-00023 and 08-00414).
As required by 10CFR50.71 (e)(2)(i), I certify that to the best of my knowledge, Revision 5 to the PBAPS Unit 1 UFSAR accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. In addition, as required by 10CFR50.71 (e)(2)(ii), no changes under the provisions of 1 OCFR50.59, but not previously submitted to the NRC, have been made.
If you have any questions or require further information, please contact Tom Loomis at (610) 765-5510.
Very truly yours, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC /i----
Updated Final Safety Analysis Report, Revision 5 August 14, 2009 Page 2
Attachment:
Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland L. Kauffman, USNRC, Region I
PBAPS PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REPLACEMENT INSTRUCTIONS Revision 5, August 14, 2009 Remove Page Insert Page
[Revisions indicated by revision bar at right margin]
Page Revision Listing (page 1 & 2) Page Revision Listing (pages 1 & 2)
Page 14 Page 14 Page 68 Page 68
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT Page Revision Listing TITLE REVISION DATE Updated Final Safety Analysis Report Title Page 4 8/27/03 Note Page 3/27/98 Table of Contents 3/27/98 Pages 1 - 13 3/27/98 Page 14 5 8/14/09 Pages 15 - 35 3/27/98 Pages 36 - 39 2 11/15/99 Page 40 3/27/98 Pages 41 - 44 2 11/15/99 Page 45 3/27/98 Page 46 3 8/27/01 Page 47 2 11/15/99 Page 48 3 8/27/01 Pages 49 - 50 2 11/15/99 Page 51 3 8/27/01 Pages 52 - 53 3/27/98 Pages 54 - 56 2 11/15/99 Pages 57 - 58 3/27/98 Pages 59 - 61 2 11/15/99 Pages 62 - 63 3/27/98 Pages 64 - 66 2 11/15/99 Page 67 3 8/27/01 Page 68 5 8/14/09 Pages 69-79 3/27/98 Appendix 1 Licensing Documents 4 8/27/03 License Reference Letters November 24, 1975 Letter to NRC 3/27/98 March 4,1987 Letter to NRC 3/27/98 December 16, 1988 Letter to NRC 3/27/98 July 12, 1989 Letter to NRC 3/27/98 August 23, 1989 Letter to NRC 3/27/98 License/Technical Specifications Amendment No. 11 to License No. DPR-12 4 8/27/03 Technical Specifications (4 pages)
Page 1 3 8/27/01 Page 2 4 8/27/03 Page 3 4 8/27/03 Page 4 4 8/27/03 AUG 14 2009 I Revision 5 I
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REVISION LISTING (Continued)
NRC SERs Safety Evaluation Supporting Amendment No. 7 3/27/98 Safety Evaluation Supporting Amendment No. 8 3/27/98 Safety Evaluation Supporting Amendment No. 9 1 10/27/98 Safety Evaluation Supporting Amendment No. 10 3 8/27/01 Safety Evaluation Supporting Amendment No. 11 4 8/27/03 AUG 14 2009 Revision 5 i
water is required to prevent overheating of the delay beds. Therefore, the emergency cooling system for the water cooled delay beds will be removed from service soon after reactor shutdown to permit decommissioning work on this system early in the schedule.
3.4.7 All piping connections which penetrate the contain-ment will be severed, capped and welded outside the containment, except for the containment vacuum breaker assembly and associated penetration.
Electrical penetrations will be left as is. The ventilation supply and exhaust ducts will be severed and welded shut outside the containment.
A six inch pressure equalization line equipped with a replaceable absolute filter will be installed on the containment to prevent a pressure differential from developing between the inside and outside of the containment. In addition, the containment vacuum breaker assembly was left as-is per NCR 95-00043.
3.4.8 The outer door of the emergency air lock and the equipment door on Elevation 116' will be welded closed. The inner doors of the personnel air lock on Elevation 116' and the access lock on Elevation 176'-6" will be welded in the open position. The interlock mechanisms in these two latter locks will be disabled and the outer door on each lock will be secured with a heavy duty padlock.
3.4.9 Flammable materials other than electrical cables and solid graphite left in the sealed reactor vessel will be removed from the containment.
AUG 14 2009 Revision 5 Other possible radiological hazards could occur in the event of a fire, flooding, or severe local storm damage. Since all readily flammable material has been removed as appropriate from the SAFSTOR facility, the chance of fire has been reduced considerably.
Flooding has been discussed in Section 4.2.
Since this SAFSTOR facility is in the immediate vicinity of Units 2-3, which are operating, any local condition which may require emergency action will be apparent to the Unit 2-3 operating staff so that they can take appropriate, timely action.
4.4.7 Processing of Unit 1 Liquid Radwaste Any liquid waste created or found at Unit 1 will be designated as Unit 1 waste and appropriately reported to the NRC in accordance with Technical Specifications. This waste will be transferred to the PBAPS radwaste facility located between Units 2 and 3 for processing. This waste will be clearly designated as belonging to the Unit 1 facility. This process will be controlled by written procedures.
AUG 14 2009 Revision 5