L-14-153, Submittal of the Updated Final Safety Analysis Report, Revision 28
| ML14153A139 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/19/2014 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14153A137 | List: |
| References | |
| L-14-153 | |
| Download: ML14153A139 (5) | |
Text
Beaver Valley Power Station P.O. Box 4
"-%Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 May 19, 2014 L-14-153 10 CFR 50.71(e) 10 CFR 50.54(a) 10 CFR 54.37(b)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Submittal of the Updated Final Safety Analysis Report, Revision 28 In accordance with the requirements of 10 CFR 50.71(e), the FirstEnergy Nuclear Operating Company (FENOC) is hereby submitting to the Nuclear Regulatory Commission (NRC) the Beaver Valley Power Station (BVPS), Unit No. 1, Updated Final Safety Analysis Report (UFSAR) Revision 28 in CD-ROM format. This submittal reflects facility and procedure changes implemented between May 13, 2012 (the end of Refueling Outage 21), and November 4, 2013 (the end of Refueling Outage 22), along with several changes implemented after Refueling Outage 22.
As required by NRC guidance for electronic submissions, Attachment 1 provides a listing of the document components that comprise the enclosed CD-ROM. In addition to the UFSAR, the CD-ROM includes the BVPS, Unit No. 1 Licensing Requirements Manual, Revision 84, and the Technical Specification Bases, Revision 24. The Technical Specification Bases are submitted in accordance with Technical Specification 5.5.10.d, "Technical Specifications (TS) Bases Control Program."
In accordance with 10 CFR 50.54(a), FENOC is hereby submitting a copy of the current revision of the FENOC Quality Assurance Program Manual (QAPM). The QAPM, Revision 19, is included in the enclosed CD-ROM. includes a summary of information removed from the BVPS, Unit No. 1 UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1.
Beaver Valley Power Station, Unit No. 1 L-14-153 Page 2 FENOC conducted a review of BVPS, Unit No. 1 plant changes for 10 CFR 54.37(b) applicability. No components were determined to meet the criteria for newly identified components as clarified by Regulatory Information Summary (RIS) 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.34(b) for Holders of Renewed Licenses."
In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes,"
as endorsed by NRC Regulatory Issue Summary (RIS) 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," a summary of regulatory commitment changes is provided in Attachment 3.
This certifies, to the best of our judgment and belief, that Revision 28 of the BVPS, Unit No. 1 UFSAR accurately presents changes made since the previous submittal that are necessary to reflect information and analysis submitted to the Commission or pursuant to Commission requirements.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at 330-315-6810.
Sincerely, Eric A. Larson Attachments:
- 1.
Document Components on CD-ROM
- 2.
Information Removed from the BVPS, Unit No. 1 UFSAR
- 3.
Commitment Change Summary Report
Enclosures:
Beaver Valley Power Station, Unit No. 1 UFSAR, Licensing Requirements Manual, Technical Specification Bases, and QAPM (on CD-ROM) cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP (without Enclosures)
Site BRP/DEP Representative (without Enclosures)
L-14-153 Document Components on CD-ROM Page 1 of 1 File Name Size 001 UFSAR List of Effective Pages Rev 28.pdf 73K 002 UFSAR Section 1.pdf 1,119K 003 UFSAR Section 2.pdf 42,901K 004 UFSAR Section 3.pdf 3,784K 005 UFSAR Section 4.pdf 1,222K 006 UFSAR Section 5.pdf 3,839K 007 UFSAR Section 6.pdf 7,087K 008 UFSAR Section 7.pdf 2,516K 009 UFSAR Section 8.pdf 1,393K 010 UFSAR Section 9.pdf 1,730K 011 UFSAR Section 10.pdf 981K 012 UFSAR Section 11.pdf 1,023K 013 UFSAR Section 12.pdf 91K 014 UFSAR Section 13.pdf 414K 015 UFSAR Section 14.pdf 6,662K 016 UFSAR Section 15.pdf 131K 017 UFSAR Section 16.pdf 257K 018 UFSAR Appendix A.pdf 543K 019 UFSAR Appendix B.pdf 1,643K 020 BVPS-1 LRM Rev 84.pdf 1,125K 021 BVPS TS Bases Rev 24.pdf 2,113K 022 FENOC QAPM Rev 19.pdf 2,849K
a L-14-153 Information Removed from BVPS, Unit No. 1 UFSAR Page 1 of 1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees periodically report a brief description of information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides a summary of the information removed from the UFSAR and the basis for removal.
- 1. Removed descriptive information in Section 4.2.3 regarding an administrative pressure limit for the Overpressure Protection System (OPPS). The statement that the nitrogen accumulators are typically charged to a pressure of approximately 675 pounds per square inch gauge (psig) was removed. The 675 psig is an administrative limit controlled by procedure and is not important to providing an understanding of the plant design and operation from either a general or system functional perspective. The removal of this administrative limit does not impact the design basis or safety analysis of the plant.
- 2. Removed excessive detail from UFSAR figures to simplify the figures. The level of detail is not required by Regulatory Guide 1.70, is not important to providing an understanding of the plant design and operation from either a general or system functional perspective, and does not impact the design basis or safety analysis of the plant.
L-14-153 Commitment Change Summary Report May 2012 - November 2013 Page 1 of 1 COMMITMENT NUMBER I SOURCE I DATE COMMITMENT DESCRIPTION CHANGE REASON FOR CHANGE ND1lNSM:1780-01 Letter N D1 NSM: 1780 09/11/1985 In response to NRC Bulletin 84-03, Refueling Cavity Water Seal, additional actions taken included: prohibiting the use of the RCCA change fixture until a cofferdam is installed to ensure complete fuel assembly submergence; and maintaining a LHSI pump available for injection to provide additional makeup capability.
Commitment closed.
Prohibiting the use of the RCCA change fixture is no longer required because the cofferdam has been installed.
BVPS no longer uses a pneumatic cavity water seal. The LHSI pump availability during refueling activities is no longer needed as a defense in depth based on the proven reliability of the seal configuration and the unlikely occurrence of significant seal leakage because of the narrow gap between the access covers and the seal itself.
List of Abbreviations Used BVPS LHSI NRC RCCA Beaver Valley Power Station Low Head Safety Injection Nuclear Regulatory Commission Rod Cluster Control Assembly