ML17125A093: Difference between revisions
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| number = ML17125A093 | | number = ML17125A093 | ||
| issue date = 04/20/2017 | | issue date = 04/20/2017 | ||
| title = | | title = Submittal of Revision to Radiological Emergency Response Plan Implementing Procedures | ||
| author name = McPherson M | | author name = McPherson M | ||
| author affiliation = Duke Energy Progress, LLC | | author affiliation = Duke Energy Progress, LLC | ||
| Line 20: | Line 20: | ||
==Subject:== | ==Subject:== | ||
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Brunswick Nuclear Plant P .0. Box 10429 Southport, NC 28461 10 CFR 50.4(b )( 5)(iii) 10 CFR 50.54( q)(5) 10 CFR 72.4 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Revision to Radiological Emergency Response Plan Implementing Procedures Ladies and Gentlemen: In accordance with 10 CFR 50.4(b)(5)(iii); 10 CFR 50.54(q)(5); and 10 CFR 72.4; Duke Energy Progress, LLC (Duke Energy), is submitting a revision to Radiological Emergency Response Plan Implementing Procedures OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC); OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases; OPEP-03.6.1, Revision 17, Re/ease Estimates Based Upon Stack/Vent Readings; and OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions-Core Damage Assessment Program (CDAM). Duke Energy has evaluated these revisions, in accordance with 10 CFR 50.54(q), and determined that the revisions are not a reduction in the effectiveness of the Radiological Emergency Response Plan and that the Plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. Enclosure 1 provides a 10 CFR 50.54(q)(5) summary for these.revised Radiological Emergency Response Plan implementing procedures. Enclosures 2 through 5 contain a copy_ of the revised Radiological Emergency Response Plan implementing procedures. This document contains no regulatory commitments. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 457-2487. Sincerely, Mark McPherson Director -Organizational Effectiveness (Acting) Brunswick Steam Electric Plant U.S. Nuclear Regulatory Commission Page 2 of 2 WRM/wrm | Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Brunswick Nuclear Plant P .0. Box 10429 Southport, NC 28461 10 CFR 50.4(b )( 5)(iii) 10 CFR 50.54( q)(5) 10 CFR 72.4 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Revision to Radiological Emergency Response Plan Implementing Procedures Ladies and Gentlemen: | ||
In accordance with 10 CFR 50.4(b)(5)(iii); | |||
10 CFR 50.54(q)(5); | |||
and 10 CFR 72.4; Duke Energy Progress, LLC (Duke Energy), is submitting a revision to Radiological Emergency Response Plan Implementing Procedures OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC); OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases; OPEP-03.6.1, Revision 17, Re/ease Estimates Based Upon Stack/Vent Readings; and OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions-Core Damage Assessment Program (CDAM). Duke Energy has evaluated these revisions, in accordance with 10 CFR 50.54(q), and determined that the revisions are not a reduction in the effectiveness of the Radiological Emergency Response Plan and that the Plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. Enclosure 1 provides a 10 CFR 50.54(q)(5) summary for these.revised Radiological Emergency Response Plan implementing procedures. | |||
Enclosures 2 through 5 contain a copy_ of the revised Radiological Emergency Response Plan implementing procedures. | |||
This document contains no regulatory commitments. | |||
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 457-2487. | |||
Sincerely, Mark McPherson Director -Organizational Effectiveness (Acting) Brunswick Steam Electric Plant U.S. Nuclear Regulatory Commission Page 2 of 2 WRM/wrm | |||
==Enclosures:== | ==Enclosures:== | ||
1. 10 CFR 50.54(q)(5) Summaries for OPEP-02.6.26, Revision 38; OPEP-03.4.8, Revision 4; OPEP-03.6.1, Revision 17; and OPEP-03.6.3, Revision 21 2. Copy of OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC) 3. Copy of OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases 4. Copy of OPEP-03.6.1, Revision 17, Release Estimates Based Upon Stack/Vent Readings 5. Copy of OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions -Core Damage Assessment Program (CDAM) cc (with all Enclosures): U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 cc (with Enclosure 1 only): U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 cc (without Enclosures): Chair -North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net U.S. Nuclear Regulatory Commission ATTN: Director, Division of Spent Fuel Storage Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 | : 1. 10 CFR 50.54(q)(5) | ||
}} | Summaries for OPEP-02.6.26, Revision 38; OPEP-03.4.8, Revision 4; OPEP-03.6.1, Revision 17; and OPEP-03.6.3, Revision 21 2. Copy of OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC) 3. Copy of OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases 4. Copy of OPEP-03.6.1, Revision 17, Release Estimates Based Upon Stack/Vent Readings 5. Copy of OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions | ||
-Core Damage Assessment Program (CDAM) cc (with all Enclosures): | |||
U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 cc (with Enclosure 1 only): U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 cc (without Enclosures): | |||
Chair -North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net U.S. Nuclear Regulatory Commission ATTN: Director, Division of Spent Fuel Storage Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001}} | |||
Latest revision as of 14:56, 6 February 2019
| ML17125A093 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/20/2017 |
| From: | McPherson M Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17125A120 | List: |
| References | |
| BSEP 17-0041 | |
| Download: ML17125A093 (2) | |
Text
ENERGY April 20, 2017 Serial: BSEP 17-0041 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Brunswick Nuclear Plant P .0. Box 10429 Southport, NC 28461 10 CFR 50.4(b )( 5)(iii) 10 CFR 50.54( q)(5) 10 CFR 72.4 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Revision to Radiological Emergency Response Plan Implementing Procedures Ladies and Gentlemen:
In accordance with 10 CFR 50.4(b)(5)(iii);
and 10 CFR 72.4; Duke Energy Progress, LLC (Duke Energy), is submitting a revision to Radiological Emergency Response Plan Implementing Procedures OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC); OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases; OPEP-03.6.1, Revision 17, Re/ease Estimates Based Upon Stack/Vent Readings; and OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions-Core Damage Assessment Program (CDAM). Duke Energy has evaluated these revisions, in accordance with 10 CFR 50.54(q), and determined that the revisions are not a reduction in the effectiveness of the Radiological Emergency Response Plan and that the Plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. Enclosure 1 provides a 10 CFR 50.54(q)(5) summary for these.revised Radiological Emergency Response Plan implementing procedures.
Enclosures 2 through 5 contain a copy_ of the revised Radiological Emergency Response Plan implementing procedures.
This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 457-2487.
Sincerely, Mark McPherson Director -Organizational Effectiveness (Acting) Brunswick Steam Electric Plant U.S. Nuclear Regulatory Commission Page 2 of 2 WRM/wrm
Enclosures:
Summaries for OPEP-02.6.26, Revision 38; OPEP-03.4.8, Revision 4; OPEP-03.6.1, Revision 17; and OPEP-03.6.3, Revision 21 2. Copy of OPEP-02.6.26, Revision 38, Activation and Operation of the Technical Support Center (TSC) 3. Copy of OPEP-03.4.8, Revision 4, Offsite Dose Projections for Monitored Releases 4. Copy of OPEP-03.6.1, Revision 17, Release Estimates Based Upon Stack/Vent Readings 5. Copy of OPEP-03.6.3, Revision 21, Estimate of the Extent of Core Damage Under Accident Conditions
-Core Damage Assessment Program (CDAM) cc (with all Enclosures):
U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 cc (with Enclosure 1 only): U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 cc (without Enclosures):
Chair -North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net U.S. Nuclear Regulatory Commission ATTN: Director, Division of Spent Fuel Storage Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001