ML042810130

Correction to Amendment Nos. 339, 341 and 340

ML042810130
Person / Time
Site:	Oconee
Issue date:	10/04/2004
From:	Olshan L NRC/NRR/DLPM/LPD2
To:	Rosalyn Jones Duke Energy Corp
Olshan L N, NRR/DLPM, 415-1419
References
TAC MB6144, TAC MB6145, TAC MB6146
Download: ML042810130 (10)

Text

October 4, 2004 Mr. Ronald A. Jones Vice President, Oconee Site Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: CORRECTION TO AMENDMENT NOS. 339, 341, AND 340 (TAC NOS. MB6144, MB6145 AND MB6146)

Dear Mr. Jones:

On August 5, 2004, the Nuclear Regulatory Commission (NRC) issued Amendment Nos. 339, 341, and 340 to Facility Operating Licenses Nos. DPR-38, DPR-47, and DPR-55 for the Oconee Nuclear Station (Oconee), Units 1, 2, and 3. The amendments revised Technical Specification 3.8.1, AC Sources - Operating, to temporarily extend the completion times for the Keowee hydro units to allow additional time for maintenance and upgrades. License Condition 3.H incorporated the commitments that the licensee made in its letter dated July 29, 2004, associated with TSC 2002-05. The amendments were in response to your application dated August 22, 2002, as supplemented by letters dated September 12, 2003, and February 4, February 16, March 23, April 28, June 17, July 6, July 12, July 19, and July 29, 2004.

At the time of issuance, the NRC staff did not attach the revised Condition 3.H operating license pages.

Enclosed are the revised operating license pages for Oconee, Units 1, 2, and 3. We regret any inconvenience this may have caused.

Sincerely,

/RA/

Leonard N. Olshan, Sr. Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287

Enclosure:

As stated cc w/encl: See next page

October 4, 2004 Mr. Ronald A. Jones Vice President, Oconee Site Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: ISSUANCE OF REVISED OPERATING LICENSE PAGES FOR AMENDMENT NOS. 339, 341, AND 340 (TAC NOS. MB6144, MB6145 AND MB6146)

Dear Mr. Jones:

On August 5, 2004, the Nuclear Regulatory Commission (NRC) issued Amendment Nos. 339, 341, and 340 to Facility Operating Licenses Nos. DPR-38, DPR-47, and DPR-55 for the Oconee Nuclear Station (Oconee), Units 1, 2, and 3. The amendments revised Technical Specification 3.8.1, AC Sources - Operating, to temporarily extend the completion times for the Keowee hydro units to allow additional time for maintenance and upgrades. License Condition 3.H incorporated the commitments that the licensee made in its letter dated July 29, 2004, associated with TSC 2002-05. The amendments were in response to your application dated August 22, 2002, as supplemented by letters dated September 12, 2003, and February 4, February 16, March 23, April 28, June 17, July 6, July 12, July 19, and July 29, 2004.

At the time of issuance, the NRC staff did not attach the revised Condition 3.H operating license pages.

Enclosed are the revised operating license pages for Oconee, Units 1, 2, and 3. We regret any inconvenience this may have caused.

Sincerely,

/RA/

Leonard N. Olshan, Sr. Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC BBonser, RII PDII-1 R/F ACRS T-2 E26 OGC DClarke GHill (6 paper copies)

LOlshan Accession No. ML042810130 Nrr-106 OFFICE PDII-1/PM PDII-1/LA (A)

PDII-1/SC (A)

NAME LOlshan DClarke MRoss-Lee DATE 9/29/2004 9/29/2004 10/4/2004 OFFICIAL RECORD COPY

Oconee Nuclear Station, Units 1, 2, and 3 cc:

Ms. Lisa F. Vaughn Duke Energy Corporation Mail Code - PB05E 422 South Church Street Post Office Box 1244 Charlotte, North Carolina 28201-1244 Ms. Anne W. Cottingham, Esquire Winston and Strawn 1400 L Street, NW Washington, DC 20005 Manager, LIS NUS Corporation 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Senior Resident Inspector U.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, South Carolina 29672 Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull Street Columbia, South Carolina 29201-1708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Drive Suite 705 Rosslyn, Virginia 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Energy Corporation ON03RC 7800 Rochester Highway Seneca, South Carolina 29672 Ms. Karen E. Long Assistant Attorney General North Carolina Department of Justice Post Office Box 629 Raleigh, North Carolina 27602 Mr. R. L. Gill, Jr.

Manager - Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 South Church Street Mail Stop EC05P Charlotte, North Carolina 28202 Mr. Richard M. Fry, Director Division of Radiation Protection North Carolina Department of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, North Carolina 28210 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer Post Office Box 1006-EC07H Charlotte, North Carolina 28201-1006

ATTACHMENT TO LICENSE AMENDMENT NO. 339 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 341 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 340 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Facility Operating License pages 8 and 8a Facility Operating License pages 8 and 8a Appendix A Technical Specifications Appendix A Technical Specifications 3.8.1-4 3.8.1-4 3.8.1-5 3.8.1-5 3.8.1-6 3.8.1-6 3.8.1-7 3.8.1-7 3.8.1-8 3.8.1-8 B 3.8.1-1 through -25 B 3.8.1-1 through -26 December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of fire.

E.

Physical Protection Duke Energy Corporation shall fully implement and maintain in effect all provisions of the Commission-approved nuclear security and contingency, and guard training and qualification plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan that contains Safeguards Information protected under 10 CFR 73.21 is entitled: Nuclear Security and Contingency Plan, with revisions submitted through April 26, 1999. The plan that does not contain safeguards information is entitled, Nuclear Security Training and Qualification Plan, with revisions submitted through August 18, 1999. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

In the update to the UFSAR required pursuant to 10 CFR 50.71(e)(4) scheduled for July, 2001, the licensee shall update the UFSAR to include the UFSAR supplement submitted pursuant to 10 CFR 54.21(d) as revised on March 27, 2000. Until the UFSAR update is complete, the licensee may make changes to the programs described in its UFSAR supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G.

The licensees UFSAR supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 27, 2000, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than February 6, 2013.

H.

Duke shall comply with the commitments of Attachment 2 to letter dated July 29, 2004, associated with TSC 2002-05.

4.

This renewed license is effective as of the date of issuance and shall expire at midnight on February 6, 2033.

-8a-5.

Steam Generator Circumferential Crack Report Following each inservice inspection of steam generator tubes, the NRC shall be notified of the following prior to returning the steam generators to service:

a.

Indication of circumferential cracking in the secondary side roll (lower roll in the upper tubesheet or upper roll in the lower tubesheet) if rerolled.

b.

Indication of circumferential cracking in the original roll or heat affected zone adjacent to the tube-to-tubesheet seal weld if no reroll is present.

c.

Determination of the best-estimate total leakage that would result from an analysis of the limiting Large Break Loss of Coolant Accident (LBLOCA) based on circumferential cracking in the original tube-to-tubesheet rolls, tube-to-tubesheet rerolls, and heat affected zones of seal welds as found during each inspection.

6.

Demonstrate that the primary-to-secondary leakage following a LBLOCA, as described in Appendix A to BAW-2374, is acceptable, based on the as-found condition of the SGs.

This is required to demonstrate that adequate margin and defense-in-depth are maintained. For the purpose of this evaluation, acceptable means a best estimate of the leakage expected in the event of a LBLOCA that would not result in a significant increase of radionuclide release (e.g., in excess of 10 CFR 100 limits). A summary of this evaluation shall be provided to the NRC within 3 months following completion of steam generator tube inservice inspection with the report required by Technical Specification 5.6.8, Item b.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Roy P. Zimmerman Roy P. Zimmerman, Acting Director Office of Nuclear Reactor Regulations

Attachment:

1) Appendix A - Technical Specifications Renewed License No. DPR-38 Date of issuance: May 23, 2000 Renewed License No. DRP-38

December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of fire.

E.

Physical Protection Duke Energy Corporation shall fully implement and maintain in effect all provisions of the Commission-approved nuclear security and contingency, and guard training and qualification plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan that contains Safeguards Information protected under 10 CFR 73.21 is entitled: Nuclear Security and Contingency Plan, with revisions submitted through April 26, 1999. The plan that does not contain safeguards information is entitled, Nuclear Security Training and Qualification Plan, with revisions submitted through August 18, 1999. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

In the update to the UFSAR required pursuant to 10 CFR 50.71(e)(4) scheduled for July, 2001, the licensee shall update the UFSAR to include the UFSAR supplement submitted pursuant to 10 CFR 54.21(d) as revised on March 27, 2000. Until the UFSAR update is complete, the licensee may make changes to the programs described in its UFSAR supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G.

The licensees UFSAR supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 27, 2000, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than February 6, 2013.

H.

Duke shall comply with the commitments of Attachment 2 to letter dated July 29, 2004, associated with TSC 2002-05.

4.

This renewed license is effective as of the date of issuance and shall expire at midnight on October 2, 2033.

-8a-5.

Steam Generator Circumferential Crack Report Following each inservice inspection of steam generator tubes, the NRC shall be notified of the following prior to returning the steam generators to service:

a.

Indication of circumferential cracking in the secondary side roll (lower roll in the upper tubesheet or upper roll in the lower tubesheet) if rerolled.

b.

Indication of circumferential cracking in the original roll or heat affected zone adjacent to the tube-to-tubesheet seal weld if no reroll is present.

c.

Determination of the best-estimate total leakage that would result from an analysis of the limiting Large Break Loss of Coolant Accident (LBLOCA) based on circumferential cracking in the original tube-to-tubesheet rolls, tube-to-tubesheet rerolls, and heat affected zones of seal welds as found during each inspection.

6.

Demonstrate that the primary-to-secondary leakage following a LBLOCA, as described in Appendix A to BAW-2374, is acceptable, based on the as-found condition of the SGs.

This is required to demonstrate that adequate margin and defense-in-depth are maintained. For the purpose of this evaluation, acceptable means a best estimate of the leakage expected in the event of a LBLOCA that would not result in a significant increase of radionuclide release (e.g., in excess of 10 CFR 100 limits). A summary of this evaluation shall be provided to the NRC within 3 months following completion of steam generator tube inservice inspection with the report required by Technical Specification 5.6.8, Item b.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Roy P. Zimmerman Roy P. Zimmerman, Acting Director Office of Nuclear Reactor Regulations

Attachment:

1) Appendix A - Technical Specifications Renewed License No. DPR-47 Date of issuance: May 23, 2000 Renewed License No. DRP-47

December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of fire.

E.

Physical Protection Duke Energy Corporation shall fully implement and maintain in effect all provisions of the Commission-approved nuclear security and contingency, and guard training and qualification plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan that contains Safeguards Information protected under 10 CFR 73.21 is entitled: Nuclear Security and Contingency Plan, with revisions submitted through April 26, 1999. The plan that does not contain safeguards information is entitled, Nuclear Security Training and Qualification Plan, with revisions submitted through August 18, 1999. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

In the update to the UFSAR required pursuant to 10 CFR 50.71(e)(4) scheduled for July, 2001, the licensee shall update the UFSAR to include the UFSAR supplement submitted pursuant to 10 CFR 54.21(d) as revised on March 27, 2000. Until the UFSAR update is complete, the licensee may make changes to the programs described in its UFSAR supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G.

The licensees UFSAR supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 27, 2000, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than February 6, 2013.

H.

Duke shall comply with the commitments of Attachment 2 to letter dated July 29, 2004, associated with TSC 2002-05.

4.

This renewed license is effective as of the date of issuance and shall expire at midnight on July 19, 2034.

-8a-5.

Steam Generator Circumferential Crack Report Following each inservice inspection of steam generator tubes, the NRC shall be notified of the following prior to returning the steam generators to service:

a.

Indication of circumferential cracking in the secondary side roll (lower roll in the upper tubesheet or upper roll in the lower tubesheet) if rerolled.

b.

Indication of circumferential cracking in the original roll or heat affected zone adjacent to the tube-to-tubesheet seal weld if no reroll is present.

c.

Determination of the best-estimate total leakage that would result from an analysis of the limiting Large Break Loss of Coolant Accident (LBLOCA) based on circumferential cracking in the original tube-to-tubesheet rolls, tube-to-tubesheet rerolls, and heat affected zones of seal welds as found during each inspection.

6.

Demonstrate that the primary-to-secondary leakage following a LBLOCA, as described in Appendix A to BAW-2374, is acceptable, based on the as-found condition of the SGs.

This is required to demonstrate that adequate margin and defense-in-depth are maintained. For the purpose of this evaluation, acceptable means a best estimate of the leakage expected in the event of a LBLOCA that would not result in a significant increase of radionuclide release (e.g., in excess of 10 CFR 100 limits). A summary of this evaluation shall be provided to the NRC within 3 months following completion of steam generator tube inservice inspection with the report required by Technical Specification 5.6.8, Item b.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Roy P. Zimmerman Roy P. Zimmerman, Acting Director Office of Nuclear Reactor Regulations

Attachment:

1) Appendix A - Technical Specifications Renewed License No. DPR-55 Date of issuance: May 23, 2000 Renewed License No. DRP-55