ML11299A011

Request for Corrected Technical Specification Pages to Resolve License Amendment Request (Lar)/Amendment Timing Coordination Issues for LARs

ML11299A011
Person / Time
Site:	Oconee
Issue date:	10/17/2011
From:	Gillespie T Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11299A011 (8)

Text

T. PRESTON GILLESPIE, JR.

__ ke Vice President LE Energy Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy.

Seneca, SC 29672 10 CFR 50.90 864-873-4478 864-873-4208 fax T.Gillespie@duke-energy.corn October 17, 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3; Docket Number 50-269, 50-270, and 50-287; Request for Corrected Technical Specification Pages to Resolve License Amendment Request (LAR)/Amendment Timing Coordination Issues for LARs Duke Energy Carolinas, LLC (Duke Energy) requests the NRC to re-issue two Technical Specification (TS) pages to retain a TS Surveillance Requirement (SR) Frequency and to resolve a pagination problem.

On March 17, 2010, Duke Energy Carolinas, LLC (Duke Energy) submitted LAR 2009-10 requesting Nuclear Regulatory Commission (NRC) approval to adopt Technical Specification Task Force (TSTF)-425, Rev. 3, which modifies Oconee Nuclear Station (ONS) TSs by relocating periodic surveillance frequencies to a licensee-controlled program. At the time of submittal, there was a pending LAR (LAR 2008-10) that proposed to change the frequency of SR 3.6.5.8 from "10 years" to "Following activities which could result in nozzle blockage." The pending LAR was approved by Amendment Nos. 369, 371, and 370 on August 24, 2010, and Duke Energy implemented it on September 21, 2010.

The NRC issued Amendment Nos. 372, 374, and 373 approving LAR 2009-10 on March 21, 2011. This amendment relocates the SR frequency for SR 3.6.5.8 to a surveillance frequency control program (SFCP). The SR frequency approved by Amendment Nos. 369, 371, and 370 is event driven rather than periodic and does not qualify for relocation to the SFCP.

Therefore, Duke Energy requests that NRC re-issue TS page 3.6.5-5 to retain this SR frequency in TSs. The request is considered administrative and is needed to resolve the coordination issues associated with pending LAR 2008-10 being approved during the time period that LAR 2009-10 was under review.

NRC issued Amendment Nos. 377, 379, and 378 on August 2, 2011, and Duke Energy implemented it on August 30, 2011. Implementation of the TS page 5.0-26 resulted in the need to move 3 lines of text from this page to the next (5.0-27). Duke Energy requests the NRC re-issue this page to correct the TS in the NRC record.

Attachment 1 provides the corrected marked-up TS pages. Attachment 2 provides the revised retyped TS pages.

If there are any questions regarding this submittal, please contact Boyd Shingleton, ONS Regulatory Compliance Group, at (864) 873-4716.

www. duke-energy. corn

U. S. Nuclear Regulatory Commission October 17, 2011 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on October 17, 2011.

Sincerely, T. Preston Gillespie, Jr., Vice President Oconee Nuclear Station Attachments:

1. Technical Specifications - Marked-up Pages

2. Technical Specifications - Reprinted Pages

U. S. Nuclear Regulatory Commission October 17, 2011 Page 3 cc w/ Attachments:

Mr. Victor McCree, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Stang, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, DC 20555 Mr. Andy Sabisch Senior Resident Inspector Oconee Nuclear Site Ms. Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201

ATTACHMENT I MARKED-UP TECHNICAL SPECIFICATION PAGES

Corrected page for Amendment Nos. 372, 374, and 373 Reactor Building Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.5.5 ------------------- NOTE-Applicable for RB cooling system after the In accordance with the completion of the LPSW RB Waterhammer Surveillance Modification on the respective Unit. Frequency Control Program Verify each automatic reactor building spray and cooling valve in each required flow path (ijrn/ntlý that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.5.6 Verify each required reactor building spray ( Im/nth* '-

pump starts automatically on an actual or '"

simulated actuation signal.

SR 3.6.5.7 Verify each required reactor building cooling lim/ntl train starts automatically on an actual or simulated actuation signal.

SR 3.6.5.8 Verify each spray nozzle is unobstructed. Following activities which could result in nozzle blockage.

OCONEE UNITS 1, 2, & 3 3.6.5-5 Amendment Nos.[30, 37/, &T70 372. 374, & 373

ATTACHMENT 2 REPRINTED TECHNICAL SPECIFICATION PAGES

Corrected page for Amendment Nos. 372, 374, and 373 Reactor Building Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.5.5 ----------------NOTE -----

Applicable for RB cooling system after the completion of the LPSW RB Waterhammer Modification on the respective Unit.

Verify each automatic reactor building spray In accordance with the and cooling valve in each required flow path Surveillance Frequency that is not locked, sealed, or otherwise Control Program secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.5.6 Verify each required reactor building spray In accordance with the pump starts automatically on an actual or Surveillance Frequency simulated actuation signal. Control Program SR 3.6.5.7 Verify each required reactor building cooling In accordance with the train starts automatically on an actual or Surveillance Frequency simulated actuation signal. Control Program SR 3.6.5.8 Verify each spray nozzle is unobstructed. Following activities which could result in nozzle blockage.

OCONEE UNITS 1, 2, & 3 3.6.5-5 Amendment Nos. 372, 374, & 373

Corrected page for Amendment Nos. 377, 379, and 378 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.8 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.10, Steam Generator (SG) Program. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h. The effective plugging percentage for all plugging in each SG.

OCONEE UNITS 1, 2, & 3 5.0-27 Amendment Nos. 377, 379, & 378