ML12356A298

Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process.

ML12356A298
Person / Time
Site:	North Anna
Issue date:	12/13/2012
From:	Price J Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-486A
Download: ML12356A298 (7)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 10 CFR 50.90 December 13, 2012 U.S. Nuclear Regulatory Commission Serial No. 12-486A Attention: Document Control Desk NL&OS/ETS Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNITS I AND 2 SUPPLEMENTAL INFORMATION FOR PROPOSED TECHNICAL SPECIFICATIONS TO ADOPT TSTF-510, "REVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBE SAMPLE SELECTION," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS In a July 30, 2012 letter (Serial No.12-486), Dominion requested amendments, in the form of changes to the Technical Specifications (TS) to Facility Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively.

The proposed amendment modifies TS requirements regarding steam generator tube inspections and reporting as described in TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection." In a December 12, 2012 telephone call, the NRC staff identified an unjustified deviation from TSTF-510 in the proposed TS change. The deviation, a typographical error, was unintended and is being corrected with the attached revised marked-up and proposed TS pages. Please replace these pages in the original submittal and complete the review of the proposed amendment using the revised pages. provides the revised marked-up TS page, and Attachment 2 provides the revised proposed TS page.

The proposed amendment does not involve a Significant Hazards Consideration pursuant to the provisions of 10 CFR 50.92.

Approval of the proposed amendment is requested by July 2013. Once approved, the amendment shall be implemented within 60 days.

Serial No. 12-486A Docket Nos. 50-338/339 Proposed LAR- Steam Generator Program Page 2 of 3 In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Virginia.

If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.

Very truly yours, J.Ylan Price WANDA D.CRAFT Notary Public Vice President - Nuclear Engineering Commonwealth of Virginia Reg. # 7520495 My Commission Expires January 31, 201k COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 1 3'ý day of QECAL-XAaA.s , 2012.

My Commission Expires: 2.(o Z.1 Notary Public "

Commitments made in this letter: None Attachments:

1. Revised Marked-up Technical Specifications Page 5.5-7

2. Revised Proposed Technical Specification Page 5.5-8

Serial No. 12-486A Docket Nos. 50-338/339 Proposed LAR- Steam Generator Program Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Suite 300 Glen Allen, Virginia 23060 State Health Commissioner Virginia Department of Health James Madison Building - 7 th floor 109 Governor Street Suite 730 Richmond, Virginia 23219 NRC Senior Resident Inspector North Anna Power Station Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738

Serial No. 12-486A Docket Nos. 50-338/339 Attachment 1 Revised Marked-up Technical Specifications Page 5.5-7 Virginia Electric and Power Company (Dominion)

North Anna Power Station Units 1 And 2

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continu

c. Provisions for SG tube ciea.Tbsfudy nrvice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall b plugged.

d. Provisions for SG tube inspections. Periodic S tube inspections shall be performed. The number and portions o the tubes inspected and methods of inspection shall be erformed with the objective of detecting flaws of any type (e. ., volumetric flaws, axial and circumferential cracks) tha may be present along the length of the tube, from the tube-t -tubesheet weld at the tube inlet to the tube-to-tubesheet weldit the tube outlet, and that may satisfy the applicable tube P criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A@ assessment shall be performed to determine the ty and location of flaws to which the tubes may be susceptible and based on this assessment, to determine which ins ection metho s need to be employed and at what locations. degradation installation

1. Inspect 100% o the tubes in each SG --- durin* Zthe irs refueling outage following SG

2. Inspect/OO%. of the t)' es at sequential periods of 44, 108, 72, a1 , thereafter 60 effective f 11 power mont s. The fir sequential riod shall be nsidered to gin after t first inservce inspection o the SGs. In ddition, inspect 50% of he tubes by th refueling out e nearest t e midpoint of e period and th remaining 50% y the refueling Replace with Insert A outage near st the end of theperiod. No SGO hall operat for more than 2 effective ful power months r three ref eling outages (whichever is les ) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for ea SG for the degradation mechanism that affected and incaindication shall not exceed 24 effective potentiallyaetfull power months or one refueling outage (whichever +9 p4es-s). If definitive information, such as from exam' ation of a pulled tube, diagnostic non-destructive testin , or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then he indication need not be treated as a crack.

results in more frequent inspections North Anna Units 1 and 2 5.5-7 Amendments NSM8-

Serial No. 12-486A Docket Nos. 50-338/339 Attachment 2 Revised Proposed Technical Specifications Page 5.5-8 Virginia Electric and Power Company (Dominion)

North Anna Power Station Units 1 And 2

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

2. (continued) be inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.

a. After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period;

b. During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period;

c. During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and

d. During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods.

3. If crack indications are found in any SG tube, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s),

then the indication need not be treated as a crack.

North Anna Units I and 2 5.5-8 Amendments