NL-13-1297, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement Process Revised Clean-Typed Page
| ML13199A181 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/17/2013 |
| From: | Pierce C Southern Co, Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-13-1297 | |
| Download: ML13199A181 (10) | |
Text
Charles R. Pierce Southern Nuclear Regu latory flairs Director Operati ng Company. Inc.
40 Inverness Center Parkway Pos t Office Box 1295 Birmingham, Alabama 35201 Tel 205 .992.7872 Fax 205.992.7601 July 17. 2013 SOUTHERN ' \
COMPANY Docket Nos. : 50-424 NL-13-1297 50-425 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-510, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection," Using The Consolidated Line Item Improvement Process Revised Clean-Typed Pages Ladies and Gentlemen:
By letter dated January 23 , 2013, Southern Nuclear Operating Company (SNC) submitted a request for an amendment to the Technical Specifications (TS) for the Joseph M. Farley Nuclear Plant (FNP) - Units 1 and 2 and the Vogtle Electric Generating Plant (VEGP) - Units 1 and 2.
Based on subsequent phone conversations between the Nuclear Regulatory Commission (NRC) and SNC staff, this letter re-submits the VEGP clean-typed pages to remove excess spaces and page-breaks between pages, which will reduce the number of TS pages impacted. The Enclosure provides the revised VEGP clean-typed pages, and supersedes the Enclosure 5 pages of the January 23,2013 amendment request in their entirety. There were no additional changes from what was provided in the January 23, 2013 amendment request. The "No Significant Hazards Determination" and the remaining Enclosures provided in the January 23, 2013 amendment request remain unchanged.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
U. S. Nuclear Regulatory Commission NL-13-1297 Page 2 Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
Respectfully submitted, C. R..~
C. R. Pierce Regulatory Affairs Director _.
- ~.
CRP/RMJ t1-Sworn to and subscribed before me this JL day of ~<
(1. n t.
,2013.
~J:(~~ Notary Public My commission expires: //- t) 2-/3 .
Enclosure:
Technical Specification Change - Clean-typed Pages (VEGP) cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. E. Tynan, Vice President - Vogtle Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle State of Georgia Mr. J. H. Turner, Environmental Director Protection Division
Vogtle Electric Generating Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-510, II Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using The Consolidated Line Item Improvement Process II Revised Clean-Typed Pages Enclosure Technical Specification Change - Clean-typed Pages (VEGP)
Tube Integrity 17 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator Tube Integrity 3.4.17 integrity shall be maintained.
All SG tubes satisfying the tube plugging shall plugged in
<ItI',.,r,rl<l'' with Steam APPLICABILITY: MODES 1, 3, and 4.
ACTIONS Separate Condition entry is allowed for each CONDITION REQUIRED ACTION COMPLETION TIME A or more tubes Ai Verify tube integrity of the 7 days the tube tube(s) is plugging and not until the next refueling outage plugged in accordance or SG tube inspection.
with the Steam Program.
A2 Plug the affected tube(s) in Prior to entering with the 4 following the Generator Program. next refueling outage orSG inspection B. Required Action and 1 in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion of Condition A not AND met.
B.2 Be in MODE 5. hours tube integrity not maintained.
Vogtle Units 1 2 17-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Tube Integrity 3.4.17 SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance with Steam Generator Program. the Steam Generator Program 3.4.17.2 Verify that tube that Prior to entering the tube plugging criteria is plugged in MODE 4 following a Vogtle Units 1 and 2 3.4.17-2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following:
- a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes.
Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.
- b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.
- 1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down), all anticipated transients included in the design specification, and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.
(continued)
Vogtle Units 1 and 2 5.5-7 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Programs and Manuals and Manuals
==c:.......;::~-=-:..==---"=-=-<...:.....;;..;::;.w.:.== (continued)
- 2. Accident induced leakage performance criterion: The primary to aC(:::taj3m induced rate for any n"""'lnn accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all and rate for an individual is not to eX(:::ee!Q 1 gpm per
- 3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."
- c. Provisions for tube plugging criteria. Tubes found by inservice inspection to ",..,... t"",,, flaws with a depth to or exceeding 40% of the nominal tube thickness shall be plugged.
The following alternate tube plugging criteria shall be applied as an alternative to depth criteria:
Tubes with service-induced flaws located greater than 15.2 inches below the top of the tubesheet do not require plugging. Tubes with service-induced flaws located in the portion of tube from top the tubesheet to 15.2 inches below the of the tubesheet shall be plugged upon detection.
- d. Provisions for tube SG tube inspections performed. number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type volumetric flaws, axial and circumferential cracks) that be present along length of the from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. Portions of tube below 1 below the top of the tubesheet are excluded from this The tube-to-tubesheet is not part of the tube. In 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 tube integrity is maintained until the next inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be based on this to determine which inspection methods need to be employed and at what locations.
Vogtle Units 1 and 2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)
- 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.
- 2. After the first refueling outage following SG installation, inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, and c below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated. The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to 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 120 effective full power months. This constitutes the first inspection period.
b) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; and c) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods.
(continued)
Vogtle Units 1 and 2 5.5-9 Amendment 1\10. (Unit 1)
Amendment No. (Unit 2)
Programs and Manuals 5.5 5.5 and Manuals 5.5.9 (continued)
- 3. If crack indications are found in portions of the tube not excluded above, then the next inspection for affected and potentially affected SG for the degradation mechanism caused the crack shall not exceed 24 full power months or one (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic nondestructive testing, or engineering evaluation indicates that a indication is not with a crack(s), then indication need not be treated as a crack.
- e. Provisions for monitoring operational primary to secondary 5.5.10 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG degradation. The program shall include:
Vogtle Units 1 and 2 5.5-10 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Reporting Requirements 5.6
.10 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9, Steam Generator (SG) Program. The report shall include:
- a. The of inspections no.l"Tnrrno,,,, on
- b. Degradation mechanisms found,
- c. Nondestructive examination techniques utilized for degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced ind icalions,
- e. Number of tubes plugged during the outage for degradation
- f. The number and percentage of tubes plugged to and the effective plugging percentage in steam generator,
- g. The results of condition monitoring, including the results of tube pulls and in-situ
- h. The primary to secondary rate observed in each (if it is not practical to assign the LEAKAGE to an individual the entire primary to secondary LEAKAGE should assumed to be from one during the cycle the inspection which is the subject of the report; and
- i. rate from the portion of the tu bes below 15.2 from top the tubesheet for the most limiting accident in most limiting SG.
In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 2.48 times the maximum operational primary to secondary rate, the report should describe how it was determined.
- j. The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the of discovery and corrective action shall be provided.
Vogtle Units 1 2 5.6-6 Amendment No. (Unit 1)
Amendment No. (Unit