ML060530037

Supplement to License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity

ML060530037
Person / Time
Site:	Calvert Cliffs
Issue date:	02/13/2006
From:	Spina J A Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML060530037 (5)

Text

James A. Spina Vice President Calvert Cliffs Nuclear Power Plant, Inc.1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.4455 410.495.3500 Fax Constellation Energy Generation Group February 13, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Supplement to License Amendment Request: Technical Improvement Regarding Steam Generator Tube Integritv Specification

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REFERENCE:

(a) Letter from Mr. G. Vanderheyden (CCNPP) to Document Control Desk (NRC), dated July 13, 2005, License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process In Reference (a) we submitted a license amendment request to revise the Technical Specification requirements related to steam generator tube integrity using Technical Specification Task Force (TSTF)-449, Revision 4 as a basis. Attached to that letter were marked up pages for the existing Technical Specifications to show the proposed change. The insert provided for Section 5.5.9 in Reference (a) was determined to not match the intent of the insert in TSTF-449, Revision 4 after removal of the bracketed information.

Removal of the bracketed information left a grammatically incorrect sentence.

A corrected insert for Section 5.5.9 is attached which corrects the grammatical error introduced when the bracketed information was removed as allowed in TSTF-449, Revision 4. Please replace the previous insert for Section 5.5.9 with this one. This change does not affect the No Significant Hazards Determination or the Environmental Assessment provided in Reference (a).Proo(

Document Control Desk February 13, 2006 Page 2 Should you have questions regarding this matter, please contact Mr. L. S. Larragoite at (410) 495-4922.Very truly yours,." STATE OF MARYLAND COUNTY OF CALVERT TO WIT: I, James A. Spina, being duly sworn, state that I am Vice President

-Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants.

Such information has been reviewed in accordance with company practice and I believe it to be reliable.(5 C.Subscribed and sworn before me a Notary P b ic in and for the State of Maryland and County of.- this /34edayof fV0aK ,2006.6 / V/W iITNESS my Hand and Notarial Seal: My Commission Expires:/ Notary Publit l ~Datd JAS/PSF/bjd

Attachment:

(1) Corrected Marked-up Technical Specification Insert cc: P. D. Milano, NRC S. J. Collins, NRC Resident Inspector, NRC R. I. McLean, DNR ATTACHMENT (1)CORRECTED MARKED-UP TECHNICAL SPECIFICATION INSERT Calvert Cliffs Nuclear Power Plant, Inc.February 13,2006 INSERT 5.5.9 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 provisions:

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.

Steam generator 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 and 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.2. Accident induced leakage performance criterion:

The primary to secondary accident induced leakage rate for any design basis 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 SGs and leakage rate for an individual SG. Leakage is not to exceed 100 gpd per SG.3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE." c. Provisions for SG tube repair criteria.

Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged.d. Provisions for SG tube inspections.

Periodic SG tube inspections shall be performed.

The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial, and circumferential cracks) that may be present along the length of the tube, 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 repair 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.

An assessment of degradation shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.

2. Inspect 100% of the tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). 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.e. Provisions for monitoring operational primary to secondary LEAKAGE.