ML052350912

(TMI Unit 1), Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria

ML052350912
Person / Time
Site:	Three Mile Island
Issue date:	08/23/2005
From:	Cowan P AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
5928-05-20231, TAC MB6475
Download: ML052350912 (5)

Text

10 CFR 50.55a August 23,2005 5928-05-20231 U S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit I (TMI Unit 1)

Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria (TAC No. MB6475)

References:

1) AmerGen Energy Company, LLC letter to NRC, dated August 11, 2005 (5928-05-20207), "Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria.

2) AmerGen Energy Company, LLC letter to NRC, dated May 3,2005 (5928-05-20102), "Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria.

As identified in Reference 1, this letter provides additional information in response to Question No. 10 of the NRC draft request for additional information received via NRC email, dated July 12, 2005, regarding TMI Unit 1 Once-Through Steam Generator Kinetic Expansion Inspection and Repair Criteria submitted in Reference 2. The additional information is provided in Attachment 1.

If any additional information is needed, please contact David J. Distel at (610) 765-5517.

Respectfully, Pamela B. Cowan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Attachment:

1) NRC Question and AmerGen Response

US. Nuclear Regulatory Commission August 23,2005 Page 2 cc: S. J. Collins, USNRC, Administrator Region I D. M. Kern, USNRC, Senior Resident Inspector, TMI Unit 1 P.S. Tam, USNRC, Senior Project Manager, TMl Unit 1 File No. 02077

ATTACHMENT 1 NRC Question and AmerGen Response

Attachment 1 5928-05-20231 Page 1 of 2 Request For Additional Information Related to TMI-1 Kinetic Expansion Inspection and Acceptance Repair Criteria May 3,2005 Letter

10. NRC Question Provide leak rate estimates (in terms of gallons per minute), based on the licensees PICEP leakage model, for circumferential cracks with lengths of 0.1, 0.2, 0.3, 0.4, 0.5, 0.6, and 0.7 inches for 0.625 inch diameter, 0.034 inch thick tubes. Utilize assumptions on pressure and temperature consistent with those used to generate PICEP leak rates for axial cracks shown on Table 6 of the licensees report ECR No. TM 01-00328, which was enclosed with the licensees letter, dated July 13, 2001. Describe values of all other input parameters used to generate these estimates (e.g., material properties, crack tortuosity, surface roughness, etc.).

Response

EPRls PICEP Rev. 4 (7 2/16/92) was used to estimate leak rates for circumferential cracks in tension with the lengths requested. These values are developed for comparative information only based on nonsafety-related, non-QA program calculations, and are not considered as design or licensing basis information. The results are provided in Table 1, below.

Pressure and temperature assumptions are consistent with Table 6 of ECR No.

TM 01-00328. The analyses were performed assuming that the tubing was freespan (i.e., it was assumed that no tubesheets, tube support plates, or other conditions on the exterior of the tube affected crack openings or flows).

The analyses results were obtained using the inputs provided in Table 2. The crack opening area was calculated for a circumferential crack in tension using the method described in NUREG/CR-3464, The Application of Fracture Proof Design Methods Using Tearing Instability Theory to Nuclear Piping Postulating Circumferential Through-wall Cracks, dated September 1983. The methodology was used to calculate the crack opening area (COA) for circumferential through-wall cracks subjected to 1310 Ibs. tension. The crack opening displacement (COD) was calculated for an elliptical opening (4*COA/nL).

Table 1 provides the crack opening displacements (COD) that were calculated using the NUREG methodology as well as the PICEP generated leak rates for flow at 2OOOF and 600°F.

Attachment 1 5928-05-20231 Page 2 of 2 TABLE 1: PICEP ANALYSIS RESULTS Assumed 100% COD (in) PICEP Leak PICEP Leak TW Circ. Crack Rate 8 200F Rate 8 600F Length (in) (gpm) (gpm) 0.1 1.578E-04 0.0021 0.0030 0.2 3.675 E-04 0.0154 0.0219 0.3 6.536E-04 0.0572 0.0812 0.4 1.044E-03 0.1490 0.21 16 0.5 1.582E-03 0.3182 0.4518 0.6 2.339E-03 0.6060 0.8605 0.7 3.435E-03 1.0820 1.5364 Note: No bending at the elevation of the flaw is assumed to occur TABLE 2: PICEP KEY INPUT PARAMETERS PARAMETER ANALYSIS VALUE Cross sectional shape Elliptical Youngs Modulus (psi) 2.9E+007 Differential Pressure (psid) 2575 Temperature (F) 600 External Pressure (psi) 14.7 Tensile Load (for COA Calc) Ibf 1310 Surface Roughness (in) 2.OE-4 Number of 90 degree turns 0 Number of 45 degree turns 0 Entrance Loss Coefficient 0.61 (default)

Friction Factor 0.0 (default)

Mode (for leakage and/or COD) 1 = Leakage only Tube diameter (inches) 0.625 Tube wall thickness (inches) 0.034