ML15113A425
| ML15113A425 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/24/1998 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| IEIN-97-080, IEIN-97-80, TAC-MA0739, TAC-MA0740, TAC-MA0741, TAC-MA739, TAC-MA740, TAC-MA741, NUDOCS 9803030216 | |
| Download: ML15113A425 (3) | |
Text
February 24, 1998 Mr. W. R. McCollum Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
STEAM GENERATOR TUBING SURVEILLANCE REQUIREMENTS TECHNICAL SPECIFICATION INTERPRETATION - OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 (TAC NOS. MA0739, MA0740, AND MA0741)
Dear Mr. McCollum:
By letter dated January 26, 1998, you described a Technical Specification (TS) interpretation related to repairs of the Unit 1 "A" steam generator tubes following the shutdown of Unit 1 on December 28, 1997, when the primary-to-secondary leakage rate exceeded the TS limit.
During discussions with the NRC staff, you explained that your interpretation of TS 4.17.4.d has resulted in the determination that the TS criteria were applicable for leakage from a degraded steam generator tube, but not for situations where the leakage is from a degraded plug or tube to-tubesheet weld(s). If leakage in excess of the TS limits is detected, TS 4.17.4.d describes criteria for expanding the number of steam generator tubes to be inspected. In accordance with NRC Information Notice 97-80, "Licensee Technical Specifications Interpretations," you submitted this interpretation and requested NRR concurrence.
For this situation, you did not increase the number of steam generator tubes to be inspected because the leakage was determined to be solely from a plug and from tube-to-tubesheet welds. The staff has reviewed your interpretation and determined that it is acceptable because performing additional nondestructive examinations of steam generator tubes would not help locate other plug or tube-to-tubesheet flaws. Approval, however, is limited to this case only.
We are not prepared to review its applicability to similar situations or other occurrences.
Therefore, our conclusion cannot be applied generically.
Sincerely, ORIGINAL SIGNED BY:
David E. LaBarge, Senior Project Manager Project Directorate 11-2 9803030216 980224 Division of Reactor Projects - 1/11 PDR ADOCK 05000269 Office of Nuclear Reactor Regulation PDR Docket Nos. 50-269, 50-270, and 50-287 cc: See next page Distribution:
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UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 24, 1998 Mr. W. R. McCollum Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
STEAM GENERATOR TUBING SURVEILLANCE REQUIREMENTS TECHNICAL SPECIFICATION INTERPRETATION - OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 (TAC NOS. MA0739, MA0740, AND MA0741)
Dear Mr. McCollum:
By letter dated January 26, 1998, you described a Technical Specification (TS) interpretation related to repairs of the Unit 1 "A" steam generator tubes following the shutdown of Unit 1 on December 28, 1997, when the primary-to-secondary leakage rate exceeded the TS limit.
During discussions with the NRC staff, you explained that your interpretation of TS 4.17.4.d has resulted in the determination that the TS criteria were applicable for leakage from a degraded steam generator tube, but not for situations where the leakage is from a degraded plug or tube to-tubesheet weld(s). If leakage in excess of the TS limits is detected, TS 4.17.4.d describes criteria for expanding the number of steam generator tubes to be inspected. In accordance with NRC Information Notice 97-80, "Licensee Technical Specifications Interpretations," you submitted this interpretation and requested NRR concurrence.
For this situation, you did not increase the number of steam generator tubes to be inspected because the leakage was determined to be solely from a plug and from tube-to-tubesheet welds. The staff has reviewed your interpretation and determined that it is acceptable because performing additional nondestructive examinations of steam generator tubes would not help locate other plug or tube-to-tubesheet flaws. Approval, however, is limited to this case only.
We are not prepared to review its applicability to similar situations or other occurrences.
Therefore, our conclusion cannot be applied generically.
Sincerely, David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: See next page
Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242 P. 0. Box 1439 Seneca, South Carolina 29679 J. Michael McGarry, Ill, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Robert B. Borsum P. O. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28242-0001 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621