ML20134C312
| ML20134C312 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/30/1997 |
| From: | Jacob Zimmerman NRC (Affiliation Not Assigned) |
| To: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| Shared Package | |
| ML20134C314 | List: |
| References | |
| GL-95-05, GL-95-5, TAC-M92506, TAC-M92507, NUDOCS 9701310348 | |
| Download: ML20134C312 (3) | |
Text
. -...
January 30, 1997 Mr. D. N. Morey Distribution:
Vice Presid::nt - Farley Project Docket File ESullivan Southern Nuclear Operating PUBLIC OGC Company, Inc.
PD 11-2 Rdg.
ACRS Post Office Box 1295 SVarga EMerschoff, RII Birmingham, Alabama 35201-1295 JZwolinski PSkinner, RII
SUBJECT:
INTERIM PLUGGING CRITERIA 90-DAY REPORTS - JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M92506 AND M92507)
Dear Mr. Morey:
By letters dated February 2, 1996, and July 26, 1995, you submitted reports in accordance with the Technical Specifications for Joseph M. Farley Nuclear Plants Units 1 and 2,respectively, that summarized the results of your assessment of the eddy current inspection results with respect to the requirements established for voltage-based tube repair criteria. The reports assess the Farley Unit 1 and 2 steam generators at the end of Cycle 13 and Cycle 10, respectively.
The NRC staff, with technical assistance from its contractor, the Pacific Northwest National Laboratory (PNNL), has reviewed the 90-day outage reports.
Based on the independent assessment of the 90-day outage reports, the NRC staff concludes that the end-of-cycle (E0C) projections of the steam generator tube degradation for tubes affected by outside diameter stress corrosion cracking are acceptable per the guidance in Generic Letter 95-05, " Voltage-Based Repair Criteria For Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking" and the draft generic letter on voltage-based steam generator tube repair criteria, respectively. The cycle-specific amendments approving the use of voltage-based repair criteria for these units included a reporting threshold for the conditional probability of 1
tube burst of 1x10-2 Both your projections and those completed by PNNL l
estimated a burst probability below this threshold.
In addition, the l
estimates of the primary-to-secondary leakage during a postulated main steam line break were below the maximum allowable accident leakage. contains a copy of PNNL's final report summarizing its assessment of the 90-day outage report submitted for Farley Unit 1, and Enclosure 2 includes PNNL's report for Unit 2.
Sincerely, Original signed by:
MC RE CENE WY Jacob I. Zimmerman, eroject Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosures:
1.
Technical Letter Report Unit 1
(\\ j 2.
Technical Letter Report Unit 2 cc w/encls:
See next page 310105 To receive a copy of this document, indicate in the box:
"C" - Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDII-2 LA: PDII:2s EMCB b D:PDiln27 l
NAME JZIMMERMAN:cn fliERRP ESULLIVAN f2s HBERK0W DATE
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WASHINGTON, D.C. 20666-0001 January 30, 1997 4
Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
SUBJECT:
INTERIM PLUGGING CRITERIA 90-DAY REPORTS - JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M92506 AND M92507)
Dear Mr. Morey:
=
By letters dated February 2, 1996, and July 26, 1995, you submitted reports in accordance with the Technical Specifications for Joseph M. Farley Nuclear Plants Units 1 and 2, respectively, that summarized the results of your assessment of the eddy current inspection results with respect to the 4
requirements established for voltage-based' tube repair criteria.
The reports assess the Farley Unit I and 2 steam generators at the end of Cycle 13 and Cycle 10, respectively.
The NRC staff, with technical assistance from its contractor, the Pacific Northwest National Labaratory (PNNL), has reviewed the 90-day outage reports.
l Based on the independent assessment of the 90-day outage reports, the NRC staff concludes that the end-of-cycle (E0C) projections of the steam generator tube degradation for tubes affected by outside diameter stress corrosion cracking are acceptable per the guidance in Generic Letter 95-05, " Voltage-Based Repair Criteria For Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking" and the draft generic letter on voltage-based steam generator tube repair criteria, respectively. The cycle-specific amendments approving the use of voltage-based repair criteria for these units included a reporting threshold for the conditional probability of tube burst of 1x10'2 Both your projections and those completed by PNNL estimated a burst probability below this threshold.
In addition, the estimates of the primary-to-secondary leakage during a postulated main steam line break were below the maximum allowable accident leakage.
Enclosurc 1 contains a copy of PNNL's final report summarizing its assessment of the 90-day outage report submitted for Farley Unit 1, and Enclosure 2 includes PNNL's report for Unit 2.
Sincerely, e
~
, acob I.
immerman, Project Manager
" Project Directorate II-2 Division of Reactor Projects - I/II 4
Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosures:
1.
Technical Letter Report Unit 1 2.
Technical Letter Report Unit 2 cc w/ enc'is: See next page
Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant cc:
Mr. R. D. Hill, Jr.
General Manager -
Southern Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Aj1 uni, Licensing Manager Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-1295 Mr. H. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard 1
Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 4
434 Monroe Street Montgomery, Alabama 36130-1701 Chairman l
Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, NW., Suite 2900 l
Atlanta, Georgia 30323 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319