ML18036A465
| ML18036A465 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/02/1991 |
| From: | Ross T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9112100214 | |
| Download: ML18036A465 (11) | |
Text
December 2,
1991 Docket No. 50-260 LICENSEE:
Tennessee Valley Authority FACILITY:
Browns Ferry Nuclear Plant, Unit 2
SUBJECT:
SUMMARY
OF A MEETING llITH THE LICENSEE ON NOVEMBER 20, 1991, REGARDING SCHEDULER EXEMPTIONS FROll CERTAIN TYPE B AND C TESTS RE(}UIRED BY 10 CFR 50, APPENDIX J On November 20
- 1991, members of the NRC staff met with the Tennessee Valley Authority (TVAf at NRC headquarters in Rockville, Maryland, to discuss TVA's anticipated difficulties in complying with the testing requirements of 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing For Mater-Cooled Power Reactors,"
at the Browns Ferry Nuclear Plant (BFNP).
Appendix J currently requires that Type 8 and C tests "shall be performed during reactor shutdown for refueling but in no case at intervals greater than 2 years."
Because of previous delays in TVA's schedule for restart of BFNP, Unit 2, a
large number of Type B (about 40 electrical penetrations,
- bellows, and valve bonnets/packings) and Type C (about 80 valve seats) leak tests are approaching their two-year limit during the current fuel cycle.
TVA is planning to request a scheduler exemption from the Appendix J limit of two years for all Type B and C tests that are coming due during Cycle 6 operations.
This exemption would be effective until January 1993, which is when TVA plans to shut down Unit 2 for its next refueling outage.
Due to the large number of Type B and C tests involved, the tlRC staff requested to meet with TVA at the NRC headquarters in Rockvi lie, Maryland, to discuss applicable details.
Enclosure 1 provides a list of the NRC and TVA meeting attendees.
Enclosure 2 is a copy of TVA's presentation handout as distributed during the November 20, 1991 meeting.
No particular decisions were made by the NRC staff at this meeting.
The meeting's principle purpose was to inform the NRC regarding the details and scope of TVA's difficulties in complying with Appendix J and to prepare the staff for TVA's exemption request.
Enclosures:
- 1. Attendees List
- 2. TVA's Handout cc w/enclosures:
See next page Original signed by Thierry H. Ross, Senior Project Manager Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 91>21002>O 9>Xa02 PDR ADOCK 05000260 P
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Distribution NRC PDR Local PDR F. Miraglia J.
Partlow S.
Varga G. Lainas F.
Hebdon T.
Ross J. Williams J. Pulsipher C. McCracken J. Monninger M. Sanders B. Wilson J. Weschelberger P. Kellogg C. Patterson OGC E. Jordan ACRS (10) 12-G-18 12-G-18 14-E-4 14-H-3 8-D-1 8-D-1 8-D-1 RII 17-G-21 RII RII 15-B-18 MNBB-3701
i C
CC:
Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 400 West Summit Hill Drive Knoxvilie, Tennessee 37902 Mr. John B. Waters, Director Tennessee Valley Authority ET 12A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Yr. W. H. Kennoy, Director Tennessee Valley Authority ET 12A 400 West Summit Hill Drive KnoxviIle, Tennessee 37902 Mr. W. F. Willis Senior Executive Officer ET 12B 400 West Summit Hill Drive Knoxville, Tennessee 37902 General Counsel Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. Dwight Nunn Vice President, Nuclear Projects Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Dr. Mark 0. Medford Vice President, Nuclear Assurance Licensing and Fuels Tennessee Valley Authority 6B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. Edward G. Wallace
- Manager, Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority 5B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. 0. J. Zeringue, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Author ity P. 0.
Box 2000
- Decatur, Alabama 35609 Mr. R.
R. Baron, Site Licensing Manager Browns Ferry Nuclear Plant Tennessee Valley Author ity P. 0.
Box 2000
- Decatur, Alabama 35609 Mr. J.
A. Scalice, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35609
- Chairman, Limestone County Commission P. 0.
Box 188
- Athens, Alabama 35611 Claude Earl Fox, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Coamission 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Route 12, Box 637
- Athens, Alabama 35611 Tennessee Valley Authority Rockvi lie Office 11921 Rockville Pike Suite 402 Rockvi lie, Maryland 20852 Mr. Dan A. Nauman Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
ENCLOSURE 1
NRC-TVA MEETING BROMNS FERRY UNIT 2 NOVEMBER 20 1991 Attendee Thierry M. Ross Fred Hebdon Joe Ili1liams Jim Pulsipher Conrad McCracken John Monninger Paul Kellogg Raul Baron Ike Zeringue John Scalice Greg Pierce Hark Medford Roger Huston Or anization NRC/NRR/PD II-4 NRC/NRR/PD II-4 NRC/NRR/PD II-4 NRC/NRR/SPLB NRC/NRR/SPLB NRC/NRR/SPLB NRC/Region II TVA/BFNP TVA/BFNP TYA/BFNP TVA/BFNP TVA/Corporate TVA/Rockville
0 BROMNS FERRY NUCLEAR POT APPENDIX J EXEHPTION REQUEST DISCUSSION OUTLINE ENCLOSURE 2
I.
Unit 2 Recovery and Restart o
Restoration effort and restart program o
Extensive rework and testing of components and systems o
SPOC process o
Successful restart program o
Successful ILRT II.
Request for relief from Appendix J testing requirements o
Successful operations since conclusion of restart program have made a mid-cycle outage unnecessary.
o Approximately 278 components tested before restart o
To support SPOC process many were done early, this included support of the extensive MOYATS program.
o Presently a program is in place which will ensure that as many components as possible will be tested during forced outages.
Example:
During a forced two and one-half day outage at the end of October twenty-five (25) such components were tested.
4
lHI'NP'PPENDIX J page 2 of 2 III. Technical Basis for Request o
All components would fall within a 25K extension limit if performed under a different tech spec surveillance (longest duration is presently identified as 182 days two Demin Water check valves) o Air tested component Type B and C leakage is currently less than 17K of 0.6La (655.9scfh),
thus sufficient margin
(-65X to the TS limit) exists to absorb the increased leakage which may result from the requested exemption.
o The four (4) water sealed isolation valves included in this extension request have not experienced significant degradation.
o The current total water sealed leakage is less than 1.5X of the Tech Spec allowable of 28.65 cfh o
Several will require de-inerting the drywell and achieving cold shutdown for about 30 days prior to performing the tests IV.
Summary All efforts to complete remaining, required testing will be consistent with BFN/TVA's goals to meet all commitments
'nless extraordinary and usual situations exist.
Furthermore, postponing the testing will pose no significant safety impact as determined by our safety evaulation and assessment.
V.
Additional Considerations/questions