ML18026B222
| ML18026B222 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/20/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409260319 | |
| Download: ML18026B222 (6) | |
Text
REGULATORY NFORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR:8409260319 DOC ~ DATE: 84/09/20 NOTARIZED: YES DOCKET FACIL:50 259 Browns Ferry Nuclear Power Stationi Unit li Tennessee 05000259 50 260 Browns Ferry Nuclear Power Stations Unit 2< Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stations Unit 3i Tennessee 05000296 AUTH BYNAME AUTHOR AFFILIATION MILLSr L ~ M ~
Tennessee Valley Author ity REC IP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Director.
SUBJECT:
For wards status info re request for exemption from 10CFR50i App J covering instrument lines<Type B testing of containment airlocks 8
Type C testing of,traversong in-cote probe sys valves, DISTRIBUTION CODE: A006D'OPIES RECEIVED:LTR,.
ENCL SIZE:
TITLE:
OR Submittal: Fire Protection NOTES:NMSS/FCAF
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE S740t 000 Chestnut Street Tower II September 20, 198II Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 By previous correspondence between TVA and
- NRC, we have requested exemption from the requirements of 10 CFR Part 50 Appendix J for the Browns Ferry Nuclear Plant.
There have been a series of recent telephone conferences between our staffs in which we have informed your staff regarding the status of Browns Ferry and which exemptions are still needed.
Enclosed is the information which was provided verbally to your staff. It is our understanding that your staff is close to documenting resolution of this issue.
If you have any questions, please get in touch with us through the Browns Ferry Project Manager.
Very truly yours, TENNESSEE VALLEY AUTHORITY Subscrib 'ug sworn to me t s
day f fore L.. Mil s, Ma ager Nuclear Licensing 198tI.
Near y Public'y Commission Expires Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
PDR An Equal Opportunity Employer o>>
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ENCLOSURE STATUS INFORMATION REGARDING REQUEST FOR EXEMPTION FROM 10 CFR 50 APPENDIX J
..BROMNS FERRY NUCLEAR PLANT Instrument lines - Instrument systems (instrument lines and instruments) are considered to be extensions of the primary containment boundary and thus will be tested by exposure to the differential pressure during the Type -A test.
No exemption is required.
Draining and venting of the seal water supply of the reactor recirculation pumps during Type A testing - Modifications were made to allow draining and venting of the seal water supply to the reactor recirculation pumps during Type A and C testing.
No exemption is required.
Type B testing of containment airlocks - Modifications have been made to facilitate testing of the personnel airlock doors at a pressure of Pa at six-month intervals.
No exemption is required.
Test airlock doors at 2.5 psig after each opening - The containment airlocks are tested at 2.5 psig within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. after each opening or every 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> s during periods of frequent openings.
This is reflected in BFN's technical specifications or revisions to the technical specification which have been requested to reflect this. It is also consistent with Appendix J.
No exemption is required.
Reverse direction Type C testing of isolation valves FCV-1-55, FCV-71-2, and FCV-73 This exemption is still requested.
Reduced pressure Type C testing of main steam isolation valves-Because of the unique design of the main steam isolation valves, they will continue to be tested at 25 psig by pressurizing between the valves.
It is TVA's understanding that this is acceptable to NRC.
Type C testing of 59 valves with water in lieu of air or nitrogen as a medium - These 59 valves are Type C tested in accordance with Appendix J.
No exemption is"required-Type C testing of the reactor building closed cooling water valves 70-74 and 70-506.
This exemption is still requested.
Type C testing of traversing in-core probe (TIP) system valves - The TIP valves will be Type C tested in accordance with Appendix J.
No exemption is required.
The modification to the nitrogen supply to the trip indexers has not been made;
- however, the existing valves in that line will be Type C tested.
Summing the leakage from Type C tests - Mhen Type C testing containment isolation valves, leakage paths are summed to verify that the total leakage is less than 0.60 La.
The "as left" path leakage assumed to be the greater leak rate of the two valves in series.
This is conservative and is in accordance with the requirements of Appendix J.
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