ML20062L476
| ML20062L476 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/23/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 8101300493 | |
| Download: ML20062L476 (3) | |
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TENNESSEE VALLEY AUTHORITY CH A T I A NOOG A TENN ESSE E 37401 1800 Chestnut Street Tower II January 23, 1981 Director of Licensing Attention:
Mr. Thomas A. Ippolito, Chief Operating Reactors Branch No. 2 U.S. Nuolear Reguistory Cecaission Slashington, DC 20555 Dear Mr. Ippolito!
In the Matter of the
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Docket Nos. 50-P59 Tennessae Valley Authority
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50-260 50-296 By letter of D. G. Eisenhut to Licensee deted Nove nber 23, 1980, TVA was requested to provide confirmation that the implementation dates spacified in NUREG-0619 "BWR Feedwater Nozzle end Control Rod Drive Return Line Nozzle Cracking," will be net.
Enclosed is our response for the Browns Ferry Nuclear Plant.
Based on the enclosure, we believe that continued operation of the Browns Ferry Nuclear Plant is justified and th* eperating licenses for Browns Ferry unita 1, 2, and 3 should not be codified, suspended, or revoked.
Very truly yours, TENNFSSEE VALLEY AUTHORITY
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L. M. Milln, Manager Nuclear Pegulation and Safety Subscr d
d sworn tg before me this [ U day of
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.g ENCLOSURE RESPONSE TO LETTER FROM D. G. EISENHUT j
TO LICENSEE DATED NOVEMBER 13, 1980 BROWNS FERRY NUCLEAR PLANT A.
Fecdwater Nozzle Cracking The following is our response to the applicable port ns of sections 4.1 through 4.4 of NUREG-0619.
1.
With reference to rerouting of the reactor water cleanup system (RNCU), the modification to provide inlet flow to all feedwater nozzles has been completed on all units.
2.
We will 'insta'll low-flow feedwater control valves on all 3 units by June 30, 1983, to satisfy the requirement in the subject NUREG.
3 We have previously reviewed our operating procedures and have revised them, where possible, to reduce feedwater-to-reactor water temperature differentials during all modes of operation. These revisions are complete with the exception of those revisions related to the feedwater low-flow control system modifications. The final revisions will be completed after installation of the feedwater low-flow modifications and before June 30, 1983.
4 We will revise our inspection progran to satisfy the inspection requirements of section 4.3 2.4 and table 2 in the subject NUREG. We will implement the revised program by June 30, 1983.
5.
In addition to the above action taken to satisfy the NUREG requiremente, we have purchased triple-sleeve spargers for changeout -
with the existing single-sleeve spargers in unit 1.
This modification is planned to be completed during the unit 1, cycle 4 outage scheduled for spring 1981. Browns Ferry units 2 and 3 presently have the triple sleeve feedwater spargers.
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Control Rod Drive Return Line Nozzle Cracking Our response to the applicable portions of Sections 8.1 throup 8.3 of the subject NUREG is as follows:
l 1.
Modifications have been completed for all three units at Browns Ferry as described in paragraphs 8.1(1) and 8.1(3) of NUR.?G-0619; i.e., the j
nozzles have been inspected and the return lines have been rerouted to the reactor watar cleanup system (RWCU) and are reaintained in a i
" valved out" configuration. Additional modifications will be I
performed as described in paragraphs 8.1(4)(a') and 8.1(4)(c'), with the exception of rerouting directly to the cooling-water header. This exception is justified on the basis that the intent of paragraph 8.1(4)(c') will be satisfied by replacing all carbon-a+ eel piping between the flow stabilizer loon and the cooling-watei+' header with stainless-steel piping. However, because of the lead. tine required for procurement of new components and the current schedule for units 1 and 3 outages, the additional modifications cannot be completed for all units at Browns Ferry until November 1, 1983.
Based on available knowledge of corrosion product forW,lon we are
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not able to identify any situation which would require. short tarm \\
careguards or compensating safety actions.
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s 2.
The requirements for postmodification testing and recurrent z
naintenance as described in Soc'lon 8.2(3) of the subjectdUREG will o
be acconplished by November 1, 1983, and a report on completiort of' 4
3 requirementswillbesubmittedwithinsixmonthsaftertheoutage,[
p allows completion of actions, as described in Section'8,3.
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