ML20247Q460
| ML20247Q460 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/19/1989 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Buggs E AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20247Q464 | List: |
| References | |
| NUDOCS 8909280202 | |
| Download: ML20247Q460 (4) | |
Text
.
1
~
^
m w,
'o - *
' ~ ~
' g UNITED STATES g
g NUCLEAR REGULATORY COMMISSION j
g p
WASHINGTON, D, C. 20555 l
/
SEP 191989 l'
Mr. Eugene D. Buggs 409-Cameron Circle, #2402 Chattanooga, Tennessee 37402 4
Dear Mr. Buggs:
This letter is in reply to your August 8,1989 letter to Chaiman Carr of the U.S. Nuclear Regulatory Commission.
In your letter you restated your concerns regarding tne reactor water cleanup (RWCU) system sample panel which is being installed at the Browns Ferry Nuclear Piant(BFN).
You also expressed concern regarding the relation of the radioactive water flowing through the RWCU sample panel to the BFN design basis.
The RWCU sample panel is designed to return the water used for on-line chanistry monitoring to the reactor coolant system via the sample return system. There is no reactor water inventory reduction associated with the on-line sampling fur -tion of the RWCU sample panel. The only reductions in reactor water inventory associated with this panel will result from tne grab samples which must be routinely drawn in order to satisfy BFN technical specification chemistry monitoring requirements. The BFN design basis therefore does encompass the water flows associated with the RWCU sample panel.
We assessed the potential of the glass rotameter to rupture due to mechanical failure of the Veriflow pressure regulating valve (PRV). This particular valve, as it is being installed per the engineering change notice, will be set for a maximum outlet pressure of 100 psig. Hence, should a mechanical failure occur, the maximum pressure to be seen by the downstream piping system would be 100 psig, which would therefore pose no threat of rupturing the rotameter, which is rated at 250 psig. We also evaluated a potential rupture of the rotameter due to an operator putting the PRV on-line too rapidly. The operating procedure for this panel will adequately ensure that the operator will bring the pressure reducer on-line gradually. Further, the design of the PRV is such that, should the upstream side of the pressure reducer be subjected to a rapid pressurization to full process pressure, the downstream side of the reducer would have a peak overpressure of 10 psig above the maximum outlet pressure setting, or 110 psig. Again, in such a scenario, the structural integrity of the glass rotameter would not be challenged.
bf~oI gp2pg gysg Y
H
f Mr. Eugene D. Buggs In summary, as we stated in our lettors to you dated April 14 June 15. July 3 and August 3. 1989, we have reviewed TVA's efforts related to your concerns. These efforts are sti.11 in progress. The NRC staff will review TVA's final resolution of the issues regarding BFh.
We appreciate your raising these concerns to the NRC. We feel that we have addressed your concerns on this issue in this and previous correspondence.
If you have or are aware of other concerns not previously brought to our attention which could impact on the safe operation of any of the TVA facilities, please contact Paul Cortland at (301) 492-0754 or by mail at the U.S. Nuclear Regulatory Commission Mail Stop OWFN 7-D-24 Washington, D.C.
20555.
Thank you for your time and attention to this matter.
Sincerely, MLul st ued by S
UDis M. Cruteyr;,m Dennis M. Crutchfield, Associate Director for Special Project's Office of Nuclear P,eactor Regulation DISTRIBUTION DCB (50-259/260/296, 50-327/328)
NRC PDR LPDR ADSP R/F TVA R/F TVA T/P R/F DMorris (EDO #4698)
TMurley/JSnf ezek FMiraglia FGillespie JPartlow DMossburg (EDO #4698)
SECY (89-0749)
DCrutchfield BDLiaw RCPierson BWilson GHubbard PCastleman 0GC TQuay
- For previous concurrences see attached ORC OFC : TVA:P5B*
- TVA:PSB/BC*: TVA:AD/IP* : hRR:TVA/D* : hR DSP NAME :PICastleman : GHubbard
- RCPierson : BDLiaw
- DCrute ield:
1.......-----...--------......-..--......-----....-....--....................--.........--------
9////89 DATE : 9/14/89
- 9/14/89
- 9/14/89
- 9/14/89
[-/ '
l 0FFICIAL RECORD COPY
. -_ _~___ ___-_-_
i I:
WErog'of -
j UNITED STATES
.s.
, ;,f -
g NUCLEAR REGULATORY COMMISSION n
A,,.
j WASHINGTON, D. C. 20555
, - -Q g
EDO Principal Correspondence Contro
'FROM:
DUE:
EDO CONTROL: 0004698 DOC DT: 08/08/89 FINAL REPLY:
' EUGENE D.
BUGGS
~TO:
CHAIRMAN CARR FOR SIGNATURE OF:
- GRN CRC NO: 89-0749 DESC:
ROUTING:
INADEQUATE ENGINEERING CALCULATIONS AT TVA
.DATE: 08/21/89 ASSIGNED TO:
CONTACT:
NRR MUR'. EY SPECIAL INSTRUCTIONS OR REMARKS:
FOR APPROPRIATE ACTION.
REF: ED0 4610 NRR RECEIVED: 8/21/89 ACTION:
ADSP:CRUTCHFIELD NRR ROUTING:
MURLEY/SNIEZEK MIRAGLIA PARTLOW GILLESPIE MOSSBURG
m
,e
^;,',
,-t
?
)
e
- ( ; j, Il j..
,4
[*
' +
v.
-OFFICE'OF THE SECRETARY IV CORRESPONDENCE CONTROL' TICKET b'
b PAPER' NUMBER:?
CRC-89-0749 LOGGING DATE:.Aug 21.,89-(ACTION OFFICE:
EDOt
' AUTHOR::..
' Eugene Boggs-t AFFILIATION:.
'TN (TENNESSEE) 1 l
= LETTER DATE:
Aug-8L89
' FILE CODE:..ID&R-5 TVA
SUBJECT:
. Inadequate' engineering calculations at.TVA--
ACTION:;-
Appropriate DISTRIBUTION:
-DSB SPECIAL HANDLING: None n
- NOTES:
DATE DUE:.
SIGNATURE:'
DATE SIGNED:
-AFFILIATION:-
Revd Off. EDO Date O ~M ^
Time -
I/ M
.. _ _ _ _ _ _ _ _ -