ML19330B690
| ML19330B690 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/29/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-16, NUDOCS 8008050381 | |
| Download: ML19330B690 (5) | |
Text
Alabarna P5wer CoH;:any 600 Norm ism Sttset P:stO'f.ca Box 2641 W '^ '
- 3:rm:nram A:abast 3Ci' Te:ephone 205 323 5341 h-L@Tlf."g..
Alabama Power a: r.n c : v =m.
July 29, 1980 Docket No. 50-348 No. 50-364 Mr. James P. O'Reilly U. S. Nuclear Regulatory Commission Region.II
-101 Marietta Street fl. W.
-Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
In response to I.E. Bulletin No. 80-16, " Potential Misapplication of-
.Rosemount Inc. Models 1151 and 1152 Pressure Transmitters With Either
' A' or 'D'. Output Codes," dated June 27, 1980, Alabara Power Company submits the enclosed response for Units 1 and 2 of Farley Nuclear Plant.
l-If there are any questions, please advise.
Yours very truly, y
F. L;' Clayty, Jr'. f RWS/rt
- Enclosures -
cc: Mr. R. A. Thomas -
Mr. G. F. Trowbridge
.,Mr. L.:L. Kintner Mr. W. H. Bradford
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- Office of I a 'E Division of Reactor Operations Inspection Washington, D. C.
Office of I & E Division of Construction Inspection Washington,-D._C.
Mr. E. Reeves Mr.'M. D. Hunt, I & E, Region II Bo l
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- .8_.008'05098l
ENCLOSURE I' tem 1-Determine if your facility has installed or plans to install Rosemount Inc. Model 1151 or 1152 pressure transmitters with c.:; n codes "A" or "D" in any safety-related application.
Response
Eight (8) Rosemount Model 1152 transmitters have been anc wo (2) Model 1152 transmitters.are currently planned to be installed at Farley Nuclear Plant (see attached table).
Four (4) of the eight installed Model 1152 transmitters are shared between Units 1 and 2, two at the River Water Structure End two at the Service Water Pond.
Two Model 1152 transmitters are utilized on each unit's Refueling Water Storate Tank (total of 4).
Two Model 1152 transmitters are currently planned for installation during the second refueling outage in the Unit 1 Condensate Storage Tank.
No Model 1152 transmitters have been installed at Farley Nuclear Plant.
i Item 2 If it is determined that your facility has the transmitters described in 1 above in any safety-related application, determine whether they can be exposed to input oressures that could result in anomalous output rignals.
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during normal operation, anticipated transients, or design bases accidents.
If the affected transmitters can be exposed to input pressures that could result in anomalous output signals, perform a worst case analysis to determine whether the anomalous signals could result in violating any design basis assumption.
The safety-related application shall include control, protective or indication functions.
If any safety-related application does not conform j
to the above requirements address the basis for cintinued plant operation
.until.the problem is resolved and provide an analysis of all potential adverse system effects which could occur as a result of a postulated pressure transmitter 'maloperation described in Enclosure 1 of this bulletin.
In each instance, the analysis should include the effects of postulated trans-mitter maloperation as it relates to indication, control and protective functions.
The analysis shall address both incorrect automatic system operation and incorrect operator actions caused by erroneous indications.
A.ddress.the.confomance to IEEE 279, Section 4.20 in your analysis.
Include in your analysis the following table:
Ja. -Complete model number, b.
. Transmitter range limits.
c.
Transmitter range setting.
d.
Range of_ process variable measured for (1) normal and (2) accident conditions.
e.
Values of process. variable which could produce anomalous indication based upon your evaluation.
f.
Service / function.
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2
-Resoonse
' Engineering evaluation.has shown the postulated defects associated with the
-overpressure condition of the Rosemount transmitters-onjthe Service Water zPond, Refueling -Water Storage Tanks, and 'the-Condensa te Storage. Tank would not occur = at-Farley Nuclear Plant since the levels required to produce anomalous indications are not possible as shown in_th+ a:: ached table.
The transmitters utilized at the River Water Structure mignt be subjected to an;o'verpressure condition'if a bubbler tube were to become clogged.
The clogged tube would.cause indication of rapidly increasing river level..The rapid increase could be attributed to either flooding cr i spurious signal, i.
and resolved by observing the redundant level indicator, or by visual' inspection of the. river. The occurrence of a clogged bubbler tube would
.not result in a' violation of any design basis assumption.
f The equipment with which-all the Model 1152 transmitters at FNP are connected is vented to atmosphere and reverse pressure conditions should not occur.
.(See attached table.)
Item 3 Submit a complete description of all corrective actions required as a result of your analysis and evaluations, together with the schedule for accomplishing the corrective actions.
(
-Response-As addressed in Item 2, the postulated defect in Rosecount Model 1152 transmitters poses no safety problem at FNP and, therefore, no corrective action'is required.
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4 ATTACllMENT PROCESS LEVELS VARIAllLE REQUIRED TO' MODEL.
. RANGE RANGE.
RANGES PRODUCE SERVICE / FUNCTION'
// -
LIMITS SETTINGS
- 1) NORMAL POTENTIAL
- 2) ACCIDENT ANOMALOUS INDICATION 115'2DPSA22PB**
0-480 in.11 0
- 1) 0 - 40 ft. 11 0*
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CONDENSATE. STORACE TANK 2
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00 This transmitter is currently planned to be installed during the second refueling outage.
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