ML19344E474

Responds to IE Bulletin 80-16 Re Rosemount,Inc Pressure Transmitter Misapplication.Feedwater Flow Transmitters Indirectly safety-related & Used Primarily for Plant Startup & Shutdown.Erroneous Indication Not Expected

ML19344E474
Person / Time
Site:	Cooper
Issue date:	07/24/1980
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
IEB-80-16, NUDOCS 8009020102
Download: ML19344E474 (4)

Text

. '

bec to DAC:ADM:

CENTRAL FILES

\ -

PDR:HQ

m. .-

M LPDR

'N COOPER P'^

0 d

Nebraska Public Power District "

* * "A"Ep,2 N5[C c

.. ~~. . -. s July 24, 1980 Mr. Karl V. Seyfrit, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Subject:

IE Bulletin No. 80-16; Potential Misapplication of Rosemount, Inc. Models 1151 and 1152 Pressure Transmitters with Either "A" or "D" Output Codes

Dear Mr. Seyfrit:

This letter is written in response to the subject bulletin. The fol-lowing items are the Nebraska Public Power District's (NPPD) responses to the license actions described in the bulletin fot- our Cooper Nuclear Statio (CNS) power reactor facility.

Item 1 Determine if your facility has installed or plans to install Rosemount, Inc. Model 1151 or 1152 pressure transmitters with output codes "A" or "D" in any safety-related application.

Response

NPPD has installed several of the 1151 differential pressure trans-mitters in fluid systems at CNS. The installed transmitters are used for feedwater flow, control rod drive water flow, RHR shutdown reactor head cooling flow and several off gas pressure and flow instruments. Of these applications, only the feedwater flow transmitters are indirectly safety-related through their use in power range =onitor calibration.

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 pressures that could result in anomalous output signals 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 8009020joSL

,.o ,

Mr. Karl V. Seyfrit July 24, 1980 Fage 2.

design basis assumption. The safety-related application shall include control, protective or indication functions. If any safety-related application does not conform to the above requirements, address the basis for continued 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 an-alysis should include the effects of postulated pressure transmitter maloperation as it relates to indication, control and protective func-tions. The analysis shall address both incorrect automatic system operation and incorrect operator actions caused by erroneous indica-tions. Address the conformance to IEEE 279, Section 4.20, in your analysis. Include in your analysis the following table:

a. 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.

Response

At Cooper Nuclear Station reactor feedwater flow indication is used to calibrate the average power range monitors (at least once per week when operating) and the local power range monitor (at least once per six weeks when operating). Feedwater flow is also used in core thermal power calculations which, in turn, are used to measure safety margins during reactivity changes. Each of these actions is performed by con-trol room operators or reactor engineers. It is highly unlikely that these operations would be initiated or continued during severe transient or accident conditions.

During all conditions of operation, flow through the feedwater piping is limited by the water supplied by the condensate booster pumps (3 pumps X 7500 gpm/ pump = 22,500 gpm). Significant reverse flow from the reactor is prevented by four in-line check valves (two valves per supply leg).

Feedwater flow indication is used primarily during plant startup and shutdown. Since these are low flow conditions, erroneous indication is not expected.

4 Mr. Karl V. Seyfrit July 24, 1980 Page 3.

Because of the impossibility of achieving suf ficient flow to produce anomalous output signals, the feed flow instruments at CNS meet the requirements of IEEE 279, Section 4.20.

The attached table provides the required information.

I Item 3 Submir 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

Not applicable.

NPPD is using the Rosemount transmitters as replacements for installed instruments which can no longer be obtained from General Electric, the original vendor., The instruments are being replaced on an as-needed basis. Our future use of these transmitters will be dictated by our needs, by the analysis of the instrument uses based on the subject bulletin and by Rosemont's eventual repair actions.

Approximately eight (8) manhours were spent in preparation and review of this report. No corrective actions were required.

If you have any questions regarding the enclosed information, please contact me.

Sincerely, J. M. Pilant Director of Licensing and Quality Assurance JMP:WEC:cg Attach.

cc: U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555

TABLE:

Trans. Range Trans. Range Value of Prac. Variable Limit Setting Range Proc. To Produce Anomalous Service /

Instrument Model No. (psid) (psid) Variable (1bm/hr) Indication (Ibe/hr) Function RFC- FT-50A 1151DPCB22B1F1 100 42 (1) 0-4.8 X 10 7.1 X 10 6 3,

(2)0-5.0X10[

6 RFC-FT-508 1151DPCB22B1F1 100 42.3 (1) 0-4.8 X 10 66 7.1 X 10 3, (2) 0-5.0 X 10 18 Feedwater Flow - APRM and LPRM calibration, core thermal power calculations, indication i

1 9

4 e

e