ML20056A347

Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed

ML20056A347
Person / Time
Site:	Beaver Valley
Issue date:	07/31/1990
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-90-001, IEB-90-1, NUDOCS 9008070081
Download: ML20056A347 (5)

Text

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F g g tw Fvw.,su mn Shggmaport, PA 5077-0004 JOHN D 9EBER vce P,esdent Nese Go+ 84128 3 0 62 %

July 31, 1990 U. S. Nuclear Regulatory commission Attn Document Control Desk' Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Socket No. 50-417, License No. NPF-73 Response to Bulletin 90-01 '

L Gentlemen:

The followAng information is provided to satisfy the reporting requirements of NRC Bulletin 90-01. '

ReDortina recuirement 1.a Confirm that Items 1, 2, 3, 4, and 5 of Requested Actions for operating Reactors have been completed.

Resconse Item 1 identification of transmitters in Safety Related or .1 L ATWS Applications) is completed. '

As specified in Item 2, DLC has identified transmitters from

'the suspect manufacturing lots which are in reactor protection or ESF systems. A replacement plan is in place, but

! -replacement is not complete.

DLC has reviewed the performance history of identified '

transmitters in safety-related or ATWS applications (Item 3).

Those exhibiting uncertain symptoms of oil loss have been placed on more frequent calibration schedules, are subject to a periodic calibration trend evaluation, and/or are-periodically compared to redundant channel information.

D Transmitters with symptoms of sluggish response and suste'1ed drift are planned for replacement.

9006070081 900733

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L Be:v0r Vallcy P wcr Statien, Unit No3. 1&2 Docket No. 50-334, License No. DPR-66  :

Docket No.,50-412, License No. NPF-73 Response to Bulletin 90-01

'Page 2 Item 4 describes a proposed enhanced surveillance program.

DLC has no plans for detecting sluggish response via actual planned or unplanned transients or tests since installed ability to gather such information is very limited. Detection  ;

of sluggishness during calibration activities is being performed and allows for a more controlled assessment of the transmitter's response. Detection of changes in process noise ,

does. not appear to be a reliable symptom of oil loss and is not being pursued. Other aspects of the described program '

have been implemented.  !

Item 5 (Justification for Continued operation) is completed. .

Reportina Reauirement 1.6 Identify the indicated manufacturer; the model number; the system

( the transmitter was utilized in; the approximate amount of time at pressure; the corrective actions taken; and the disposition (e.g.,

returned to vendor for analysis) of Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters that are believed to have exhibited symptoms indicative of loss of fill-oil or have been confirmed to have experienced a loss of fill-oil. This should include Model 1153 Series B, Model 1153 Series D and Model 1154 transmitters manufactured after July 11, 1989. ,

Resoonse ,

DLC has not identified Rosemount transmitters exhibiting clear symptoms of oil loss in any safety related or ATWS 3 applications.

Reoortina Reauirement 1.C Identify the system in which the Model 1153 Series B, 1153 Series D, and Model 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil are utilized and provides a l schedule for replacement of there transmitters which are in use in the reactor protection or eng.neered safety fettures actuation systcms.

Resoonse

l. Attachment 1 provides a table of transmitters identified by Rosemount which are insta11ad in reactor protection or ESF systems.

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, Benvcr Vallcy Pow;r Stcticn, Unit N 0. 1&2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Response to Bulletin 90-01 Page 3 ReDortina Recuirement 2 Model 1153 Series B, Model 1153 Series D and Model 1154 ,

transmitters that, subsequent to providing the response required by Item 1 above, exhibit symptoms of loss of fill-oil or are confirmed to have experienced a loss of fill-oil should be reviewed for reportability under existing NRC regulations. If determined not to be reportable, ' addressees are requested to document and maintain, in accordance with existing plant procedures, information consistent with that requested in Item ib) above for each transmitter identified.

ResDonse T'ansmitters identifited as having symptoms of oil loss in the D.ture will be evaluated f.or reportability ae required.

Documentation, which is consistent with reporting requirement Ib, will be maintained for a reasonable time period (several years) for instances which do not require reporting to the NRC.

Very truly yours, d .

7 ks--

. . S eber Vice President Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. A. W. DeAgazio, Project Manager .;

Mr. R. Saunders (VEPCO)

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ATTACHMENT 1-REACTOR PROTECTION OR ESF TRANSMITTERS FROM ROSEMOUNT SUSPECT LIST Serial Schedule for Mark Number Plant' ~ Model System ' Number ReDlacement FT-RC-436 BVPS-1 1154HP5RB Reactor Coolant 412771 8th Fa'neling Outage.

2CCP-FT-107B BVPS-2 1153DD5PA RCP Thermal 406044 2nd >c.Jeling Outage Barrier Flow 2QSS-LT-100A LePS-2 1153DB5PA RWST Level 405684 September, 1991.

2QSS-LT-100B BVPS-2 1153DBSPA RWST Level 405685 September, 1991 i

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l COMMONWEALTH OF PENNSYLVANIA) (

) SSt COUNTY OF BEAVER ) 1 I

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.3 On this ( (( day of /7dSL- , 1990,

• before me, (- A//u [, /b/14dI, ,

a Notar Public in and for said Commonwealth and County, personally appeared J. D. Sieber, who being duly sworn, deposed, and said that (1) he is Vice President - Nuclear 1

of -Duquesne Light, (2) he is duly authorized to execute and file'the foregoing Submittal on behalf of said company, and (3) the statements .

setforth in the Submittal'are true and correct to the best of his knowledge, information and belief. '

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