ML20082N875

Forwards Hd Hukill Re Emergency Feedwater Sys Flow Device Testing.Info Potentially Relevant to Plant Design & Procedures Phase of Proceeding

ML20082N875
Person / Time
Site:	Crane
Issue date:	12/06/1983
From:	Baxter T METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Chilk S NRC OFFICE OF THE SECRETARY (SECY)
References
NUDOCS 8312080003
Download: ML20082N875 (5)

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werTEm'S DenECT DL4L NuMSEm December 6, 1983 822-1090 Mr. Samuel J. Chilk Secretary U.S. Nuclear Regulatory Commission Washington, D.C.

20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No.1)

Docket No. 50-289 (Restart)

Dear Mr. Chilk:

Please find enclosed a copy of the following document, which includes information potentially relevant and material to matters under adjudication in the plant design and procedures phase of this proceeding, which is now before the Commission:

Letter 5211-83-346, November 23, 1983, H. D. Hukill, GPU Uuclear, to J. F. Stolz, NRC, EFW Flow Devices (D/P) Testing.

Respectfully submitted,

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Thomas A. Baxter Counsel for Licensee 1

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TAB:jah Enclosure cc:

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Docket No. 50-289 i,

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i SERVICE LIST Chairman Nunzio J. Pall =*ino Dr. Reginald L. Gotchy U.S. Nuclear Regulatory Cr==4==4m Atanic Safety and Licensing Appeal l

Washington, D.C.

20555 Board U.S. Nuclear Regulatory Ocnnission Comnissioner Victor Gilinsky Washington, D.C.

20555 U.S. Nuclear Regulatory M_ maim Washingtcm, D.C.

20555 Ivan W. 9nith, Esquire hinsioner 'Rrznas M. Ibberts Cbmi-n, Atcznic Safety and Licensing Board U.S. Nuclear Regulatory Cr==4=sion U.S. Nuclear Regulatory Ocnnission Washingtcm, D.C.

20555 Washington, D.C.

20555 h 4=sioner James K. Asselstfae U.S. Nuclear Regulatory Ccmimissica Sheldon J. Wolfe, Alternate Gaiman Atanic Safety and Licensing Board Washington, D.C.

20555 U.S. Nuclear Regulatory Ocnnission Washington, D.C.

20555 Ccenissioner Fr darick M. Bernthal U.S. Nuclear Regulator / Ctanission Mr. Gustave A. Lirs:iAm var, Jr.

Washingtcm, D.C.

20555 Atanic Safety and Licensing Board Docketing and Service section U.S. Nuclear Regulatory Ocnnission W =hington, D.C.

20555 Office of the Secretary U.S. Nuclear Regulatory Otanission Richard J. Rawson, Esquire Washington, D.C.

20555 Office of Enocutive Imgal Director U.S. Nuclear Regulatory Ocenissicn Gary J. Bdles, Esquire Washington, D.C.

20555 Chaiman, Atcmic Safety and Licensing Appeal Board John A. Iavin, Esquire U.S. Nuclear Regulatory Otanission Assistant Counsel Washington, D.C.

20555 Pennsylvania Public Utility Ocamission P. O. Bcot 3265 Dr. John H. Buck Harrisburg, PA 17120 Atomic Safety and Licensing Appeal Board Marjorie M. Aamodt U.S. Nuclear Regulatory Comnimaion R. D. 5 Washington, D.C.

20555 Coatesville, PA 19320 l,

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Douglas R. Blazey, Esquire Steven C. Sholly Chief Counsel Union of Concerned Scientists Department of Environmental Rescroroes 1346 Cuurdcut Avenue, N.W., #1101 514 Executive House, P. O. Box 2357 Washington, D.C.

20036 Harriah rg, PA 17120 l

ANGRY / M PIIC Ms. Iouise Bradford 1037 Maclay Street M ALERP Harrisburg, PA 17103 1011 Green Street Harrisburg, PA 17102 Chauncey Kepford Judith H. Johnsrud Ellyn R. Weiss, Esquire Envitumental Coalition on Nuclear Power Harmon & Weiss 433 Orlando Avenue 1725 Eye St., NW, Suite 506 State College, PA 16801 Washington, D.C.

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Wnter's Dire : Dia Nu.Det.

November 23, 1983 5211-83-346 J

Office of Nuclear Reactor Regulation Attn:

J. F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 EW Flow Devices (D/P) Testing In our submittal of August 25, 1983 (5211-83-231), GPUN described the differ-ential pressure (d/p) flow measuring system using annubars for the Emergency Feedwater System.

In item III.F of the enclosure to that letter, we indicated that "the flow instrumentation are reliable and accurate and are designed to monitor the full range of system flow requirements".

Recent tests perforned on the EW system in conjunction with OTSG testing indicated oscillations at low flow conditions (less than approxi=ately 100 sp=) outside the 1 10% criteria.

GPUN's preliminary evaluation conclude.* that cavitation on the outlet of the feedwater flow control valve during low flow conditions caused the oscillations.

Tests indicate that at high flow conditions (above 400 gpm) the d/p flow instru-ments are within i 10%.

We have concluded that the oscillations at low flows de not af fect the functional capability of the EW system or the ability of the operator to take proper action and are, therefore, acceptable for the following reasons:

a.

T.mergency feedwater flow is initiated auto =atically on loss of all RCS pumps or both feedwater pumps.

Should initiation occur, the accuracy of the instrument would be within allowable limits for high flows to confirm that EW flow is sufficient.

For low flow conditions the flow instrunent confirms the proper initiation of EW (i.e. flow is occuring).

Accuracy of flow rate is not necessary at low flows.

In addition, EW flow would be automatically controlled by tne ICS on steam generator l

1evel, not EW flow rate. Based on this, Ine :.:n flow devices will provide indication to the operator that the syste is functioning.

GDU Nuclear Corporation is a subsidiary of the Genera: utii: U:iitties Cctrora:icr

2_

b.

During manual takeover of the emergency feedwater systen, the operater does not control feed flow based on this flow indicating instrument alone.

Energency Feedwater continues te be contrc11ed based on CTSG level and pressure (level to prevent over/under-filling and pressure to prevent over-cooling).

The operator's attentien is focused on these instruments when regulating flow. The emergency feedwater flow indication provides only one positive means of verifying t' hat flow is being delivered to the steam generators; it is not relied upon to regulate flow.

This clarification describes the EFW d/p flow system as currently installed and tested. Therefore, GPUN concludes that the EFW flow indicating system is acceptable and meets the requirements of NUREG 0737 and our commitment reflected in the Partial Initial Decision of December 14, 1981. However, during the Power Esca-lation testing. data vill be collected and used to' assist the operators in under-standing how the EW flow devices are expected to perform under various EFR flow conditions.

Sincerely, o

l H. D.

u 11 Director of TMI-l EDH:LWH:vj f:j rg ec:

J. Vsn Vliet R. Conte

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