ML20134H163

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Interim Deficiency Rept (CDR 85-00-10) Re Emergency Feedwater Sys High Flow Isolation Logic seal-in.Initially Reported on 850724.Seal-in for High Flow Signal Will Be Provided So Interlock Stays in Place Until Manually Reset
ML20134H163
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 08/01/1985
From: Johnson W
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
(CDR-85--10), (CDR-85-00-10), SBN-852, NUDOCS 8508280301
Download: ML20134H163 (3)


Text

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l j ( Wendell P. Johnson Vice President

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Pubuc Service of New HampeNr0 SB - 85 T.F. 02.2.2 New Hampshire Yankee Division United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard W. Starostecki, Director Division of Project and Resident Programs

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of July 24, 1985, W. N. Fadden and D. E. Groves (YNSD) to J. Grant (Region 1)

Subject:

Interim 10CFR50.55(e) Report; Emergency Feedwater System High Flow Isolation Logic Seal-In (CDR 85-00-10)

Dear Sir:

On July 24, 1985, we reported a 10CFR50.55(e) item to Region 1

[ Reference (b)]. The following information is provided under the reporting requirements of 10CFR50.55(e):

Description of Deficiency Emergency Feedwater (EFW) flow to a steam generator faulted by a Feedwater (FWLB) or Main Steam Line Break (MSLB) is isolated automatically with redundant isolation valves when high flow is detected. This is required to ensure flow to the intact steam generators, to limit the energy release to the containment and to conserve the water in the CST.

The isolation logic includes an interlock to block a ccncurrent high flow isolation of the nonfaulted steam generators, on a train basis, when a high l

flow condition exists. The final design does not seal-in the high flow j logic. The interlock will be removed automatically when the faulted steam generator's EFW isolation valves close and reduco flow below the high flow signal reset point. With the faulted steam generator isolated, the flow to l

the intact steam generators will increase above the high flow setpoint. This will result in the sequential isolation of emergency feedwater to all steam 8enerators.

Analysis of Safety Implications ,

The accident analysis for the FWLB and MSLB assumes that emergency feedwater flow to the intact steam generators is at design flow 1 minute after the event. A complete isolation and a 10 minute delay for operator action to open the isolation valves for the intact steam generators may result in steam generator dryout.

g82 301 850801 -

S OCK 05000443 hl PDR \

P.O. Box 300 Seabrook,NHO3874 Telephone (603)4/4-9521 yk er

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United States Nuclear Regulatory Commission

' Attention: Mr. Richard W. Starostecki Page 2

.The high flow signal seal-in was to be included in the design to prevent the sequential isolation of all steam generators. The seal-in was not included when producing the detailed design drawings. This is considered an isolated event.

Corrective Action We will correct this problem by providing a seal-in for the high flow signal so that the interlock will remain in place until manually reset from the Control Room. This will prevent closure of the remaining emergency feedwater isolation valves on the same power train. EFW will always be available to at least 2 steam generators. High flow isolation / logic seal-in will be alarmed. A final report will be submitted when the corrective action has been completed.

Very truly yours, ZW Wendell . Johnson Vice President ec: Atomic Safety and Licensing Board Service List Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 4

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