ML20198F768

Part 21 & Deficiency Rept SD-82 Re Core Exit Thermocouple Sys Provided by Westinghouse.Initially Reported on 850509. Total in-core Sys Error Falls Between 6 & 39.8 F.Final Rept Will Be Submitted by 851112

ML20198F768
Person / Time
Site:	Millstone
Issue date:	10/30/1985
From:	Opeka J, Sears C NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-85-497-000 F0860A, F860A, PT21-85-497, PT21-85-497-000, SD-82, NUDOCS 8511140425
Download: ML20198F768 (3)

Text

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L October 30,1985 Docket No. 50-423 F0860A Dr. Thomas E. Murley Regional Administrator U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

References:

(1)

3. F. Opeka letter to T. E. Murley, F0779A, dated June 6, 1985.

(2)

3. F. Opeka letter to T. E. Murley, F0788A, dated August 29, 1985.

(3) 3.

F.

Opeka letter to T.

E.

Murley, F0844A, dated September 30,1985.

Dear Dr. Murley:

Millstone Nuclear Power Station, Unit flo. 3 Reporting of Potential Significant Deficiencies in Accordance with 10CFR50.55(e):

Core Exit Thermocouples (SD-82)

In a May 9,1985 telephone conversation between your Mr. T. Rebelowski and our Mr. R. K. McCarthy, Northeast Nuclear Energy Company reported a potential significant deficiency in the construction of Millstone Unit No. 3 in accordance with 10CFR50.55(e). The potential significant deficiency involved the core exit thermocouple systems provided by Westinghouse.

As noted in Reference (1), while performing equipment qualification testing of the core exit thermocouples, Westinghouse noted that the total system error exceeded the errors assumed in the Westinghouse Emergency Response Guidelines. These guidelines were used to develop the Emergency Operating Procedures.

References (2) and (3) provided status concerning our efforts to resolve this issue.

Westinghouse has supplied the necessary qualification reports which include an evalyation of the results of additional testing demonstrating the equipments' ability to perform its safety function in a harsh environment.

8511140425 851030 PDR ADOCK 05000423 S

PDR 1%

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I The enclosed Attachment I details the accuracy error associated with the individual components comprising the incore thermocouple system.

If one J.

assumes that the individual component errors are independent of one another, the total system error for MP3 application is 39.80F as indicated in Attachment I.

However, this manner of calculating the system error was illustrated to be conservative by an Incore Thermocouple System Engineering Test conducted on a representative system. Although.the hardware associated with the system was unaged prior to its subjection to a standard 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LOCA ramp, a maximum a

i error of 160F was obtained indicating that the individual component errors are not independent of one another but dependent on one another. Therefore, the system error for the incore system would fall somewhere between 60F and 39.80F.

Based upon the above information, an evaluation will be performed to determine 4

the applicability for Millstone 3 application.

As such, a final report cannot be provided at this time. We will provide a final j

report concerning this matter by November 12,1985.

Very truly yours, i

NORTHEAST NUCLEAR ENERGY COMPANY 1

3. F. Opeka

\\

Senior Vice President i

i i

4 By: C. F. Sears -

]

Vice President i

cc:

Mr. 3. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 I

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6 ATTACEMENT I In order to calculate the syste= error, the following errors, as documented in E430, E44A anc WCAF-10920, vould be used for the various ec=ponents:

Recc :

Descristien Error ESI-44A/E44A Reference Junc: ion Bex(RJ3)

10*F WCAP-10920/WCAF-10919 Thermoccuple Connector (Lemo) 213.9'?

and Pot:ing Adaptor / Cable Splice Asse=bly ISE-43C/E42C Each Type K Ther=occuple 24.l*F (S:ainless Steel Potting Adap:0: vich Splice)

ISI-43C/I43C Each Coppe Ther=occuple

6.7'T (Stainless Steel Fo::ing Adapter with Splice)

ISE-43C/E43C RT3 Fo::ing Adapter vi:h

1.0*F Splice The to:al sys:e= er:c: vould be calcula:ed as fellows:

1 Reference June: ice Sex (RJ3)

10*F 1 Ther:cecuple Conae :cr (Le=0) and Pe::ing

13.9*F Adap:::/ Cable Splice Assembly 2 (Each) Type K Thermocouple Stainless Steel

8.2*F Fot:in; Adapter vi:h Splice 1 (Esch) Copper Ther=cccuple 5: sinless 5: eel

6.7*?

Pc::ing Adap:cr with Splice 1 RTD Po::ing Adap:or vi:h Splica

1.0*F Total Sys:e= Error 39.8'?

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