ML20054J690

Provides Response to 820427 Request for Addl Info Re Environ Qualification of safety-related Electrical Equipment

ML20054J690
Person / Time
Site:	Maine Yankee
Issue date:	06/24/1982
From:	Garrity J Maine Yankee
To:	Clark R Office of Nuclear Reactor Regulation
References
TASK-2.D.3, TASK-2.E.1.2, TASK-2.F.1, TASK-2.F.2, TASK-TM JHG-82-111, MN-82-120, NUDOCS 8206290449
Download: ML20054J690 (4)

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(207) 623-3521 wg June 24, 1982 MN 82-120 JHG-82-lll United States Nuclear Regulatog Commission Washington, D. C. 20555 Attention:

Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch #3 Mr. Robert A. Clark, Chief

References:

(a) License No. OPR-36 (Docket No. 50-309)

(b) USNRC Letter to MYAPCo, dated April 27, 1982 (c) MYAPCo Letter to USNRC, dated February 11, 1982, MN-82-25 (d) MYAPCo Letter to USNRC, dated January 15, 1982, MN-82-04 (e) MYAPCo Letter to USNRC, dated June 3,1982, H4-82-108 (f) MYAPCo Letter to USRNC, dated February 25, 1982, MN-82-34

Subject:

Environmental Qualification of Safety-Related Electrical Equipment - Request for Additional Information

Dear Sir:

In response to your letter, Reference (b), the following information is provided:

Item A.l.MM RC-9: We will submit the report on the in-core instrumentation test and the supporting documentation for the associated electrical connections by October 1, 1982.

HPSI-8: The document associated with the NUS Qualification Document Review Package for this component was requested and submitted under Item A.1.h.

Item A.3 Two ELEC worksheets do not contain information with respect to the specified operating time. Reference (c) stated that these components have the same operating time as that listed on the worksheets of the equipment with which they are associated. This associated equipment is listed below:

[g6Yb ELEC-13: See Worksheets CAAS-1, CVCS-2, CVCS-3, LPSI-3, MG-1, PCC-1, PS-1, PS-3, and PV-2.

ELEC-14: See Worksheets CAAS-2, CLMS-5, CVCS-5, CVCS-6, CVCS-7, CVCS-8, HPSI-4, HPSI-5, LPSI-5, MG-3, MG-4, MS-1, MS-2, PCC-4. PS-2, PS-4, PV-3, RC-8, and SCC-2.

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MalNE VANKEE AVOMIC POWER COMPANY United States Nuclear Regulatory Commission June 24, 1982 Attention: Mr. Robert A. Clark Page 2 The most restrictive operating time for these components under DBE and

!ELB conditions is "long term."

Item B.1.a.

TMI Action Plan equipment installed as of 1/1/81:

PAM-9 Accustic Transmitter (II.D.3)

PAM-10 Acoustic Accelerometer (II.D.3)

It should be noted that RC-5 and ELEC-15, pressurizer heater distribution cabinet and cables (II.E.3.1), should be deleted from the list as they' are not required for accident mitigation, since the HPSI pump will be used to maintain system over pressure.

1 Item B.l.b.

TMI Action Plan equipment installed after 1/1/81:

PAM-2 Containment Radiation Detector (II.F.1.3)

PAM-6 Sump Level Transmitter (II.F.1.5)

PAM-7 Containment Pressure Transmitter (II.F.1.4)

PAM-8 Containment Pressure Transmitter (II.F.1.4)

Item B.l.c.

Provided in Attachment 1 is a correlation of all TMI related system component evaluation worksheet numbers with their respective NUREG 0737 item numbers.

Items II.E.4.2, II.E.3.1, II.G.1, II.E.4.1 and II.B. 3 did not require the installation of equipment in a harsh environment; therefore, worksheets are not necessary.

Item B.l.d.

As noted in the discussion above, worksheets have been provided for all installed equipment.

Item B.I.e.

-Installation dates have been noted in Attachment 1.

Item B.2 The reactor level instrumentation _ (II.F.2.3) was not previously identified and as engineering is still in progress, test reports and associated correspondence are not yet identified.

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MAINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission June 24, 1982 Attention: Mr. Robert A. Clark Page 3 Item B.3 This information has already been provided to the NRC in References (d) and (e).

We trust this information is satisfactory. However, should you have any questions please contact us.

Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY John H. Gdn y, e

r Director Nuclear Engineering Licensing RHG:pjp Attachment I - NUREG G737 - TMI Item #'s cc: Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103

United ' States Nuclear Regulatory Commission Attention:. Mr. Robert A. Clark ATTACENENT I Associated Elec.

NUREG-0737 Approximate Function Worksheet

' Equipment Item No.

Inst. Date Containment Hydrogen Monitor.

.PAM-1 Elec-3 II.F.1. 6 12/82(1)

Containnent Radiation Detector PAM-2 Elec.3,-6 II.F.1.3 7/81 Primary System Pressur( Transmitter PAM-5 Elec-3,-5,-6 II.F.2 12/82(1)

Sump Level; Transmitter PAM-6 Elec-3,-6 II.F.1.5 7/81 Containment Pressure Transmitter PAM-7 Elec-25 II.F.1. 4 3/82 PAM-8 Elec-3.

Acoustic Transmitter P44-9 Elec-3, II.D.3 1980

' Acoustic Accelerometer PAM-10 N/A II.D.3 1980 Primary System Temp. Transmitter RC-6

,Elec-3,-6 II.F.2 12/82(1)

In-Core Thermocouple RC-9 (2)

II.F.2 12/82(1)

Steam Generator Level Transmitter FW-1 Elec-3,-5,-6 II.E.1.2 12/82(3)

. Notes:

(1) Installation is planned for the next ' refueling outage, provided there are no changes in current equipment delivery schedules.

-(2) Design of this system is in progress. Documentation to be submitted by October 1, 1192. (Item A.l.MM)

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(3)' See MYAPCo. letter to USNRC dated February 25, 1982, MN 82-34.