ML20245H459

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Requests Exemption from 10CFR50,App A,Gdc 57 Re Use of Check Valves in Auxiliary Feedwater Sys to Satisfy Closed Sys Isolation Criteria for Facility Containment
ML20245H459
Person / Time
Site: Beaver Valley
Issue date: 07/08/1989
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908170105
Download: ML20245H459 (7)
v • d • e


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Be ver Va ley Power Station Shippingport. PA 150770004 ce Pr u Nuce Group W 21 M 5255 July 8, 1989 l

L U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Request for Exemption to GDC-57 Gentlemen:

The purpose of this submittal is. to request an. exemption, pursuant to 10 CFR 50.12, from 10CFR50,-Appendix A,' General Design Criterion (GDC) 57.

This request specifically addresses the use of check valves in the Auxiliary Feedwater System which are proposed to satisfy the closed system ' isolation criteria for the Beaver Valley Unit No. 1 containment.

Duquesne Light Company has developed and implemented a Design Basis Reconciliation Program.

An evaluation of the Unit No. 1 Auxiliary Feedwater System was recently completed and resulted in a finding which was identified as a

deviation to GDC-57.

This deviation was a result of a plant modification, required for initial licensing in response to an Atomic Energy Commission (AEC) question, in which we committed to remove power from three (3) isolation valves (MOV-FW-158A,B,C) to satisfy single failure criteria (Attachment 1).

These

valves, therefore, do not fully comply with the GDC-57 as they are no longer remote-manual.

An early version of the original FSAR for Unit No. 1 states in Section 5.3.2,

" Penetration Classifications and Isolation Valve Arrangements" that the containment penetrations conform with the 1971 General Design Criteria, with certain exceptions.

FSAR Tables 5.3-1 and 5.3-1A identified penetration numbers 76, 77, and 78 as Class B penetrations.

These penetrations are for the main feedwater lines which include the auxiliary feedwater lines branching into them downstream of the main feedwater line containment isolation valves.

(Refer to the attached Figure 1

and UFSAR Figure 10.3-5.)

Valve numbers MOV-FW-156A,B,C and VGW-60A-Q (total of 3) were identified as

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the containment isolation valves for these penetrations.

A subsequent update to the Unit No.

1

UFSAR, Revision' 2 (1984),

correctly identified the VGW-60A-Q valves as MOV-FW-158A,B,C.

On approximately March 4,

1974, the AEC provided Duquesne Light company with AEC Regulatory Staff Position 36 to which we responded in FSAR Amendment 8

(4/26/74).

It was in response to this AEC position that we committed to remove power from MOV-158-A,B,C in order to satisfy the single active (electrical) failure criteria 890817010G 89070S Acol ADOCK0500gg]4 l

PDR P

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heaverValleyPowerStation,UnitNo.

1 Docket No. 50-334, License No. DPR-66 Page 2 stated in AEC position 36.

The MOV-158-A,B,C valves were identified as maintenance valves in our response to the AEC position and were not-considered as containment isolation valves as documented in the original issue of the Unit No.

1-Technical Specifications.

The Technical Specifications identified valves MOV-FW-151A,B,C,D,E,F as containment isolation valves.

While this modified configuration no longer met GDC-57, the configuration itself was acceptable to the AEC as evidenced by the design being licensed at Virginia Electric Power Company's North Anna plants.

(ie: use of a simple check valve as the outside containment isolation valve to satisfy GDC-57)

The piping class break from Safety Class 2 to Class 3 occurs upstream of auxiliary feedwater system check valve numbers FW-42, 43, and 44.

As can be seen on Figure 1 and UFSAR Figure 10.3-5, the Technical Specification containment isolation valves are located on Safety Class 3

piping which is not acceptable as'a containment boundary piping classification.

This request satisfies several different criteria applicable to 10CFR50.12(a)(2) which are:

(i)

To re-install the power leads to make the MOV-FW-158A,B, and C valves remote-manual would result in conflicts with other rules or regulations of the Commission.

(ii)

Plant modifications are not necessary to achieve the underlying purpose of the rule since similar configurations have already been determined to satisfy the rule.

(iii) Excessive costs would be incurred if plant modifications or re-analyses were performed.

We will process UFSAR changes during the next' annual UFSAR update pending final resolution of this issue.

If you have any questions regarding this submittal, please contact me or members of my staff.

Very truly yours,

.A D. Sieber Vice President Nuclear Group Attachments cc:

Mr. J.

Beall, Sr. Resident Inspector Mr.

W.

T. Russell, NRC Region I Administrator Mr.

P. Tam, Sr. Project Manager Mr. R. Saunders (VEPCO)

I

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ATTACHMENT 1 l

BVPS FSAR_

Amendment 8

't 4/26/74

)

l AEC R EGULATORY - STAFF - POSITION 36 (3/4/74)

With regard to the auxiliary f eedwater system we require that the system be capable of sustaining a

passive failure inside the containment and a

single active (electrical) failure outside containment..

We also require that the instrumentation,-

control-and electrical equipment pertaining to this system be designed to-conform with the requirements of IEEE 279-1971 and IEEE 308-1971.

RESPONSE-l i

There is no portion of the auxiliary feedwater' system (AFWS) 'per

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se which is located within the containment.

The system, with the exception of the primary plant demineralized water-storage tank

.and pump suction piping, is located in - the auxiliary _feedwater pump cubicle and main steam and valve cubicle.

The system-is designed. such that for any accident requiring the a

use of the AFWS, a single active (electrical) failure in the AFWS d

will not preclude the system's ability to perform its function.

In order to ensure this single failure protection, the power leads to the motor operators of the maintenance valves (MOV's 158 A,B,and c shown in Figure 10. 3-5) will be removed and operation of the, manual-handwheels will be administrative 1y controlled.

The positions of these valves are indicated in the control room.

With this change, ' the instrumentation, control, and electrical equipment of this system conforms to-the requirements of IEEE 279-1971 and IEEE 308-1971.

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