ML19323C562

Application for Amend 46 to Ol,Providing Proposed Tech Spec Changes.Revisions Include Addition of safety-related Hydraulic Snubbers to Table 3.7-4 & Mod of Surveillance Requirements for Auxiliary Feedwater Sys.Affidavit Encl

ML19323C562
Person / Time
Site:	Beaver Valley
Issue date:	05/14/1980
From:	Dunn C DUQUESNE LIGHT CO.
To:
Shared Package
ML19323C563	List: ML19323C562 ML19323C564
References
TAC-10007, TAC-11055, TAC-42091, TAC-42200, TAC-42924, TAC-43002, TAC-43063, TAC-44632, TAC-8132, NUDOCS 8005160331
Download: ML19323C562 (4)

Text

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May 14, 1980 Director of Nuclear Reactor ?.egulaticn United States Nuclear Regulatory Ce mission Attn:

Mr. Steven A. Varga, Chief Operating Reactors 3 ranch No. 1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Request For Amendment No. 46 to Operating License Gentlemen:

Enclosed are three (3) signed originals and ten (10) copies of proposed changes to the Beaver Valley Power Station, Appendix A Technical Specifications.

These changes provide for (1) addition of safety-related hydraulic snubbers to Table 3.7-4 as a result of plant modifications, (2) re-vised surveillance require ents for the auxiliary feedwater system in accord-ance with NRC guidelines, (3) codification of the surveillance requirement for auxiliary feedwater flow rate indication at the Remote Shutdown Panel, (4) installation of the Control Room Chlorine Detection System, (5) verifi-cation of containment liner weld channels and plugs integrity, (6) instal-lation of station service bus underveltage relays, (7) modification of the reactor coolant pump breaker position anticipatory reactor trip logic to prevent spurious reactor trips and (S) redefining the tern OPERA 3LE as request-ed in NRC correy.ondence.

Also included with this submittal is the revised proposal for license amendment which will incorporate the requirements of 10 CFR 50, Appendix I for inclusion in Appendix A of the Technical Specifications (See Attach-ment A).

This change was criginally submitted on April 11, 1979.

Co==ents were received from Mr. D. Wigginton in December 1979.

All of these comments have teen inccrporated into this present submittal except for the co==ents noted in Attachment 3, Radiological Effluent Technical Specifications. The specification for an oxygen analyzer has been deleted from this sub=ittal. We are atte=pting to provide a reliable system, and we will submit a technical specification for the oxygen requirements as soon as the system is installed cnd operable.

THIS DOCUMENT CONTAINS s'h 6 ' ' y[p 0

l POOR QUAUTY PAGES ay #o N &

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1 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Request For Amendment No. 46 to Operating License Page 2 i

Safety Evaluation Attachment C - This change is necessitated by the addition of snubbers to plant systems during plant modifications. The OSC and ORC have reviewed the change and have determined that no unreviewed safety question results, and the change will enhance plant safety by requiring surveillance testing of the in-stalled snubbers.

1 Attachment D - This change is in response to NRC guidelines set forth j

with regard to auxiliary feedwater subsequent to TMI-2.

The OSC and ORC l

have reviewed the change and have determined it results in improved plant j

safety. The change will result in a more thorough verification that the j

auxiliary feedwater system is operable following maintenance or surveillance testing.

Attachment E - This change is requested because auxiliary feedwater flow indication during normal operation and during auxiliary feedwater pump opera-

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tion on recirculation indicated zero. Therefore, the surveillance required by the specification is not meaningful.

In order to perform the surveillance correctly, the AFW system must be operating and feeding the steam generators.

This can be accomplished during plant startup following an extended outage.

The OSC and ORC have reviewed this change and have concurred that no unreview-ed safety question results from the change.

Attachment F - The Beaver Valley Power Station Operating License con-tains a condition which requires installation of a control room chlorine detection system during the first refueling outage. Concurrent with the system installation, this technical specification change is being submitted.

The OSC and ORC have reviewed the change and have concurred that the change enhances the plant safety posture. Also included with this attachment are system logic diagrams and manufacturers data for the chlorine detection system.

Attachment G - Thic change is requested for verification of containment liner weld channels and plugs integrity. The change will require a visual inspection of all accessible surfaces, liner test channels and the dome area for any indication of liner degradation. The OSC and ORC have reviewed the change and determined no unreviewed safety question results from the change.

Attachment H - This change is requested as a result of installation of undervoltage relays on the Class IE 4160 volt and 480 volt buses. These relays will provide protection for Class IE electrical equipment against a sustained undervoltage condition. The OSC and ORC have reviewed the change j

and determined plant safety is improved by the requested change.

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Request For Amendment No. 46 to Operating License Page 3 Safety Evaluation (continued)

Attachment I - This change is requested to prevent spurious reactor trips which occur when the output of the vital bus inverters is inadvertently short-circuited. The original design of the RCP breaker position trip caused a reactor trip whenever the plant was above setpoint P-8 and one RCP breaker opened. This was an anticipatory trip which functioned in addition to the low RCS flow trip. This RCP breaker position trip was not considered in the plant safety analysis for any accident conditions. The proposed change will elimi-nate the RCP breaker position trip with a single breaker open above P-8.

However, the RCP breaker position trip with two out of three breakers open above setpoint P-7 will be retained. The OSC and ORC have reviewed the change and have determined that since the RCP breaker position trip was a redundant trip and was not considered in the safety analysis, no unreviewed safety question results from the change.

Attachment J - This change is in response to NRC correspondence con-cerning the definition of OPERABLE and the operability of plant systems, subsystems, trains, components or devices. The OSC and ORC have determined that no unreviewed safety question results from the change.

In accordance with 10 CFR 170.22, we are enclosing a check in the amount of $12,300 for this Class IV license amendment.

l Very truly yours, me C. N. Dunn Vice President, Operations Attachment cc:

U.S. Nuclear Regulatory Commission c/o Document Managemeat Branch Washington, DC 20555 Mr. D. A. Beckman U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 4

(CORPORATE SEAL)

Attest:

Jupu

.ll AA T. Welfer, Jk.

Secretary COMMONWEALTH OF PENNSYLVANIA)

) SS:

COUNTY OF ALLEGIENY On this

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day of N/1 $/

1980, before me, Tfourrm w nunwwnw a Notary Public in and for said Commonwealth and County, personai'iy appeared C. N. Dunn, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.

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DONALD W. SHANNON, NOTARY PUBLIC PITTSBURGH, ALLEGHENY COUNTY MY COMMISSION EXPIRES JUNE 7,1983 Member, Pennsylvania Association of Notares i

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