ML20062A249

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Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Containment Structural Integrity Surveillance Spec 4.6.1.6.1 to Reflect Wording Contained in STS
ML20062A249
Person / Time
Site: Beaver Valley
Issue date: 10/01/1990
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20062A251 List:
References
TAC-77638, TAC-77639, NUDOCS 9010190252
Download: ML20062A249 (2)


Text

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hey Power $tatch Shawr,; port PA15077M October 1, 1990 n

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m2, m ms U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Proposed Operating License Change Request No. 181/45 (TAC Nos. 77638 and 77639)

Gentlemen:

Enclosed are:

1.

An application for amendment to the above licenses to revise the Containment Structural Integrity Surveillance Specification 4.6.1.6.1 to reflect the wording contained in the Standard Technical Specifications.

2.

Documents designated Attachments A,

B and C which set forth the change in the Technical specifications, the safety analysis, including the no significant hazards evaluation, and the typed replacement Technical Specification pages.

We hereby request that the NRC process this application for amendment to our. operating license in an expedited manner in accordance with 10 CFR 50.91(a) (6).

Unit No.

2 is in a refueling outage and during the inspection of the containment liner, it was observed that a number of containment liner test channel vent plugs were

missing, our first indication of missing vent plugs occurred on approximately September 17, 1990, as we performed the required inspections which preceed our Type A containment leakage rate test.

The existing Technical Specifications would require that we remov9 the test channels associated.with the missing vent plugs.

The number of missing vent plugs has resulted in an estimated 1500 feet of test channel which would have to be removed in order to satisfy the Technical Specifications.

It is more prudent from a radiological perspective and from a technical perspective to justify leaving the test channel intact and request a

change to the Technical Specifications.

The information presented in the attachments provides our technical basis for leaving the test channels installed.

This Type A

test is the first performed following_

commercial operation and as such is the first scheduled containment liner inspection since pre-op testing where we could have discovered

'.the missing vent plugs.

s - y] Q 9010190252 901001 PDR ADOCK 05000334-40SL P

PNU gg,

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'"* Proposed dperating Lic nsa Ch2ng3 R:qu t

Page 2 It is requested that the NRC approve this proposed change in time ~to support our current outage schedule for entering.Hode 4.

This is presently scheduled to occur October 24, 1990.

i Sincerely, LN

'. D. Sieber ice President j

Nuclear Group l'

cci Mr. J.. Beall, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr.

A.'W.

DeAgazio, Project Manager i

Mr. R. Saunders (VEPCO) l 4

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