ML20058C334

From kanterella
Jump to navigation Jump to search
Application for Amends to Licenses DPR-62 & DPR-71, Clarifying Primary Containment Isolation Sys Requirements
ML20058C334
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 10/24/1990
From: Loflin L
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058C337 List:
References
NLS-90-208, NUDOCS 9011010172
Download: ML20058C334 (2)


Text

__.. _ _.._

CD&L Caroline Power & Light Company f

i OCT 241990 StR1At:

NtS 90 208 i

10 CFR 50.90 TSC 84TSB08 i

United States Nuclear Regulatory Commission i

ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PIANT, UMIT NOS.1 AND 2 DOCKET NOS. 50 325 & 50 324/ LICENSE NOS. DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT PRIMARY CONTAINMENT IS01ATION SYSTEM (NRC TAC NOS. 67991 AND 67992)

Centlemen:

I On February 19, 1988 (Serial: NLS 88 051), Carolina Power &' Light Company

[

requested a chuge to the Technical Specification:' for the Brunswick Steam 3

Electric Plant, Units 1 and 2.

The proposed change chrifies isolation system instrumentation requirements contained in Technical Specitication Tables 3.3.2 1, 3.3.2 2, 3.3.2 3 and 4.3.2 1-and relocates Technical Specification Tables 3.6.3 1 and 3.6.5.2 1 to a plant procedure.

Based on a recent request by the NRR Project Manager and the anticipated issuance of the Company's February 28, 1990 (Serial: NLS 90 043-) license i

amendment request concerning service water system operability and the Company's February 15, 1989 (Serial: NLS 89 023). license amendment request concerning secondary containment isolation instrumentation, the following changes have been incorporated with the typed Technical Specification pages:

1.

On Index page XI, the page number for Bases Section 3/4.7.2 has been revised to reflect the anticipated issuance of the Company's February 28, 1990 license amendment request concerning service water system operability.

2.

Page 3/4 3 17 has been replaced with page 3/4 3 17a containing footnotes (1) through (1) to, reflect the anticipat ed issuance of the Company's February 15, 1989 license amendment request concerning secodary containment isolation instrumentation.

2.

On page 3/4 3-23 (Unit 1 only), the reference to footnote "(h)"

i for 1. tem 1.c.3 has been changed to "(f)" as previously discussed with the NRR Project Manager.

3.

A note referencing the next available page has been added to pages 3/4 6-14.

.wr,

$. b O 411 Fayettevme Street

  • P. O Boa 1551
  • Haieigh. N C. 27602 l "t

,n y., n

. n ?: -

ADOCK O h gDR

'l

i I

Document C:ntrol De:k NLS 90 208 / Page 2 1

For your convenience in issuance of the proposed request, typed Unit 1 and Unit 2 Technical Specification pages are provided in Enclosures 1 and 2 respectively.

These pages supersede, in their entirety, those provided in CP&L's submittal dated August 9, 1990, 1990 (Serial: NLS 90 162).

.; provides instructions for incorporation of the proposed changes

='

into the Technical Specifications for each unit.

l Please refer any questions regarding this submittal to Mr. W. R. Murray at (919) 546 4661.

Yours very truly, L.

f in Manage Nuclear'Licens:ng Section VRM/wrm

(\\cor\\pcispgs1.)

Enclosures:

1.

Technical Specification Pages Unit 1 2.

Technical Specification Pages Unit 2 3.

Instructions for Incorporation 4.

Summary List of Revisions cc:

Mr. Dayne H. Brown Mr. S. D. Ebneter Mr. N. B. 14 Mr. R. L. Prevatte