ML20245H587

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Requests Tech Spec Page 3/4 3-92 of Amends 130 & 160 to Licenses DPR-71 & DPR-62,respectively,be Reissued to Correct Error Re Instrument Tag Numbers
ML20245H587
Person / Time
Site: Brunswick  
Issue date: 06/21/1989
From: Loflin L
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-89-177, TAC-72061, TAC-72062, NUDOCS 8906300009
Download: ML20245H587 (4)


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Carolina Power & Light Company JUN 21 1989 SERIAL: NLS-89-177 United States. Nuclear Regulatory Commission ATTENTION: Document Control Det k Washington, DC 20555 1

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 j

DOCKET NOS. 50-325 & 50-324/ LICENSE NOS DPR-71 & DPR-62

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REQUEST FOR CORRECTED PAGE.

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'(NRC TAC NOS. 72061 AND 72062).

Gentlemen:

p On May 22, 1989, the NRC issued Amendments 130 and 160 to the Technical.

Specifications for the Brunswick Steam Electric. Plant (BSEP)., Units 1 and 2.

The amendments were issued as requested by Carolina Power &

Light Company (CP&L) in a letter dated February 1, 1989.

During subsequent review of these amendments, the Company determined that an error was introduced in Table 4.3.6.1-1 (Page 3/4.3-92) of the BSEPf2 Tecnnical-Specifications. This error was introduced in the February 1,.1989 license amendment request referenced above and was not discovered until after Amendment 160 had been issued. Amendments 130 and 160 were intended to remove only the instrument tag numbers from Table 4.3.6.1-1 and administrative 1y revise the tabic.

No changes to surveillance. requirements were intended.

Technical ~ Specification Table 4.3.6.1-1, Item 2 provides the surveillance requirements for the reactor vessel pressure - high instrumentation relative to the anticipated transient without scram (ATWS)-recirculation pump trip system. A channel check is not necessary for the transmitter portion of the logic, and a channel calibration is required only at refueling intervals. There should be a reference to i

Footnote,(a) in the channel check column associated with the transmitter to indicate that a channel check is not required. Also, there should be a reference to Footnote (b) in the channel calibration column to state that transmitters are exempt from monthly channel calibrations.

These references do not exist on the BSEP-2 Technical Specification page issued by Amendment 160. The correct references are shown on the

. corresponding Technical Specification Table for BSEP-1.

Therefore, CP&L requests that the NRC re-issue Technical Specification Page 3/4 3 92 for

.BSEP-2 to correct this error. A corrected page for BSEP-2 is provided in Enclosure 1.

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411 Fayetteville Street e P O. Box 1551

  • Raleigh, N. C 27602 I

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1 8906300009 890621 PDR ADOCK 05000324 j

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  • 1 Documsnt Control Desk NLS-89-~177. /.Page 2 Please refer any questions regarding this submittal to Mr. William R.

Murray at (919) 546 4661.

Yours very truly, Leonard. Loflin Ma ger Nuclear Lic.nsing Section BAB/bab

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Enclosure cc:

Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny

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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324 OPERATING LICENSES DPR-71 6 DPR-62 REQUEST FOR CORRECTED PAGE i

(NRC TAC NOS. 72061 AND 72062)

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CORRECTED TECHNICAL SPECIFICATION PAGE - UNIT 2 i

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l TABLE 4.3.6.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CHECK TEST CALIBRATION 1.

Reactor Vessel Water Level -

Low, Level 2 b

$ (a)

NA

?,(b )

Transmitter:

Trip Logic:

D M

M 2.

Reactor Vessel Pressure - High Transmitter:

NA(a)

M R(b)

Trip Logic:

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(a) The transmitter channel check is satisfied by the trip unit channel j

check. A separate transmitter check is not required.

(b) Transmitters are exempted from the monthly channel calibration.

BRUNSWICK - UNIT 2 3/4 3-92 Amendment No.100 s