ML20059N171

Forwards Correction to Amend 144 to License DPR-71 ,per 900920 Telcon

ML20059N171
Person / Time
Site:	Brunswick
Issue date:	09/27/1990
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-90-196, NUDOCS 9010100191
Download: ML20059N171 (2)

Text

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CD&L Carolins Power & Light Company.

SEP 271990 SERIAL:

NLS-90-196 10 CFR150,90 TSC 88TSB25 United States. Nuclear Regulatory Commission-ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK' STEAM ELECTRIC PIANT, UNIT NO.1 DOCKET No. 50-325/ LICENSE NO DPR-71

-CORRECTION,TO RECENTLY ISSUED LICENSE AMENDMENT NO..144

'(NRC TAC NO 76164)

Centlemen:

Carolina Power & Light Company has received Amendment No.:144 dated September 11, 1990 to the Facility operating. license for the Brunswick Steam-Electric Plant,-Unit 1.

During. review of the amendment approval package,- the Company. identified several typographical errors on.Index page:XII which-require correction.

As discussed in a telephone call with the NRR Projet c Manager on September 20, 1990, The Company hereby submits a corrected Technical Specification Index page XII-for re-issuance.

Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.

Yours very truly,

$.k. f&

& J. L. l 0 05 Leonard I. Loflin Manager Nuclear Licensing. Sectio.i WRM/wrm

(\\cor\\rscs-cor)

Enclosure cc:

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

, d G.i 411 Fayetteville Street

• P. O Box 1551

• Raleigh. N. C. 27602

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. ~ : u 9010100191 900927 AAffV8[

PDR ADOCK 05000325 P

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_r INDEX

,t-BASES' SECTION PACE =

3/4.7 PLANT SYSTEMS (Cont inued)

'3/4.7.3 FLOOD PROTECTION.........................................

B 3/4 7 3/4. 7.4 REACTOR CORE I SOLATION - COOLING SYSTEM.................... B-3/4 7-1 3/4.7.5 SNUBBERS.................................................

B 3/4.7-2 3/4.7.6 SEALED SOURCE CONTAMINATION..............................

B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS.................................

B 3/4-7 3/4.7.8 FIRE. BARRIER PENETRATIONS................................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS.............'......................

B.3/4-8-1.

3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH...............=.......................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................

B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION.....................................

B 3/4 9 3/4.9.4 DECAY. TIME...............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS...........................................

B 3!4'9-1 3/4.9.6 C RANE AND HOI ST OPE RABI LITY..............................

B-3/4 9-2 3/4.9.7 CRANE T RAVEL-S PENT FU EL STORACE P00 L.....................

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 W ATER LEVEL-REACTOR FUEL STOR ACE P00L.................... B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL.....................................

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINHENT INTEGRITY.............................B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)....................

B 3/4 10-l' l-3/4.10.3 SHUTDOWN HARCIN DEMONSTRATIONS...........................

B 3/4 10-1 3 / 4.10. 4 R EC I R C U LAT I ON L00 PS......................................

B 3/4 10-1 3 / 4.10. 5 P LA NT S ER VI C E W AT ER.....................................

B 3/4 10-1 BRUNSWICK - UNIT 1 XII Amendment No. 144 t

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