BSEP-97-0226, Forwards Replacement TS Pp 3/4 5-2 Which Corrects Identified Discrepancy Re TS 4.5.1.b.Amend 215 Incorrectly Requires Verification of Sys Flow When Steam Is Being Supplied to Turbine at 1000,+20 & -18 Psig

From kanterella
Jump to navigation Jump to search

Forwards Replacement TS Pp 3/4 5-2 Which Corrects Identified Discrepancy Re TS 4.5.1.b.Amend 215 Incorrectly Requires Verification of Sys Flow When Steam Is Being Supplied to Turbine at 1000,+20 & -18 Psig
ML20148E682
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 05/16/1997
From: Jury K
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20148E688 List:
References
BSEP-97-0226, BSEP-97-226, TAC-M98129, TAC-M98218, NUDOCS 9706030218
Download: ML20148E682 (2)


Text

- _ _ . . . -- . - . . ..

. 1,

\

c ..

CP&L Carolina Power & Ught Company PO Box lo429 Southport, NC 28461-o429 MAY 161997 SERIAL: BSEP 97-0226 t i

U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk '

. Washington, DC 20555

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 CORRECTION TO LICENSE AMENDMENT NO. 215 4

(NRC TAC NOS. M98218 AND 98129)

Gentlemen:

On April 18,1997, the NRC issued Amendment Nos.184 and 215 to the facility operating licenses for the Brunswick Steam Electric Plant, Unit (BSEP), Nos.1 and 2, respectively. The amendments consisted of changes to the Technical Specifications (TS) regarding response time testing surveillance requirements for certain sensors and instrumentation loops for the Reactor Protection System, the Emergency Core Cooling System, and Isolation Actuation System. 1 A discrepancy has been identified on TS page 3/4 5-2 for BSEP Unit No. 2 regarding  ;

TS 4.5.1.b. Due to the use of an inaccurate version of TS page 3/4 5-2, Technical Specification 4.5.1.b, issued by Amendment No. 215, incorrectly requires verification of system flow when steam is being supplied to the turbine at 1000, +20, -18 psig. TS 4.5.1.b should actually require verification of system flow when steam is being supplied to the turbine at 1000,

((

+20,-80 psig. The value of 1000, +20, -80 psig was included in the original issuance of the BSEP Unit No. 2 Standard Technical Specifications and has not been revised through the

/

license amendment process. In order to correct the discrepancy, CP&L requests that a revised l Amendment No. 215 BSEP Unit No. 2 TS page 3/4 5-2 be issued. A replacement TS page 3/4 5-2 is enclosed.

Please refer any questions regarding this submittal to Mr. Mark Turkal, Supervisor - Licensing at (910) 457-3066. I t

Sincerely, A A.

, Keith R. Jury M nager- Regulatory Affairs 0300.10 Brunswick Steam Eiectric eiant 9706030218 970516 f blllllhfll*h

    • hflflllfll PDR ADOCK 05000324: a -
p. PDR ,
o .-

(

o- " Document Control Desk-

. BSEP 97-0226 / Page 2 WRM/wrm Enclosure

' pc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN.: Mr. Luis A. Reyes, Regional Administrator Atlanta Federal Center.

61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303 U S. Nuclear Regulatory Commission ATTN: Mr. C. A. Patterson, NRC Senior Resident inspector -

8470 River Road Southport, NC 28461-U. S. Nuclear Regulatory Commission ATTN.: Mr. Dmid C. Trimble, Jr. (Mail Stop OWFN 14H22) 11555 Rockville i ke Rockville, MD 208J2-2738 Mr. Mel Fry Acting Director- Division of Reactor Protection North Carolina Department of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221 The Honorable J. A. Sanford Chairman - North Carolina Utilities Commission i P.O. Box 29510 l Raleigh, NC 27626-0510 l l

l

__. . _ _ _ . . . . _ - . , _ _ . . _ , _ . . . _