ML20044D819

From kanterella
Jump to navigation Jump to search
Application for Amends to Licenses NPF-9 & NPF-17,correcting Error in Table 3.3-2, Reactor Trip Sys Instrumentation Response Times, Contained in License Amends 128 & 120 to Licenses NPF-9 & NPF-17,respectively
ML20044D819
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 05/06/1993
From: Mcmeekin T
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20044D820 List:
References
NUDOCS 9305200343
Download: ML20044D819 (4)


Text

. _ _ _ . _ _ _ _ _

I. .

ll, l 1 1 .

. DukeIbwer Company T C Kutrus  ;

McGuire Nuclear Generation Department l' ice President  ;

12700 Hagers ferryRoad(MG01A) (704)S75-4800 Huntersville, AC28075-8985 (704)STS-4809 Fn 1 i

DUKEPOWER J

I May 6, 1993 l i

U.S. Nuclear Regulatory Commission Washington, DC 20555  ;

Attention: Document Control Desk

Subject:

McGuire Nuclear Station, Units 1 and 2  !

Docket Nos. 50-369 and 50-370  :

Proposed Technical Specification Change  ;

l i

1 Gentlemer.  :

\

Pursuant to 10 CFR 50.4 and 50.90, attached is a proposed l

license amendment to Appendix A, Technical Specifications, of

Facility Operating Licenses, NPF-9 AND NPF-17 for McGuire Nuclear Station Units 1 and 2, respectively.

The proposed change, which is. editorial in nature, would correct an error in Table 3.3-2 that was made with-license amendment 128/120 for unit 1 and 2 respectively.

Attachment I cintains the background and justification'for the proposed change. Attachment 2 contains the proposed Technical Specification change. Attachment 3 contains the _ analysis performed in accordance with the standards contained in 10 CFR 50.92, which concludes that the amendment does not involve a j significant Hazards Consideration. The proposed amendment has been reviewed and has been determined to have no adverse safety  ;

or environmental impact.

Duke Power is forwarding a copy of this amendment request l

application and No Significant Hazards Consideration analysis to the appropriate North Carolina state officials.

Should there be any questions concerning this proposed amendment or if additional information is required, please call L. .J.

Kunka at (704) 875-4032.

Very truly yours, tofly /  :

T. C. McMeekin

~

9305200343 930506 -

PDR ADDCK 05000369 f l P PDR 60l)

L nvaa on nauwse

o Document Control Desk Page 2 l May 6, 1993 Attachments I  !

xc: (W/ Attachments)

Mr. S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission, Region II s

Mr. Dayne Brown, Chief Radiation Protection Branch Division of Facility Services Department of Human Services, State of NC l i Mr. T. A. Reed, Project Manager [

j Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mr. P.K. VanDoorn NRC Resident Inspector McGuire Nuclear Station .

American Nuclear Insurers M & M Nuclear Consultants 4

INPO Records Center l

Document Control Desk Page 3 May 6, 1993 i

T.C. McMeekin, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this revision to the McGuire Nuclear Station License Nos. NPF-9 and NPF-17 and that all statements ,

and matters set forth therein are true and correct to the best of his knowledge.

L/ '

T.C. McMeekin, Vice President Subscribed and sworn to before me this /1 th day of May, 1993.

l I

kl- -

Notpry ublic

(

i l My Commission expires:

i i

/Olnwbn /3 l993 ,

i

_ . _ -. - - .-. - - = - _ _ . - - - - - . . _ - .. ..

l

. l ATTACHMENT 1 BACKGROUND / JUSTIFICATION l On March 22, 1985,.the Nuclear Regulatory Commission ist .4 l Amendment 42 and 23 to Facility Operating License NPF-9 and in F -  !

17 for McGuire Nuclear Station, Units 1 and 2 respectively. l This amendment changed the Technical Specifications to reflect the transition to the use of optimized fuel assemblies. In Table 3.3-2 of this amendment, the Response Time for the Steam Generator Water Level--Low-Low reactor trip was changed from 5 2 seconds to 5 2.0 (Unit 1), 3.5 (Unit 2) seconds. (See Attachment 4) j On May 15, 1985, The NRC issued Amendment 43 to Facility Operating License NPF-9 and 24 to Facility Operating License NPF-17 to change the Technical Specifications to reflect the  !

second of several stages involved in the continuing transition  ;

to the use of optimized fuel assemblies. This amendment changed  ;

the Response Time for the Steam Generator Water Level--Low-Low '

reactor trip to 1 3.5 seconds. (See Attachment-4) ,

The time response remained 5 3.5 seconds until November 27, 1991, when the NRC issued Amendment 128/110 which revised the .

Technical Specifications to reflect the loading of B & W-fuel .

into McGuire Unit I for Cycle 8 and various other changes. In (

this amendment, the only change to Table 3.3-2 requested and i discussed in the SER was the deletion of thu Power Range Neutron l Flux Negative Rate Trip. (See Attachment 4) The deletion of {

t this trip required the renumbering of the remaining trips in Table 3. 3-2. When Table 3.3-2 was received, page 2 of the table [

had been renumbered, but the time response for the Steam l Generator Water Level--Low-Low reactor trip had been changed to l 5 2.0 (Unit 1), 3.5 (Unit 2) seconds which was the same as in i Amendment 42/23. This change had not been requested and was not discovered during the review of Amendment 128/110 by Duke Power Company.

i i

On March 6, 1992, the NRC issued Amendment 130/112 which changed <

l the Technical Specifications to reflect the reload of McGuire l Unit 2 Cycle 8 with B & W fuel. This change was administrative I in nature and made the McGuire Unit 2 Technical Specifications  !

identical to the Unit 1 Technical Specifications approved by Amendment 128/110. The above referenced error was included in this amendment and was not detected during the review of the amendment.

Based on the preceding discussion, Duke Power requests that the time response for Steam Generator Water Level--Low-Low in Technical Specification Table 3.3-2 be changed to 5 3.5 seconds.

The proposed change to the Technical Specification is given in Attachment 2. Since this change is only returning Technical Specification Table 3.3-2 to the previously approved condition, this change should be considered administrative in nature.

l 2

- .,. ,, _.