ML20064F941

Addendum to 921210 TS Change Request 154,modifying TS 15.3.5 & 15.4.1 to Incorporate Items Identified from Comparison of Safety Analyses in Plant FSAR W/Lco & Surveillance Sections of Ts,To Revise Line Item 3.b.i to Remove Double Asterisk

ML20064F941
Person / Time
Site:	Point Beach
Issue date:	03/08/1994
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20064F942	List: ML20064F941 ML20064F958
References
CON-NRC-94-020, CON-NRC-94-20 VPNPD-94-027, VPNPD-94-27, NUDOCS 9403150503
Download: ML20064F941 (2)

Text

, .. . . - - . ~ . . . - .-

A i

i

\4fsconsna 1

'Electnc n'

- PONER COMPANY

- 231 w M<.ny2r1 Po. Box 2046. Mu Aee 'M 53201 2046 (M4) 221234%

)

l

'VPNPD-94-027 NRC-94-020 March 8, 1994  ;;

Document Control Desk

' U.S. NUCLEAR REGULATORY COMMISSION l Mail Station P1-137 '

Washington, DC 20555

' Gentlemen: g

.i DOCKETS 50-266 AND 50-301 ADDENDUM TO-TECHNICAL SPECIFICATIONS CHANGE REOUEST 154  :

' MODIFICATIONS TO TECHNICAL SPECIFICATIONS SECTIONS 15.3.5 AND 15.4.1 '!

.. POINT . BEACH 3UCLEAR PLAUT. UNITS 1 AND 2 On December 10, 1992, Wisconsin Electric Power Company,-the licensee for Point Beach Nuclear Plant, submitted Technical ~

Specifications Change Request 154 " Modifications to' Technical  :

Specifications sections 15.3.5 and 15.4.1." This Technical Specifications Change Request proposed to modify. Sections 115.3.5.

and 15.'4.1 to incorporate items identified from a comparison of  ;

the safety analyses in the Point Beach Nuclear Plant-Final' Safety j Analysis Report (FSAR) with-the Limiting Conditions for Operation >

(LCO) and surveillance sections of the current' Technical Specifications. i In the original change request, modifications were proposed thatL would remove Column 4, " Minimum Degree of Redundancy," from Technical Specification Tables 15.3.5-2, 15.3.5-3, and 15.3.5-4. -

To' ensure that the minimum degree of redundancy was maintained, should an instrument channel be declared inoperable, the following -j footnote was proposed for addition.to each of the three tables: ~

"If a channel'is determined to be inoperable, resulting in one less-than the total number of channels being operable, power operation may continue if the following conditions are met:

1. The minimum number of oparable channels is still satisfied. . .

l

2. The affected channel is placed in' trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />." - ,

l This note is consistent with standard Technical Specification .

requirements'and is applicable'only to thoso line-items in-the.

~

three . tables highlighted with a double asterisk, "**".-

9403150307 940308 h ON l PDR ADOCK 05000266' ic ,;

, P: PDR' l A su M h* W & w s D e s i M m tim 'l k . . . . l1( )

e- i 4

Document Control Desk March 8, 1993 Page 2 i

During a recent review of the change request, it was determined that an error was made in the submittal. Line Item 3.b.1, "Undervoltage on 4KV Buses (A01 & A02)," of Table 15.3.5-3,

" Engineered _ Safety Features," specifies the channel requirements-necessary to ensure the operability of the autostart feature for the turbine-driven auxiliary feedwater pumps. The functional unit of this line item consists of two channels. A trip of one of the two channels will cause the protective feature to' actuate. This line item is currently highlighted with a double asterisk, which would require placing the inoperable channel in' trip within one hour of the inoperability determination. However, since the trip of only one channel is required to cause an autostart of the turbine-driven auxiliary foodwater pump, complying with this proposed requirement would result in an undesired start of the pump.

Therefore, this addendum is beir.g submit ni in order to revise Line Item 3.b.i to remove the double asterisk. This line item modification removes the proposed requirement to place the inoperable channel in trip within one hour. This change will make Line Item 3.b.i consistent with the other line~ items in the tables that have two channels with the trip of only one channel being required to actuate a protective feature, and is equivalent to our existing specification.

In order to facilitate your review of this change, a revised ,

Technical Specification page with the correction is attached.

This attacbed page. replaces the like page in our original submittal. Please contact us if there are any questions.

i Sincerely, W

BobLnhf#1'#

Vice esident Nuclear Power FDP/jg Enclosure cc: NRC Regional Administrator, Region III NRC Resident Inspector

. .-. .