RC-94-0073, Application for Amend to License NPF-12,revising TSs Re Limiting Safety Sys Settings Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint

Application for Amend to License NPF-12,revising TSs Re Limiting Safety Sys Settings Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint

ML20064G545
Person / Time
Site:	Summer
Issue date:	03/11/1994
From:	Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20064G548	List: ML20064G554 RC-94-0073, Application for Amend to License NPF-12,revising TSs Re Limiting Safety Sys Settings Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint
References
RC-94-0073, RC-94-73, NUDOCS 9403160225
Download: ML20064G545 (4)

Text

. . . - -

- hn So a

, ,, Sogth CaroHna Electric & Gas Company SC 29065 Nuclear Operations engnsv SCE&G

.sema w ..,

March 11, 1994 Refer to: RC-94-0073 Document Control Desk U. S. Nuclear Regulatory Commission ,

Washington, DC 20555 Attention: Mr. G. F. Wunder

)

Gentlemen:

Subject:

VIRGILC.SUMMERNUCLEARSTATION(VCSNS) ]

DOCKET NO. 50/395 OPERATING LICENSE NO NPF-12 TECHNICAL SPECIFICATION CHANGE - TSP 930002 LIMITING SAFETY SYSTEM SETTINGS - REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETP0INTS ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT

]

In accordance with 10 CFR 50.90, South Carolina Electric & Gas Company (SCE&G) is submitting an amendment request to License NPF-12 to change the Technical Specifications (TS) for VCSNS. The proposed change revises TS Tables 2.2-1, Reactor Trip System (RTS) Instrumentation Trip Setpoints, and 3.3-4, Engineered Safety Feature Actuation System (ESFAS) Instrumentation Setpoints,'and associated Bases.

SCE&G requests NRC review and approval of this change by August 31, 1994, in order to support Refueling Outage 8 activities.

The purpose of this change is to include additional Process Measurement Accuracy (PMA) uncertainties for the narrow range steam generator water level low-low trip functions for the Model D3 steam generators and to change Tables 2.2-1 and 3.3-4 to a two column format.

The amendment request is contained in the following enclosures:

Enclosure 1 - Proposed TS Change Enclosure 2 - Description and Safety Evaluation Enclosure 3 - Determination of No Significant Hazards Consideration The proposed TS change has been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee.

1 C; D r .r ,

-v v udv 9403160225 940311 PDR ADOCK 05000395 i P PDR a

i Document Control Desk Letter l TSP 930002  ;

Page 2 of 2 Please note that the proposed TS Change Request is affected by three previous SCE&G TS Change Request submittals.

TSP 930015, submitted October 29, 1993, letter number RC-93-0272, affects pages 2-5, 2-6, 2-7, 2-9, 2-10, B 2-3, and 3/4 3-28.

TSP 930016, submitted February 25, 1994, letter number RC-94-0049, affects page 3/4 3-26.

TSP 890022, submitted January 29, 1993, letter number RC-93-0021, affects Bases page B 3/4 3-la. TS Bases Page B 3/4 3-la includes an old revision to these Bases which was never incorporated. This change request supersedes the change referenced on letter number RC-93-0021.

I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information, and belief.

Should you have any questions concerning this issue, please call Mr. Philip A. Rose at (803) 345-4052 at your convenience.

Very truly yours, John L. Skolds PAR: led Enclosures c: 0. W. Dixon Jr.

R. R. Mahan (w/o Enclosures)

R. J. White S. D. Ebneter NRC Resident Inspector J. B. Knotts Jr.

A. A. Craft (DHEC)

Central File System RTS (TSP 930002)

File (813.20)

NUCLEAR EXCELLENCE - A SUPHER TRADITION!

Enclosure 1 to Document Control Desk Letter TSP 930002 i Page 1 '

PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST - TSP 930002 VIRGIL C. SUMMER NUCLEAR STATION LIST OF AFFECTED PAGES PAGE SECTION CHANGE DESCRIPTION 2-4 2.2.1 Deleted Equation 2.2-1 due to 2 column format change.

2-5 Table 2.2-1 Deleted TA, Z, & S columns from Table due to 2 column fomat change.

2-6 Table 2.2-1 Deleted TA, Z, & S columns from Table due to 2 column fomat change.  !

Revised Allowable Values to Function i 13 " Steam Generator Water Level Low-Low" and Function 14 " Steam /Feedwater ,

Flow Mismatch Coincident with Steam l Generator Water Level Low-Low" due to PMA uncertainties.

2-7 Table 2.2-1 Deleted TA, Z, & S columns from Table due to 2 column format change.

2-9 Table 2.2-1, Revised OVERPOWER DELTA T equation -

Note 3 l administrative change due to '

typographical error. j 2-10 Table 2.2-1, Revised OVERPOWER DELTA T definition -

Note 3 administrative change due to typographical error.

B 2-3 8 2.2.1 Deleted discussion on methodology of I determining operability when setpoint 4 is found to exceed Allowable Value, due to 2 column format change.

3/4 3-15 3.3.2 Deleted Equation 2.2-1 due to 2 column-format change and Process Measurement Accuracy (PMA) uncertainties.

Transferred Surveillance Requirements  !

4.3.2 from page 3/4 3-15a due to-repagination.

3/4 3-15a 4.3.2 Page deleted due to repagination of page 3/4 3-15.

Enclosure 1 to Document Control Desk Letter TSP 930002 Page 2 LIST OF AFFECTED PAGES Continued PAGE SECTION CHANGE DESCRIPTION 3/4 3-25 Table 3.3-4 Deleted TA, Z, & S columns from Table due to 2 column format change.

3/4 3-26 Table 3.3-4 Deleted TA, Z, & S columns from Table due to 2 column format change.

3/4 3-27 Table 3.3-4 Deleted TA, Z, & S' columns from Table due to 2 column format change.

3/4 3-28 Table 3.3-4 Deleted TA, Z, & S columns from Table due to 2 column format change.

Revised Allowable Value to Function 6.c., " Steam Generator Water Level -

Low-Low," due to PMA uncertainties.

3/4 3-28a Table 3.3-4 Deleted TA, Z, & S columns from Table due to 2 column format change.

3/4 3-28b Table 3.3-4 Deleted TA, Z, & S columns from Table due to 2 column format change.

B 3/4 3-1 B 3/4.3.1, Deleted discussion on methodology of B 3/4.3.2 determining operability when setpoint )

is found to exceed the Allowable Value, due to 2 column format change.

l 8 3/4 3-la B 3/4.3.1, Deleted discussion on methodology of  !

B 3/4.3.2 determining operability when setpoint i is found to exceed the Allowable l Value, due to 2 column format change. l Included a paragraph from previous submittal (TSP 890022, Amendment 108) which was never incorporated. This change request supersedes the' change referenced on letter number RC 0021, dated January 29, 1993.

I l