ML20065S903: Difference between revisions

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=Text=
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8                                                                    South CaroHna Doctric & Osa Company              Jo n Sko e
          ,            4                                                      Jonhnsvine. SC P90h5-                            Nuclear operanons -            l (803) $45 4040                                                                    l c
        '*                              SCEAG
                                        ~~
DEC 181990
:                                                                                                                                                                l i
Document Control Desk                                                                                                          ,
U. S. Nuclear Regulatory Commission                                                                                            :
Washington, DC 20555 Gentlemen:
s
 
==Subject:==
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OFERATING LICENSE NO. NPF-12                                                                                    ,
TECHNICAL SPECIFICATION CHANGE - TSP 880025-0 INCREASED SURVEILLANCE TEST INTERVALS AND ALLOWED OUTAGE TIMES FOR REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
 
==References:==
1.LetterfromC.O. Thomas (NRC)toJ.J.Sheppard(WOG) dated u
February 21, 1985                      " Safety Evaluation by the Office of Nuclear Reactor Regulation-.WCAP-10271 Evaluation of Surveillance'Freauencies and Out of Service Times for the
<                                                        Reactor Protection Instrumeatation System."
: 2. Letter from Charles E. Rossi (NRC) to Roger A. Newton (WOG) dated February 22, 1989                      " Safety Evaluation'by the Office of-
                                                      -Nuclear' Reactor Regulation Review of Westinghouse Report
                                                        .WCAP-10271 Supplement 2 and WCAP-10271 Supplement'2, Revision 1 on Evaluation of Surveillance Frecuencies and Out of Service Times for the Enaineered Safety Features Actuation SNLtem."
: 3. WCAP-10271 Supplement 1-P-A, Evaluation of Surveillance Freauencies and Out of Service Times for the Reactor Protection Instrumentation System, May 1986.
: 4. WCAP-10271-P-A Supplement 2, Revision 1, Evaluation of _
Surveillance Frecuencies and Out of Service Times for the Enaineered Saffly_ features Actuation System, May.1989.
: 5. Letter from Charles E. Rossi (NRC) to Gerard T. Goering (WOG)
                                                      -dated April-30, 1990 (NRC Supplemental-Safety Evaluation for-WCAP-10271 Supplement 2, Revision 1).                                                                ,
                                'In accordance with_ 10CFR50.90, South Carolina-Electric & Gas Company (SCE&G)-
is enclosing a requested amendment to License NPF-12-to change the Technical-Specifications (TS)fortheVirgilC.SummerNuclearStation--(VCSNS).-The
    ~
1 proposed change is a revision to TS 3/4.3.1, " Reactor Trip System Instrumentation," 3/4.3.2, " Engineered Safety Feature Actuation System,"cand associated Basis 3/4.3. The proposed change revises surveillance test intervals (STI).and allowed outage times (A0T) for Engineered Safety Features                                                -
                              - Actuation System (ESFAS) and Reactor Trip System (RTS) instrumentation =in agreement with WCAP-10271.
h2260157I90121s.
p        ADOCK 05000395-P t
engyg                                    PDR
 
    .  -                                                                                                                                                                              i I
Document Control Desk                                                                                                                                            i TSP 880025-0                                                                                                                                                      j Page 2                                                                                                                                                            l j
The proposed TS change is identified in Enclosure 1.                                                            The safety evaluation,                            l including confirmation of the applicability of the generic analysis and accountability of instrument drift in the setpoint calculation methodology, is provided in Enclosure 2.                                                        A proposed no significant hazards evaluation performed pursuant to 10CFR50.92 is provided in Enclosure 3.
The changes proposed are needed to minimize: 1) the potential impact of current testing: inadvertent trips, unnecessary transients and challenges to safety systemst and 2) maintenance requirements on the plant: significant time and effort to plan, perform, track and review testing, surveillance and maintenance activities. Therefore, SCE&G requests NRC review and issuance of the proposed amendment by May 31, 1991, and that the revised TS be made effective within 60 days of NRC issuance of the License Amendment.
The proposed TS change has been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee.
I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information ar.d belief.
Should you have any questions concerning this issue, please call Mr. M. W.
Gutierrez of my staff at (803) 345-4392.
Very truly yours
                                                                                                                        &            /to6 John L. Skolds MWG:JLS: led Attachments c:                                              0. W. Dixon, Jr.
E. C. Roberts R. J. White S. D. Ebneter G. F. Wunder General Managers NRC Resident Inspector J. B.-Knotts, Jr.
H. G. Shealy NSRC l                                                                    NPCF RTS (TSP 880025)
FILE (813.20)
NUCLEAR EXCELLENCE - A SUMER TRADITIONI b}}

Latest revision as of 03:56, 6 January 2021

Application for Amend to License NPF-12,consisting of Tech Spec Change TSP 880025-0,increasing Surveillance Test Intervals & Allowed Outage Times for Reactor Trip Sys & ESFAS Instrumentation
ML20065S903
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/18/1990
From: Skolds J
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20065S905 List:
References
NUDOCS 9012260157
Download: ML20065S903 (2)


Text

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

.i

)

8 South CaroHna Doctric & Osa Company Jo n Sko e

, 4 Jonhnsvine. SC P90h5- Nuclear operanons - l (803) $45 4040 l c

'* SCEAG

~~

DEC 181990

l i

Document Control Desk ,

U. S. Nuclear Regulatory Commission  :

Washington, DC 20555 Gentlemen:

s

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OFERATING LICENSE NO. NPF-12 ,

TECHNICAL SPECIFICATION CHANGE - TSP 880025-0 INCREASED SURVEILLANCE TEST INTERVALS AND ALLOWED OUTAGE TIMES FOR REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

References:

1.LetterfromC.O. Thomas (NRC)toJ.J.Sheppard(WOG) dated u

February 21, 1985 " Safety Evaluation by the Office of Nuclear Reactor Regulation-.WCAP-10271 Evaluation of Surveillance'Freauencies and Out of Service Times for the

< Reactor Protection Instrumeatation System."

2. Letter from Charles E. Rossi (NRC) to Roger A. Newton (WOG) dated February 22, 1989 " Safety Evaluation'by the Office of-

-Nuclear' Reactor Regulation Review of Westinghouse Report

.WCAP-10271 Supplement 2 and WCAP-10271 Supplement'2, Revision 1 on Evaluation of Surveillance Frecuencies and Out of Service Times for the Enaineered Safety Features Actuation SNLtem."

3. WCAP-10271 Supplement 1-P-A, Evaluation of Surveillance Freauencies and Out of Service Times for the Reactor Protection Instrumentation System, May 1986.
4. WCAP-10271-P-A Supplement 2, Revision 1, Evaluation of _

Surveillance Frecuencies and Out of Service Times for the Enaineered Saffly_ features Actuation System, May.1989.

5. Letter from Charles E. Rossi (NRC) to Gerard T. Goering (WOG)

-dated April-30, 1990 (NRC Supplemental-Safety Evaluation for-WCAP-10271 Supplement 2, Revision 1). ,

'In accordance with_ 10CFR50.90, South Carolina-Electric & Gas Company (SCE&G)-

is enclosing a requested amendment to License NPF-12-to change the Technical-Specifications (TS)fortheVirgilC.SummerNuclearStation--(VCSNS).-The

~

1 proposed change is a revision to TS 3/4.3.1, " Reactor Trip System Instrumentation," 3/4.3.2, " Engineered Safety Feature Actuation System,"cand associated Basis 3/4.3. The proposed change revises surveillance test intervals (STI).and allowed outage times (A0T) for Engineered Safety Features -

- Actuation System (ESFAS) and Reactor Trip System (RTS) instrumentation =in agreement with WCAP-10271.

h2260157I90121s.

p ADOCK 05000395-P t

engyg PDR

. - i I

Document Control Desk i TSP 880025-0 j Page 2 l j

The proposed TS change is identified in Enclosure 1. The safety evaluation, l including confirmation of the applicability of the generic analysis and accountability of instrument drift in the setpoint calculation methodology, is provided in Enclosure 2. A proposed no significant hazards evaluation performed pursuant to 10CFR50.92 is provided in Enclosure 3.

The changes proposed are needed to minimize: 1) the potential impact of current testing: inadvertent trips, unnecessary transients and challenges to safety systemst and 2) maintenance requirements on the plant: significant time and effort to plan, perform, track and review testing, surveillance and maintenance activities. Therefore, SCE&G requests NRC review and issuance of the proposed amendment by May 31, 1991, and that the revised TS be made effective within 60 days of NRC issuance of the License Amendment.

The proposed TS change has been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee.

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

Should you have any questions concerning this issue, please call Mr. M. W.

Gutierrez of my staff at (803) 345-4392.

Very truly yours

& /to6 John L. Skolds MWG:JLS: led Attachments c: 0. W. Dixon, Jr.

E. C. Roberts R. J. White S. D. Ebneter G. F. Wunder General Managers NRC Resident Inspector J. B.-Knotts, Jr.

H. G. Shealy NSRC l NPCF RTS (TSP 880025)

FILE (813.20)

NUCLEAR EXCELLENCE - A SUMER TRADITIONI b