ML20058K442

Forwards Response to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions

ML20058K442
Person / Time
Site:	Summer
Issue date:	06/29/1990
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9007060031
Download: ML20058K442 (6)

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. South C:nlina Electric &' Gas C;mpany Cllle S. Brednam :  !

i! " P.O. Box 88 We2 Prisidlnt Jenkinsville, Sc 29065 Nuclear Operations

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(803) 345-4040

.SCEAG' ,

4 9Cnen.Neuv+y June 29, 1990 i 7

Document Control Desk U.-S. Nuclear Regulatory Commission Washington, 0. C. '20555

Subject:

Virgil C. Summer Nuclear Station '

Operating License No. NPF-12 Docket No. 50/395 Response to Generic Letter 90-04 Gentlemen:

South Carolina Electric & Gas Company (SCE&G) has reviewed the status of applicable Generic Safety Issues (GSIs) per the request of Generic Letter

. 90-04. Updates reflecting the current status of the GSIs are attached to this letter.

'Should you have any questions, please advise.

Very truly yours,

0. S. Bradham h  :

CJM/0SB: led Attachment i

L c: 0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts R. V. Tanner S. D. Ebneter J. J. Hayes, Jr.

General Managers C. A. Prica R. J. Waselus K. E. Nodland J.'C.-Snelson NRC Resident Inspector

, J. B. Knotts, Jr NSRC.

NDCF RTS (LTR900004)

File (815.14) o 9007060031-900629 '

~PDR ADOCK 05000395 >

P PDC

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~'- - A FACILITY NAME: V. C. Summer DOCKET NO.: 50/395 ~

LICENSEE: NPF STATUS OF LICENSEE IMPLENENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACit0NS GSI/(MPA No.) TITLE APPLICABILITY STATUS

• C(TMENTS 40 (B065) Safety Concerns Associated With All BWRs NA Pipe Breaks In The BWR Scram System 41 (8058) BWR Scram Discharge Volume Systems All BWRs NA 43 (B107) Reliability Of Air Systems All Plants I - 7/90 Hayes-Bradham 3/14/89 Letter on actions due.

51 (L913) Improving the Reliability of All Plants I - 12/91 Ref. SCE&G-NRC letter Open-Cycle Service Water Systems of 1/31/90.

67.3.3 (A017) Improved Accident Monitoring AII Plants C - 7/88 SE dated 7/27/88 -

NRC reviewing. '

75** (B076) Item 1.1 - Post-Trip Review All Plants C - 9/85 Novak-Dixon letter of (Program Description and 9/24/85. ,

Procedure) 75 (8085) Item 1.2 - Post-Trip Review - f.11 Plants .C .6/86 Hopkins-Nauman letter i Data and Information capability of 6/9/86. '

• Please follow attached guidance.for completing this column.

• • The 16 items listed for GSI 75 all relate to actions derived from the generic implications of -

Salem ATWS events. . Item numbers correspond to Generic Letter 83-28 action item numbers.

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GSI/(MPA No.) TITLE- APPLICABILITY STATUS

• COMMENTS 75 (B077) Item 2.1 - Equipment Classi- All Plants C - 1/87 Hopkins-Nauman letter.

l fication and Vendor Interface of 1/30/87.

(Reactor Trip System Components) . . ,

! 75 (B086) Item 2.2.1 - Equipment.Classifi- All Plants C - 11/87 Hopkins-Nauman letter cation for Safety-Related Components of 11/5/87.

75 (LOO 3) Item 2.2.2 - Vendor Interface All Plants C - 5/85 Dixon-Denton letter of for Safety-Related Components- 5/20/85. '

75 (8078) Items 3.1.1 & 3.1.2 - Post - All Plants C - 11/85 Novak-Nauman letter of Maintenance Testing (Reactor Trip System Components) 11/4/85.

75 (B079) Item 3.1.3 - Post-Maintenance All Plants C - 9/86 Hopkins-Nauman' letter of~

Testing-Changes to Test Require- 9/15/86.

ments (Reactor Trip System Components) 75 (B087) Items 3.2.1 & 3.2.2 - Post- All Plants 3.2.1 C - 11/85 Maintenance Testing (All 0ther Novak-Nauman letter of Safety-Related Components) 11/G/85.

3.2.2 0 - 2/86 Rubenstein-Nauman letter 75 (8088) Item 3.2.3 - Post-Maintenance All Plants 2/24/86.

Testing-Changes to Test Require- C - 9/86 Hopkins-Nauman letter of 1 ments (All Other Safety-Related 9/15/86.

Components).

75 (8080) Item 4.1 - Reactor Trip System All Plants Reliability (Vendor-Related C - 11/85' Novak-Nauman letter of Modifications) 11/4/85.

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GSI/(MPA No.) TITLE- APPLICABILITY STATUS

• COMENTS 75 (B081) Items 4.2.1 & 4.2.2 - Reactor All PWRs C'- 2/86 Rubenstein-Nauman ltr.

Trip System Reliability- of 2/24/86.

Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (8082) Item 4.3 - Reactor Trip System All W and B&W C - 11/85 Modification auth. i69 ,

Reliability - Design Modifications Plants Novak-Dixon letter of (Automatic Actuation of Shunt Trip 11/23/83. Modification!

Attachment for Westinghouse and B&W completed 11/25/85. -

Plants) 75 (8090) Item 4.3 - Reactor Trip System All W & B&W C - 7/89 TS Amendment #78 Reliability - Tech Spec Changes Plants Ref. Hayes-Bradham (Automatic Actuation of Shunt letter of 6/6/89.

Trip Attachment For Westinghouse and B&W Plants) 75 (8091) Item'4.4 - Reactor Trip System All B&W Plants NA Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

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GSI/(MPA No.) TITLE APPLICABILITY STATUS

• COMMENTS 75 (8092) Item 4.5.1 - Reactor Trip System All Plants C - 11/85 Novak-Nauman letter -

Reliability-Diverse' Trip Features of 11/4/85.

(System Functional Testing) 75 (8093) Items 4.5.2 & 4.5.3 - Reactor Trip All Plants 4.5.2 C - 1/87 Hopkins-Nauman letter System Reliability - Test Alterna- of 1/30/87.

tives and Intervals (System 4.5.3 C - 6/89 Hayes-Bradham letter:

Functional Testing) of 6/12/89.

86 (8084) Long Range Plan for Dealing All BWRs NA with Stress Corrosion Cracking n BWR Piping 7

93 (8098) Steam Binding of Auxiliary All PWRs C 2/86 Nauman-Grace letter of-Feedwater Pumps 2/14/86 and Generic Letter 88-03.

99 (L817) RCS/RHR Suction Line Valve All PWRs C - 5/90 TS Amendment #89 Interlock on PWRs Hayes-Bradham letter of 3/6/90. Modification 124 Auxiliary Feedwater System ANO-1&2, Rancho . tomplete 5/14/90.

Reliability Seco, Prairie NA Island 1&2, Crystal River-3 Ft. Calhoun A-13 (B017) Sndbber Operability Assurance - All Plants NC OL issued 10/82 Nydraulic Snubbers g - " " - ~ ' '

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GSI/(MPA No.1 TITLE -APPLICABILITY STATUS

• C0fetENTS1 A-13 (8022) Snubber Operability Assurance - All Plants- NC 'OL issued 10/82..

-Mechanical Snubbers -

A-16 (D012) Steam Effects on BWR Core Oyster Creek NA Spray Distribution & NMP-1 4

A-35 (8023) Adequacy of Offsite Power All Plants NC Systems NUREG-0717 --V.C. Summer SER Section 8.2.2 B-10 (Supplement 14)

Behavior of BWR Mark III All BWR Mark III NA Containments Plants' B-36 Develop Design, Testing and All. Plants with .NA OL application submitted, Maintenance Criteria for OL Applications 12/76.

Atmosphere Cleanup System' After 4/1/80 Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems B-63 (8045) Isolation of Low Pressure All Plants NC Systems Connected to the Reactor

. NUREG-0717.- V.C. Summer.l Coolant System Pressure SER Section 5.4.3.

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