ML20044A001

Provides Current Implementation Status of Generic Safety Issues at Plant,In Response to Generic Ltr 90-04

ML20044A001
Person / Time
Site:	Point Beach
Issue date:	06/18/1990
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-90-060, CON-NRC-90-60, TASK-***, TASK-OR GL-90-04, GL-90-4, VPNPD-90-301, NUDOCS 9006270285
Download: ML20044A001 (6)

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l Wisconsin Electnc PONER COMPANY 231 W Michgn Po Box 204$. MitwoAee. WI 53201 (414)221-2345 VPNPD-90-301-NRC 060 I-June 18, 1990 U. S. Nuclear Regulatory Commission

. Document Control Desk Mail Station P1-137 Washington, DC 20555 Gentlemen DOCKET Nos. 50-266 and 50-301 RESPONSE TO GENERIC LETTER 90-04 STATUS OF IMPLEMENTATION OF GENERIC SAFETY ISSUES POINT BEACH NUCLEAR PLANT UNITS 1 & 2 Enclosed are completed documentation sheets indicating the status of the implementation of generic safety issues (GSI) as identified in Generic Letter 90-04 dated April 25, 1990. This status summary provides the current implementation status for each of the GSIs identified in your letter for the Point Beach Nuclear Plant.

Except as indicated otherwise,-the listed status and completion dates-are applicable for both Point Beach Nuclear Plant units.

Please contact us if you have any questions concerning this summary.

Very truly yours pn /

C. W. F y Vice President Nuclear Power C,WK/ dad Enclosures Copy to: NRC. Regional Administrator, Region IV NRC Resident Inspector 01{:

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FACILITY NAME: POINT BEACH NUCLEAR PLANT, Units 1 and 2 .

DOCKET NO.: 50-266 and 50-301 LICENSEE: Wisconsin Electric Power Company STATUS OF LICENSEE IMPLEMF3fTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIRENENTS OR CORRECTIVE ACTIONS

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GSI/(MPA No.1 TITLE APPLICABILITY STATUS

• CONMFETS 40 (B065) Safety Concerns Associated All BWRs NA with Pipe Breaks in BWR Scram System 41 (B058) BWR Scram Discharge Volume All BWRs NA Systems LTR 7/27/89 IA accum-43 (B107) Reliability of Air Systems All Plants I U1 5/91 ulators for crossover U2 11/90 steam dump system 51 (L913) Improving the Reliability All Plants I U1 5/91 Inspection and cleaning i of Open Cycle Service Water U2 11/90 of piping and Hx. instru-Systems mentation for fan coolers 67.3.3 (A017) Improved Accident Monitoring All Plants C NRC SER 7/11/86' 75** (B076) Item 1.1 - Post-Trip Review All Plants C NRC SER 7/29/85 (Program Description and WE LTR 11/7/83 Procedure) and 9/10/85 75 (ABO 85) Item.1.2 - Post-Trip Review All Plants C NRC SER 10/2?/85 Data and Information Capability WE LTR 4/11/86

• 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 Salen ATWS events. Item numbers correspond to Generic Letter 83-28 83-l 28 action item numbers.

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GSI/(MPA No.1 TITLE APPLICABILITY STATUS

• CosentuTS 75 (B077) .T. tem 2.1 - Equipment All Plants C NRC SER 6/21/88 .

Classification and Vendor WE LTR 3/27/87 Int.erface (Reactor Trip 5/11/88 System components) 75 (B086) Item 2.2.1 - Equipment All Plants C NRC SER 12/11/89 Classification for WE LTR 3/27/87 Safety-Related Components 75 (LOO 3) Item 2.2.2 - Vendor Inter- All Plants E GL 90-03 9/1990 face for. Safety-Related Components 75 (B078) Items 3.1.1 & 3.1.2 - All Plants C Post-Maintenance Testing WE LTR 4/11/86 NRC SER 10/24/85 (Reactor Trip System components) 75 (B079) Item 3.1.3 - Post- All Plants NC Maintenance Testing-Changes WE LTR 11/7/83 NRC SER 10/18/85 to Test Requirements (Reactor Trip System Components) 75 (B087) Item 3.2.1 & 3.2.2 - All Plants C Post-Maintenance Testing WE LTR 4/11/86 NRC SER 2/5/87 (All Other Safety-Related Components) 75 (B088) Item 3.2.3 - Post- All. Plants NC Maintenance Testing-Changes WE LTR 11/7/83 NRC SER 10/18/85 to. Test Requirements (All Other Safety-Related Compo-nents) 75 (B080) Item 4.1 - Reactor Trip All Plants NC System Reliability (Vendor- WE LTR 11/7/83 NRC SER 10/24/85 Related Modifications)

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i' APPLICABILITY STATUS

• COMMENTS GSI/(MPA No.} TITLE Items 4.2.1 & 4.2.2 - Reactor Ali.PWRs C 75 (8081). WE LTR 11/7/83 NRC SER 5/16/85 Trip System Reliability-Maintenance and Testing .

12/28/84 >

(Preventative Maintenance and .

Surveillance Program for Reactor Trip Breakers)

Item 4.3 - Reactor Trip System - All W and 88W C j 75 (8082) WE LTR 4/11/86 NRC SI' 9/26/84 -

! Reliability - Design Modifications Plants (Automatic Actuation of Shunt Trip 5/13/87 ,

Attachment for Westinghouse and B&W ~

Plants)

Item 4.3 - Reactor Trip System All W & 88W C l 75 (8090) Plants WE LTR 8/8/85 NRC SER 6/17/86

' Reliability - Tech Spec Changes l (Automatic Actuation of Shunt LIC AMDS 100 U1 Trip Attachment For Westinghouse 103 U2 and 88W Plants) l Item 4.4 - Reactor Trip System All 88W Plants NA 75 (8091)

Reliability (Improvements in P.a intenance and Test Procedures for B&W Plants)

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APPLICABILITY STATUS

• COFMENTS GSI/(MPA No.) TITLE 75 (B092) Item 4.5.1 - Reactor Trip System All Plants C Reliability-Diverse Trip Features WE LTR 11/7/83 NRC SER 10/24/85 '

(Systen Functional Testing) 4/11/86 15 (8093) Items 4.5.2 & 4.5.3 - Reactor Trip All Plants C System Reliability - Test Alterna- WE LTR 4/11/86 NRC SER 6/14/89 '

tives and Intervals (System Functional Testing) 86 (8084) long 'tange Plan for Dealing All BWRs NA with Stress Corrosion Cracting in SWR Piping 93 (8098) Steam 3inding of Auxiliary All PWRs C ,

Feedwater Pumps WE LTR 2/25/86 NRC LTR 4/12/88 3/23/88 99 (LS17) RCS/RHR Sc tion Line Val e All PWRs C Interlock on PWRs 4/07/90 WE LTRS 12/30/88 2/02/89 124 Auxiliary Feedwater System AND-1&2, Rancho NA Reliability Seco. Prairie 1sland 1&2, Crystal River-3 ,

Ft. Calhoun .

Sndber Operability Assurance - All Plants C NRC SER 5/25/82 P.-13 (3017)

Hydraulic Snubbers LIC. Amends Uh69 U$4

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5-TITLE APPLICABILITY STATUS

• COMMENTS GSI/(MPA No.)

A-13 (8022) Snubber Operability Assurance - All Plants NA WE LTR 2/19/81  !

Mechanical Snubbers -

4 A-16 (D012) Steam Effects on SWR Core Oyster Creek NA

Spray Distribution & MMP-1  ;

A-35 (8023) f,de-;_::y of Offsite Power All Plants C WE LTR - 9/30/83 Systees B-10 8ehavior of WWR Mark III All WWR Mark III NA Containments Plants  !

8-36 Develop Design, Testing and All Plants with . NA Maintenance Criteria for OL Applications  ;

Atmosphere Cleanrp System After 4/1/90 i Air Filtration md Adsorption

Units for Egineered Safety ,

Features Systems and for .

Moreel Ventilation Systems' B-63 (8045) Isolation of Low Pressure - All Plants C - WE LTR 5/18/81 i Systems Connected to the Reactor Coolant System Pressure ,

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