ML18057A310

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Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions.
ML18057A310
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/25/1990
From: Johnson B
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9006290048
Download: ML18057A310 (7)


Text

  • '*

consumers Power PDWERINli MICHlliAN'S PROliRESS General Offices: 1945 West Parnall Road, Jackson,' Ml 49201 * (517) 788-0550 June 25, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT RESPONSE TO GENERIC LETTER 90 STATUS OF GENERIC SAFETY ISSUES By letter dated April 25, 1990, NRC transmitted Generic Letter 90-04 entitled, "Request for Information on Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements on Corrective Actions." This letter provides Consumers Power Company's response to the Generic Letter for Palisades. Consumers Power Company has reviewed and reported on, by use of the attached table, the status of implementation of Generic Safety Issues which are applicable to Palisades.

~v~~<rr Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0690-0362-NL02 900t.29004::::

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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 ENCLOSURE 1 FROM GENERIC LETTER 90-04 STATUS OF GENERIC SAFETY ISSUES June 25 , 1990 5 Pages OC0690-0362-NL02

  • "I FACILITY NAME: PALISADES PLANT DOCKET NO: 50-255 LICENSEE: CONSUMERS POWER CO STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/(MPA No) TITLE APPLICABILITY STATUS COMMENTS 40 (B065) Safety Concerns Associated With All BWRs NA Pipe Breaks in the BWR Scram System 41 (B058) BWR Scram Discharge Volume Systems All BWRs NA 43 (B107) Reliability of Air Systems All Plants c Project complete. CPCo letter 7/15/90.

51 (L913) Improving the Reliability of All Plants I Projected Complete '92 REFOUT Open-Cycle Service Water Systems CPCo Letter 1/29/90 67.3.3 (A017) Improved Accident Monitoring All Plants c NRC SER 7/19/88 75* (B076) Item 1.1 - Post-Trip Review All Plants c NRC SER 11/5/85 (Program Description and 8/9/85 Procedure) 75 (B085) Item 1.2 - Post-Trip Review All Plants c NRC SER 6/30/86 Data and Information Capability Projected 9/1/90

  • 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.

OC0690-0362-NL02

---~---1 GSI/(MPA No) TITLE APPLICABILITY STATUS COMMENTS 75 (B077) Item 2.1 - Equipment Classi- All Plants c NRC SER 6/6/88 fication and Vendor Interface 12/10/87 (Reactor Trip System Components) 75 (B086) Item 2.2.1 - Equipment Classif i-cation for Safety-Related Components All Plants c NRC SER 8/21/88 e

75 (L003) Item 2.2.2 - Vendor Interface All Plants E Response due 9/21/90 for Safety-Related Components 75 (B078) Item 3.1.1 & 3.1.2 - Post- All Plants c NRC SER 8/15/85 Maintenance Testing (Reactor Trip System Components) 75 (B079) Item 3.1.3 - Post-Maintenance All Plants c NRC SER 4/22/86 Testing-Changes to Test Require-men ts (Reactor Trip System Components) 75 (B087) Items 3. 2.1 & 3.2.2 - Post- All Plants c NRC SER 8/15/85 Maintenance Testing (All Other Safety-Related Components) 75 (B088) Item 3.2.3 - Post-Maintenance All Plants c NRC SER 4/22/86 Testing-Changes to Test Require-men ts (All Other Safety-Related Components) 75 (BOSO) Item 4.1 - Reactor Trip System All Plants c NRC SER 8/15/85 Reliability (Vendor-Related Modifications)

OC0690-0362-NL02

GSI/ (MPA No) TITLE APPLICABILITY STATUS COMMENTS 75 (B081) Items 4.2.1 & 4.2.2 - Reactor All PWRs c NRC SER 6/19/85 Trip System Reliability -

Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 - Reactor Trip System All W and B&W NA Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor Trip System All W & B&W NA Reliability - Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B091) Item 4.4 - Reactor Trip System All B&W Plants NA Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

OC0690-0362-NL02

' 'l GSI/(MPA No) TITLE APPLICABILITY STATUS COMMENTS 75 (B092) Item 4.5.1 - Reactor Trip System All Plants c NRC SER 8/15/85 Reliability-Diverse Trip Features (System Functional Testing) 75 (B093) Items 4.5.2 & 4.5.3 - Reactor Trip All Plants c NRC SER 1/12/90 System Reliability - Test Alterna- NRC SER 1/12/90 tives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for Dealing All BWRs NA with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of Auxiliary All PWRs c NRC SER 5/25/88 Feedwater Pumps 99 (L817) RCS/RHR Suction Line Valve All PWRs I Projected complete date; Interlock on PWRs submittal of restructured Tech Specs - 1990. 6/28/89 124 Auxiliary Feedwater System AN0-1&2, Rancho NA Reliability Seco, Prairie Island 1&2, Crystal River-3 Ft Calhoun A-13 (BOl 7) Snubber Operability Assurance - All Plants c Tech Spec Amendment 3/12/82 Hydraulic Snubbers OC0690-0362-NL02

GSI/(MPA No) TITLE APPLICABILITY STATUS COMMENTS A-13 (B022) Snubber Operability Assurance - All Plants c Tech Spec Amend 3/12/82 Mechanical Snubbers A-16 (D012) Steam Effects on BWR Core Oyster Creek NA Spray Distribution & NMP-1 A-35 (B023) Adequacy of Offsite Power All Plants c Issue to be addressed in Systems restructured Tech Spec submitted 1990 per ltr 1/24/89 B-10 Behavior of BWR Mark III All BWR Mark III NA Containments Plants B-36 Develop Design, Testing and All Plants with NA Maintenance Criteria for OL Applications Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems B-63 (B045) Isolation of Low Pressure All Plants c NRG Letter 8/12/80 Systems Connected to the Reactor NRG order dated 4/20/81 ~

Coolant System Pressure Boundary OC0690-0362-NL02