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-20 -PALISADES PLANT RESPONSE TO GENERIC LETTER 90-04 -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.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector

-Palisades Attachment OC0690-0362-NL02 900t.29004::::

PDF\ A:OOCK p A CMS ENERGY COMPANY OC0690-0362-NL02 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 FACILITY NAME: PALISADES PLANT DOCKET NO: 50-255 LICENSEE:

CONSUMERS POWER CO STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES GSI/(MPA No) 40 (B065) 41 (B058) 43 (B107) 51 (L913) 67.3.3 (A017) 75* (B076) 75 (B085) RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS TITLE Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR Scram Discharge Volume Systems Reliability of Air Systems Improving the Reliability of Open-Cycle Service Water Systems Improved Accident Monitoring Item 1.1 -Post-Trip Review (Program Description and Procedure)

Item 1.2 -Post-Trip Review Data and Information Capability APPLICABILITY STATUS All BWRs NA All BWRs NA All Plants c All Plants I All Plants c All Plants c All Plants c *"I COMMENTS Project complete.

CPCo letter 7/15/90. Projected Complete '92 REFOUT CPCo Letter 1/29/90 NRC SER 7/19/88 NRC SER 11/5/85 8/9/85 NRC SER 6/30/86 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

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-All Plants c NRC SER 8/21/88 e cation for Safety-Related Components 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 GSI/(MPA No) 75 (B092) 75 (B093) 86 (B084) 93 (B098) 99 (L817) 124 A-13 (BOl 7) OC0690-0362-NL02 TITLE Item 4.5.1 -Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing) Items 4.5.2 & 4.5.3 -Reactor Trip System Reliability

-Test tives and Intervals (System Functional Testing) Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Auxiliary Feedwater System Reliability Snubber Operability Assurance

-Hydraulic Snubbers APPLICABILITY All Plants All Plants All BWRs All PWRs All PWRs AN0-1&2, Rancho Seco, Prairie Island 1&2, Crystal River-3 Ft Calhoun All Plants STATUS c c NA c I NA c COMMENTS NRC SER 8/15/85 NRC SER 1/12/90 NRC SER 1/12/90 NRC SER 5/25/88 ' 'l Projected complete date; submittal of restructured Tech Specs -1990. 6/28/89 Tech Spec Amendment 3/12/82 GSI/(MPA No) A-13 (B022) A-16 (D012) A-35 (B023) B-10 B-36 B-63 (B045) OC0690-0362-NL02 TITLE Snubber Operability Assurance

-Mechanical Snubbers Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems Behavior of BWR Mark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary APPLICABILITY All Plants Oyster Creek & NMP-1 All Plants All BWR Mark III Plants All Plants with OL Applications All Plants STATUS c NA c NA NA c COMMENTS Tech Spec Amend 3/12/82 Issue to be addressed in restructured Tech Spec submitted 1990 per ltr 1/24/89 NRG Letter 8/12/80 NRG order dated 4/20/81