ML19298E237
| ML19298E237 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/28/1990 |
| From: | Eddy J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-83-28, GL-90-04, GL-90-4, NUDOCS 9007050180 | |
| Download: ML19298E237 (8) | |
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@NFWERING C00SumBfS power MENNIAN'S PROGRE55 General of f stes-212 We,t Michipen Avenue. Jack son, Mi A9201 * (617) 788 05t>0 June 28, 1990 Nuclear Regulatory Commission Document Control Desk k'ashington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT RESPONSE TO GENERIC LETTER 90 STATUS OT GENERIC SAFETY ISSUFS 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 Big Rock Point. 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 Big Rock Point.
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J Daniel Eddy Plant Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point Attachment 9007050180 900<W pDR ADOCK 0500(
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4 ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 ENCLOSURE 1 FROM GENERIC LETTER 90-04 STATUS OF GENERIC SAFETY ISSUES June 28, 1990 6 Pages OC0690-0362-NLO2
FACILITY N/uME: BIG ROCK POINT DOCKET NO:
50-155 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 COW.ENTS 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) ltem 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
- Status column completed per attached guidance.
- The 16 items listed for GSI 75 all relate to setions derived from the generic implications of Salem AIWS events.
Item numbers correspond to Generic Letter 83-28 action item numbers.
OCC<90-0362-NLO2
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 (Reactor Trip System Components) 75 (B086)
Item 2.2.1 - Equipment Classifi-All Plants C
NRC SER 6/3/88 cation for Safety-Related Components 75 (LOO 3)
Item 2.2.2 - Vendor Interface All Plants E
Response due 9/24/90 for Safety-Related Components 75 (B078)
Item 3.1.1 & 3.1.2 - Post-All Plants C
NRC SER 11/19/85 Maintenance Testing (Reactor Trip System Components) 75 (B079)
Item 3.1.3 - Post-Maintenance All Plants C
NRC SER 11/19/85 Testing-Changes to Test Require-ments (Reactor Trip System Components) 75 (B087)
Items 3.2.1 & 3.2.2 - Post-All Plants C
NRC SER 11/19/85 Maintenance Testing (All Other Safety-Related Components) 75 (B088)
Item 3.2.3 - Post-Maintenance All Plants C
NRC SER 11/19/85 Testing-Changes to Test Require-ments (All Other Safety-Related Components) 75 (B080)
Item 4.1 - Reactor Trip System All Plants NA See GL 83-28 Reliability (Vendor-Related Modifications)
CC0690-0362-NLO2
GSI/(MPA No)
TITLE APPLICABILITY STATUS COMMENTS 75 (B081)
Items 4.2.1 & 4.2.2 - Reactor All PWRs NA Trip System Reliability -
Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082)
Item 4.3 - Reactor Trip System All V 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 V & 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-NLO2
GSI/(MPA No)
TITLE APPLICABILITY STATUS COMMENTS 75 (B092)
Item 4.5.1 - Reactor Trip System All Plants C
NRC SER 11/19/85 Reliability-Diverse Trip Features (System Functional Testing) 75 (B093)
Items 4.5.2 & 4.5.3 - Reactor Trip All Plants C
NRC SER 2/13/89 System Reliability - Test Alterna-NRC SER 8/10/89 tives and Intervals (System Functional Testing) 86 (B084)
Long Range Plan for Dealing All BWRs C
CPCo Letter 4/25/90 with Stress Corrosion IGSCC Program Rev 2 Cracking in BWR Piping 93 (B098)
Steam Binding of Auxiliary All PWRs NA Feedwater Pumps 99 (L817)
RCS/RHR Suction Line Valve All PWRs NA Interlock on PWRs 124 Auxiliary Feedwater System ANO-162, Rancho NA Reliability Seco, Prairie Island 162, Crystal River-3 Ft Calhoun A-13 (B017)
Snubber Operability Assurance -
All Plants NC NRC Letter 4/2/82 Hydraulic Snubbers OC0690-0362-NLO2
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
NRC Letter 8/12/80 Systems Connected to the Reactor NRC order dated 4/20/81 Coolant System Pressure Boundary OC0690-0362-NLO2
Attachment to From GL 90-04 GUIDANCE FOR COMPLETING STATUS COLUMN IN ENCLOSURE 1 1.
Provide a separate entry for each licensed reactor unit.
If the informa-tion is identical for multiple units, so state.
2.
If a GSI is not applicable to a unit (s), enter "NA".
3.
If a GSI is applicable but no changes were necessary to implement the resolution, enter "NC".
If the CSI implementation was completed prior to issuance of the operating license, enter "NC",
as no post-licensing changes were necessary.
4.
If a GSI is applicable, submittal of information and/or changes were necessary and such submittals were made or changes are complete, enter "C".
Also identify the licensee's document (s) to the NRC which certified completion, and the document date(s).
5.
If a GSI is applicable and changes are necessary but such changes are not yet fully implemented, enter "I" and the projected month and year of completion.
Provide a brief explanation of the outstanding work in the " Comments" column.
6.
If impicmentation guidance for a resolved GSI was issued recently at,d the licensee is still evaluating the appropriate response, enter "E" and the projected response date.
7.
The " Comments" column may be used to explain any entry in the " Status" column.
OC0690-0362-NLO2