ML20039B446
| ML20039B446 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/11/1981 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 15092, NUDOCS 8112230047 | |
| Download: ML20039B446 (2) | |
Text
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- o Consumers Power James W Cook Vice President - Projects, Engineering and construction General offices
- 1945 West Parnall Road, Jackson, MI 49201 * (517) 788 045J December 11, 1981 Harold R Denton, Director Office of Nuclear Reactor Regulation 6
j Division of Licensing US Nuclear Regulatory Commission Washington, DC 20555
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-,Ah MIDLAND PROJECT N.
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otgyd.y[ *h RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON GENERIC UNRESOLVED S?JETY ISSUES 9
REF: NRC (E G ADENSAM) LTR DATED 11/30/81
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FILE: 0505.8 SERIAL: 15092 4
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ENCLOSURE: SCOPE We have reviewed your request in the reference for additional information (Question 400.9).
We note that the Board has not made a final determination as to the admissibility of contentions 28-50 of Mrs. Mary Sinclair referred to in your letter. We also note from a review of Enclosure 2 to your letter and other recent SER's that the Staff has identified 17 Unresolved Safety Issues which it considers to be the substantive safety issues referred to by the Appeal Board in ALAB-444.
The enclosure delineates the proposed scope of the response. We have discussed the format and timing of our response with NRC Project Management and hereby request a meeting with the Generic Issues Branch at your earliest convenience in order to finalize the scope, content, and timing of the response.
JWC/TJS/jvm hOJ CC RJCook, Midland Resident Inspector
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RHernan, US NRC DBMiller, Midland Construction (3)
RWHuston, Washington UFI oc1281-0514a131 h223OO4781121T 4
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1 MIDLAND PIANT SCOPE: RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON GENERIC UNRESOLVED SAFETY ISSUES A.
Applicable Issues with NRC Staff Technical Resolution 1.
Asymmetric Blowdown Loads on Reactor Primary Coolant Systems (A-2) 2.
ATWS (A-9) 3.
Qualification of Class IE Safety-Related Equipment (A-24) 4.
Reactor Vessel Pressure Transient Protection (A-26).
5.
Residual Heat Removal Requirements (A-31) 6.
Control of Heavy Loads Near Spent Fuel (A-36)
B.
Applicable Issues for which NRC Staff Technical Resolution has not been Reached 1.
Waterhammer (A-1) 2.
Steam Generator Tube Integrity (A-5) 3.
Reactor 7essel Materials Toughness (A-11) 4.
Steam Generator and Reactor Coolant Pump Support (A-12) 5.
Systems Interaction (A-17) 6.
Seismic Design Criteria (A-40) 7.
Containment Emergency Sump Performance (A-43) 8.
Station Blackout (A-44) 9.
Shutdown Decay Heat Removal Requirements (A-45) 10.
Seismic Qualification of Equipment in Operating Plants (A-46) 11.
Safety Implications of Control Systems (A-47) 12.
Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment (A-48)
TJS 12/11/81 mil 281-0514b131