ML18051A541
| ML18051A541 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/15/1983 |
| From: | Johnson B CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8308220229 | |
| Download: ML18051A541 (3) | |
Text
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consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 August 15, 1983*
Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Connnission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - PALISADES HEAVY LOADS COMPLIANCE RESPONSE TO DRAFT TER C5506-379 NRC letter dated July 14, 1983 and entitled "Control of Heavy Loads Phase I" requested Consumers Power Company to respond to the three unresolved items indicated in Section 3.1 of the Draft Technical Evaluation Report (TER) on Heavy Loads proposed by NRC contractor, Franklin Research Center.
The three identified unresolved items and our responses are as follows:
No 1:
"Implement an acceptance and continuing compliance testing program for special lifting devices in accordance with Section 5.0 of ANSI N14.6-1978."
Response
When special lift devices, as defined by NUREG 0612, are purchased or fabri-cated, it will be specified that they be designed, fabricated and acceptance tested in accordance with ANSI Nl4.6-1978 and Section 5.1.1(4) of NUREG 0612.
Continuing compliance with Section 5.3 of ANSI Nl4.6-1978, as modified by the second consistent approach to Exception 3 on Page 8 of Reference 3 (ie, in lieu of a 150% load test, the critical welds will be subject to Non-Destructive Examination (NDE) at no greater than 5-year intervals), will be insured by including the modified Section 5.0 requirements in the 40-year In-Service Instruction (ISI) Master Plan.
This is considered adequate since the existing special lift devices are used during refueling outages.
8308220229 830815 PDR ADOCK 05000255 P
PDR OC0883-0011A-NL02
DMCrutchfield, Chief Palisades Plant HEAVY LOADS COMPLIANCE RESPONSE TO DRAFT TER C5506-379 August 15, 1983 2
No 2:
"Complete the assessment of the design of special lifting devices in accordance with sections of ANSI Nl4.6-1978."
Response
The design calculations of the (1) Reactor Vessel (RV) Head lift' device; (2) Upper Guide Structure (UGS) lift device; (3) Core Support Barrel (CSB) lift device; and, (4) Missile Shield Lift Device have been reviewed and all have safety factors in excess of 3 to yield strength and 5 to ultimate strength.
No impact testing was done on any of the materials used for fabrication; however, those metals used are stable at the ambient temperatures at which they are tised.
The RV head lift device, UGS lift device and CSB lift device have been used numerous times in the past 10 years without any indication of being strained beyond their design limits and have shown no adverse effects because of that use.
In view of this fact, our review of the design calculations, and the fact that the devices were built and designed by a NSSS and were subject to their quality control and quality assurance procedures, we believe that use of these devices does not adversely affect safety.
The missile shield lift device has been purchased within the past year and has not been used.
Each component of this device has been proof tested to at least 150% of its working load.
It is our judgment that use of this device will not adversely affect safety.
The enumerated special lift devices are used with the Reactor Building polar crane.
Maximum hoist speed of this crane is 6 fpm.
Dynamic loading caused by that hoist speed is considered negligible when considered in conjunction with the design safety factors.
No 3:
"Complete the design review of electrical overhead travelling cranes within the scope of NUREG 0612 to determine their equivalence, in matters related to load*handling reliability, to cranes designed and fabricated in accordance with CMAA;.,.70 and ANSI B30.2-1976."
Response
The design of the Reactor Building crane and the design of the Auxiliary Building crane were compared to the requirements of CMAA-70 and ANSI B30.2-1976 by the manufacturer - Dresser Industries.
In their opinion, the Auxiliary Building crane meets the mandatory electrical, structural and mechanical design requirements of CMAA~70 *and ANSI B30.2-1976.
The Reactor Building crane also meets these standards except.when a 135-ton load is OC0883-0011A-NL02
~..
DMCrutchfield, Chief Palisades Plant
- HEAVY LOADS COMPLIANCE RESPONSE TO DRAFT TER C5506-379 August 15, 1983 3
carried within* 6 feet of the bridge rail.
At this point a stress of 15.25 ksi is formed in the bridge end ties.
CMAA allows only 14.4 ksi.
This 0.85 ksi code overstress is considered as insignificant - especially when compared to the 17.6 ksi allowed in the bridge girders.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades OC0883-0011A-NL02