ML20066J938
| ML20066J938 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/26/1982 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 3F-1182-09, 3F-1182-9, NUDOCS 8211290330 | |
| Download: ML20066J938 (3) | |
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.Po.w..e.._r November 26,1982
- 3F-1182-09 File: 3-0-3-a-6 Mr. John F. Stolz, Chief Operating Reactor Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0612 Control of Heavy Loads
Dear Mr. Stolz:
Florida Power Corporation hereby submits the following response to comments contained in your Draft Technical Evaluation and discussions with your staff concerning NUREG-0612.
Justification of Excluded Overhead Handling Systems it has been determined by Florida Power Corporation that the hand operated incore instrument Container Holst (ICHT-8), which is rated to I ton, is not required to perform lif ts in excess of 1000lb. This hoist is used during the installation and removal of incore instruments to pull and handle the incore instruments, lift miscellaneous tools, and transfer failed instruments to the fuel trr sfer carriage. None of the above mentioned lif ts meet the FPC criteria for a heavy loac Therefore, ICTH-8 will be administratively derated to a capacity of 1000lb and will be excluded from further NUREG-0612 consideration.
Lifting Devices (Not Specially Designed)
The results of an FRC evaluation of dynamic loads revealed that if a compensation factor of 1/2% of the static load /ffm crane hook speed is incorporated into the sling rating, a sufficient margin of safety will be attained. The hook speeds for non-exempt cranes at Crystal River Unit 3 are as follows:
FHCR-7 16.2 ft/ min FHCR-5 4.8 f t/ min C3 CWCR-1 14.3 ft/ min RCCR-1 4 ft/ min RCCR-2 27 ft/ min or 9 ft/ min SFHT-7 16.6 f t/ min
@211290330 821126 DR ADOCK 05000302 PDR General Office 3201 Thirty-fou in street sourn. P O Box 14042, st Petersburg. Rorda 33733 813-866-5151
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Mr. John F. Stolz Division of Licensing U. S. Nuclear Regulatory Commission Page To minimize the effects of dynamic loading during lifts performed by RCCR-2 the high speed (27 ft/ min) switch will be disconnected. Based on this data and the FRC evaluation, all slings and other special lifting devices not specially designed have been derated by 10%
to compensate for dynamic loading.
Special Lifting Devices Florida Power Corporation is currently evaluating a proposal from Babcock & Wilcox to supply information concerning the design of special lif ting devices. The analysis of this information will be submitted in conjunction with our nine (9) month report which is currently scheduled to be completed by October 31,1983.
Because facilities to perform an NDE on the reactor vessel head and internals lifting device were not available during Cycle IV, the NDE will not be performed until Cycle V. Several options are currently being considered to provide the necessary facilities to perform the examination.
Safe Load Paths As previously discussed in our June 15, 1982 letter, Florida Power Corporation is using a comprehensive set of administrative controls to assure that safe load paths are followed for critical lif ts in the reactor building. It was stated in the letter that: the Reactor Building Coordinator and the Shift Supervisor will approve all lif ts. This should be changed to state that the Reactor Building Coordinator or the Shift Supervisor will approve alllifts inside the Reactor Building.
Similar administrative controls will be used to control heavy loads in other critical areas.
During a refueling outage (or other major outages) an Auxiliary Building Coordination (ABC) will be present in the auxiliary building to supervise and coordinate operations. The ABC will be familiar with NUREG-0612 requirements and aware of safe load handling practices.
During operations, when an ABC is not assigned, the Shift Supervisor or a position similarly qualified in NUREG-0612 requirements will assume the same responsibilities.
All lifts involving FHCR-3 sr FHCR-7 will be approved by the ABC, or the Shif t Supervisor or his designee prior to the lift. There is only one load path available to SFHT-7, therefore, these Administration Controls will not be applied to this crane.
The Maintenance Supervisor or his designee in charge of the work will approve all lifts involving CWCR-1.
The Maintenance Supervisor will be aware of NUREG-0612 requirements concerning CWCR-1 and will assur that his designee is similarly informed.
Crane Design As stated in our June 15, 1982 letter, a analysis of the Intake Structure Gantry Crane CWCR-1 will be submitted as part of the nine (9) month report.
N Mr. John F. Stolz Division of Licensing U. S. Nuclear Regulatory Commission Page Requirements for structural changes to the Reactor Building Polar Crane RCCR-1 and the Auxiliary Building Crane FHCR-5 will be determined subsequent to Florida Power Corporation's review of the Crane Design Evaluation (submitted June 15,1982) and the load drop analysis (to be submitted with the nine (9) month report. This will allow FPC to evaluate and schedule all of the proposed modifications in an efficient and cost effective manner.
Heavy Loads over Spent Fuel A detailed analysis to determine whether the spent fuel pool missile shields can withstand the impact of the 5 ton hydraulic jack used to retension the reactor containment tendons, will be performed and submitted with the nine (9) month report.
Tendon inspection is required every five (5) years and was last completed during Refuel 111 in 1981. Therefore, the hydraulic jack will not have to be used until 1986. Prior to the next use of the 5 ton jack, the analysis will be complete and requirements will be addressed in technical specifications at that time.
Should there be further questions, please contact this office.
Very truly ygu s i
i}lGNEDpy.
P. Y. Baynard Assistant to the Vice President Nuclear Operations DP/ mig I
cc:
Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 3100 l
Atlanta, Ga. 30303 l
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