ML20054G404

Forwards Crane Design Evaluation for Crystal River Unit 3: Comparison to NUREG-0612, in Response to NRC 820120 Request for Addl Info Re NUREG-0612, Control of Heavy Loads

ML20054G404
Person / Time
Site:	Crystal River
Issue date:	06/15/1982
From:	Mardis D FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20054G405	List: ML20054G404 ML20054G419
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 3F-0682-17, 3F-682-17, NUDOCS 8206210524
Download: ML20054G404 (6)

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1. 3F-0682-17 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:

By letter dated January 20, 1982, you forwarded comments to Florida Power Corporation based upon your consultants review of previous submittals pertaining to control of heavy loads (NUREG-0612). In light of your Draf t Technical Evaluation Report and discussions with your staff, Florida Power Corporation hereby provides responses to your January 20,1982 request for additional information.

Safe Load Paths Although Florida Power Corporation has not committed to permanently marking load patt s, through the use of a comprehensive set of administrative controls, the intent of NUREG-0612 has been met. In compliance with Crystal River Unit 3 (CR-3) Technical Specifications, a Senior Reactor Operator (SRO) will directly supervise all core alterations af ter the initial fuel loading. The SRO in charge of the alterations will have no other concurrent responsibilities during those operations. A Reactor Building Coordinator (RBC) will be present in the reactor building to supervise and coordinate operations. The RBC will be familiar with NUREG-0612 requirements and aware of safe load handling procedures. All lif ts will be approved by the RBC and the Shif t Supervisor prior to the lift. In addition, written procedures containing figures designating the proper load paths have been prepared. In conjunction with the use of the load path diagrams, the person in charge of the lif t will have the option of using visual reinforcements to temporarily mark the load paths when he determines they are necessary.

Procedures A list of procedures applicable to NUREG-0612 is presented in Attachment 1. A typical CR-3 procedure for crane operation will contain the following information. I o5$

8206210524 920615 PDR ADOCK 05000302 PDR p

General Office 320i thirty-fourin street soutn. P O Box 14042. St Petersburg. Florda 33733 813-866-5151

Mr. John F. Stolz

1. 3F-0682-17 Page 1. A description of the overhead handling system to be used including the type of crane, its rating, type of drive units, type of hoists, controls, and the applicable limit switches and wheel stops.

2. References to other applicable procedures.

3. The limits and precautions for handling particular loads.

4. Setpoints.

5. General Crane Operating Procedures describing handling of the bridge travel, trolley travel, and hoist motion; the use of appropriate hand signals; and procedures for preoperational checkout and visual inspection.

6. Post-operational checkout procedures.

7. Design data, including maximum loads and equipment speeds.

8. Attachments including a crane load matrix and safe load path sketches.

Deviation from Procedures When it is not possible to follow a safe load path or a safe load path does not exist for the particular load to be moved, a tenporary procedure change request must be processed in accordance with Administrative Instruction Al-400. This requires that authorization for the change be acquired from the Nuclear Operations Shif t Supervisor.

It must also be authorized by a supervisor, determined by the Shift Supervisor to be qualified in the {scipline for which the change is generated, or by the Nuclear Operations Tech deal Advisor.

Temporary changes to procedures are reviewed by the Plant Review Committee (PRC) within fourteen (14) days. These changes will not alter the intent of the original procedure.

Slings and Lif ting Fixtures The procedures for testing and tagging slings and other special lif ting fixtures are defined in Surveillance Procedure SP-601 (Table 1). The procedures for tding include requirements for visual inspection, load testing, and magnetic particle or liquid penetrant testing.

Subsequent to the tests or examination, each sling and associated lif ting hardware (shackles, eyebolts, links, etc.) is tagged. The tags denote (1) the use load and (2) the test / examination date marked on the compression sleeve or the metal tag.

t _. . . - - - -_ __. _ - .

Mr. John F. Stolz

1. 3F-0682-17 Page Intake Structure Gantry Crane The procedures for operating the intake structure gantry crane (GWCR-1) are described in Operating Procedure OP-421-F. The gantry crane is used primarily for pulling the circulating water pumps and motors for maintenance and for pulling the stop-logs in the intake structure. The pump maintenance area is located on the western side of the intake structure while the storage area for the stop-logs is located in the eastern section of the intake structure.

The essential equipment located in the intake structure are two 48" conduits that carry water to the N 6 ear Service Sea Water (NSSW) pumps. There are no valves or pumps associated witn this system that are located in the intake structure. The conduits traverse the crane runway at the extreme eastern end of the intake structure.

The use of exclusion areas in this situation is believed to meet the objectives of the NRC guidelines. Because the essential equipment occupies only a small portion of the crane's operational area, the protection of the NSSW conduits is accomplished most effectively through the use of exclusion zones while lif ts made in areas where there is no essential equipment are not unnecessarily restricted.

Spent Fuel Shipping Casks FPC will develop procedures in compliance with NUREG-0612 for handling spent fuel shipping casks. This procedure will be prepared prior to the use of these casks.

Crane Design Attachment 2 is a report on the analysis performed on the reactor building polar crane and the auxiliary building crane. The analysis of the intake structure gantry crane will be completed by June 15,1983 (i.e., as part of the 9-n , nth report).

Training Procedures The program developed by FPC for training, qualification, and conduct of crane operators has been prepared in compliance with the requirements of ANSI B30.2-1976.

Special Lif ting Devices FPC is currently pursuing with another Babcock & Wilcox utility, the possibility of a cost sharing program for the analysis of special lif ting devices. The analysis is complete, and only the financial arrangements must be settled before the analysis can be obtained. Submittal of this analysis is scheduled for August 1,1982.

Dynamic Loading FPC is obtaining crane maximum hook speeds to determine if the consideration of dynamic loading is necessary. Efforts to obtain accurate values has taken longer than anticipated. Submittal of the results of this determination is scheduled for August 1, 1932.

Mr. John F. Stolz

//3F-0682-17 Page Load Testing Load testing following maintenance and inspection by both operating and non-operating personnel is performed as required by Surveillance Procedure SP-601, " Procedure for Load Testing Slings and Lifting Fixtures."

Heavy Loads Over the Spent Fuel Pool

1. Reactor Building Mechanized Scaffolding The reactor building mechanized scaffolding will not be used to retension-the reactor containment tendons. The final disposition of the scaffolding is currently being considered.

2. Five Ton Hydraulic Jack A detailed structural analysis will be performed 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. This analysis will be included in our 9-month report.

3. Spent Fuel Pool Missile Shields As discussed in the CR-3 Final Safety Analysis Report Section 9.6.1.5, the spent fuel pool missile shields have been designed to float. Therefore, the spent fuel is not considered a possible load drop target for the missile shields. For this reason, the missile shields should be excluded from consideration.

4. Spent Fuel Pool Divider Gates The question of the spent fuel pool divider gates is lef t open. It will be addressed in the 9-month report.

Special Reviews for Heavy Loads Over the Core The requirements of this section were met and implemented, as listed below, prior to the use of the applicable equipment during the 1981 refueling. Implementation has been achieved through the use of the procedures in Attachment 1.

1. Procedures for installation of rigging or lif ting devices and movement of loads were reviewed.

2. Visual inspections of load bearing components of cranes, slings, and special lifting devices were made in accordance with the appropriate procedures.

Mr. John F. Stolz

//3F-0682-17 Page 3. Appropriate repairs or replacement of defective components were made.

4. Crane operators have been properly trained and are familiar with the specific procedures used.

Should there be further questions, please contact this office.

Very truly yours, 0)w S David G. Mardis Acting Manager Nuclear Licensing KRW:mm Attachments cc: Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303

. ATTACHMENT 1 CR-3 PROCEDURES THAT ARE DIRECTLY APPLICABLE TO NUREG 0612.

Administrative Instructions Al-400 Plant Operating Quality Assurance Manual Control Document Operating Procedures OP-421 Operation of CR-3 Overhead Cranes and Hoists OP-421-A Operation of the Reactor Building Polar Crane (RCCR-1) .

OP-421-C Operation of the Auxiliary Building Overhead Crane (FHCR-5)

OP-421-D Operation of the Missile Shield Gantry Crane (FHCR-7)

OP-421-E Operation of the Reactor Vessel Tool Handling Jib Crane OP-421-F Operation of Intake Structure Gantry Crane Surveillance Procedures SP-530 Demonstration of Auxiliary Building Overhead Crane (FHCR-5) Interlock Operability SP-531 Spent Fuel Handling Bridge Interlock Surveillance SP-532 Reactor Building Main and Auxiliary (FHCR-1 and FHCR-2) Fuel Handling Bridges Electrical Interlock Surveillance SP-601 Procedure for Load Testing Slings and Lif ting Fixtures Preventive Maintenance Procedures PM-109 Inspection and Maintenance of Miscellaneous Cranes and Hoists PM-143 Inspection and Maintenance of Whiting Cranes PM-144 Inspection and Maintenance of Electrical Components of Cranes and Hoists Performance Testing Procedures PT-202 Auxiliary Building Overhead Crane Load Test PT-203 Reactor Building Polar Crane Load Test PT-204 Miscellaneous Cranes and Hoists Load Test