ML17212A504

Forwards Response to 801222 Generic Ltr Re Control of Heavy Loads.Guidelines Published in NUREG-0612, Control of Heavy Loads, Addressed.Review Ongoing.Final Rept Will Be Submitted by 810930.Diagrams & Tables Encl

ML17212A504
Person / Time
Site:	Saint Lucie
Issue date:	08/06/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0612, RTR-NUREG-612 GL, L-81-338, NUDOCS 8108110495
Download: ML17212A504 (31)

Text

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'CCESSION 'NBR:8108110495 DOC ~ DATE', 81/08/06 NOTARIZED!: NO DOCKEiT ¹ FACILi:50 389 St+ Lucie Planti Unit 2<. Fl or ida Power 8 Ligh't" Co>', 05000389 AUTH', NAME~ AUTHOR AFFILIATION UHRIGg R E", ~ Florida Power 8 Light Co, RKCIP VAMKt

~ RECIPIENT AFFIL'IATION EISENHUT'iD.G ~ Division of Licensing

SUBJECT:

Forwards response to 801222'eneric l tr re contr ol of he'avy loads. Guidelines published in NUREG-0612~ "Control of Heavy Loads~" addressed. Review ongoing, Final, rept will be.

submitted by 810930 Diagj ams L tables encl.

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DISTRIBUTION CODE!t B030S COPIES RECEIVED: LiTR ENCL' SIZE'4:

Contr ol of Heavy Loads- Near. Spent Fuel (USIA A 36) PRE OLt 'ITLE~:

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>Qll/yz i/trwt FLORIDA POWER & LIGHT COMPANY August 6, 1981 L-81-338 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: St. Lucie Unit 2 Docket No. 50-389 Control of Heav Loads Attached is Florida Power 8 Light Company's (FPL) initial response to the NRC letter dated December 22, 1980 concerning the control of heavy loads. The letter requested FPL review the controls for handling heavy loads at St. Lucie Unit 2 and determine the extent to which the NRC guidelines published in NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants", will be met when the unit becomes operational. This report provides the information requested in Section 2. 1 of Enclosure (3) to the Generic Letter. FPL is continuing its review and a final report providing the information requested in Sections 2.2, 2.3, and 2.4 of that letter will be submitted to you at the end of September.

Very truly yours, Rob t E. Uhrig ice President Advanced Systems 5 Technology REU/TCG/ah Qo>O Attachment cc: J. P. O'Reilly, Director, Region II (w enclosure)

Harold F. Reis, Esquire (w/o enclosure)

Si08ii0495 Si0806 PDR ADOCK 05000389' PDR PEOPLE... SERVING PEOPLE

ST. LUCIE UNIT 2 RESPONSE TO NRC RE UEST FOR ADDITIONAL INFORMATION ON CONTROL OF HEAVY LOADS (SECTION 2.1)

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TABLE OF CONTENTS Section Title ~Pa e Introduction Identification of Plant Load Handling Systems Safe Load Paths IV Special Procedures Lifting Devices VI Crane Inspection, Testing and Maintenance .3'III VII Crane Design Summary IX References A endices A. Tables Table l Listing of All Plant Heavy Load Handling Systems

,Table 2 Listing of Major Heavy Loads Periodically Handled in the Vicinity of Irradiated Fuel B. Safe Load Paths Sketches Sketch 1 Reactor Building Cranes Sketch 2 Fuel Cask Crane Sketch 3 Pump Room Monorails Sketch 4 Intake Structure Bridge Crane Sketch 5 Turbine Gantry Crane Sketch 6 Component Cooling Mater Pump Monorail

1. Introduction On December 22, 1980 the NRC issued a generic letter on the subject of control of heavy loads. The letter requests Plorida Power and Light Company to review the controls for handling heavy loads at St.

Lucie Unit No. 2 and to determine the extent to which the NRC guide-lines published in NUREG 0612 will be met when the plant becomes operational. The letter further requests that a report be submitted in two parts addressing general and specific requirements respectively for overhead handling systems. Part one of the report is submitted here. Sections II thxu VII provides the information requested by Section 2.1 of Enclosure 3 of the NRC generic letter. Section VXll provides a summary.

IX. Identification of Plant Load Handlin S stems Section 2.J..l and 2.1.2 of Enclosure 3 of the NRC December 22, 1980, letter requests a xeview of plant arrangements to identify all heavy load handling systems. It also requests a determination of those load handling systems from which a load drop could damage i.rradiated fuel ox safety-related systems.

A complete listing of al1 heavy load handling systems has been prepared for St. Lucie Unit No. 2 (a heavy load for St. Lucie Unit No. 2 as defined in, NUREG 0612 is approximately 1380 pounds). Each system was visually inspected in the field where possible or reviewed on the drawings and classified into Groups I and II as follows:

Group I Heavy load handling systems from which a load drop could conceivably result in damage to irradiated fuel or systems required for plant shutdown or decay heat removal taking no credit for interlocks, technical specifications, operating procedures, detailed structural analysis ox system redundacy.

Group II Heavy load handling systems excluded from Group I based upon a determination by inspection that there is sufficient physical separation from any load-impact point and any safety related component.

Table I in Appendix A provides this listing and classification.

III. Safe Load Paths Sections 2.3(a) and (b) of Enclosure 3 of the NRC generic letter request drawings ox sketches identifying safe load paths and a discussion of measures taken to ensure that operators reamin within these areas.

Page 1 of 5

P Safe load paths have been defined as requested and ax'e shown on Sketches 1 thru 6 in Appendix B. All of the Group I load handling systems have safe load paths defined except for the following with the reasons given below:

1. Refueling Machine

2. Fuel Transfer Machine

3. Spent Fuel Bridge Crane These devices are used during refueling operations and do not handle loads weighing more than one spent fuel assembly wi.th a handling tool.

The consequences of a fuel handlind accident have been evaluated in the FSAR and offsite doses were determined to be within acceptable limits.

Also the operation of this equipment is described in detail in the Technical Specifications and the FSAR.

4. Refueling Canal Bulkhead Monorail

5. Cask Storage Pool Bulkhead Mnorail Due to the physical configuration of these monorails, load handling is restricted to one path. Special procedures for the handling of the bulkheads by these monorails will be prepared however, to minimize the potential of a load drop near spent fuel.

6. Charging Pump Monorails

7. Diesel Generator Monorails Each Diesel Generator and Charging Pump has its own monorail, physically separated from other safety related equipment. These monorails are used solely for the purpose of servicing the Charging Pumps and Diesel Generators and are physically incapable of carrying loads over other safety related equipment. The Technical Specifications:require that sufficient backup equipment must be operational for a piece of equipment to be taken out of service for maintenance. Therefoxe, a heavy load can only fall on a pump or generator which i.s not required for plant safe shutdown.

The St. Lucie Unit No. 1 plant administrative procedure AP0010438 "Control of Heavy Load Lifts" describes the measures taken to ensure that load handling operations remain within safe load paths and defines these areas.

Any deviation from the safe load area requires prior Facility Review Group approval. This administrative proceduxe was prepared as part of the interim actions required in the NRC December 22, 1980 generic letter for Unit No. 1 and is available at the plant for review. This procedure will be revised to include Unit No. 2 heavy load handling when that unit

'becomes operational.

Page 2 of 5

IV. S ecial Procedures Section 2.1.3 (c) of Enclosure 3 of the NRC generic letter requests that heavy loads listed in Table 3-1 of NUREG 0612 be tabulated along with the load weight, designated lifting device and special handling pxoceddxe. These are significant heavy loads which are periodically handled in the vicinity of irradiated fuel in the reactor core or spent fuel pool.

Table 2 in Appendix A of this report provides this 'tabula.ation and lists the special procedures developed for Unit No. 1 which follow the guidelines of NVREG 0612 Section 5.1.1 (2) for these loads.

Special procedures for the handling 'of the refueling canal bulkhead pressurizer missile shield and Xn-Service-Inspection tool are being developed for Unit No. l. All of these 'procedures will be revised to include Unit No. 2 when that plant becomes operational. A special procedure for the handling of the cask storage pool bulkhead will be developed for Unit No. 2 and implemented when required. All of th'ese above mentioned procedures will be available at the plant for review.

V. Liftin Devices (slin s, beams and s ecial ri in s)

Section 2.3,.3 (d) of Enclosure 3 of the NRC generic letter requests that lifting devices comply with AHSX B30.9-1971 or ANSX N14.6-19/8,'s applicable. t The current St. 'Lucie Unit No. 1 plant administrative procedure AP0010438 is being revised to require that lifting devices for all load handling systems in Group I meet the requirements of these ANSI standards. This revision will be completed and in effect prior to Unit No. 2 operation. This procedure will include Unit No. 2 in its scope when that unit becomes operational.

VX. Crane Xns ection, Testin and Maintenance Section 2.1.3 (e) of Enclosure 3 of the NRC generic letter requests verification that ANSX B30.2-1976 Chapter 2-2 has been invoked with respect to crane inspection, testing and maintenance.

The St. Lucie Unit No. 1 program for crane inspection, testing and maintenance will follow this ANSX standard at the time Unit No. 2 becomes operational and will include Unit No. 2 within its scope at that time and will be available at the plant for review.

Section 2.1.3 (f) of Enclosures 3 of the NRC generic letter requests verification that crane design complies with the guidelines of the Crane Manufacturers Association of America Specification 70 "Specifi-cations for Electric Overhead Traveling Cranes" (CMAA //70) and Ch'aptex 2-"1 of ANSI B30.2l".1976 "Overhead and Gantry Cranes."

Page 3 of 5

The design of load handling systems follow CHAA I/70 or CMAA //74, "Specification for Top Running and Under Running Single Girder Electric Overhead Traveling Cranes" as applicable. The OSHA (Occupational Safety and Health Administration) safety requirements, which include the ANST requirements, are followed in the design.

VIII . ~Summam This report documents the first phase of Florida Power and Light Company's review of the controls fox the handling of heavy loads at the St. Lucie Unit No. 2 plant when the plant becomes operational as requested by the NRC generic letter dated 12-22-80. The second phase of oux xeview is underway and a report is scheduled to be submitted by the end of September. This report will provide the specific information requested in sections 2.2, 2a3 and 2.4 of the NRC generic letter.

Page 4 of 5

IX. References

1. NUREG-0612 "Control of Heavy Loads at Nuclear Power Plants"

2. NRC Generic Letter "Control of Heavy Loads" dated December 22, 1980.

3. Enclosure 3 of Generic Letter "Request for Additional Infor-mation on Control of Heavy Loads"

4. ANSI B30.2-1976 "Overhead and Gantry Cranes"

5. ANSI B30.9 1971 "Slings"

6. ANSI N14.6 1978 "Standard for Special Lifting Devices fox Shipping Containers Weighing 10,000 pounds (4500 kg) or More for Nuclear Materials"

7. Crane Manufacturers Association of America (CMAA) Specification 70 "Specifications for Electric Overhead Traveling Cranes"

8. Electric Overhead Crane Institute (EOCI) Specification 63; "Specifications for Electric Overhead Traveling Cranes" St. Lucie Unit No. 1 Procedures:

9. Plant Maintenance Procedure M-0015 "Reactor Vessel Maintenance Sequence of Operations"

10. Plant Maintenance Procedure M-0913 "General Operating Procedure for Handling and Loading of the NFS-4 Cask"

11. Plant Operating Procedure OP-1630022 "Spent Fuel Handling Machine Operation"

12. Plant Operating Proceduxe OP-1630023 "Fuel Transfer System Operations"

13. Plant Operating Procedure OP-1630024 "Refueling Machine Operation"

14. Plant Administrative Procedure AP0010438" "Control of Heavy Load Lifts" Page 5 of 5

APPENDIX A TABLES

TABLE I LISTING OF ALT, PLANT HEAVY LOAD HANDLING SYSTEMS 1.

NAME Pump room monorails (2)

LOCATION Reactor Auxiliary Bldg. El.

-0.50'ATED CAPACITY (TONS) GROUP

2. Charging pump A,B&C monorails (3)

3. Control element assembly drive Reactor Auxiliary Bldg. El. 7 1/2 generator monorail 19.50'otor

4. Drumming station monorail 10

5. Maintenance monorail (switchgear Reactor Auxiliary Bldg. El. 43.00'oom) 7 l/2 6.

7.

Resin handling Steam pumps jib hoist generator feedwater monorail Turbine Generator Bldg. El. 19.50'0

8. Steam generator feedwater pump cooling shroud monorail

9. Condenser monorails (8) 1/2

10. Turbine gantry cranes (2) Turbine Generator Bldg. El. 62.00' 200/35 Units No. 1 & 2

11. Reactor polar crane Reactor Bldg. 200/50

12. Auxiliary telescoping jib crane (future)

13. Maintenance hatch jib hoist

14. Vacuum relief valve monorail

15. Refueling machine (Continued)

TABLE I LISTING OF ALL PLANT HEAVY LOAD HANDLING SYSTEMS (CONT'D)

RATED CAPACITY NAME LOCATION (TONS) GROUP

16. Refueling machine hoist Reactor Bldg.

17. Fuel transfer machine Reactor Bldg. /Fuel Handling Bldg.

18. Fuel pool pump monorails (2) Fuel Handling Bldg. El. 19 50'uel

19. Spent fuel handling machine Handling Bldg. El. 62.00'l

20. Refueling canal bulkhead It II II monorail

21. Cask storage pool bulkhead monorail

22. New fuel bridge crane

23. New fuel elevator

24. Fuel cask bridge crane Fuel Handling Bldg. El. 150/15 95.83'iesel

25. Diesel generator monorails(8) Generator Bldg.

26. Intake structure bridge crane Intake Stx'ucture 45

27. Intake structure trash rake monorail

28. Component cooling water pump Component Cooling Mater Area monorail

• These load handling systems are designed to handle fuel elements which is, legs than 1 ton, (Continued)

1 TABLE I LISTING OF ALL PLANT HEAVY LOAD HANDLING SYSTEMS (CONT'D)

GROUP I Overhead Handling Systems from which a load drop may result in damage to systems required for plant shutdown or decay heat removal. (no credi t taken for interlocks, technical spec's, operating precedures, detailed structural analysis or system redundancy).

GROUP II- Overhead Handling Systems excluded from Category T. based upon a determination by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal. (i.e., sufficient physical separation).

TABLE 2 LISTING OF MAJOR HEAVY LOADS PERIODICALLY HANDLED IN THE VICINITY OF IRRADIATED FUEL APPROX. LOAD DESIGNATED LOAD IDENTIFICATION WEIGHT (lbs) LIFTING DEVICE PROCEDURE Spent Fuel Shipping 200,000 Fuel Cask Crane M-'0913 Cask Refueling Canal 2,500 Refueling Canal Being Bulkhead Bulkhead Monorail Pr'epared Reactor Missile Shields 145,700 Polar Crane H-0015 Slings Pressurizer Missile 110,000 Polar Crane-4 Being Shield Slings Prepared Polar Crane Load 4,000/'1,500 Polar Crane AP0010438 Block Hain/Aux.

Reactor Vessel Head 3829800 Polar Crane/Head M-0015 Lift Rig Upper Guide Structure 128, 800 Polar Crane-Upper M-0015 Guide Structure Lift Rig In-Service-Inspection 9,000 Polar Crane Being Tool Prepared Fuel Cask Crane Load 8,500 Fuel Cask Crane AP0010438 Block New and Spent Fuel 1,380 Fuel Transfer Machine OP-1630023 Elements Spent Fuel Handling OP-1630022 Machine Refueling Machine OP-1630024 Cask Storage Pool 2,500 Cask Storage Pool To Be Prepared Bulkhead Bulkhead Monorail

APPENDIX B SAFE LOAD PATHS

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