L-81-276, Forwards Response to NRC Re Licensee Interim Actions & Addl Info Re Control of Heavy Loads.Justification for Changes or Mods Necessary to Meet NRC Guidelines Will Be Provided W/Final Rept
| ML17212A277 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/02/1981 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-81-276, NUDOCS 8107070261 | |
| Download: ML17212A277 (30) | |
Text
DOCKEtT: 0 05000335'OTES!
REGVLATO INFORMATION DISTRIBUTION'EM (RIDS)
ACCESSION NBR:8107070261.
DOC ~ DATE:: 81/07/02 NOTARIZED:
NO FACILE:50<<335 St, Lucie Plant~ 'Unit iE 'Florida Power 8 Light Co..
AUTH~ NAME AUTHOR AFFII IATION UHRIG~R,E ~
Florida Power 8 Light Co, REC IP B NAMEl RECIPIENT AFFILIATION EISENHUT'iDBG.
Division of Licensing
SUBJECT:
Forwards response to NRC 801222 ltr"re licensee: {ntei im actions 8 addi info re'ontrol of heavy loads<Justification for changes or-mods necessary to meet" NRC guidelines'ill beI provided w/,final rept, DISTRIBUTION CODE::
A033S COPIES RECEIVEDILiTR, g'NCL g
SIZE:iA~
TITLE. Conr tol of Heavy Loads Near Spent Fuel 7USI A 36)
Operat7ng, ReactorI RECIPIENT ID CODE/NAME)
ACTION:
OR~
03 BC INTERNAL'/0 CORE 8
RAO ASSESS
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09 COPIES LTTR ENCL' "7
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1 1
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04 18E 07 OR ASS SS BR 12'EG FI 01 COPIES LTTR ENCL>
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2 1
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1 LPDR NTIS 03>>
JUL 09 1981 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 38 ENCL 38
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P.O. BOX 529100 MIAMI,F L 33152 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Directo Division of Licensing U.
S. Nuclear Regulatory Commission S
Washington, D. C.
20555
Dear Mr. Eisenhut:
Re:
St. Lucie Unit 1
Docket No. 50-335 Control of Heav Loads Oj 6 )981~
10 tJJ e'8 1I~S gQ~'L~
FLORIDAPOWER & LIGHT COMPANY
= July 2, 1981 L-81-276 Florida Power
& Light Company has reviewed the NRC letter dated December 22,
- 1980, concerning the Control of Heavy Loads with respect to St. Lucie Unit 1.
A report of our actions in response to the request for implementation of interim actions and our report containing the Section 2.1 information requested in that letter are included as attachments to this letter.
Florida Power
& Light Company also commits to implement those changes and modifications which we find necessary as soon as possible, without waiting for staff review.
We cannot,
- however, commit to a completion schedule until we have completed our investigation and submit our final report.
When we submit our final report, we will also provide justification for any changes or modifications that would be required to fully satisfy the guidelines of Enclosure 1 of the December 22, 1980 NRC letter which we believe are not necessary for St. Lucie Unit 1 ~
It should also be noted that in the attached report of the Section 2.1 information, the Group I items in the Listing of all Plant Load Handling Systems are those from which a load drop may result in damage to systems required for plant shutdown or decay heat removal with no credit taken for interlocks, technical specifications, operating procedures, structural analysis, or system redundancy.
We are confident that this group will be greatly reduced, if not eliminated, when appropriate credit is given for these items.
I Very truly yours, Robert E. Uhrig Vice President Advanced Systems
& Technology REU/PLP/ras cc:
Mr. J.
P. O'Reilly, Region II Harold F. Reis, Esquire 2bi 810702 PDR ADOC PDR g 05000335 P
PEOPLE.
~. SERVING PEOPLE
tl
Re:
St. Lucie Unit 1
Docket No. 50-335 Interim Actions for Control of Heav Loads 1.
Safe load paths have been identified per the guidelines of Section 5.1 ~ 1(1) of NUREG 0612 in Administrative Procedure (AP)0010438, Rev 0
"Control of Heavy Load Lifts".
This procedure has been approved by the Facility Review Group and will be implemented prior to the next refueling outage.
2.
Procedures have been developed to cover load handling operations for heavy loads that are or could be handled over or in proximity to irradiated fu'els or safe shutdown equipment.
These procedures will be implemented prior to the next refueling outage, when they will next be used.
3.
Crane operator qualification, training and conduct will be addressed as an appendix to Administrative Procedure 0010438 and will be implemented prior to the next refueling outage.
The requirements of ANSI Standard B
30.2.0-1976 and the recommendations of Nuclear Mutual Limited's Property Loss Prevention Standard on Cranes and Rigging'issued for trial use February 1980) are being reviewed to prepare a single policy for FP&L on crane operator requirements.
We expect to resolve this issue in the near future and then prepare and implement the appendix to the administrative procedure.
A description of the actions we intend to take on this item will be included with our final response on NUREG 0612.
For the interim,
- however, a training program in accordance with ANSI B
30.2.0-1976 is being developed, and our standard company physical for new employees meets or exceeds the physical requirements of the ANSI standard.
(Except for vision standards which are 20/40 in both eyes verses 20/30 in one eye and 20/50 in the other eye as prescribed in the ANSI standard).
It is also our intention to exclude Nuclear Control Center Operators (NCCO)
(and their operation of refueling equipment) from coverage by the NUREG 0612 requirements.
It is our judgement that the qualification and training of the NCCO's meets or exceeds the NUREG 0612 requirements.
4.
St.
Lucie Unit 1
has a
program established for inspecting, testing and maintaining cranes.
A review of this program is presently in progress to verify that the program meets the requirements of Section 5.2.2(6) of NUREG 0612.
The program will be revised where necessary to meet the NUREG 0612 requirements prior to the next refueling outage.
5.
A special review of crane operations over the core has been conducted and these operations are addressed in AP 0010438.
Some revisions are expected to be made prior to the refueling outage.
4 L~ \\
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ST. LUCIE UNIT 1
RESPONSE
TO NRC REQUEST FOR ADDITIONAL INFORMATION ON CONTROL OF HEAVY LOADS (SECTION 2.1)
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TABLE OF CONTENTS Section Title Introduction Identification of Plant Load Handling Systems
~Pa e
III Safe Load Pa'ths IV Special Procedures V
Lifting Devices VI Crane Inspection, Testing and Maintenance VII Crane Design 2
VIII Summary i
IX References A
endices A.
Tables Table 1 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
Sketch 2
Sketch 3
Sketch 4
Sketch 5
Sketch 6
Reactor Building Cranes Fuel Handling Building Cranes Pump Room Monorails Diesel Generator Building Monorails Intake Structure Bridge Crane Charging Pump Monorails
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.
1 and to determine the extent to which the NRC guidelines published in NUREG 0612 are met.
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 thru VII provides the information requested by Section 2.1 of Enclosure 3 of the NRC generic letter.
Section VIIIprovides a summary.
Identification of Plant Load'andlin S stems Section 2.1.1 and 2.1.2 of Enclosure 3 of the NRC December 22, 1980 letter requests a review 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 irradiated fuel or safety-related systems.
A complete listing of all heavy load handling systems has been pre-pared for St. Lucie Unit No. 1.
A heavy load for St. Lucie Unit No.
1 as defined in NUREG 0612 is 1380 pounds.
Each system was then 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 or system redundancy.
Group II Heavy load handling systems excluded from Group I based upon a determinat'ion by inspection that there is sufficient physical separation from any load-impact point and any safety related component.
Table 1 in Appendix A provides this listing and classification.
Safe Load Paths Sections 2.3(a) and (b) of Enclosure 3 of the NRC generic letter request drawings or sketches identifying safe load paths and.a discussion of measures taken to ensure that operators remain with-in these areas..
Safe load paths have been defined as requested for all those load handling systems in Group 1 except the special fuel handling equipment.
Safe load paths have not been delineated further for the spent fuel handling machine, refueling machine or fuel transfer
machine since the operation of this equipment is described in detail, in existing plant procedures and the FSAR.
The safe areas for the remaining Group I cranes are shown on Sketches 1 thru 6.
The St:. Lucie 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.
This procedure requires that a sign be posted at the controls of each affected crane stating that loads in excess of 1380 pounds shall not be carried out of the safe load path and that a map of the safe load area be posted.
Any deviation from the safe load area requires prior Facility Review Group approval.
This administrative procedure has been prepared as part of the interim actions required in the NRC December 22, 1980 generic letter.
Operator training and qualification is underway so that this procedure willbe fully implemented prior to the September 1981 refueling outage.
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 procedure.
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 tabulation and lists the special procedures which follow the guidelines of NUREG 0612 Section 5.1.1 (2) for most of these loads.
Special procedures for the handling of the fuel pool bulk-head, pressurizer missile shield and In-Service-Inspection tool are being developed and will be referenced in the second part of this report due in September.
Liftin Devices (slin s beams and s ecial ri in )
Section 2.1.3 (d) of Enclosure 3 of the NRC generic letter requests that lifting devices comply with ANSI B30.9-1971 or ANSI N14.6-1978 as applicable.
The current St. Lucie 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 by the date required in the NRC generic letter.
Crane Ins ection Testin and Maintenance Section 2.1.3 (e) of Enclosure 3 of the NRC generic letter requests verification that ANSI B30.2-1976 Chapter 2-2 has been invoked with respect to crane inspection, testing and maintenance.
The St. Lucie plant has an established program for. inspection, testing and maintaining cranes.
This program is pxesently under review to determine to what degree this ANSI standard is satisfied and will be revised if xequired, prior to the next refueling outage.
Vll.
Crane Desi n Section 2.1.3 (f) of Enclosure 3 of the NRC generic letter requests verification that crane design complies with the guidelines of the Crane Manufacturers Association of America Specification 70 "Specifications for Electric Overhead Traveling Cranes" (CHAA /170) and Chapter 2-1 of ANSI B30.2-1976 "Overhead and Gantry Cranes".
The following Group I bridge cranes fall under the scope of the CMAA f/70 specification and the ANSI B30.2 standard which cover top running multiple gixdex electric overhead traveling cranes.
1.
Reactor Building Polar Crane 2.
Fuel Cask Crane 3.
Intake Structure Crane 4.
Spent Fuel Handling Machine 5.
Refueling Machine These cranes were designed to the Electric Overhead Crane Institute Specification 61, "Specifications for Electric Overhead Traveling Cranes" (EOCI f/61) and ANSI B30.2-1967.
These specifications and standards are the precedessoxs to CHAA 870 and ANSI B30.2-1976 and were in effect at -the time of the manufacture of these cranes.
They are similar to the succeeding specifications and standards now in effect and equivalent.
The primary differences between the EOCI Pr61 and CHAA f170 specifications are an advancement in girder design practice and higher allowable stresses in the CHAA iI70 specification.
Although the St. Lucie No.
1 cranes are designed to the older EOCI 1361 specification which calls for ASTM A7 steel the higher grade ASTM-A36 steel has been used which is in conformance with the CHAA /$70 specifications.
During the upcoming refueling outage a new 1 ton telescoping jib crane will be installed in the Reactor building.
The design of this crane has been specified to conform wi.th CMAA 870, CMAA Pr74 and ANSI B30.'2-3.'976 VXXI.
~Summax This report documents the first phase of Florida Power and Light Company's review of the controls for the handling of heavy loads at the St. Lucie Unit No.
1 plant as requested by the NRC Generic letter dated 12-22-80.
A total of thixty-nine (39) load handling systems were identified, twelve (12) of which were found to be affected by NUREG 0612 "Control of Heavy Loads at Nuclear Power Plants".
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 for Shipping Containers Neighing 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 61 "Specifications for Electric Overhead Traveling Cranes."
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."
ll.
Plant Operating Procedure OP-1630022 "Spent Fuel Handling Machine Operation."
12.
Plant Operating Procedure OP-1630023 "Fuel Transfer System Operations."
13.
Plant Operating Procedure OP-1630024 "Refueling Machine Operation."
L4.
Plant Administrative. Procedure AP-0010438 "Control of Heavy Load Lifts."
APP ENDIX A
TABLES
TABLE 1 LISTING OF ALL PLANT HEAVY LOAD HANDLING SYSTEMS NAME l.
2.
3.
5.
6.
7.
8.
9.
10.
11.
12.
13.
14.
15.
16.
17.
18.
19.
20.
21.
22.
23.
24.
25.
26.
27.
28.
29.
30.
Laundry filter monorail Waste filter monorail Pump room monorails (2)
Charging pump A, B, 6
C monorails (3)
Boric Acid preconcentrator filter monorail Hot machine shop bridge crane Hot machine shop jib hoist Turbolator monorail Control element assembly drive motor generator monorail Purification filter monorail Hydraulic compactor monorai1 Drumming station bridge crane Drumming station monorail Maintenance monorail Resin handling jib hoist Steam generator feedwater pumps monorail Condensor monorails (8)
Gantry cranes Units 1
& 2 (2)
Turbine canopy monorails Polar crane Auxiliary telescoping jib crane (future)
Refueling Machine Refueling Machine hoist Maintenance hatch hoist Fuel transfer machine Fuel pool purification filter monorail Spent fuel handling machine Fuel pool bulkhead monorail New Fuel bridge crane New fuel elevator I OCATION Reactor Auxiliary Bldg.
El.-0.50'eactor Auxiliary Bldg.
EL.-19.50'I 11 Reactor Auxiliary Bldg.
E1.43.00' If u
II Turbine Generator Bldg.
E1.19.50'eactor Bldg/Fuel Handling Bldg.
Fuel Handling Bldg.
E1.19.50'uel Handling Bldg.
E1.62.00'urbine Generator Bldg.
El.62.00'I II II 11 Reactor Bldg.
RATED CAPACITY
~(TONS 10 10 5
5 10 5
1 2
7-1/2 10 10 10 10 7-1/2 1
20 3-1/2 200/35 3
175/50 10 3
5 1
GROUP IIIIIIII IIIIII IXIIIIII IIIrIII IIIIIIII IIIIII
I
TABLE 1 LISTING OF ALL PLANT HEAVY LOAD HANDLING SYSTEMS NAME LOCATION RATED CAPACITY
~TONS GROUP 31.
32.
Fuel cask bridge crane Diesel generators A & B monorails (2x2) 33.
Intake structure bridge crane 34.
Rake guide monorail (2) 35.
Fish basket jib boom hoist 36.
Chlorine cask monorail 37.
Blowdown filter monorail 38.
Covered work area bridge crane 39.
Cold machine shop jib hoist
'Puel Handling Bldg.
Diesel Generator Bldg.
Intake structure Intake area Blowdown Bldg.
Covered work area Cold machine shop El. 95. 83 lo5/15 1
45 2
1 2
1 7-1/2 2
III TIIIIIIIII 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 credit taken for inter-locks, technical spec's, operating procedures, detailed structural analysis or system redundancy.)
GROUP II Overhead Handling Systems excluded from Category I 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).
1*
TABLE 2 LISTING OF MAJOR HEAVY LOADS PERIODICALLY HANDLED IN THE VICINITY'"OF IRRADIATED FUEL LOAD IDENTIFICATION LOAD DESIGNATED HEIGHT (lbs)
LIFTING DEVICE PROCEDURE Spent Fuel Shipping Cask Fuel Pool Bulkhead 50, 000 5,000 Fuel Cask Crane Fuel Pool bulkhead Monorail M-0913 Being Prepared Reactor Missile Shields 145,700 Polar Crane 4
Slings M-0015 Pressurizer Missile Shield Polar Crane Load Block Main/Aux.
Reactor Vessel Head Upper Guide Structure Xn-Service-Inspection Tool Fuel Cask Crane Load Block 96,000 3,800/
1,500 219,300 128,800 9,000 3,000 Polar Crane 4
Slings Polar Crane Polar Crane/Head Lift Rig Polar Crane Upper Guide Structure Lift Rig Polar Crane Fuel Cask Crane Being Prepared AP0010438 M-0015 M-0015 Being Prepared AP0010438 Nev and Spent Fu'el Elements 1,380 Fuel Transfer Machine Spent Fuel Handling Machine Refueling Machine OP-1630023'P-16'30022 OP-1630024
APPENDIX B
SAFE LOAD PATHS
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p)~i'KETCH 1 SI SAFE LOAD PATHS Reactor Buildin Cranes 1.
Polar Crane 2.
Auxiliary Jib Crane 3.
Refueling 1iachine 1 Ton:hoistr
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SAFE LOAD PATHS SKETCH 2 Fuel Handlin Buildin Cranes 1.
Fuel Pool Bulkhead Honorail 2.
Fuel Cask Crane
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SAFE gPAD PATHS SKETCH 3 Pum Room Honoralls
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SKETCli 4 Diesel Generator Buildin Honorai
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SAFE LOAD PATHS SKETCH 5 Intake Structure Brid e Crane
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SAFE LOAD PATHS SKETCH 6 Char in Pum Monorails