ML20072D958
| ML20072D958 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/31/1983 |
| From: | UNITED ENGINEERS & CONSTRUCTORS, INC. |
| To: | |
| Shared Package | |
| ML20072D935 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 9763.006-S-N-5, NUDOCS 8306230458 | |
| Download: ML20072D958 (147) | |
Text
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DOCKET NOS.: 50-443 50-444 SEABROOK STATION RESPONSE TO NRC GENERIC REQUEST FOR ADDITIONAL INFORMATION RELATING TO NUREG - 0612
.neswi VMh'""
SEABROOK STATION
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PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK, NEW HAMPSHIRE Prepared by United Engineers & Constructors Inc.
N O!No4is REPORT NO. 9763.006-S-N-5 A PDR REVISED: MAY 1983
TABLE OF CONTENTS TAB
- 1. INTRODUCTION
- 2. NRC LETTER OF REQUEST
- 3.
SUMMARY
- 4. RESPONSE TO SECTION 2.1 (ENCLOSURE 3)
General Requirements for Overhead Handling Systems
- 5. RESPONSE TO SECTION 2.2 (ENCLOSURE 3)
Specific Requirements for Overhead Handling Systems Operating in tha Vicinity of Fuel Storage Pools
- 6. RESPONSE TO SECTION 2.3 (ENCLOSURE 3)
Specific Requirements for Overhead Handling Systems Operating in the Containment
- 7. RESPONSE TO SECTION 2.4 (ENCLOSURE 3)
Specific Requirements for Overhead Handling Systems Operating in Plant Areas Containing Equipment Required 'for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling.
- 8. TABLES Table 2.1.3(C)-1 Tabulation of Heavy Loads Table 2.4.2-1 Load / Impact Area Matrices, Sheets 1 through 10.
- 9. APPENDICES Appendix I Analysis of RV Head Lifting Rig and Internals Lifting Rig (Special Lifting Devices)
- 10. ATTACHMENTS Attachment A Conduit and Cable Tray Review Attachment B Piping Review Attachment C Safety-Related Equipment Review Attachment D HVAC Review
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.! l TABLE OF CONTENTS (Cont'd) i l
- 11. LOAD PATH DRAWINGS l
9763-F-805272 9763-F-805273 l
- 9763-F-805274'
. 9763-F-805275 i 9763-F-805276 9763-F-805277 9753-F-805278 9763-F-805279 9763-F-805280 9763-F-805281 '
9763-F-805282 9763-F-805283 9763-F-805284 4
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- 1. INTRODUCTION This report is in response to the NRC generic request for a review of the control of heavy loads at nuclear power plants, as contained in their letter dated December 22, 1980, and included herein in Section 2 for ease of reference. The report documents the results of a comprehensive review of the load handling operations at Seabrook Station and specifically addresses Enclosure 3 to the above letter,
" Request for Additional Information on Control of Heavy Loads."
The information is presented in a request / response foreat which follows the same general format of Enclosure 3.
The above NRC letter requested that the report be submitted in two parts:
Part 1 - Response to Section 2.1 of Enclosure 3.
Part II - Response to Sections 2.2, 2.3, and 2.4 of Enclosure 3.
Since the Seabrook Station is not yet operational, all the information requested is being provided in this one combined report without any reference to Part I or Part II.
For the purposes of this evaluation, a heavy load is defined in accordance with NUREG-0612, as a load whose weight is greater than the combined weight of a single spent fuel assembly and its handling tool, i.e., a load greater than 2000 pounds, The original issue of this report, dated September 1982, was forwarded to the NRC for review by PSNH on September 24, 1982 under letter SBN-331.
The present Revision 1 to this report, dated May 1983, is an update prepared in response to the NRC's draft technical evaluation of the original report, dated November 23, 1982, and supplemented by the NRC's letter to PSNH, dated December 28, 1982.
- 2. NRC LETTER OF REQUEST The generic letter which follows was sent to all licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits.
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION YvASHINGTON. D. C. 20606 i / dH I 31981 December 22, 1980
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TO ALL LICENSEES OF OPERATING PLANTS AND APPLICANTS FOR OPERATING LICENSES AND HOLDERS OF CONSTRUCTION PERMITS
- Gentlemen:
Subject:
Control of Heavy Loads In January 1978, the NRC published NUREG-0410 entitled, "NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants -
Report to Congress." As part of this program, the Task Action Plan for Unresolved Safety Issue Task No. A-36 " Control of Heavy Loads Near Spent Fuel," was issued.
He have completed our review of load handling operations at nuclear power plants. A report describing the results of this review has been issued as NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants -
Resolution of TAP A-36." This report contains several recommendations to be implemented by all licensees and applic.r.nts to ensure the safe handling of heavy loads.
The ouroose of this letter is to reouest that you review your controls for the handlino of heavy loads to determine the extent to which the guidelines of Enclosure 1 are cresently satisfied at your facility, and to identify the channes and modifications that would be required in order to fully satisfy these cuidelines.
l To expedite your compliance with this request, we have enclosed the j following:
NUREG-0612, " Control of Heavy Loads at '!uclear Power Plants" (Enclosure
! 1).
I Staff Position - Interim Actions for Control of Heavy Loads (Enclosure 2).
l Request for Additional Information on Control of Heavy Loads (Enclosure l 3).
- 41th the exceotion of licensees for Indian Point 2 and 3, Zion 1 and 2 and Three Mile Island 1 (These were creviously sent a letter) i
-3_
2- December 22, 1980 You are reouested to imolement the interim actions described in Enclosure 2 as soon as possible but no later than 90 days from the date of this letter.
In order to enable the NRC to determine whether operating licenses should be modified (10 CFR 50.54(f)), operating reactor licensees are reouested to provide the following:
- l. Submit a report documentino the results of your review and the recuired chanoes and modifications. This report should incluce the information identified in Sections 2.1 through 2.4 of Enclosure 3, on how the guidelines of NUREG-0612 will be satisfied. This report should be submitted in two parts according to the following schedule:
- Submit the Section 2.1 information within six mcnths from the date of this letter.
- Submit the Sections 2.2, 2.3 and 2.4 information within nine months.
- 2. Furnish confirmation witnin six months that imolementation of those chanoes and modifications you find are necessary will commence as soon as cossible without waiting on staff review, so that all such changes, beyond the above interim actions, will be completed within two years of submittal of Section 2.4 for the above report.
- 3. Furnish justification within six months for any chanoes or modifications that would be reouired to fully satisfy the ouidelines of Enclosure 1 which you believe are not necessary.
The criteria in NUREG-0612 are also applicable to applicants for operating licenses. Such applicants are expected to provide the information reouested by item 1 above and to meet the same schedule of implementation es indicated in 2 above. Any item for which the implementation date is prior to the exoected date of issuance of an operating license will be considered to be a prerequisite to obtaining that license.
For any date that cannot be met, furnish a proposed revised date, justification for the delay, and any planned compensating safety actions during the interim.
This request for information was approved by GAO under a blanket clearance number R0072 which expires November 30, 1983. Comments on burden and duplication may be directed to the U.S. General Accounting Office, Regulatory Reports Review, Room 5106, 441 G Street, N.W., Washington, D.C. 20548.
Sincerely,
\ /
~l0HQ ~)6 ll 11 Darrell G E'isenhut, Director
' Division o Licensing
Enclosures:
- 1. NUREG-0612
- 2. Staff Position
- 3. Request for Additional Information cc: w/o Enclosure (1)
Service List l
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- 3.
SUMMARY
i A systematic evaluation of all load handling systems has been performed to determine the extent to which the guidelines of NUREG-0612 are satisfied for Seabrook Station. Since the principal causes of load handling accidents reported in the past include operator errors, rigging failures, lack of adequate inspection and inadequate procedures, greater emphasis has been placed in these areas in assuring safe handling of the heavy loads. The crane operator training program and periodic
. inspection and maintenance program for the cranes, monorail systems and lifting equipment will meet the applicable requirements outlined in NUREG-0612 and other standards such as ANSI B30.2, ANSI B30.9, ANSI-
. B30.10, ANSI N14.6, ANSI B30.ll and ANSI B30.16 as discussed in this report. The load handling operations will be governed by approved procedures and safe load path drawings, as applicable.
A review of the plant general arrangement drawings indicates that, in general, either the cranes do not travel over spent fuel or safety related equipment, or the reliability of the load handling system is enhanced by providing increased safety factors and increased inspection of the critical components. In some instances, redundancy and physical separation of the safety related equipment continues to maintain the
- safe shutdown and decay heat removal capabilities following a load drop.
l The following four monorail systems have been upgraded to increase their reliability, and consequently make the likelihood of a load drop
. extremely smail:
l (a) Emergency feed pump monorail.
I (b) Primary component cooling water pump service monorails.
. (c) Filter cask monorail.
4 (d) CVCS heat exchanger service monorail.
The spent fuel bridge and hoist and the manipulator crane auxiliary hoist have been derated to one(1)-ton capacity to preclude inadvertent use of these load handling systems with heavy loads. Similarly, the boric acid batching monorail has been derated to 50 percent of its original capacity to limit the use of this monorail to loads lighter than half the hoist capacity, and thereby ensure increased' safety margins.
The special lifting devices for the spent fuel cask, reactor coolant pump motors, reactor cavity seal ring, equipment hatch cover and the removable panels of the pressurizer enclosure wall have not yet been designed. The design of these devices will be in compliance with the intent of NUREG-0612 requirements. An evaluation of these special lifting devices will be provided later, prior to any load handling operations at the plant involving these specific loads.
Some exceptions have been taken to the requirements of NUREG 0612 and Enclosure 3 to the NRC. letter; however, these exceptions do not reduce the reliability of the load handling operations. Alternatives in lieu of literal compliance with these requirements are discussed to demonstrate their equivalency and/or adequacy.
In conclusion, load handling operations at Seabrook Station will meet the intent of NUREG-0612 in regard to assuring safe handling of heavy loads identified in this report.
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- 4. RESPONSE TO SECTION 2.1 (ENCLOSURE 3)
GENERAL REQUIREMENTS FOR OVERHEAD HANDLING SYSTEMS "NUREG 0612, Section 5.1.1, identifies several general guidelines related to the design and operation of overhead load-handling systems in the areas where the spent fuel is stored, in the vicinity of the reactor core, and in other areas of the plant where a load drop could result in damage to equipment required for safe shutdown or decay heat removal. Information provided in response to this section should identify the extent of potentially hazardous load-handling operations at a site and the extent of conformance to appropriate load-handling guidance."
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REQUEST 2.1-1
" Report the results of your review of plant arrangements' to identify overhead handling systems from which a load drop may result in damage to any
-system required for plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures or
, detailed structural analysis)."
RESPONSE TO 2.1-1 The overhead load handling systems identified during our plant review are listed below along with their capacities and locations:
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- TAG NO. HANDLING SYSTEM CAPACITY LOCATION 4
MM-CR-3 Polar Gantry Crane 420 Ton Main Containment 50 Ton Auxiliary FH-RE-24 Radial Arm Stud 2 Tons . Containment Tensioner Hoists (3)
FH-RE-1 Spent Fuel Cask Handling 125 Ton' Main, Two Fuel Storage Crane Aux. Hooks,@ 5 Building Tons each I
CS-CR-5 Filter Cask Monorail 7.5 Tons Primary Auxi-Hoist liary Building
- CS-CR-6 Boric Acid Batching 4.5 Tons (2.25T)* Primary Auxi-Monorail Hoist liary Building CS-CR-13 CVCS Heat Exchanger 5 Tons Primary Auxi-Service Monorail Hoist liary Building i
CS-CR-14A, Charging Pump Service 2.5/2.5/6.0 Tons Primary Auxi-
-14B, -14C Monorail Hoist liary Building
. CC-CR-15A, Component Cooling Water 5 Tons Primary Auxi-CC-CR-ISB Pump Service Monorail liary Building Hoist CBS-CR-18A & Radioactive Pipe Tunnel 2 Tons Radioactive CBS-CR-18B Service Monorail Hoist Pipe Tunnel
TAG NO. HANDLING SYSTEM CAPACITY LOCATION MS-CR-25A, Main Steam and Feedwater 7.5 Tons MS and FW Pipe MS-CR-25B Pipe Chase Crane Chase FW-CR-27 . Emergency Feed Pump 5 Tons Emergency Feed-Monorail Hoist water Pump Building
- DG-CR-28A, Diesel Generator Service 8 Tons Diesel DG-CR-28B Crane Generator Building
- Capacity shown in parentheses is the derated capacity.
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REQUEST 2.1-2
" Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety related component to permit a determination 4
by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal."
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RESPONSE TO 2.1-2 -
The following load handling systems have been excluded from the above
- category because no safety related systems or components required for plant shutdown or decay heat removal are located in the areas served by these overhead handling systems:
TAG NO. HANDLING SYSTEM CAPACITY LOCATION MM-CR-1 Turbine Building Crane 210 Ton Main Turbine 30 Ton Auxiliary Building MM-CR-2 Heater Bay Crane 100 Ton Main Turbine 15 Ton Auxiliary Building ,
ES-CR-26 Generator Breaker Crane 5.5 Tons Turbine Building CO-CR-29A To Condenser Water Box 4 Tons Turbine
- 29X Monorail Hoist Building CW-CR-22 Circulating Water Stop 10 Tons Service and Log Monorail Hoist CW Pump House CW-CR-23 Pump House Trash Removal 1 Ton Service and Basket Monorail Hoist CW Pump House PAH-CR Ventilation Service 1 Ton Primary Auxi-Monorail Hoist liary Building
. CS-CR-35 Equipment Hatch Monorail 2 Tons Primary Auxi-Hoist liary Building 1
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TAG NO. . HANDLING SYSTEM - CAPACITY' . LOCATION WS-CR-7 Waste Process General 4 Tons Waste Service 80 Monorail Processing Hoist Building' l WS-CR-8 Waste Process General 4 Tons Waste Service 40 Monorail Processing Hoist Building RS-CR-12 Resin Sluice Service 2 Tons Waste Monorail Holst _ Processing Building '
WS-CR-4 Solid Waste Handling 30 Tons Waste Crane Processing Building i
AAH-CR-20 Decontamination Service 5 Tons Administration Monorail Hoist and Service Building MM-CR-30 RCA Shop Crane 5 Tons Administration and Service Buitving In addition, the following systems are excluded from further-coosideration i since they do not handle heavy loads. A " heavy load" is defined in accordance with Section 1.1 of NUREG-0612, i.e., a load whose weight is greater-than the combined weight of a single spent fuel assembly and its handling tool. (A load greater than 2000 pounds.)
TAG NO. HANDLING SYSTEM CAPACITY LOCATION FH-CR-33 Jib Crane 0.75 Tons containment FH-RE-5 Manipulator Crane 1.5 Tons (IT)* Containment Auxiliary Hoist t
FH-RE-2 Spent Fuel Pool Bridge 2 Tons (IT)* Fuel Storage l and Hoist Building l
- Capacities shca. in parentheses are the derated capacities.
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RH-CR-32 RHR, CS, SI Equipment 0.75 Tons Equipment Vault Monorail Hoist Vault (P.A.B.)
SW-CR-16 -Service Water Strainer 1 Ton Outside Primary Monorail Hoist Auxiliary Building The manipulator crane auxiliary hoist, although rated at 1.5 ton, does not carry heavy-loads. The loads handled by this hoist such as control rod drive shaft, drive shaft unlatching tool, shaft handling tool, guide tube cover and cover handling tool, thimble plug and the associated handling tool etc. weigh much less than 2000 pounds. Similarly, the spent fuel pool bridge and hoist handles only light loads such as fuel assemblies with or 4 without control elements and their associated handling tools, burnable poison rod assembly and its handling tool etc.
Furthermore, during plant operation phase, the manipulator crane auxiliary hoist and the spent fuel pool bridge and hoist will be derated by posting one ton capacity rating on the unit to caution the operators against using these hoists to lift heavier loads. However, if over the life of the plant a situation arises requiring use of the hoists with loads greater than 2000 pounds, it would be thoroughly reviewed by the Station Operating Review Committee.
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REQUEST 2.1-3 "With respect to the design and operation of heavy-load-handling systems in the containment and the spent fuel pool area and those load-handling systems-identified in 2.1-1, above, provide your evaluation concerning compliance
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with the guidelines of NUREG 0612, Section 5.1.1. The following specific information should be included in your reply:
(a) Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel and safety-related equipment."
1 RESPONSE TO 2.1-3 (a) 1 The following drawings depict the safe travel paths for heavy loads which, if dropped, could impact the irradiated fuel or components in the systems I required for shutdown or decay heat removal. Also shown on these layout drawings are the locations of the safety related equipment and spent fuel, where applicable. To the maximum extent practicable, handling of heavy loads over safety related equipment-is avoided in identifying the safe load paths. Also, in defining these load paths consideration has been given to i the safety related equipment located on lower elevations below the operating s floor for the load handling system in question.
Drawing No. Title
. 9763-F-805272 containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 1 of 9) 9763-F-805273 containment Building
[ Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 2 of 9) 9763-F-805274 Containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 3 of 9)
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Drawing No. Title 9763-F-805275 Containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 4 of 9) 9763-F-805276 Containment Building Elev.-25'-0" Safe Load Paths for Polar Crane (Sheet 5 of 9) 9763-F-805277 Containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 6 of 9) 9763-F-805282 containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 7 of 9) 9763-F-805283 containment Building-Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 8 of 9)
, 9763-F-805284 Containment Building Elev. 25'-0" Safe Load Paths for Polar Crane (Sheet 9 of 9) 9763-F-805279 Fuel Storage Building Elev. 25'-0" Safe Load Paths for Cask Handling Crane 9763-F-805280 Primary Auxiliary Building Elev. 25'-0" t
Safe Load Paths for Monorails 9763-F-805281 Primary Auxiliary Building Elev. 53'-0" Safe Load Paths for Monorails 9763-F-805278 Emergency Feedwater Pump Bldg.
, Elev. 27'-0" l Safe Load Paths for Monorails
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One of the requirements of Section 5.1.1-(1) of NUREG 0612 is that "these load paths should be clearly marked on the floor in the area where the load is to be handled." PSNH, however, takes exception to this requirement due the-following considerations:
The safe load paths have been delineated on the drawings listed above.
During the crane operator training program, emphasis will be placed on the need to adhere to these safe load paths. Heavy loads will be moved by the safest and shortest routes in accordance with the approved load handling procedures and the safe load path drawings. The crane operator will be directed by a signal person using standard signals given in ANSI B30.2-1976 and ANSI B30.11-1980. The signal person will ensure that the load is moved along the designated path; and any deviations, if required, will be handled per procedure AQ 1.002, Station Operating Procedures.
Due to the number of paths and their configurations (particularly in the containment) as well as the frequent utilization of the felt paper to control contamination, it is felt that marked load paths, in general, will not contribute to ensuring the safe handling of the heavy loads at Seabrook.
Therefore, load paths will not be marked on the floor.
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REQUEST 2.1-3 (b)-
"A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including procedures, if any, for deviation from these paths."
RESPONSE TO 2.1-3 (b)
All heavy loads identified in response to Section 2.1-3 (c) (to follow) will be handled along the well defined safe load paths. The drawings showing safe load paths will be referenced in the applicable load handling procedures which form part of the overall plant operation and maintenance procedures.
Additionally, for those load handling systems for which the load path is not fixed, a reduced size print of the load path drawing (8h x 11" or larger) will be attached to the load handling procedure.
The load paths identified on the layout drawings follow the safest and shortest routes with consideration given to maintaining safe distances from spent fuel and safe shutdown equipment. In general, a load will be moved as close to the floor as practical except to clear any equipment or other physical obstructions in the travel path. In addition, appropriate notes of the precautionary nature are also included, as required, on the load path drawings. Any deviations from these safe load paths or written procedures governing the load handling operations will be handled per procedure AQ 1.002, Station Operating Procedures.
l To summarize, loads will be handled along established safe load paths in accordance with the approved procedures by trained and experienced personnel under the supervision of competent maintenance supervisors.
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REQUEST 2.1-3 (c)
, "A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG-0612, Section 5.1.1 (2)."
RESPONSE TO 2.1-3 (c)
Heavy loads that will be handled by the cranes and monorail-hoists identified in response to section 2.1-1, above, are listed in Table 2.1.3(c)-1. For each load handling system tabulated, the loads to be carried are included along with the estimated weight of the load, its designated lifting device, applicable load path drawing and the reference drawing /s.
Also included for each load is the reference to the load handling procedure, i.e.,_whether a ' general'.or ' specific' procedure.will be prepared for a particular load. The procedures will be developed in accordance with Section 5.1.1 (2) of NUREG-0612 and will be available prior to use of the load handling system.
'Each ' specific' procedure (See Table 2.1.3(c)-1) will contain detailed step-by-step instructions for handling a particular load including identification of required equipment, safety precautions and reference to safe load paths.
Where a ' specific' procedure is not intended, a ' general' procedure (See Table 2.1.3(c)-1) encompassing basic rigging will be developed to cover the handling of miscellaneous loads.
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' REQUEST 2.1-3 (d)
" Verification that lifting devices identified in 2.1.3-C, above, comply with the requirements of ANSI N14.6-1978 or ANSI B30.9-1971 as appropriate. .For
. lifting devices where these standards, as supplemented by NUREG 0612, Section 5.1.1 (4) or 5.1.1 (5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability."
i RESPONSE TO 2.1-3 (d)
The.various lifting devices employed in handling the heavy loads at Seabrook are identified in Table 2.1.3(c)-1. Of these devices, the following are categorized as special lifting devices:
(i) Reactor Vessel Head Lifting Rig, Load Cell and Load Cell Linkage Assembly.
(ii) Internals Lifting Rig, Load Cell and Load Cell Linkage Assembly.
-(iii) Spent Fuel Cask Lif ting Device (iv) Reactor Coolant Pump Motor Lifting Device (v) Reactor Cavity Seal Ring Lifting Device (vi) Equipment Hatch Cover Handling Device (vii) Pressurizer Enclosure Wall Handling Device r The reactor vessel head and internals lifting rigs and associated load cell and linkage assemblies have been evaluated by Westinghouse to verify compliance with the requirements of ANSI N14.6 and NUREG 0612,
- - - - , _ . . _ . - - _ . . ~ . . . , _ . . . . , . - __-,,,...,m-, . __ . . . , - , . , . . . - . - , , - , . . . . . , - ~ . . . , . , . _ . . . ~ . . - . . . _ _ _ . , . . . -
1 Section 5.1.1.-(4). The results of this assessment are included in Appendix 1.
j The design of the spent fuel cask and lifting device has not yet been 4
finalized. A detailed review of the lifting device will be performed to verify compliance with ANSI N14.6-1978, once the cask design has been.
selected, and the results of the analysis will be provided to the NRC prior to any cask handling operations at the plant site.
The reactor coolant pump motor lifting device, reactor cavity. seal ring lifting device, equipment hatch cover handling device and the pressurizer enclosure wall handling device will comply with the requirements of ANSI N14.6-1978 and NUREG 0612. The results of the evaluation to be performed to determine compliance with these applicable standards _will be made available to the'NRC for review, prior to use of these devices with their respective -
loads. 'The design of these four special lifting devices has not been finalized.
'All special lifting devices will be subjected to periodic testing and f inspection to verify continued compliance in accordance with the provisions of Section 5 of ANSI N14.6-1978 with the following clarifications / exceptions.
(a) The tests or inspections as outlined below in (c) will be performed-prior to use of the lifting device if it is not used for a period exceeding one year.
I (b) Where the usage frequency is more than once a year, the tests and
. inspections will be performed annually.
i (c) A 100 percent load test using the actual load plus visual examination of critical welds and parts will be conducted as part of.the lift. A periodic non-destructive surface examination of i
r critical welds and/or parts'will be performed to insure continued adequacy.
(d) All special lifting devices will be visually inspected by maintenance personnel prior to each use instead of every three months (5.3.7) for indications of damage or deformation.
- Alternative load tests and non-destructive examination frequency proposed above are based upon the following considerations:
- 1. Load testing to 150 percent of the total weight before each use would require special fixtures and is impractical to perform.
Therefore, these special lifting devices will be tested at 100 percent of the load to be carried. Also, with the use of load cell for the head and internals lift rigs, all lifting and lowering is monitored at all times.
- 2. ' Access to the welds for surface examination, for most of these special lift rigs, is difficult as they are stored in containment or fuel storage building and some contamination is present.
- 3. The items that are welded remain assembled and cannot be used for any other lift other-than their intended function. The devices are stored in protected areas, away from adverse environmental conditions and physical abuse that could have deterimental estect
- on the integrity and reliability of these special lifting devices.
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- 4. Dimensional checking is not ircluded since these structures are large and the results of dimensional measurements would always be l questionable, and will not serve any useful purpose.
The standard lifting devices (which are not specially designed) listed in Table 2.1.3(c)-1, such as slings with or without spreader bars, shackles, R
etc. will meet the requirenents of ANSI B30.9-1971 as supplemented by Section 5.1.1 (5), NUREG 0612. The standard lifting devices used to carry heavy loads will maintain a minimum safety factor of five based upon nominal breaking strength. Where the loads are handled over or near spent fuel and/or safety related equipment, a safety factor of 10 will be maintained as indicated on the load path drawings. In selecting the p, coper sling size,
. the rated load used will be the sum of the static and dynamic loads, the I dynamic load being the greater of 15% of the static load or 0.5% of static I
load for each foot per minute of hook speed. PSNH takes no exceptions to
, the requirements of B30.9-1971 or Section 5.1.1(5).,
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REQUEST 2.1-3 (e)
" Verification that ANSI B30.2-1976 Chapter 2-2, has been invoked with respect to crane inspection, testing and maintenance. Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives".
RESPONSE TO 2.1-3 (e)
A crane inspection, testing and maintenance program will be developed and implemented in accordance with the requirements of Chapter 2-2 of ANSI B30.2-1976, as classified for standby service. Frequency of tests and inspections will be as per Section 5.1.1 (6) of NUREG 0612.
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j REQUEST 2.1-3 (f)
" Verification that crane design complies with.the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of' equivalency of actual design requirements for instances where specific compliance with these standards is not provided."
RESPONSE TO 2.1-3 (f)
Overhead and Cantry Cranes (Top Running Bridge)
The polar gantry crane and the spent fuel cask handling crane have been designed . in accordance with the guidelines of CMAA Specification No. 70 and ANSI B30.2-1967, Overhead and Cantry Cranes. At the time of design and fabrication of both these cranes, ANSI standard B30.2-1976 was not in existence. A comparison of design revisions of Chapter 2-1 from 1967 to 1976 edition and the review of United Engineers and Constructors crane specifications 9763.006-257-2 and 9763.006-257-3 indicates that the design of the cranes complies with the requirements of ANSI B30.2-1976.
Monorail Systems and Underhung Cranes
, The miscellaneous monorail-hoists and the underhung cranes identified above in Table 2.1.3(c)-1 except the radial arm stud tensioner hoists, are designed to the following applicable ANSI standards:
ANSI B30.11 - Monorail Systems and Underhung Cranes 4
ANSI B30.16 - Overhead Hoists (Underhung)
[ In addition, the design complies with the'following applicable specifications of Monorail Manufacturers Association (MMA) and Hoist Manufacturers Institute (HMI):
Pe(A Specifications for Underhung Cranes and Monorail Systems HMI-100-74 Standard Specifications for Electric Wire Rope Hoists The radial are stud tensioner hoists are designed to HMI-100-74 and Westinghouse Specification 953432. Since the applicable volumes of the overall general standard B30 for monorails and underhung cranes are 530.11 and B30.16, it is considered that the intent of the request 2.1-3 (f) in regard to the design of these load handling systems has been met.
i I
REQUEST 2.1-3 (g)
" Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification and conduct".
RESPONSE TO 2.1-3 (g)
No exceptions are taken to the requirements of ANSI B30.2-1976 in regard to qualification, training or conduct of crane operators. The crane operators will be trained in accordance with the requirements of Chapter 2-3 of B30.2-1976. A crane operator training and qualification program will be developed and implemented prior to fuel loading and start-up of the plant.
This program will play an important role in assuring safe handling of the heavy loads at Seabrook.
The crane operators will be required to receive class-room instruction, and gain practical operating experience under the direction of other qualified operators, for each type of crane on which they are to become qualified. In addition to a physical examination as per Section 2-3.1.2 (b) of B30.2-1976, each operator trainee will be required to pass a written examination at the end of the formal instruction program. The practical training will continue until the trainee can demonstrate competent operation of the crane and pass the practical test. Proper training records documenting this operator training will be kept at the plant site. The operators will be required to requalify periodically.
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- 5. Response to Section 2.2 (Enclosure 3)
Specific Requirements for Overhead Handling Systems Operating in the Vicinity of Fuel Storage Pools "NUREG 0612, Section 5.1.2, provides guidelines concerning the design and operation of load-handling systems in the vicinity of stored, spent fuel. Information provided in response to this section should demonstrate that adequate measures have been taken to insure that in j this area, either the likelihood of a load drop which might damage spent fuel is extremely small, or that the estimated consequences of such a drop will not exceed the limits set by the evaluation criteria of NUREG 0612, Section 5.1, Criteria I thru III".
REQUEST 2.2-1 "Idettify by name, type, capacity, and equipment designator, any cranes physically capable (i.e., ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying loads which could, if dropped, land or fall into the spent fuel pool."
RESPONSE TO 2.2-1 There are no such cranes.
Both the spent fuel pool bridge and hoist, and the cask handling crane in the Fuel Storage Building are excluded, and the justification is provided below in Response 2.2-2.
REQUEST 2.2-2
" Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads or are permanently prevented from movement of the hook centerline closer than 15 feet to the pool boundary, or by providing a suitable analysis demonstrating that for any failure acde, no heavy load can fall into the fuel - storage pool."
RESPONSE TO 2.2-2 The following cranes are excluded from our response to 2.2-1, above:
EQUIPMENT NO. CRANE MANUFACTURER CAPACITY FH-RE-2 Spent Fuel Pool Dwight Foote Inc. 2 Tons (Derated Bridge and Hoist (Hoist by P&H) Capacity-1T)
FH-RE-1 Spent Fuel Cask Whiting Corp. 125 Ton Main Handling Crane (5 Ton Hoists 2 6 5 Ton Aux.
by P&H)
- 1. Spent Fuel Pool Bridge and Hoist The spent fuel pool bridge and hoist does not handle heavy loads.
The only loads carried by the hoist over the spent fuel pool are the fuel assemblies with or without control elements and their associated handling tools, and burnable poison rod assemblies and handling, tools. The hoist will be derated to one (1) ton by displaying new rated load on the unit, clearly legible from the operating position. Therefore, this load handling system has not
'been included.
- 2. Spent Fuel Cask Handling Crane The cask handling crane is excluded because of its location in the Fuel Storage Building relative to the spent fuel storage pool.
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The design of the layout of the cask loading pool, spent fuel storage area and cask storage and decontamination area eliminates the need to move the cask and other heavy loads over the spent fuel. Since both the cask handling crane rails are outside the boundaries of the spent fuel storage pool--both rails are on the east side--it is physically impossible for any of the three hooks to travel over the spent fuel storage pool.
i The cask loading pool is separated from the spent fuel storage area by a six foot thick reinforced concrete wall with a stainless steel liner on each side. An isolation gate is provided in the wall, with the lowest point of the gate opening being above the top of the fuel in the storage racks. The steel gate is in the
- closed position whenever the spent fuel cask or other heavy lords ate handled over the-cask loading pool. Figure 2.2.2-1 shows approximate locations of the above areas and limits of travel of the main and auxiliary hooks.
In the extreme position of the trolley, the centerline of the 125 ton main hook is 10 feet away from the spent fuel storage pool boundary. The cask design has not yet been finalized; however, use of the preliminary dimensions in the load drop analysis indicates that in the unlikely event of a cask drop in the loading pool, integrity of the storage pool will not be breached nor would any damage occur to the stored spent fuel. A loss of spent fuel storage pool water will be prevented by the isolation gate in the wall.
The centerline of the two 5 ton auxiliary hooks, in the extreme
. position of the hoists, cannot move closer than 8'-8" to the storage pool boundary.
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The auxiliary hook number 1 is normally used to handle single fuel elements. The new fuel containers, each weighing about 6,700 pounds, are normally handled by auxilairy hook number 2. The area in the Fuel Storage building allocated to storage and handling of the new fuel containers eliminates the need to carry the containers near the spent fuel storage area or the cask loading pool. In the unlikely event of inadvertent carrying of the new fuel containers near the 1
spent' fuel storage area and coincident failure of the load handling system, the container will fall in the cask loading pool only since the center of gravity of the load falls approximately 2'-8" from the outer edge (or 8'-8" from the inner edge) of the spent fuel storage pool wall.
PSNH takes exception, on the basis of plant specific design, to the 15 feet requirement for minimum distance of the hook centerline from the spent fuel pool boundary. The ten (10) feet separation presently allowed in the Seabrook Station design is more than sufficient, due to the physical layout, to ensure that the cask, if dropped, does not fall into the spent fuel storage pool or compromise its integrity. The limits imposed on the hook travel will again b reviewed, when the cask dimensions are finalized; and, if necessary, feasibility of moving the fixed mechanical stops to increase this distance will be examined.
The cask handling crane is not a seismic Category I component; however, in compliance with Regulatory Guide 1.29 the crane design i
q parameters are specified to provide adequate quality control of fabrication and design so that in the event of an Operating Basis Earthquake (OBE) or Safe Shutdown Earthquake (SSE), the crane will not fail in such a manner as to impair the functioning of any plant feature designated as seismic Category I. The crane is prevented from being dislodged off its rails during the SSE by mechanical anti-derailing devices.
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i In addition, the cask handling crane includes the following safety features which contribute to the reliability of the load handling operations:
a) Dual limit switches, each of different design, are provided in series to stop the main and auxiliary hooks in their highest safe positions and prevent a "two-blocking" incident. Limit switches are also provided to restrict the downward travel of the hooks.
b) Low or no voltage for any motion automatically stops the motion and sets brakes.
c) The drives for the bridge, trolleys and hoists are variable speed with an inching control on the main hoist. Controls for all motions are full magnetic, 5 step timed acceleration type. In addition, main hoist control includes magnet operated i electric shoe type brakes to provide positive controlled speed regulation in both hoisting and lowering, d) The hoist motor shaft is provided with two electrically released, spring actuated double shoe type DC load holding i
brakes each rated at 150 percent of motor full load torque.
e) The crane is designed for a minimum safety factor of 5 in accordance with CMAA Specification No. 70 and ANSI B30.2-1967.
i However, taking into consideration the actual weight of the 7
i heaviest anticipated load handled, the factor of safety provided t is expected to be more than five.
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, Furthermore, the spent fuel shipping cask or other heavy loads cannot travel over any safety related equipment. The spent fuel pool cooling equipment is located in a separate area in the Fuel i
Storage Building beyond the operating area of the cask handling crane. Although no credit is taken in the above discussion for safe load paths, load handling procedures and other technical specifications; it is, however, pointed out that the administrative controls, proper operator training, Icad paths and procedures will help ensure the safe handling of the heavy loads, with loads being maintained as far away from the spent fiel pool boundary and as close to the floor as practical.
Radiological consequences of a spent fuel cask drop accident are presented in FSAR Section 15.7.5. The results of a conservative analysis and a realistic analysis are summarized in Table 15.7-28.
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REQUEST 2.2-3
" Identify any cranes listed in 2.2-1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this r evaluation (i.e., complete compliance with NUREG 0612, Seciton 5.1.6 or l
1-partial compliance supplemented by suitable alternative or additional design l features). For each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment 1."
RESPONSE TO 2.2-3 Refer to Response 2.2-1.
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REQUEST 2.2-4 "For cranes identified in 2.2-1, above, not categorized according to 2.2-3, demonstrate that the criteria of NUREG 0612, Section 5.1, are satisfied. '
Compliance with criterion IV will be demonstrated in response to Section 2.4 of this request. With respect to criteria I through III, provide a discussion of your evaluation of crane operation in the spent fuel area and your determination of compliance. This response should include the following information for each crane."
RESPONSE TO 2.2-4 Refer to Response 2.2-1. No cranes fall in this category.
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- 6. RESPONSE TO SECTION 2.3 (ENCLOSURE 3)
Specific Requirements for Overhead Handling Systems Operating in the Containment "NUREG 0612, Section 5.1.3 prcvides guidelines concerning the design and operation of load-handling systems in the vicinity of the reactor core. Information provided in response to this section should be sufficient to demonstrate that adequate measures have been taken to ensure that in this area, either the likelihood of a load drop which might damage spent fuel is extremely small, or that the estimated consequences of such a drop will not exceed the limits set by the evaluation criteria of NUREG 0612, Section 5.1, criteria I through III."
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REQUEST 2.3-1
" Identify by name, type, capacity, and equipment designator, any cranes physically capable (i.e., taking no credit for any interlocks or operating procedures) of carrying heavy loads over the. reactor vessel."
RESPONSE TO 2.3-1 The following cranes and monorail-hoists can carry heavy loads over the reactor vessel:
EQUIPMENT NO. CRANE TYPE CAPACITY MM-CR-3 Polar Cantry Crane Revolving Over- 420 Ton Main head Bridge 50 Ton Aux.
FH-RE-24 Radial Arm Stud Monorail 2 Ton each Tensioner Hoists (3)
REQUEST 2.3-2
" Justify the exclusion of any cranes in.this area from the above category by verifying that they are incapable of carrying heavy loads, or are
- permanently prevented from the movement of any load either directly over the reactor vessel or to such a location where in the event of.any load-handling system failure, the load may land in or on the reactor vessel."
RESPONSE TO 2.3-2 The following load handling systems are not listed above in Response 2.3-1.
The justification for their exclusion is provided below:
EQUIPMENT NO. CRANE TYPE CAPACITY FH-CR-33 Jib Crane Jib 0.75 tons i FH-RE-5 Manipulator Crane Traveling Bridge 1.5 tons Auxiliary Hoist and Hoist (Derated Capacity-1T)
The jib crane is not capable of carrying heavy loads. It is used primarily to handle studs, and tools required to unbolt and remove the reactor ve.ssel head during refueling operations.
The manipulator crane auxiliary hoist handles only light loads such as
- control rod drive shaft, drive shaft unlatching tool, shaft handling tool, guide tube cover and cover handling tool, thimble plug and its associated handling tool etc. Also, the auxiliary hoist will be derated to one(1) ton i
capacity to preclude inadvertent use of this hoist with heavier loads. The new rated capacity will be marked on the hoist unit. (The main hoist system f
is supplied with redundant paths of load support such that failure of any
- one component will not result in a drop of the fuel assembly).
REQUEST 2.3-3
" Identify any cranes listed in 2.3-1, above, which you have evaluated as having sufficient design features to make the likelihood of a inad drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).
For each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment I."
RESPONSE TO 2.3-3 The polar gantry crane has been evaluated as having sufficient design features to make the likelihood of a load drop extremely small. The basis selected for this evaluation is essential compliance with NUREG 0612, Section 5.1.6, supplemented by additional design features.
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Polar Cantry Crane
- 1. Rated Capacity Manufacturer Whiting Corporation Design Rated Load (DRL) 420 ton Main 50 ton Auxiliary Maximum Critical Load (MCL)
Main Hook 210 tons (See Note 1)
Auxiliary Hook 25 tons (See Note 2)
Note 1: Maximum anticipated load with fuel in the reactor vessel is, however, 168 tons.
Note 2: The only exception is the equipment hatch cover which weighs more than 25 tons. However, in the unlikely event of a load drop, resulting damage to the plant eq ipment will not affect the decay heat removal process, nor would there be any damage to the spent fuel. The equipment hatch cover will be handled only when the reactor is in cold shutdown, with the residual heat removal system removing decay heat.
- 2. Point-By-Point Comparison with NUREG 0554 The following evaluation is a point-by point comparison of the design, fabrication, inspection, testing, and maintenance of the polar crane to the requirements delineated in NUREG 0554. Where the design features differ from those of NUREG 0554, they are presented along with an explanation to demonstrate their equivalency and/or adequacy.
Section 1. Introduction Section 2. Specification and Design Criteria 2.1 Construction and Operating Periods Requirement: The allowable design stress limits for the crane intended for plant operation should be those indicated in Table 3.3.3.1.3-1 of CMAA Specification No. 70 reflecting the appropriate duty cycle.
Actual: This requirement is met. The allowable stresses used in the design of the polar crane are as per CMAA Specification No. 70 for Class A1 (Standby Service).
2.2 Maximum Critical Load (MCL)
Requirement: The Design Rated Load (DRL) should be at least 15%
greater than the Maximum Critical Load (MCL).
Actual: The requirement is met. The DRL is 200 percent of the MCL, and is considered to be an important factor in proving the adequacy of the polar gantry crane.
~2.3 Operating Environment Requirement: The operating enviornment including minimum and maximum ,
pressure, maximum rate of pressure increase, temperature, humidity and emergency corrosive or hazardous conditions should be specified as well as proper venting and drainage requirements to avoid collapse and standing water.
Actual: The crane design complies with this section of NUREG 0554. The following service conditions are specified in the Polar Crane Specification 9763-006-257-2:
Design Temperature, Minimum -200F Design Temperature, Maximum +1200F Temperature (accident conditions) 2960F 1
Wind Loading 35 mph (while in operation) 110 mph (while not in use)
Pressure (normal operation) Atmospheric to 15.7 psia
- Pressure (accident conditions) 52 psig I Pressure (pressure test) 60 psig
Pressure Change 4 psi /sec Relative Humidity 30-100%
Radiation Dose 50 mR/ Hour Aqueous Spray pH 8.0-10.5 Boron (calculated as boric 4 w%
acid)
Sodium Hydroxide 1.75 w%
All enclosed portions of the crane equipment have positive openings to the environment.
2.4 Material Properties Requirement: Materials for structural members essential to structural integrity should be tested for brittle fracture per ASTM E-208 (Drop Weight Test) or ASTM A-370 (Charpy Test).
Minimum operating temperatures based on drop weight test should be obtained from paragraph NC 2300 of Section III or for Charpy test from paragraph ND 2300 of Section III of the ASME Boiler and Pressure Vessel Code.
OR Cold proof load test should be performed.
Actual: Material testing for brittle fracture was in accordance with the above requirements. Load bearing members of cranes including weld metal and bolting whose failure
could damage components were impact tested in conformance with United Engineers Specification No.
9763-MPS-2 including the following:
t Impact testing shall be performed in accordance with ASME Section VIII Division II, Article M-2 (including exemptions) as modified below:
(a) Testing is not required for material thickness of 5/8" or less.
i (b) Testing is not required for all thicknesses of ,
material for pipe, tube, fittings, pumps and valves with a nominal pipe size of 6" diameter or less.
(c) Testing of support and crane welds when required shall be performed as required by Article T-2 as specified for Category B joints.
(d) Impact testing of materials for cranes shall be conducted at 300F below the lowest service tempera-ture.
(e) The lateral expansion value in Table AM 211.1 shall be 0.025" in lieu of 0.015".
2.5 Seismic Design Requirement: Crane should be designed to restain load during an SSE; and the bridge and trolley should remain on their respective runways with wheels prevented from leaving 4
the tracks. Design should also be in accordance with 4
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l regulatory position 2 of Reg. Guide 1.29, Seismic Design Classification.
Actual: Although the polar crane is not classified as Seismic Category I equipment, the design does include considera-tion of Safe Shutdown Earthquake (SSE) and Operating Basis Earthquake (OBE). The dynamic forces resulting from SSE and OBE accelerations corresponding to the response spectra for the containment operating floor were considered in the modal seismic analysis of the crane load bearing elements. The dynamic analysis was performed in accordance with the procedures stipulated in United Engineers Specification 9763-SD-257-2. The analysis assumed that the crane and trolley were both in the parked position and that the crane was unloaded.
Due to the infrequent use anticipated for this crane, the combined probability of the event involving a heavy load lift and the occurrence of an SSE is expected to be extremely low. Therefore, this assumption is considered to be valid.
The crane design and construction is in accordance with regulatory position C2 of Reg. Guide 1.29, i.e., the crane will not fail in such a manner as to damage safety related equipment or in any way prevent the performance of their safety function in the event of a seismic event equal to SSE. The bridge and trolley are equipped with earthquake restraints (up-kick lugs) which are designed t to prevent the crane from overturning and leaving the rails during an SSE.
2.6 Lamellar Tearing Requirement: All weld joints whose failure could result in the drop of a critical laod, and the base metal at the joints susceptible to lamellar tearing should be non-destruc-tively examined.
Actual: These requirements are met. The polar-crane specifica-tion 9763-006-257-2 required the crane supplier to perform radiographic examination on the cover plate splice welds in the tension members of the bridge girders in accordance with the United Engineers Standard 9763-WS-3. All other welds were required to be examined by magnetic particle technique as per 9763-WS-3. All load bearing welds were specified to be full penetration type.
2.7 Structural Fatigue Requirement: Fatigue-analysis for the critical load bearing structures and components should be performed. The cumulative fatigue usage factors should reflect effects of the cyclic loading from both the construction and operating periods.
Actual: Construction usage was identified in the crane speci-fication 9763-006-257-2 and, therefore, was considered f
. by the crane manufacturer in order to assure placement of the crane into the proper classification. The polar crane was designed in accordance with CMAA Specification No. 70. The allowable stress range values for the polar crane are in accordance with Table 3.3.3.1.3-1 which takes into consideration the number of loading cycles.
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The polar crane is classified as Al and meets the intent of Section 2.7.
2.8 Welding Procedures Requirement: Preheat and postweld heat treatment temperatures should be specified for all welds. Welds whose failure could result in the drop of a critical load should be postweld heat treated per Subarticle 3.9 of AWS DI.1, Structural Welding Code.
1 Actual: This requirement is met. Welding was performed in ac-cordance with United Engineers Specification 9763-WS-3 which further makes reference to AWS D1.1 as the applicable standard for welding, welding procedure qualifications and welder performance qualifications.
All welding _ procedures and qualifications were approved by United Engineers.
Section 3 Safety Features 3.1 General 3.2 Auxiliary Systems Requirement: 1. Auxiliary hoisting systems employed to lift or assist in handling critical loads should be single-
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- 2. The main hoisting mechanism should be provided with redundant or dual components.
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Actual:- 1&2. The main and auxiliary hoists are not single-failure proof; however, they have sufficient design features to guard against a load drop. The hoists a
are equipped with dual upper limit switches to prevent two-blocking. The heavy loads identified in Table 2.1.3(c)-1 do not exceed 50% of.the rated
- capacity of the hoists, with the exception of equipment hatch cover, thereby increasing the available safety factors to 10 or greater. A minimum safety factor of 5 will be maintained while handling equipment hatch cover with the auxiliary hoist and the hatch cover handling boom.
The equipment hatch cover will be handled only when the reactor is in COLD SHUTDOWN with the residual heat removal system in operation. Technical Specifications also prohibit opening of the equipment hatch during refueling operations. In the unlikely event of a handling system failure resulting in a load drop, damage to the plant equipment will be limited, and will not affect the spent fuel or decay heat removal process. The Preventive Maintenance and Inspection Program to be implemented for all cranes will reveal any deterioration of the lifting equipeent and allow for repairs prior to component failure.
T 3.3 Electric Control Systems Requirement: Provide fail safe controla and limiting devices such that when disorders due to inadvertent operator action, component malfunction or disarrangement of subsystem
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Section 4 Hoisting Machinery 4.1 Reeving System Requirement: 1. Dual reeving system each providing separate load balance on the head and load blocks through a configuration of ropes and rope equalizers, is required.
- 2. Rope sizing should include effects of impact loads, acceleration and emergency stops. Maximum loads C
(including static and inertia forces) on each indi-vidual wire rope in the dual reeving system with MCL attached, should not exceed 10% of the manufacturer's published breaking strength.-
- 3. Maximum fleet angle from drum to lead sheave in the load block or between individual sheaves should not exceed 3 1/20 at any one point during hoisting, except that for the last 3 feet of maximum lift elevation, the fleet angle may increase slightly.
The use of reverse bends should be limited.
- 4. The pitch diameter of running sheaves should be selected in accordance with CMAA Specification 70.
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Actual: 1. The main hoist reeving system is a 2-rope system 7- using dual drums and two separate ropes, each l
reeved through upper and lower sheaves to an equalizer sheave and anchored to one drum. The reeving configuration consists of 32 parts (2 ropes x 16) of 1 1/4" diameter 6 x 37 IWRC extra improved plow steel wire rope.
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- 2. The ropes have been sized to include effects of I
impact loading, acceleration and emergency stops.
The maximum load on each of the individual wire r
l ropes in the reeving system with the MCL attached, does not exceed 10% of the published breaking strength.
- 3. The reeving is designed such that the flect angle relative to the drum or sheaves does not exceed j 4.750 during any operating condition. As per l
7 Appendix C to NUREG 0612, Modification of Existing
! Cranes, larger than recommended fleet angles have been accepted for similar applications. The crane inspection and preventive maintenance program to be implemented at Seabrook will assure the continued i
l integrity of the wire ropes.
- 4. The polar crane has been designed in accordance with CMAA Specification 70. The pitch diameter of all running sheaves is 24 times the rope diameter.
l The auxiliary hook is equipped with a single rope reeving system employing a single drum and 12 parts of 5/8" diameter 6 x 37 regular lay wire center rope. The anticipated loads to be handled by this hook during plant operation will provide design y safety factors of greater than 10, except equipment hatch cover for which a minimum safety factor of 5 is maintained.
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4.2 Drum Support Requirement: The load hoisting drum should be provided with structural and mechanical safety devices to limit the drop of the drum and thereby prevent it from disengaging from its holding brake system if the drum shaft or bearings were to fail or fracture. '
- - Actual
- Each of the two load hoisting drums is supported at each end by a roller bearing rounted in a pedestal, and is driven through a gear and pinion at one end. The erane design does not include any special retaining features to limit the excessive drop of the drum in the event of a shaft or bearing failure. Therefore, depending upon the failure, the drum might disengage from the driving pinion, or alternatively in the case of a small drop it may still remain partially engaged. However, this failure is not credible because of increased safety margins allowed in the design of the polar crane. By considering an MCL of 210 tons, the safety factor provided is 10.
4.3 Head and Load Blocks Requirement: 1. The load block assembly should be provided with two
, load-attaching points, each designed to support a
. Load of three times the load being handled without l
permanent deformation.
j' 2. The individual component parts of the hoisting system should each be designed for a static load of 200% of the MCL.
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- 3. Each load-attaching point should be load tested at 200% of the MCL. Dimensional measurements of the hook configuration should be made, and NDE should be performed both before and after the test.
- 4. The load blocks should be non-destructively
, examined by surface and volumetric techniques, and the results should be documented.
Actual: 1. The crane is equipped with a single attachment sister hook (main) with a pin hole and safety latches. As per Appendix C to NUREG 0612, a safety
' factor of 10 is provided to compensate for loss of the single-failure proof feature.
- 2. .The individual components of the vertical hoisting
- system are designed for a static load of 200% of the MCL.
- 3. The main hook including pin hole was load tested in the shop at 150% of the design rating or 300% of the MCL. A longitudinal magnetic particle test and ultrasonic inspection were performed as per above requirements. The load-attaching points were also subjected to a load test in the field in accordance with ANSI B30.2 at 250% of the MCL.
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- 4. The load blocks were examined by magnetic particle and ultrasonic inspection techniques during manu-facture, in accordance with the polar crane speci-fication and other applicable standards. The results of the NDE have been documented.
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The 50 ton auxiliary hook is of the single prong type and ir equipped with a safety latch. The increased safety factors provided for the auxiliary hoisting system enhance the reliability of the load hoisting system. The above load tests and NDE were also performed on the auxiliary hook.
4.4 Hoisting Speed Requirement: Maximum hoisting speed for the critical load should be limited to that given in.the 'alow' column of Figure 70-6 of CMAA Specification No. 70.
Actual: The polar crane hoist speeds comply with the above requirement.
4.5 Design Against Two-Blocking '
Requirement: 1. Provide means within the reeving system located on the head or load block combinations to absorb or control the kinetic energy of rotating machinery during a two-blocking incident.
OR Provide two independent travel limit devices of different design and activated by separate mechanical means, t
- 2. The protective control system for load hang-up l
should consist of load cell systems in the drive i train or motor current sensing devices or mechanical. load limiting devices.
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- 3. The auxiliary hoist, if supplied, should be equipped with two independent travel limit switches.
. Actual: These requirements are met.
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- 1. The main hoist is equipped with dual upper limit switches to prevent two-blocking. One of the two load hoisting drums contains a screw type limit switch (which also limits the downward travel) in addition to a weight type limit switch which is directly actuated by the traveling load block.
- 2. A load cell on the main hoist provides load indication in the cab and is equipped with an adjustment feature. The power supply to the hoist l
motor is interrupted at a preset load value.
- 3. TF auxiliary hoist is provided with two indepen-dent travel limit switches.
4.6 Lifting Devices Requirement: The lifting devices that are attached to the load block should be conservatively designed with a dual or auxiliary device or combination thereof. Each device should be designed to support a load of three times the load (static and dynamic) being handled without permanent deformation.
l l Actual: Refer to item 4 in this section on polar crane for a detailed evaluation of the lifting devices.
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4.7 Wire Rope Protection d
Requirement: If side loads cannot be avoided, the reeving system should be equipped with a guard that would keep the wire rope properly located in the grooves on the drum.
Actual: The proper operator training and load handling proce-dures will assure that the significant side pulls are avoided under all circumstances.
4.8 Machinery Aligoment Requirement: Where gear trains are interposed between the holding 4
brakes and the hoisting drum, these gear trains should be of single failure proof design.
Actual: The hoisting machinery is not equipped with single failure proof or redundant gear trains. Depending upon the failure, a single active component failure in the gear train between the holding brakes and the hoisting drum could render the train ineffective in transmitting power or holding the drum with the brakes activated.
However, increased factors of safety employed in the design of the gear case and other components will make such failures incredible.
'4.9 Hoist Braking System Requirement: 1. The minimum hoist braking system should include one power control braking system and two holding brakes. Each holding brake should have a minimum capacity of 125% of the torque developed during the A
hoisting operation at the point of brake application.
- 2. The holding brake system should be single failure proof.
- 3. Provision for manual operatiot; of the hoisting brakes during emergency conditions should be included in the crane design.
Actual: 1. Both the msin and the auxiliary hoist are each equipped with a separate braking system which is comprised of an eddy current brake and two DC load holding brakes. Each holding brake is rated at 150% of the motor full load torque.
- 2. One of the two holding brakes is directly applied to the motor shaft and the other with a time delay is designed to apply to an intermediate shaft in the gear train. Following a malfunction or failure of one brake, the other independent brake is capable of holding the hoisting drums to eliminate the possibility of an accidental load drop. The l interposing gear trains are discussed-in 4.8, above.
The brakes are automatically applied upon power l interruption or in the event of an overspeed or l overload condition.
- 3. The holding brakes are not equipped with any lever
! or other design feature to aid in controlled lowering i of the load under emergency conditions. However, l the design of this crane makes the occurrence of an event requiring such action extremely remote. The
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main hoist and the auxiliary hoist each have an independent precision drive in addition to the primary drive. However, should a manual lowering of the load be required, one of several means of i
control of brake shoe adjustment could be ?ocally l devised to permit a controlled lowering of the t
l load.
Section 5 Bridge and Trolley 5.1 Braking Capacity Requirement: 1. The maximum torque capability of the driving motor and gear reducer for trolley and bridge should not exceed the capability of the gear train and brakes to stop the trolley or bridge from maximum speed with DRL attached.
- 2. Mechanical drag-type brakes should not be used to control movements of the bridge and trolley.
Control and holding brakes should each be rated at 100% of maximum drive torque.
- 3. Brakes should be activated in the event of a power j shut-off, malfunction in the power supply or an overspeed condition.
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- 4. Opposite-drive wheels on bridge or trolley should
, be matched and have identical diameters.
l S. Trolley and bridge speeds should be limited as per CMAA Specification No. 70.
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Actual: The braking system is generally in accordance with the above requirements; and also complies with the requirements of CMAA Specification No. 70. Each bridge drive motor is equipped with a Whiting 6" solenoid brake type "SESA" (Covered), designed for a minimum torque of 100% of the rated full load torque. The trolley brake L provides a minimum torque of 50% of the rated full load torque of the drive motor as per CMAA Specificatien No. 70. Both the bridge and trolley brakes-automatically apply torque and act as parking, fail-safe brakes upon loss of power or full release of the
! controller button. Controls for all motions are specified to be full magnetic 5 step, timed acceleration type.
5.2 Safety stops t
Requirements: Mechanical and/or electrical limiting devices should be provided to prevent over-travel or overspeed of the trolley and bridge. .
Actual: The crane design complies with this requirement. Four (4) fixed mechanical stops are provided at the end of the trolley rails, and prevent overtravel of the trolley by coming in contact with spring bumpers attached to the trolley trucks. No stops are required for the revolving bridge.
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Section 6 Drivers and Controls 6.1 Driver Selection Requirement: The maximum torque capability of the electric motor drive for hoisting should not exceed the rating or capability of the individual components required to hoist the MCL at maximum design speed.
Actual: The electric drive motors were selected in accordance with the requiremente established in CMAA Specification No. 70 and meet the intent of this Section.
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6.2 Driver Control Systems Requirement: If the crane is used to lift spent fuel assemblies, the contro1Lsystem should be adaptable to include interlocks that will prevent trolley and bridge movements while the load is being hoisted free of the reactor vessel or storage rack.
Actual: The polar gantry crane does not handle spent fuel i.
assemblies.
f 6.3 Malfunction Protection Requirement: Means should be provided in the motor control circuits to sense and respond to excessive current, excessive temperature, overspeed, overload and over-travel.
Controls should be provided to absorb the kinetic energy of the rotating machinery and stop the hoisting movement if one rope or one of the dual reeving systems should t
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fail or if an overloading or overspeed condition should occur.
Actual: The design of the motor control circuitry is in compliance with the above requirement; and includes necessary protection features such as overload relays, overspeed switch, load sensing devices and under voltage protection.
6.4 Slow Speed Drives Requirement: If jogging or plugging is to be used, the control circuit should include features to prevent abrupt change in motion.
Actual: This requirement is met. Precision or inching drives are provided to reduce the main hoist speed to 2.4 inches per minute and the auxiliary hoist speed to 22.8 inches per minute. The normal or slow speed for either hoist can be selected from the " NORMAL-INCHING" switch-located on the control panel in'the cab or from a similar switch on the pendant station. The control system is considered to be adequate to protect against an abrupt change in motion. Also, the proper training program will stress the need to avoid any abrupt change in motion which could cause load swings.
6.5 Safety Devices l
Requirement: Safety devices such as limit switches provided for mal-function, inadvertent operator action or failure should be in addition to and separate from the limiting means or control devices provided for operation.
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Actual: The design of the polar crane complies with this requirement.
The travel limit switches as discussed in the preceding sections are separate from normal control functions provided for operation.
6.6 Control Stations Requirement: The controls-for normal operation, and provisions for emergency controls should preferably be located in a cab on the bridge. Additional operator stations, when provided,
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should have control systems similar to the main etation.
Electrical interlocks should be included so as to permit the crane operation from only one control station at any one time.
Actual: The requirement is met. .The polar crane is equipped with two control stations, a cab mounted on the underside of the bridge and a pushbutton pendant station. Both these stations have similar control functions with proper electrical interlocks as per above requirements. Manual transferring of the load is possible under emergency conditions.
Section 7 Installation Instructions 7.1 General 4
Requirement: Installation instructions should be provided by the manu-facturer.
Actual: The requirement is met. Complete instructions for unloading, extended storage, erection and testing of the polar crane were provided by the manufacturer.
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7.2- Construction and Operating Periods Requirement: 1. 'The construction operating requirements should be defined separately.
- 2. At the end of the construction period, the crane should be modified as needed for the performance requirements of the plant operating service:.
- 3. After construction use, the crane should be thoroughly inspected by NDE and load tested for the operating phase.
- 4. NDE extent and acceptance criteria should be defined in the design specification.
- 5. If allowable stress limits are to be exceeded during construction, added inspection supplementing that described in Section 2.6 should be specified and developed.
- 6. During and after installation of the crane, the proper assembly of electrical and structural components should be verified.
- 7. The integrity of control, operating and safety 1
systems should be verified.
Actual: The'above requirements are met.
- 1. The operating requirements for the construction phase were defined in the polar crane specification.
- 2. Modification of the polar crane is not required.
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- 3. The polar crane will be thoroughly inspected and refurbished, if necessary. The crane will be reload tested if any modifications or alterations, temporary or not, have invalidated the original load test. Also, pursuant to the satisfaction of Section 7.2 of NUREG 0554, the polar crane will be ratested for the operating phase as follows:
Main Hoist A rated load test at 125 percent of the MCL (i.e.
at 262.5 tons) will be conducted in accordance with ANSI B30.2. In addition, an operational or no-load test will be performed in accordance with the requirements of ANSI B30.2.
Auxiliary Hoist C
4 A rated load test at 125 percent of the DRL (i.e.
at 62.5 tons) will be conducted in accordance with ANSI B30.2. Also, an operational or no-load test will be performed in accordance with the require-ments of ANSI B33.2 4
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. 4. NDE extent and acceptance criteria were not defined in the crane specification for removal from con-struction phase to plant operation phase. These will be defined in a written procedure prior to use r
of the crane in the operation phase.
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i S. Allowable stress limits will not be exceeded during the construction phase.
- 6. Proper assembly of electrical, structural and mechanical components was verified.
- 7. Integrity of control, operating, and safety systems will be verified during crane checkout and load test.
1 Section 8 Testing and Preventive Maintenance 8.1 General Requirements: 1. Make a complete check of all mechanical and electrical systems of the crane before the tests.
- 2. Information concerning shop testing should be available at the plant site.
Actual: These requirements are met.
- 1. All mechanical and electrical systems were thoroughly inspected and checked out irior to the field acceptance tests.
- 2. In addition to required tests and inspection as per technical specifications, all hooks were load tested
[ in the shop to 1.5 times the design rating. A longitudinal magnetic particle test and ultrasonic inspection were performed on the hooks both before and'after the load test. A no-load running test of 1
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all motors was conducted. The necessary documen-tation concerning these tests is available in QA-
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files at the plant.
8.2 Static and Dynamic Load Tests l
! Requirement: A static load test at 125% of the maximum critical load 1
(MCL) should be performed. Full performance test with 100% of the MCL including verification of the proper functioning of all limiting and safety control devices should he conducted.
Actual: For the main hoist and the auxiliary hoiet, a static load test at 125% of the MCL and a performance test at or above 100% of the MCL will be performed as per above requirement. Proper functioning of all limit switches and other safety control devices will be verified.
l 8.3 Two-Block Test l
Requirement: 1. When equipped with an energy-controlling device between the load block and the head block, the complete hoisting machinery should be allowed to i two-block. The test should be conducted at s!-)w i
l speed without load, i
l 2. Crane should be tested for load hangup.
! Actual: 1. Appendix C to NUREG 0612, allows the crane to be I
furnished with two independent travel limit switches in lieu of a design to withstand a two-l blocking incident. This alternative is selected l
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for the polar crane; and the proper functioning of the dual upper limit switches was verified during rated load test and operational tests. Limit switches for the main hoist and the auxiliary hoist will be again verified for proper functioning at the time of crane turnover to operations, as part of the operational tests.
- 2. Interleck alternative as outlined in Appendix C is selected in lieu of load hang-up protection. An -
overload sensing system is provided on the main hoist with read-out and adjustment in the control cab. In the event, the hoist load exceeds the set-point of the load sensing device, power supply to
, the hoist motor is interrupted, thus preventing overloading of the hoisting machinery.
8.4 Operational Tests Requirement: Operational tests should be performed to verify the proper functioning of limit switches and other safety devices.
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Actual: The requirement is met. Inspection and operational tests were performed in :-aordance with ANSI B30.2.
These tests including verifi ation of proper functioning I of all limit switches will be again performed at I
l turnover to operating phase.
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8.5 Maintenance i
Requirement: The critical load handling cranes should be continuously maintained above MCL capacity. The MCL should be e
clearly marked for each hoisting unit.
l Actual: The polar cranc as well as other cranes and monorails l are subject to a periodic inspection and maintenance i program as outlined in this report. The crane l inspection, testing and maintenance program is I considered an extremely important componeat in the overall safe load handling operations at Seabrook. The MCL will be marked on the crane in addition to the design rated load.
Section 9 Operating Manual Requirement: Manufacturer should provide an operating manual for the i crane.
Actual: This requirement is met. . Whiting Corporation provided a crane manual which contains information on checking,
{ operating, and maintaining the polar crane.
Section 10 Quality Assurance l
l Requirement: A quality assurance program should be established to the extent necessary to include recommendations of NUREG 0554 for the design, fabrication, installation, testing
, and operation of the cranes. The applicable procurement l
I documents should specify a quality assurance program consistent with the pertinent provisions of Regulatory l
Guide 1.28, " Quality Assurance Program Requirements (Design and Construction)".
Actual: A quality assurance program in accordance with the requirements of United Engineers Standard 9763-QAS-2, which applies to non-nuclear safety (NNS) class items, was specified for the polar crane. A quality assurance manual and written procedures such as welding procedures; welding procedure qualifications; heat treatment, NDE, test, inspection and cleaning procedures is a requirement of this standard. Under this program, material certifications or material test reports are required to satisfy code or specification requirements.
The procedures and documents contain appropriate quantitative or qualitative criteria for determining compliance with the applicable standards or specifications. Sufficient records are prepared as work is performed to furnish documentary evidence of the I
quality of item. All fabrication, inspection, and test operations performed by Contractors and their l Subcontractors are subject to surveillance by the Engineer and the Owner.
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- 3. Seismic Analysis The crane is designed to remain in place during and after the seismic event. As described above under point-by point comparison, both the bridge and trolley wheel trucks are equipped with anti-derailing devices which prevent the bridge and trolley from disengaging from their respective runway rails when the crane is subjected to seismic excitations. A general purpose computer program, ANSYS, was used to perform the modal dynamic analysis of the crane. A detailed description of the method of analysis and assumptions are given in Section RAI 220.23 (3.7(B).3) of the FSAR.
The mathematical model assumed the crane to be in a parked position at the time of the seismic event equivalent to SSE. Also, no lifted load was considered in the seismic analysis. This assumption is based upon the fact that the crane will not be in use for a great majority of the time during plant operation phase. The seismic occurrence at the time the crane is in use and carrying a heavy load, is considered to be a low probability event.
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- 4. Lifting Devices l
An evaluation of the lifting devices for the polar crane with respect to the guidelines of NUREG 0612, Section 5.1.6 is provided below:
(a) Standard Lifting Slings The standard lifting slings and associated fittings will meet the L requirenents of ANSI B30.9-1971. An allowance for dynamic loading will be added to the static load as per Section 5.1.1(5) of NUREG 0612. Furthermore, in selecting the proper sling size, the load used will be twice the sum of the static and dynamic loads so derived; j i.e., a safety factor of 10 or greater will be maintained in accordance with the requirements of Section 5.1.6.
i (b) RV Head Lifting Rig, Load Cell and Load Cell Linkage Assembly i
Refer to Appendix I (c) Spreader Assembly The spreader assembly is part of the RV head lifting rig and is used to handle reactor missile shield during refueling operations.
Analysis of the spreader assembly is included in Appendix I.
(d) Internals Lifting Rig, Load Cell and Load Cell Linkage Assembly Refer to Appendix I (e) RC Pump Motor Lifting Device i
i The reactor coolant pump motor lifting device will meet the
( requirements of applicable standards, ANSI N14.6-1978 as supplemented by NUREG-0612, Sections 5.1.1 and 5.1.6.
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(f) Equipment Hatch Cover Handling Device, Reactor Cavity Seal Ring Lifting Device, and Pressurizer Enclosure Wall Handling Device The'se special lifting devices will comply with the requirements of ANSI N14.6-1978 as supplemented by NUREG-0612.
- 5. Interfacing Lift Points An evaluation of the attachment points for heavy loads with respect to the guidelines of NUREG 0612, Section 5.1.6 follows:
(a) Reactor Vessel Head and Upper Internals Refer to Appendix I, Analysis of Special Lif ting Devices.
(b) RC Pump Motor Lifting Lugs The four lifting lugs for the reactor coolant pump motor are designed with a safety factor of 6, based upon ultimate strength.
In the event of a failure of a single lift point, the load will be transferred to the other two points with the safety factor reduced to 3 (assuming conservatively that only two of the three remaining lugs assume the full load). Because of a four lift point system, the load is expected to be retained under these conditions.
(c) Neutron Shield Panels Each shield panel is provided with three lifting lugs with a design safety factor of 8.6 based upon ultimate strength. Failure
- of a single attachment point would result in an uncontrolled move-ment of the panel, but not necessarily a load drop. The safety factor is considered to be adequate since the load would be imme-diately set down and not moved until repairs are made to the j failed lift point.
L (d) Reactor Cavity Seal Ring l
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- f. The seal ring is equipped with twelve (12) 3/4" shoulder eye bolts for lifting purposes which are equi-spaced along the circumference J
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with two bolts provided at each of the six locations. Failure of a single eye bolt is not expected to disturb the static balance or result in a load drop.
(e) Reactor Missile Shield The three lifting lugs are designed with a safety factor of five (5) which is considered to be adequate to provide sufficient safety margin against a load drop.
(f) Stud Tensioner The two stud tensioner lifting eyes have a safety factor of greater than 10.
(g) Equipment Hatch Cover The equipment hatch cover is equipped with four lifting lugs with a safety factor of seven (7). Failure of a single lift point would result in transfer of the load to two points with a reduction in safety factor by 50%. A load drop is, however, not expected to occur.
(h) Removable Pressurizer Enclosure Wall (2 Sections) l An evaluation of the lift point system for the two removable panels of the pressurizer enclosure wall will be provided later when the design of the lifting device is finalized, r
The above evaluation indicates that the polar crane is substantially in compliance with the guidelines of NUREG 0554, although some design fea-tures required by 0554 may not be present. This is further supplemented i
by the fact that the heavy loads anticipated during plant operation phase do not exceed half the hoist design capacities.. The increased safety factors, as a result, will contribute significantly to the over-all reliability of the load handling systems in the Containment. In addition, the periodic inspection and maintenance program to be developed and implemented in accordance with the applicable standards, coupled with a comprehensive operator training program, proper load handling procedures and load path drawings will help assure the safe handling of the loads in this area.
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i REQUEST 2.3-4 "For cranes identified in 2.3-1 above, not categorized according to 2.3-3, demonstrate that the evaluation criteria of NUREG 0612 Section 5.1 are satisfied. Compliance with Criterion IV will be demonstrated in your l . response to Section 2.4 of this report. With respect to Criteria I through
! III provide a discussion of your evaluation of crane operation in the-
! containment and your determination of compliance. This response should include the following information for each crane:
- a. Where-reliance is placed on the installation and use of electrical interlocks or mechanical stops, indicate the circumstances under which these protective devices can be removed or bypassed and the administrative procedures invoked to ensure proper authorization of such action. . Discuss any related or proposed technical speci-
- fication concerning the bypassing of such interlocks.
f b. Where reliance is placed on other site-specific considerations l
(e.g., refueling sequencing) provide present or proposed technical specifications and discuss administrative or physical controls provided to ensure the continued validity of such considerations.
c.- Analyses performed to demonstrate compliance with Criteria I through III should conform with the guidelines of NUREG 0612, Appendix A.
Justify any exception taken to these guidelines, and provide the specific infogmation requested in Attachment 2, 3 or 4, as appropriate for each analysis performed.
I.
RESPONSE TO 2.3-4 The only other crane which is not categorized according to 2.3-3 above, is the radial arm stud tensioner hoist. These three (3) stud tensioner hoists l
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> l of 2 ton capacity each are, however, not evaluated as per this subsection. ,,
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ThesehoistaareexcludedbecEsseofthedallowingreasons: , ,
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, The stud tensioner hoists are used for removal and installation of stud S, tensioners during reaccor vessel head removal and installation. In '
normaloperation',(thesehoistsarenotstoredonthemonoralIsattached s ,
l-to the underside of the head lifting device, and therefore do not pone -
(j any safety hasard.. During1 refueling stiutdowns, the hoists are suspended fromthemonorailsandhandlest[ab'sandstudten'cioners. 's The heaviest , .'
g %
load is the stud tensioner weighing about 2,500 pounds. Since these ,
components are handled only when the head is'still covering the reactor (/ '\' -
. 'i %
vessel, no damage can be caosed to the irradiated fuel or safety related n equipment. Whentheheadisrebovedtoitsstoragelocation,thestud tensionerhoistsarealsoreNyedalongwiththeheadliftintdevice.
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- 7. RESPONSE TO SECTION 2.4 (ENCLOSURE 3)
- Specific Requirements for Overhead Handling Systems Operating in Plant Areas Containing Equipment Required for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling l "NUREC 0612, Section 5.1.5, provides guidelines concerning the design and operation of load-handling systems in the vicinity of equipment or components required for safe reactor shutdown and decay heat removal.
Information provided in response to this section should be sufficient
, to demonstrats that adequate measures have been taken to ensure that in these areas, either the likelihood of a load drop which might prevent safe reactor shutdown or prohibit continued decay heat removal is extremely small, or that damage to such equipment from load drops will be limited in order not to result in the loss of these safety related functions. Cranes which must be evaluated in this section have been previously identified in your response to 2.1-1, and their loads in your response to 2.1-3-C".
(
4
- . c E
C, ,j '
1.
i i T
- _ _ . - _ _ . . _ . _ , , . , _ - - _ . _ , . . ~ . - _ _ , _ . . . _ . . _ , .. .
. - - _ _ - _ . - . - _ _ = - _ ._ . . - . - . - . _ . _ _ . - = _ ..-
REQUEST 2.4-1
" Identify any cranes listed in 2.1-1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features). For each crane so evaluated, provide the load-handling system (i.e., crane-load-combination) information specified in Attachment 1."
RESPONSE TO 2.4-1 The polar gantry crane has sufficient design features to make the likelihood of a load drop extremely small. A detailed evaluation of the design, fabri-cation, installation, inspection, etc. of the polar crane appears in our response to Section 2.3. The cask handling crane and the stud tensioner hoists have been excluded for reasons given in the preceding sections. A comprehensive hazard evaluation of the remainder of the cranes listed in 2.1-1 is provided in this section.
REQUEST 2.4-2 "For any cranes identified in 2.1-1 not designated as single-failure proof in 2.4-1, a comprehensive hazard evaluation should be provided which includes the following information:
- s. The presentation in a matrix format of all heavy loads and potential impact areas where damage might occur to safety-related equipment. Heavy loads identification should include designation and weight or cross-reference to information provided in 2.1-3-C.
Impact areas should be identified by construction zones and elevations or by some other method such that the impact area can be located on the plant general arrangement drawings. Figure 1 provides a typical matrix."
RESPONSE TO 2.4-2-a The load / impact area matrices showing loads that will be handled by the crane or monorail-hoist and the potential impact areas are included in Table 2.4.2-1, Sheets 1 through 10.
._ - - =- ._. . .- _ . . - -- . - . - . _ - - - . = - --
REQUEST 2.4-2-b "For each interaction identified, indicate which of the load and impact area combinations can be eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical' interlocks, or other site-specific considerations. Elimination on the basis of the afore-i mentioned considerations should be supplemented by the following specific information:
(1) For load / target combinations eliminated because of separation and redundancy of safety-related equipment, discuss the basis for determining that load drops will not affect continued system operation (i.e., the ability of the system to perform its safety-related function).
(2) Where mechanical stops or electrical interlocks are to be provided, present details showing the areas where crane travel will be prohibited. Additionally, provide a discussion concerning q the procedures that are to be used for authorizing the bypassing of interlocks or removable stops, for verifying that interlocks are functional prior to crane use, and for verifying that interlocks are restored to operability after operations which require bypassing have been completed.
(3) Where load / target combinations are eliminated on the basis of l other, site-specific considerations (e.g., maintenance sequenc-l ing), provide present and/or proposed technical specifications and f discuss administrative procedures or physical constraints invoked
( to ensure the continued validity of such considerations."
e - v - - - ~ , . , . --, . - - - , , , a-, n , , - - --.---ven- - , , - , - - . . -- - ,, - - .--- -, . - - . - -- - ,- -
l RESPONSE TO 2.4-2-b All load tnd impact area combinations for the following cranes have been eliminated because of separation and redundancy of safety-related equipment and other site specific considerations such as maintenance sequencing.
j (i) Charging Pump Service Monorail Hoists (CS-CR-14A, -14B and -14C)
Three service hoists, each located in a separate room, are provided for maintenance of the charging pumps. A load drop can damage only a single pump which has already been taken out of service for repair or maintenance. Since normal plant shutdown can be accomplished with any one of the three charging pumps, a load drop in the event of a handling system failure cannot prevent the chemical and volume control system from performing its safety-related functions.
(ii) Radioactive Pipe Tunnel Service Monorail Hoists (CBS-CR-18A and ISB)
A separate monorail-hoist is provided to service the sump isolation valve and associated encapsulation vessel in each of the two indepen-dent and fully redundant trains of the containment spray system.
The two trains and monorail-hoists are separated by a 24-inch thick reinforced concrete wall. In the unlikely event of a load drop in one area, the re'dundant system would remain functional. Therefore, t .a load drop will not result in the loss of safety functions of the L containment' spray system.
(iii) Main Steam and Feedwater Pipe Chase Cranes (MS-CR-25A and 25B)
I These cranes, 25A located in West Chase and 25B in East Chase,
- service the main steam and feedwater containment isolation valves
l l
l and~are used only after the reactor coolant system has been cooled down, with the residual heat removal system removing decay heat.
Therefore, any potential damage to the main steam and feedwater systems resulting from a load drop cannot affect the decay heat removal process.
(iv) Diesel Generator Service Cranes (DG-CR-28A and 28B)
The two redundant diesel generator units and their associated auxiliaries are located in separate and independent enclosures within a seismic Category I building. One service crane is provided in each enclosure for repair and maintenance of the
, diesel generator. Since only one diesel generator will be removed from service at any one time, a load drop could result in damage to only this one unit and/or its auxiliary systems. The redundancy of the other generator will allow for plant operations for 7 days, with no loss of safety-related functions. However, as specified in the Seabrook technical specifications, if the damaged unit cannot be restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the plant will be brought to at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The above cranes and monorails will be prevented from being dislodged off the rails in an unloaded condition during a seismic event equal to safe shutdown earthquake.
I i
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, ,,- , . . , ,.--.v..
_, c.,_. .~. - .. - - . - ~ _ . , , , . - _ . . . . - . , _ _ . _ _ _ . . _ - - , - . _ . . _ , , . _,_
l l
i REQUEST 2.4-2-C "For interactions not eliminated by the analysis of 2.4-2-b, above, identify any handling systems for specific loads which you have evaluated as having sufficient design features to mak'e the likelihood of a load drop extremely small and the basis for this evaluation (i.e., complete compliance with i
NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features). For each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment 1."
RESPONSE TO 2.4-2-C The boric acid batching monorail, the emergency feed pump monorail, CVCS heat exchanger service monorail, filter cask monorail and the component cooling water pump service monorails are considered to have sufficient design features to make the likelihood of a load drop extremely small for all load-impact area combinations. The basis selected for this evaluation is essential compliance with Section 5.1.6, NUREG 0612, including increased
- design safety factors. A detailed discussion of these five monorails l follows.
r BORIC ACID BATCHING MONORAIL HOIST (CS-CR-6)
The boric acid batching monorail system is designed for a capacity of 4.5 tons. The normal loads anticipated for this hoist such as pallets of boric acid will be limited to 50 percent of the hoist capacity. That is, the monorail will be derated to 2.25 ton capacity. In addition, the standard
! lifting apparatus will have a safety factor of 10 or greater, or will be of l
-redundant design.
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- . _ . ._s. . .. -.,, - _ - _ _ . _ , _ _ . . - , , _ _ . . . _ _ . . . . . - _ - . , . _ _ , - - - . - -
EMERGENCY FEED PUMP MONORAIL HOIST (FW-CR-27)
This is a 5 ton monorail with a hand chain hoist normally used to handle individual pump, turbine or motor components during maintenance or repair of the two emergency feed pumps. All of these loads weigh much less than half the monorail capacity each, thus ensuring twice the required design safety j- factors as per applicable design standards.
The pump motor (4800 pounds) or turbine (3900 pounds) if handled as a complete unit also weigh lesa than half the hoist capacity. The only load heavier than 5000 pounds will be the pump unit which weighs 5700 pounds.
However, the feed pump will be first disassembled and only individual pump parts such as casing, rotor etc. will be handled by the hoist. Considering these increased safety factore for the individual loads together with a safety factor of 10 or greater for the standard lifting devices, the likeli-hood of a load drop will be extremely small. (The monorail has been upgraded from a 4 ton to 5 ton capacity).
CVCS HEAT EXCHANGER SERVICE MONORAIL (CS-CR-13)
The rated capacity of the heat exchanger service monorail has been increased from 3 tons to 5 tons. All the loads to be handled by this monorail weigh l 1ess than half the hoist capacity. Therefore, available design safety fac-l tors for he monorail track and the hand chain powered hoist are increased to twice the values required by the applicable design standards. In addition, the standard lifting devices such as slings and associated fittings will be l selected for each load to provide a minimum design safety factor of 10, or l
! will be of redundant-design.
As a result, the reliability of the load handling system will be enhanced through increased safety factors; and consequently the likelihood of a load I
i drop during load handling operations is considered to be extremely small.
i i
l
. FILTER CASK MONORAIL (CS-CR-5) 4 The rated capacity of the filter cask monorail has been increased from 4.5 tons to 7.5 tons. The new capacity is designed to provide increased safety
- margins for all loads, thereby contributing substantially to the overall reliability of this load handling system. The rated capacity of the mono-rail is such that the weight of the heaviest load, the filter cask, does not exceed half the hoist capacity, thus providing twice the required design safety factors.
In addition, the hoist is equipped with safety control devices such as two independent upper limit switches of different design, a lower limit switch, and an inching drive capability. Also, the lifting devices will maintain a safety factor of 10 or greater, or will be of redundant design.
COMPONENT COOLING WATER PUMP SERVICE MONORAILS (CC-CR-15A and ISB) 4 These monorails have also been upgraded from an initial capacity of three (3) tons to'five (5) tons to provide increased safety margins. The hoists are of the hand chain powered type, and are used during maintenance of the
, primary component cooling water pumps in the two loops. The monorail capacity
( and weights of the various loads such as the pumps, pump motors etc. are such that safety factors of approximately two times the required values will
! be assured during handling of these loads. The standard lifting apparatus will also provide a minimum safety factor of 10, or will be of dual or redundant design, r
l The design of the above five monorails will prevent the hoists from leaving the tracks in an unloaded condition during a seismic event equal to safe
( shutdown earthquake (SSE). The monorails are not designed to retain the lifted load during an SSE. However, occurrence of a seismic event at the same time when the hoist is in use and supporting a load is considered to be a low probability event.
L i
. - . , - . _ _ _ , , _ - - . - _ - - - . - _ . , ...#.. ., . . . . ~ _ _ , - - - -__ - , - _ _ - _ _ _ . _ _ _ _
REQUEST 2.4-2-d For interactions not eliminated in 2.4-2-b or 2.4-2-c, above, demonstrate using appropriate analysis that damage would not preclude operation of sufficient equipment to allow the system to perform its safety function following a load drop (NUREG 0612, Section 5.1, Criterion IV). For each l analysis so conducted, the following information should be provided:
(1) An indication of whether or not, for the specific load being investigated, the overhead crane-handling system is designed and constructed such that the hoisting system will retain its load in the event of seismic accelerations equivalent to those of a safe shutdown earthquake (SSE).
(2) The basis for any exceptions taken to the analytical guidelines of NUREG 0612, Appendix A.
(3) The information requested in Attachment 4.
L RESPONSE TO 2.4-2-d I
( No load and impact area interactions fall in this category.
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t I
TABLE M.I.1(C)-1 (Sheet 1 of 5)
SEABROOK STATION - UNITS I & 2 TABULATION OF HEAVY LOADS i
LOAD RANDLING WEICHT LOAD PATH PROCEDURE REFERENCE 14AD IDENTIFICATION (Ibs) LIFTINC DEVICE DRAWING SPECIFIC / GENERAL DRAWING CRANE / MONORAIL - HOIST CONTAINMENT Polar Cantry Crane MM-CR-3 420 Ton Main 50 Ton Auxiliary Neutron Shield Panel (8) 10,000 each Main / Aux. Hook & 805284 Ceneral 815542 Whiting Corporation Slings (See Note 2)
Reactor Cavity Seal Ring- 18,625 Main / Aux. Hook & 805273 Specific 805556 Slings (See Note 1)
Reactor Missile Shield 40,000 Main Hook and 805282 Specific 101933 and Support (plus CRDM (with spreader Spreader Assembly cooling fans) assembly)
CRDM Cooling Air Duct See Note 3 Auxiliary Hook and 805276 General 609605 and Supports Slings 609608 Heaviest Section 609609 Reactor Vessel Head 336,218 (with Main Hook, RV Head 805275 S pecific F.P. #50234 and Attachments lifting rig) Lifting Rig, Load F.P. #50246 Cell, and Linkage Assembly Internals Lif ting Rig 18,350 Main Hook, Load Cell 805272 Specific F.P. #53998 and Linkage Assembly Upper Internals 152,000 (with Main Hook, Internals 805272 S pecific F.P. #50209 lifting rig) Lifting Rig, Load Cell and Linkage Assembly Lower Internals 340,000 (with Main Hook, Internals Not Required Specific /Ceneral lifting rig) Lifting Rig, Load Cell and Linksga Assembly 1
Jib Crane (including 3,000 Auxiliary Hook and 805272 General F.P. #54824 hoist and trolley) Slings t
Stud Tensioners 2,500 Aux. Hook & Slings 805283 Ceneral F.P. #50215 i
TABLE 2.1.3(C)-1 (Sheit 2 af 5)
SEABRO0E STATION - UNITS 1 & 2 TABULATION OF HEAVY LOADS LOAD HANDLINC WEIGHT LOAD PATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (Ibs) LIPTINC DEVICE DRAWING SPECIPIC/CENERAL DRAWINC R.V. Head Stud, Nut and 700 Aux. Hook & Slings 805274 Ceneral Washer Assembly RC Punp Motor 100,260 Main Hook & Motor 805277 S pecific F.P. #50218 Lifting Device RC Pump Motor Supoort 9,300 Main / Aux. Hook & 805277 Ceneral F.P. #50218 Slings RC Pump Internals 44,900 Main Hook & Slings 805277 Specific F.P. #50218 RC Pump Assembly 94,400 Main Book & Slings 805277 S pecific F.P. #50218 (including casing)
RC Pump Removable Con- 37,000 Main Hook & Slings 805277 Specific /Ceneral 101445 crete Pluss (2 sections) (Heaviest)
RC Pump Handling Frame 10,000 f.ux. Hook & Slings 805277 Ceneral 1868 E 98 Plug for In-Core 10,000 Aux. Hook & Slings Not Required Detector Drive 420 Ton Hoist Load Block 30,000 N/A N/A -
F.P. f52461 50 Ton Hoist Load Block 2,000 N/A N/A -
F.P. #52462 Miscellaneous Equipment Aux. Hook & Slings 805275 Ceneral -
in Containment Annulus Area Pressurizer Missile 4,000 Aux. Hook & Slings 805276 Ceneral/ Specific 101939 Shield (3 Sections) i Heaviest Section 5quipment Hatch Cover 35,150 Aux. Hook, Hatch 805273 Specific /Ceneral F.P. #10552 (including airlock) Cover Handling Boom F.P. #10556 (Part of Polar Crane) and Hatch Cover Handling Device Pressuriser Enclosure 85,000 each Main Hook and Pres- 805276 Ceneral 101939 Wall - Two Removable suriser Enclosure Panels Wall Handling Device
l TABLE 2.1.3(C)-I (Sheet 3 of ST
- SEABROOK STATION - UNITS 1 & 2 TABULATION OF HEAVY LOADS LOAD HANDLING WEIGHT LOAD FATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (Ibs) LIFTING DEVICE DRAWING SPECIFIC /CENERAL DRAWING Ladial Arm Stud Tensioner Stud Tensioner 2,500 Slings 805283 Ceneral F.F. #50215 Hoists (3) RV Head Stud, Nut 700 Spring Scale 805274. General i 2 Ton capacity each and Washer Assembly 4
, Guide Stude 650 Spring Scale Not Required General FUEL STORACE BUILDING
]
Spent Fuel Cask Spent Fuel Cask (Cask design not yet finalised) 805279 Specific j Handling Crane !
l FH-RE-1 New Fuel Shipping 6,700 Main / Aux. Nook #2 805279 Specific /Ceneral 125 Ton Main Container and Four-Leg Sling
! 5 Ton Aux. (2) Assembly Whiting Corporation New Fuel Assembly 1,700 (with Auxiliary Hook fl 805279 Specific /Ceneral FIG. 4.2-2 handling tool) and New Fuel (FSAR) 1 Assembly Handling
. Tool crane Load Block 5,900 N/A N/A -
F.F. 55593 (125 Ton)
I Irradiated Specimen (Design not yet finalised) i Cask ..
Failed Fuel Container (Design not yet finalis ed)
FRIMARY AUKILIART BUILDING
- Filter Cask Filter Cask (CVCS (Cask design not yet finalised) 905280 Ceneral F.F. #
Monorail Hoist. system)
, CS-CR-5 4
7.5 Ton Capacity Concrete Floor Flug 3,000 Slings 805280 General 805869 Boric Acid Hatch Cover (2 sections)- 1,300 each Slings 805281 Ceneral 101598 Batching Monorail
! Hoist CS-CR-6 Fallets of Boric Acid Less than Slings 805281 Ceneral -
j 4.5 Ton capacity 4,500 lbs.
(Derated Capacity j - 2.25T)
TABLE 2.1.1(C)-I (Sheet 4 cf 5)
SEABROOK STATION - UNITS I & 2 TABULATION OF HEAVY LOADS LOAD HANDLINC WElGHT LOAD PATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (1bs) LIFTING DEVICE DRAWINC SPECIFIC /CENERAL DRAWINC CVCS Heat Removable Concrete Floor 5,000 each. Slings 805280 General 101528 Exchanger Service Plus (2 sectiocs)
Nonorail Holst CS-CR-13 Heat Exchanger Tube 2,150 Slings 805280 General F.P. #50163 5 Ton Capacity Bundle (Heaviest)
(Unit #1 only)
Charging Pump Charging Pump Slings See Note 4 Ceneral F.P. f50153 Service Monorail Components Hoist CS-CR- 14A,148 & 14C Charging Pump Motor 4,905 Slings See Note 4 Ceneral F.P. #50153 2.5/2.5/6.0 Ton Capacity Gear 2,700 Slings See Note 4 Ceneral F.P. #50153 Component Cooling Primary Component Cooling 3,600 Slings 805280 Ceneral F.P. #50626 Water Pump Water Pump l Service Monorail Hoist PCCW Pump Motor 5,270 Slings 805280 Ceneral F.P. #50626 CC-CR-15A & 155 F.P. #51153
- 5 Ton capacity each EMERCENCY FEEDWATER PUMP BUILDING Emergency Feed Emergency Feedwater 5,700 Sling. 805278 Ceneral F.P. #22432 Pump Monorail
^
Pump F.P. #22433 Hoist FW-CR-27 Emergency Feedwater 4,800 Slings 805278 ceneral F.P. #22435
. 5 Ton Capacity Pump Motor
}
I Emergency Feedseter 3,900 Slings 805278 Ceneral F.P. #22431
' Pump Turbine
! S'-0" x 4'-6" Removable 4,000 Slings 805278 Ceneral 101660 2ncrete Floor Flug 101664 Diesel Generator Building Diesel Generator Miscellaneous Diesel Slings See Note 4 Ceneral Service Crane Generator Componenta I DG-CR-28A & 288 8 Ton Capacity each Turbocharger (Heaviest 2,160 Slings See Note 4 Ceneral anticipated lift) i
TABLE 2.1.3(C)-1
~{Sheat 5 af 5)
SEABROOK STATION - UNITS I & 2 TABULATION OF HEAVY LOADS LOAD HANDLINC WEICHT LOAD PATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (Ibs) LIFTINC DEVICE DRAWING SPECIFIC /CENERAL DRAWING MAIN STEAM AND FEEDWATER PIPE CHASE Main Steam and MS isolation Valve Assembly 14.065 Slings See Note 5 Ceneral F.P. #23003 Feedwater Pipe A-260 Actuator 3,327 Slings See Note 5 General F.P. #23003 Chase Crane Limitorque Operator 225 Slings See Note 5 Ceneral F.P. #23003 MS-CR-25A & 255 FW Isolation Valve 5,241 Slings See Note 5 Ceneral F.P. #20915 7.5 Tan Capacity each Assembly FW Isolation Valve 4,369 Slings See Note 5 Ceneral F.P. #20915 FW Isolation Valve 672 Slings See Note 5 Ceneral F.P. #20915 Operator RADIOACTIVE PIPE TUNNEL Radioactive Pipe Encapsulation Vessel 1,000 Holst Hook See Note 4 Ceneral F.P. #53343 Tunnel Service Head Monorail Hoist CBS-CR-18A & 185 Encapsulation vessel 1,200 Hoist Hook and Two- See Note 4 General F.P. f53343 2 Ton capacity each Skirt Leg Sling Assembly Sump Isolation Valve Less than Slings See Note 4 Ceneral F.P. #90911 Topworks (16" CBS- 2,500 lbs.
V8 and V14)
NOTES:
- 1. Specific Procedure A specific procedure governs critical load handling operations requiring unique procedures, and provides detailed instructions for the movement and handling of such loads, or performance of complex tasks requiring greater detail to ensure safe handling of loads.
- 2. General Procedure: A general procedure governs all crane and load handling operations not requiring a specific procedure, and .sy serve as a reference document for specific procedures.
- 3. The design of the ductwork/ supports for the CRDM has not been finalized. The weights of these components will be added at a later date.
- 4. Load path is confined to the monorail track within a compartment that is separated by concrete walls from the adjoining compartment /s containing redundant equipment and associated monorails.
- 5. Load path is the entire area of crane travel within the two rails. The load is handled only when the plant is in cold shutdown with the residual heat removal system in operation.
TABLE 2.4.2-1 (Sheet 1 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2 CRANE: FILTER CASK MONORAIL HOIST (CS-CR-5) 7.5 Ton capacity LOCATION BUILDING : PRIMARY AUXILIARY BUILDING IMPACT Zone: Column Line 3-5 AREA Column Line A-B Elev. 25'-0" ,
Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Filter Cask (7000 lbs)** Floor Elev. 25' Seal Water Heat Ex- D R movable Floor Plugs -0" (Monorail changer, Seal Water (3000 lbs each) Elev. 40'-6") Injection Filter, Seal Water Return Filter, Reactor Coolant Filter Demineralizer Pre-f filter, all located j
in individual com-l partments below 3' thick reinforced concrete slab.
CVCS piping and
! valves below 25' elevation. (Valve l operators i.e.
extensions for some drain valves and isolating valves for the above equipment are above 25' elev.)
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f *See Sheet 10 of 10
- Weight to be confirmed s l
L
TABLE 2.4.2-1 (Sheet 2 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX dEAVY LOADS
- NUREG 0612 SEABROOK STATION UNITS 1 & 2 4
CRANE: BORIC ACID BATCHING MONORAIL HOIST (CS-CR-6) 4.5 Ton Capacity **
LOCATION BUILDING : PRIMARY AUXILIARY BUILDING IMPACT Zone: Column Line 5-6 AREA Column Line B-D Elev. 53'-0" Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Hatch Cover in 2 sections Floor Elev. Boric acid tank D (1300 lbs each) 53'-0" CS-TK-4B located (Monorail elev. at floor elev.
67'-0") 25'-0", below boric acid batching tank.
Pellets of boric acid (Lecd in one lift will not exceed 4500 lbs) l I
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I *Sze Sheet 10 of 10
- Darated capacity - 2.25 T i
l I
J TABLE 2.4.2-1
- (Sheet 3 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREC 0612 SEABROOK STATION UNITS 1 & 2 r
l CRANE: CVCS HEAT EXCHANGER SERVICE MONORAIL HOIST (CS-CR-13) 5 Ton capacity i
LOCATION BUILDING : PRIMARY AUXILIARY BUILDING 1
IMPACT Zone: Column Line 2-4
.,. AREA Column Line A-B Elev. 25'-0"
- Hazard
-Safety Related Elimination LOADS Elevation Equipment Category
- Cencrete Floor Plug in Floor Elev. 25' Letdown Heat Ex- D j 2 sections (5000 lbs each) -0" (Monorail changer, Letdown
- Elev. 45'-6") Reheat HK, Letdown Chiller HK, Moderating
, HX , all located in individual compart-
}. ments below 3' thick l reinforced concrete slab. CVCS Piping and Valves located below 25' elev. '
(Valve operators i.e., extensions for l
isolating valves for l above equipment are I
located above 25'-0" elevation) l Host Exchanger Tube same as above same as above D Bundle (2150 lbs -
l 'Hecviest Tube Bundle) i l
r l
- See Sheet 10 of 10 ,
_....-v___ _ . . _ _ ,_ _ ,,_.______.__.___,__.,....,_.____,,.._...,__,,_.m. _
TABLE 2.4.2-1 .
(Sheet 4 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2 CRANE: CHARGING PUMP SERVICE MONORAIL HOISTS, (CS-CR-14A, 148, & 14C) 2.5/2.5/6.0 Ton capacity LOCATION BUILDING : PRIMARY AUXILIARY BUILDING IMPACT Zone: Column Line 3-5 AREA Column Line C-D Elev. 7'-0" Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Ch rging Pump Components Floor Elev. Charging Pump, B Charging Pump Motor 7'-0" (Rail Associated CVCS Gacr Elev. 18'-7") Piping i
CSee Sheet 10 of 10
TABLE 2.4.2-1 (Sheet 5 of 10)
CONTROL OF. LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREC 0612 SEABROOK STATION UNITS 1 & 2 CRANE: COMPONENT COOLING WATER PUMP SERVICE MONORAIL HOISTS (CC-CR-15A & 15B) l' 5 Ton Capacity
(
LOCATION BUILDING : PRIMARY' AUXILIARY BUILDING IMPACT Zone: Column Line 2-4 AREA Column Line A-C 3
Elev. 25'-0"
) Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Primary Component Cooling Floor El. 25'-0" PCCW Pumps and PCCW D Wcter Pump (3600 lbs) (Monorail El. System Piping. CVCS 35'-0") Piping and Valves below 2 to 4' thick
- PCCW Pump Motor (5270 lbs) reinforced concrete slab (El. 25'-0").
Valve operators i.e.,
extensions located above 25'-0" elev.,
for isolating valves for:
- Letdown Reheat HX
( - Letdown Chiller HX l - Letdown Flow Con-I trol Valve PCV 131
- Seal Water Return Filter
- Regenerative l Demineralizer r - Seal Water Inject-tion Filters (drain valves)
- Cation Bed Demineralizers
- 3" line from Moderating HX to RC Filter
- 3" line from RC Filter to RHR Pump
- See Sheet 10 of 10
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l TABLE 2.4.2-1 (Sheet 6 of 10) !
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2
( CRANE: RADI0 ACTIVE PIPE TUNNEL SERVICE MONORAIL HOISTS (CBS-CR-18A & 185) 2 Ton Capacity LOCATION BUILDING : RADIOACTIVE PIPE TUNNEL IMPACT Zone: Piping Zone 28A AREA Pipe Tunnel Elev. (-) 34'-6" Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Encapsulation Vessel EL. (-) 34'-6" valves 16" CBS-V8, B Hsad (1000 lbs) V14 & Piping Encapsulation Vessel EL. (-) 34'-6" Valves 16" CBS-V8, B Skirt (1200 lbs) V14 & Piping
! Sump Isolation Valve EL. (-) 34'-6" Valves 16" CBS-V8, B Tcpworks (Less than V14 & Piping 2500 lbs) t F
l l
CSee Sheet 10 of 10 l
- - - ~ . - - . , . - _ , _ _
TABLE 2.4.2-1 (Sheet 7 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2 i
l CRANE: MAIN STEAM AND FEEDWATER PIPE CHASE CRANES (MS-CR-25A & 25B) 7.5 Ton Capacity LOCATION BUILDING : MS AND FW PIPE CHASE IMPACT Zone: East Chase Floor Elev. 3'-0" AREA West Chase Floor Elev. 3'-0" Hazard Safety Related Elimination LOADS Elevation Equipment Category
- MS Isolation Valve EL. 20'-0" Safety Valve and C Assembly main steam and feedwater piping MS Isolation Valve EL. 20'-0" Safety Valve and C Actuator (A-260), main steam and Limitorque Operator feedwater piping FW Isolation Valve EL. 20'-0" Safety Valve and C Assembly main steam and FW Isolation Valve feedwater piping FW Isolation Valve EL. 20'-0" Safety Valve and C Operator main steam and feedwater piping l
- See Sheet 10 of 10
.. . _ . . . . . . - - -_ = . _ . .
. TABLE 2.4.2-1
, (Sheet 8 of 10)
CONTROL OF~ LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2 i
i .
5 Ton Capacity
^
CRANE: EMERGENCY FEED PUMP MONORAIL HOIST (FW-CR-27)
LOCATION BUILDING : EMERGENCY FEEDWATER PUMP BUILDING r IMPACT Zone: Area around monorail in entire building AREA Elev. 27'-0" i Hazard Safety Related Elimination LOADS Elevation Equipment Category
D Parts turbine, pump, motor and feed-water piping.
Emergency FW Pump Motor Floor El. 27'-0" Emergency FW D (4800 lbs) turbine, pump, and feedwater
- piping. ,
i-Emergency FW Pump Turbine Floor El. 27'-0" Emergency FW pump, D
, (3900 lbs) motor, and feed-water piping.
}
i
- Concrete Floor Plug Floor El. 27'-0" Emergency FW pump, D
-(4000 lbs) motor, turbine, and i feedwater piping.
L i
i
- See Sheet 10 of 10
?
. .- _ . . _ , . . . - _ . . _ , , . . . - - - - ~ - . . - _ . - . . - - . - . - - _ . - . ._____ _ .. .- -.._.---- . , . , . . . . _ . . , . - . - - . _ .
TABLE 2.4.2-1 (Sheet 9 of 10)
CONTROL OF LOAD / IMPACT AREA MATRIX HEAVY LOADS NUREG 0612 SEABROOK STATION UNITS 1 & 2 CRANE: DIESEL GENERATOR SERVICE CRANES, (DG-CR-28A & 28B) 8 Ton Capacity LOCATION BUILDING : DIESEL GENERATOR BUILDING IMPACT Zone: Column Line 5-9 AREA Column Line A-E Elev. 21'-6" Hazard Safety Related Elimination LOADS Elevation Equipment Category
- Diesel Generator Parts EL. 21'-6" Diesel Generator, B cnd Assemblies Diesel Auxiliary Systems i
l l
- See Sheet 10 of 10 I
TABLE 2.4.2-1 (Sheet 10 of 10)
LOAD / IMPACT AREA MATRIX SEABROOK STATION UNITS 1 & 2 Hazard Elimination Categories f
A. Crane travel for this area / load combination prohibited by electrical interlocks or mechanical stops, i
B. System redundancy and separation precludes loss of capability of system to perform its safety-related function following this load drop in this area.
C.- Site-specific considerations eliminate the need to consider load / equipment combination.
D. Likelihood of handling system failure for this load is. extremely small (i.e. section 5.1.6 NUREG 0612 satisfied).
E. Analysis demonstrates that crane failure and load drop will not damage safety-related equipment.
4
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. . _- -_ -. . .__ _ _ ~
APPENDIX I ANALYSIS OF RV HEAD LIFTING RIG AND INTERNALS LIFTING RIG-(SPECIAL LIFTING DEVICES) 1.0 Reactor Vessel Head and Internals Lift Riga, Load Cell and Load Cell Linkage 1.1 General An evaluation of the reactor vessel head and internals lift rigs, load cell and load cell linkage was performed by Westinghouse to determine the acceptability of these devices to meet the requirements of NUREG-0612 and ANSI N14.6-1978. The conclusions of this evaluation are summarized in this Appendix. These special lifting devices, for the most part, were manufactured under Westinghouse surveillance with identified hold points, procedure review and personnel qualification.
1.2 Comparison with ANSI N14.6 Requirements ANSI N14.6-1978 contains requirements for the design, fabrication, test-I ing, maintenance and quality assurance of special lifting devices. A detailed comparison of these requirements with those used in the design, manufacture, inspection and testing of RV head and internals lift rigs was made, and a stress report was prepared in accordance with ANSI N14.6.
Also, a critical items list which identifies the critical load path parts and welds, the material of these items and the non-destructive examination performed was compiled.
l l
i This comparison shows that these special lifting devices meet the intent of ANSI N14.6 for design, fabrication and quality control. The RV head and internals lift rigs and load cell were proof tested upon completion with a load of approximately 125 percent of the design weight instead I-l l _ _ . . _ _ - _ . _ .- _ _ _ _ _ - . _ . _ _ _ _ _ . . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . . _ . . - _ _ . _
of 150 percent of the rated load. Following the load test, all parts, particularly welds were visually inspected for cracks or obvious deformation and critical welds were magnetic particle examined. A 125 percent load test conducted in accordance with the requirements established j at the time of fabrication, in lieu of 150 percent load test, is considered
( to be adequate to demonstrate the integrity of these devices.
i Tests and inspections to verify continuing compliance of these devices 1
are discussed in Section 4 of the main report. A 150 percent load test or annual non-destructive tests and examinations required by ANSI N14.6 are not practical to perform annually or prior to each use. A 100 per-cent load test, visual check and non-destructive examination will be performed as follows to verify continued compliance:
(a) Reactor Vessel Head Lift Rig After reassembly of the spreader assembly, lifting lug and upper lifting legs to the upper portion of the lift rig, all load bearing welds will be vis,ually checked. The vessel head will then be slightly l raised above its support and held for 10 minutes. At this time l visual inspection of the sling block lugs to the lifting block I
welds and spreader lug to spreader arm welds will be performed.
If no indications are detected the lift will proceed. Simultaneously, the load cell readout will be constantly monitored throughout the duration of the lift.
I (b). Reactor Vessel Internals Lift Rig l
l Similarly, visual inspection of all load bearing welds will be conducted. All critical bolted connections will be checked to insure adequate engagement. After connection to the upper or lower internals, the assembly will then be slightly raised above its support and held for 10 minutes. At this time, visual inspection t
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of the sling black lugs to the lifting block welds will be performed.
If no, indications are detected, the lift will proceed with constant monitoring of the load cell readout until completion of the lift.
l (c) Non-Destructive Examinetion of RV Head and Internals Lift Rigs and l
e ,, -
Load Chil Linkage h..
s .
. 3 In addition <ro,the 100% load te'ste-using the actual loads and the
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, . y } co,n, current visual inspection.of cri.cical, w, elds and components, s
~ ' iperiodic non-desteractive surface ex'asinations for these items will
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/'betperformed to insure continued adequacy.
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Mair.titiance and inspection procedures will addreas Section 5.1.3 N
through'5.1.8 of ANSI N14.6 (Owner's Responsibilities) in conjunction with Westinghouse recoussendations. These sectio'ns include require-I N.,' s-saents for scheduled periodic testing, spedial. identification and mark.ing, astntenance, repair, testing and use'.
s 't x .
'\ ,e j- 1.3 y. Stress Report , _s . '
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- A stre'ss' report was' prept. red for RV head lif t rig, internals lift rig,
,; ' load cell'and load cell linkage in accordance with the criteria of l > ANSI N14.6. The design criteria of Section 352. were used for evaluating '
i ,
l- load bearin.g members when subjected to loading conditions resulting in 3, shear or t' ensile stressas. The resulting stres ec are within acceptable *
, N w stress limits.
.-t s')
Application of these design load factors to other loading conditions is' notaddressedinAkSIN14.6.. However, these stress design factors have been used to determine the str' esses in the load bearing dembers when .
[. subject to other loading conditions, viz. bearing and bending. Thi.s is j an extre:nely conservative approach, and in some instances the resulting
' i , .
stresses are not in strict, compliance with the design criteria. These
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! are, however, localized stresses and can be considered under Section
! 3.2.1.2 which states that the stress design factors of 3.2.1.1 are not intended to apply to situations where high local stresses are relieved by slight yielding.- None of the bearing or bending or combined stresses l reach the yield stress, and in fact, all of these stresses meet the l
l design criteria of AISC Code.
f
! In conclusion, these special'1ift devices meet the ANSI N14.6 criteria for tensile and shear stresses and meet other appropriate criteria for loading conditions that result in combined and bearing stresses.
1.4 Conclusions t
(a) The ANSI N14.6 requirements for design, fabrication and quality
, assurance are generally in agreement with those used for these special lift devices.
(b) The ANSI N14.6 criteria for stress limits associated with certain stress design factors for tensile and shear stresses are adequately satisfied.
I j (c) The application-of the ANSI N14.6 criteria for stress design factors l are only for shear and tensile loading conditions. Other loading l
conditions are to be analyzed to other appropriate criteria, and these criteria are satisfied.
l (d) These devices are not in strict compliance only with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance. Alternate equivalent and/or adequate tests and inspection program, as permitted by NUREG 0612, will be L implemented that should enable these devices to be considered in
, 3
' compliance with the intent of ANSI N14.6.
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.L ._ . _ _ , _ _ _ . . - - . _ . . - - , ..,- _ _ _ - - . . . . _ _ _ . . - ~
a In conclusion, the reactor vessel head and internals lift rigs, load cell and load cell linkage meet the intent of NUREG-0612 and ANSI N14.6-1978 for design, fabrication, inspection, assembly and operation. Initial acceptance tests and proposed tests and inspections to verify continuing compliance are considered to be adequate to satisfy the intent of NUREG-0612.
2.0 Interfacing Lift Points for RV Head and Upper Internals 2.1 Interfacing Lift Points for Reactor Vessel Head TLo lift point system for the reactor vessel closure head consists of three lugs spread 1200 apart on the outside surface of the closure head.
The lugs are attached to the head by full penetration welds, and are designed with the following safety factors:
Design Safety Facter Type of Loading Based Upon Ultimate Strength (a) Based upon combined 6.5 stress (b) Based upon shear 8.9 stress (c) Based upon bearing stress 3.6
! Note: The above safety factors are based upon 80 kai ultimate strength for the lug materials, SA-533 GR. B (Class 1). Ultimate strength for SA-533 GR. B (Class 1) is given to be 80-100 kai.
2.2 Interfacing Lif t Points for Upper Internals The detailed stress analysis of the internals lift rig including rotolock studs has been performed using weight of the lower internals.
The upper internals weigh less than one-half of the lower internals.
The design safety factors for the rotolock studs based upon ultimate strength of the material and the weight of the upper internals are in i excess of 10, for all loading conditions resulting in tensile stress, combined shear stress or bearing stress.
L i
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ATTACHMENT A (Sheet 1 of 2)
NUREG 612: COFDUIT & CABLE TRAY REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRANINGS REMARKS
- 1. MM-CR-3 Polar Gantry Crane CTMT 805052 Not Examined 805053 Excluded by design 805055 805056
- 2. RH-RE-24 Radial Arm Stud CTMT 805054 Not Examined Tensioner Hoists Excluded by design
- 3. RH-RE-1 Spent Fuel Cask Fuel Storage 805058 See Note 1 Handling Crane Bldg. 805059 805084
- 4. CS-CR-5 Filter Cask Mono- PAB 805215 See Note 1 rail Hoist 805062
- 6. CS-CR-6 Boric Acid Batch- PAB 805062 See Note 1 ing Monorail Hoist 805066
- 7. CS-CR-14A Charging Pump PAB 805061 See Note 1
-14B Service Monorail 805065
-14C Hoist i
- 8. CC-CR-15A Component Cooling PAB 805062 See Note 1
-15B Water Pump Service 805064 Monorail Hoist 805066
- 9. CBS-CR-18A Radioactive Pipe Radioactive 805540 See Note 1
-18B Tunnel Service Pipe Tunnel Monorail Hoist (EL-34'-0")
ATTACHMENT A
.(Sheet 2 of 2)
NUREG 612: CONDUIT & CABLE TRAY REVIE9 ITEM EQUIPMENT AREA. REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 10. MS-CR-25A' Main Steam & W MS & W 202063 See Note 2
-25B Pipe Chase Crane Pipe Chase 202064
- 11. W-CR-27 Emergency Feed Emergency 310453 See Note 3 Pump Monorail W Pump Hoist Bldg.
- 12. DG-CR-28A Diesel Generator Diesel Gen. 202068 See Note 1
-28B Service Crane Bldg. 202069 202070 NOTE 1: Safety-related cable trays and/or conduits do not-exist below this crane.
NOTE 2: These cranes are excluded from detailed evaluation because of site. specific considerations.
NOTE 3: The likelihood of a load drop is considered to be extremely small because of increased design safety ;
factors.
i I
i
ATTACHMENT B (Sheet 1 of 2)
NUREG 612: PIPING REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 1. MM-CR-3 Polar Gantry Crane CTMT 805051 805052 Not Examined -
805053 excluded by design i
- 2. FH-RE-24 Radial Arm Stud CTMT 805055 Not Examined -
Tensioner Hoists excluded by design I 3. RH-RE-1 Spent Fuel Cask Fuel Storage Bldg. 805058 No piping *
^
Handling Crane 805059 below this 805084 crane 805088
- 4. CS-CR-5 Filter Cask PAB 805215 No piping below Monorail Hoist this crane
- 6. CS-CR-6 Boric Acid Batching PAB 805066 No other system Monorail Foist 805062 piping in this 805063 area
- 7. CS-CR-14A Charging Pump Service PAB 805213 No piping below
-14B Monorail Hoist 805214 this crane except
-14C suction and dis-charge piping for the individual I pump served.
ATTACHMENT B (Sheet 2 of 2)
NUREG 612: PIPING REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS l
- 8. CC-CR-15A Component Cooling Water PAB 805215 No piping below
-15B Pump Service Monorail 805216 this monorail Hoist 805213 except CC Water
- pump connections and check valves in the discharge lines.
- 9. CBS-CR-18A Radioactive Pipe Radioactive 805540 No other system
-18B Tunnel Service Pipe Tunnel piping below this Monorail Hoist (E1.-34'-0") crane 2
- 10. MS-CR-25A Main Steam & MS & FW 202063 See Note 1
-25B FW Pipe Chase Pipe Chase 202064 Crane
- 11. FW-CR-27 . Emergency Feed Emergency 202296 FW-4613-01-1506-8" Pump Monorail FW Pump Bldg. FW-4610-04-02-3" Hoist
- 12. DG-CR-28A Diesel Generator Diesel Generator 202070 No piping below
-28B Service Crane Bldg. 202068 this crane Note 1: These cranes are excluded from detailed evaluation because of site specific considerations.
l
1 ATTACHMENT C (Sheet 1 of 2)
NUREC 612: SAFETY-RELATED EQUIPMENT REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EOUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 1. MM-CR-3 Polar Cantry Crane CTMT 805054 Steam Generators, 805051. Reactor Coolant 805052 Pumps, Pressurizer 805053 805055 805056
- 2. FH-RE-24 Radial Arm Stud CTMT Not examined -
Tensioner Hoists excluded by design
- 3. FH-RE-1 Spent Fuel Cask Fuel Storage 805058 No safety-related Handling Crane Bldg. 805059 equipment in this.
area
- 4. CS-CR-5 Filter Cask Mono- PAB 805064 CS-E-5 Seal Water rail Hoist 805062 HX, Valve Operators, and piping.
- 5. CS-CR-13 CVCS HX Service PAB 805062 CS-E-5 HX, Valve Monorail Hoist 805011 Operators, CS-E-3 HX, CS-E-4 "'l, CS-E-7 HX, CS-E-8 HX and piping
- 6. CS-CR-6 Boric Acid Batching PAB 805062 CS-TK-4B, Boric Acid Monorail Hoist 805066 Tanks
- 7. CS-CR-14A Charging Pump Service PAB 805061 .See Note 1
-14B Monorail Hoist 805065
-14C
- 8. CC-CR-15A Component Cooling PAB 805062 Valve Operators,
-15B Water Pump Service CC-P-llA, llB, llc Monorail Hoist & llD
ATTACHMENT C
-(Sheet 2 of 2) 4 NUREG 612: SAFETY-RELATED EQUIPMENT REVIEW ITEM EQUIPMENT AREA REFERENCE
- ~
NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 9. CBS-CR-18A Radioactive Radioactive 805540 Motor operated valves
-18B Pipe Tunnel Pipe Tunnel 16" CBS-V14, V8 4 Service Monorail (Elev. - 34'-0")
Hoist
- 10. MS-CR-25A Main Steam MS & FW 202063 See Note 2.
-25B & FW Pipe Chase Pipe, Chase 202064 Crane
- 11. FW-CR-27 Emergency Feed Emergency 202296 FW-V67, V68 Valves, Pump Monorail FW Pump IR-50 Instrumentation
- Hoist Bldg. Rack
- 12. DG-CR-28A Diesel Generator Diesel Generator 202070 Fuel Oil Storage Tank' 4 -28B Service Crane Bldg. 202068 26A & 26B, Valves Air Compressor.
)
NOTE 1: These monorails are not evaluated in detail because of separation and redundancy of the safety related equipment.
NOTE 2: These cranes are excluded from detailed evaluation because of the site' specific considerations.
I 4
l i
i
ATTACHMENT D (Sheet 1 of 2)
NUREG 612: HVAC REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 1. MM-R-3 Polar Gantry Crane CTMT 604128 Not examined -
604129 Excluded by design 604130 604131
- 2. FH-RE-24 Radial Arm Stud CTMT Not examined -
Tensioner Hoists excluded by design
- 3. FH-RE-1 Spent Fuel Cask Fuel Storage 604136 See Note 1 Handling Crane Building 604137 604143
- 4. CS-CR-5 Filter Cask PAB 604110 See Note 1 Monorail Hoist 604111 1
- 5. CS-CR-6 Boric Acid Batching PAB 604109 See Note 1 Monorail Hoist
- 6. CS-CR-13 CVCS Heat Exchanger PAB 604110 See Note 1 Service Monorail 604111 Hoist 604113 i 7. CS-CR-14A Charging' Pump Service PAB 604111 See Note 1
-14B Monorail Hoist
-14C i
- 8. CC-CR-15A Component Cooling PAB " 604110 See Note 1
-15B Water Pump Service 604111 Monorail Hoist 604114 604115 I
i 1
. _ - . _ _ _ _ _ _ - _ ~, _ . . . . ..
ATTACHMENT D (Sheet 2 of 2)
NUREG 612: HVAC REVIEW ITEM EQUIPMENT AREA REFERENCE NO. NUMBER EQUIPMENT NAME CONSIDERED DRAWINGS REMARKS
- 9. CBS-CR-18A Radioactive Pipe Radioactive See Note 1
-18B Tunnel Service Pipe Tunnel Monorail Hoist
- 10. MS-CR-25A Fain Steam & MS & FW Pipe 604165 See Note 1
-25B Feedwater Pipe Chase 604168 Chase Crane 604171
- 12. DG-CR-28A Diesel Generator Diesel Generator 604097 See Note 1
-28B -Service Crane Bldg. 604098 604123-Note 1: No safety-related HVAC equipment or ducts below this crane.
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