ML19352B247
| ML19352B247 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 06/22/1981 |
| From: | CINCINNATI GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19352B246 | List: |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8106290373 | |
| Download: ML19352B247 (16) | |
Text
{{#Wiki_filter:O O DOCKET NO. 50-358 WM. II . ZIMMER NUCLEAR POWER STATION UNIT 1 CONTROL OF IIEAVY LOADS June 22, 1981 O O
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THE CINCINNATI GAS & ELECTRIC COMPANY rM F CINCINNATI.oHto 45204 C. A. DORG M At4 N Stmon vect Passiogw?
' Docket No. 50-358 June 24, 1981 Mr. Ilarold Denton, Director Office of Nuclear Reactor Regulation -
U.S. Nuclear Regulatc.cy Commission Washington, D.C. 20555 RE: WM. H. ZIM11ER NUCLEAR POWER STATION - UNIT 1 - SUPPLEMENTAL INFORMATION IN - RESPONSE TO NRC LETTER OF DECEMBER 22, 1980 REGARDING CONTROL OF HEAVY LOADS
Dear Mr. Denton:
In reply to the NRC letter of December 22, 1980 from Darrell-G. Eisenhut to all licensees of operating plants and applicants for operating licenses and holders of_ construction e permits, there are attached six copies of supplemental S q, information in response to Section 2.1 of Enclosure 3 to the above referenced NRC letter. Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By fk -
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E. A. BORGMANN EAB: dew Enclosure cc: Without Enclosure Charles Bechhoefer George E. Pattison M. Stanley Livingston Andrew B. Dennison Frank F. Hooper Troy B. Conner, Jr. State of Ohio ) James P. "enstormaker County Of ilamilton) ss Steven G. Smith William J. Moran Sworn to and subscribed before J. Robert Newlin William G. Porter, Jr. me this 25A day of June, 1981. James D. Flynn F. T. Daniels p U W. Peter Heile M(u,wA b James H. Feldman, Jr. John D. Ucliver ptaryPublic Mary Reder MARGARET L HUBER David K. Martin Notary Pub!'.c. S:M Cf Cho My Commissi n [ spires Aug. IJ,1%J
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I WM. II . ZIMMER NUCLEAR POWER STATION s i UNIT 1 CONTROL OF IIEAVY LOADS June 22, 1981 In response to Darren G. Eisenhut's December 22, 1980 letter concerning control of heavy loads, the following information is submitted. Section 2.1 of enclosure 3 to the above referenced NRC letter (attached) requires a " review of plant arrangements to identify all overhead handling systems from which a load drop mr/ result in damage to any system required for plant shutdown or decay heat removal." All cranes installed or planned for use at the Wm. H. Zimmer Nuclear Power Station have been individually reviewed as required above. Those hoists, which because of their location alone, have some probability of causing damage to systems required for plant shutdown or decay heat removal as the result of a load drop are listed in Table 1. Also included in Table 1 are the hoist capacity, (') location by elevation, location by row / column plant coordinates, and the equipment removal drawings upon which it can be located. Section 2.1 of enclosure 3 allows the exclusion of any overhead handling system f rom Table 1 by verifying sufficient physical separation frem any load impact point to any safety related component to permit a determination by inspection that no heavy load drop can result in daniage to any system or component required for plant shutdown or decay heat removal. The following discussion provides justification for removal of various handling systems from Table 1. Item 107 is a 20 ton monorail overhead hoist designed for tube bundle removal and overi.aul of the IB reactor building closed cooling water heat exchanger (spare) and residual hett removal heat exchangers 1A and IB. Sufficient physical separation exists, insuring that inadvertant drop of any of the above components would not cause damage to any other system required for safe shutdown or decay heat removal. The IB V
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RBCCW heat exchanger, shown on sheet 1 of the equipment removal plans, is separated by 12 feet from the north bank hydraulic control units, and by two floors from the RilR heat exchangers. The R!iR heat exchangers are separated from each other in adjacent cubicles and are located two floors beneath the IB RBCCW heat exchanger. Item 120 is a 15 ton monorail overhead hoist. The cranc shown on sheet 4 of the equipment removal plans is designed for overhaul of the high pressure core spray pump shown on sheet 5 of the equipment removal plans. Sufficient physical separation exists, ensurirg that inadvertant drop of the high pressure core spray pump components would not cause damage to any other system required for safe shut-down or decay he .t removal. Item 121 is a 4 ton monorail overhead hoist. The hoist shown on sheet 4 of the equipment removal plans is designed for overhaul of the Reactor Core Isolation Cooling system shown on sheet 5 of the (~'T
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equipment removal plans. Sufficient physical separa-tion exists, ensuring that inadvertant drop of the RCIC system components would not cause damage to any other systen required for safe shutdown or decay heat removal. Item 122 is a 2 ton monorail hoist located inside the suppression pool chamber. The hoist shown on sheet 4 of the equipment removal plans is used for performance of any corrective or preventative main-tenance required in the pool. Any such activities performed with the unit is cold shutdown would not cause damage to any component required for decay heat removal. Items 123 and 124 are 2 ton monorail overhead hoists. The hoists shown on sheets 6 and 1 of the equipment removal plans are designed for removal of the IB (1A) standby gas treatment system fan or various filtering agents in the SBGT train. LJ
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t U-Inadvertent- drop of any components of either SBGT train would not cause damage to any other system required for safe shutdown or decay heat removal. Item 126 is a lh ton manual hoist which may be positioned at four locations in the main steam tunnti above the outboard main steam isolation ' valves. Maintenance on these valves involving heavy lifts could only be reasonably performed with the unit in cold shutdown. No conceivable load drop could result in damage to any component required for decay heat removal. Items 203 and 204 are planned future hoists for use in the diesel generator rooms. Each of the three diesels will be served by two 1 ton and one 5 ten hoists. The accidental dropping of a diesel engine component will have no effect upon any other system required for safe shutdown or decay heat ramoval. Item 412 is two 8 ton monorail hoists located in the service water pump structure. The hoists shown on sheet 16 of the equipment removal plans
() are used for corrective maintenance activities on the service water. pumps. l Taking account for the removtblo slabs shown, 4 sufficient physical separation exists, ensuring that inadvertent drop of a service water pump component would not cause damage to any other system required for safe shutdown or decay heat removal. l . Section 5.1.1 of NUREG 0612 provides guideliner for the control of heavy loads. The following discussion provides the results of our evaluation ! for compliance with these guidelines for the TABLE 1 LOAD !!ANDLING SYSTEMS not previously addressed in this report.
- Equipment removal paths have been identified and are shown on the equipment removal plans. Particular :
drawings for each load handling systen are being developed from these equipment removal plans. f i MM- , -
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, 1 Administrative controls are being. developed and'shall be in place prior to initial fuel loading. The administrative controls shall require specific imple-menting procedures for the handling of heavy loads over or in close proximity to irradiated fuel on the plant refueling floor. These implementing procedures shall include; identification of required equipment, any
- inspections required before load movement, and the handling sequence to be followed including a drawing of the equipment removal path.
The movement of heavy loads,-other than on the refueling floor, shall be under the control'of the raintenance supervisor. All appropriate precautions and-the equipment removal path shall be defined on the plant werk request for those load handling devices previously identified as having potential for damage to safe shutdown equipment. 1 Table 2 contains a listing of the loads which are handled by each crane, the loads weight, required l rigging equipment, and controlling document. The-required rigging equipment, listed in Table 2, apply _ j3 to loads handled on the plant refueling floor only. . (/ This equipment or equivalents defined in the future, will be specifically required by the plant implementing piocedure covering the subj ect activity. Movements of heavy loads performed in other areas of the plant which hav> potential for damage to safe shutdown equipment are administratively controlled through the station work request. Items 103, 104 and 105 of Table 1 have been deleted j since by their capacity they are incapable of handling j heavy loads.
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Oa The rigging equipment listed in Table 2 satisfies the requirements of ANSI B 30.9. The rigging slings were selected with a minimum design capacity of 110% of the , static load. Based upon a maximum hoisting speed of i
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5.5 ft/ min, the 100 margin is deemed adequate for the applied dynamic loads. Verification of conformance to ANSI N14.6 for the reactor head strongback and Dryer /Seaarator strongback
-is presently.being persued through t.1e General Electric Company who specified and supplied the equipment. ,
However, the following design and construction features have been verified.
- 1. Equipment. was constructed in accordance with General Electrlc Design Drawings.
- 2. Material was specified and approved by General
. ectric. ,
- 3. Reactor head strongback was proof tested to 100 tons and dryer / separator strongback was proof tested to 104 tons.
O 4. All structural welds were magnetic particle inspected.
- 5. Weiders and procedures were qualified in accordance with ASME boiler and pressure vessel code section'IX.
- 6. Nameplates were attached to the reactor head strong-back listing an 80 ton capacity sad the dryer / separator strongback listing a 52 ton capacity at 194.25" spacin 204.50" spacing. The dryer /g and 38 ton separator strongback capacityhook at block is labeled for 60 ton capacity. 7 All crancs at the Wm. H. Zimmer Nuclear Power Station, which are under control of the Electric Production Depart-ment, are periodically inspected as required by ANSI.B.30.2.0.
All cranes are designated as either regular or standby : service. Crancs used more than twice a week are designated ! as regular use. All crancs o nd hoists undergo a before use + insnection. All regular use c ranes or standby use cranes being operated regularly for more than a month, undergo a documented monthly inspection. All cranes undergo a yearly ., docenented inspection. ! l , i i W
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a As described in the Wm. 11 . Zimmer Nuclear Power Station Final Safety Analysis Report, the Reactor Building crane is designed per the requirements of ANSI B.30.2.0 and CMAA-70. Other overhead hoists installed at the Zimmer Station are specified to meet the requirements of ANSI B.30.16, overhead hoists. All personnel who operate cranes or hoists at the Wm. R. Zimmer Nuclear Power Station have received documented classroom training in the ar eas of rigging, lifting, hand signals and rigging inspection. In addition, personnel who operate cab-operated crancs have received hands-on training on such equipment during the preopera-tional testing programs at the plant. n n _/ L
O O O TABl.E I (NO.) 6 CAPACm Tla)l l.I.Y I FII"Mlm OF MM N M g ygg; IllRitEE OR I4tillMNT TO BE LilTLD OF Ff.Vti OR
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OF TRAVLI, 101 fliin Reactor Bldg. Cranc-Aux, licnyk _ 110-10 658'-3" 5.!!'-0" 627'-9" 15-28 A-F_ j _b8 liri k e Cia _ne_ ltR 102 ruel lltalling Kih Crane 1/2 - 627'-9" 627'-9" 25-27 B-D 6,8 Flectric twR 100 lbs. 627'-9" 627'-9" 25-27 D-C 6,8 thain- Minual 103 -thannel II.endling Ikun . lib Crane - 101 lEl flarkiling . lib Crane 1/2 -
$27'-9" 627'-9" 23-25 li-C 6,8 I;lectric 1%R 105 Relief 6 Safety Valve Phint. 2 5R2'-10" 520'-10" - 18-25 B-D 1 8,11 Electric 8%R 107 RIR 6130W (110 llcat Exchanger 20 565'-6" 503' 6" 53S'.0" 27-28 B-E 1,11 Ulw tric Itu 108 Main Steam Ilitch Slabs 6 Isolation Valves 18 564'-6" 532'-0" 586'-0" 21 E-F 1,8,11 Electric ItR Recirculating hann Mitors 24.45 552'-8 '
525'-7" 525' 7" 18-25 _ B- E 3 8,11_ tame IKR 109 111 llatch Stabs 6 ICIC thintenance 15 543'-0" 503'-6" 525'-7" 15-18 _ E-F 2,8,11 . _ Electric IsR _ 112 IWW (I AI fleat lachanger 20 542'-0" 503'-6" 525'-7" 23-28 A-B- 2,8,11 Elr tric 1%R 113 Deletel 114 hateMiintenance 21/2 133'-10 I/4 " 525'-7" 525'-7" 21-25 B-E _24,1,l_ thain IWR
, 115 Deleted 6 580'-4" 525'-7" 525'-7" 18-21 B- D 2,11 Gialn Chain li.C.T.
__U!L _l'D3til Acess Itach Cover 118 la Pressure Core Spray 518'-0" 475'-6" 503'-6" 25-28 B-C 4 Electric IKR 8 4 520'-b 7/8' 119 IllR hrys 1 520'-7" 475'-6" 503'-h" 27-28 D-E 4,11 Electric 1%R I 520'-7" 120 llich l'ressure for Spray hunn 15 522'-7" 475'-6" 503'-6" 15-18 A-B 4.8 1lectric Giain II.C.T. 121 _RCIC Turbine nrnp 6 Corwienser 4 ~ 521'-07/8 " 475'-6" 503'-6" 15-18 D-F. 4.8.11 Electric ItR _11 p_ypyession Pool Service 2 51S'-0 T" 4 475'-6" - 18-27 B-E 4,8,11 Flectric 1%R 123 Stars!by Gis ritters 2 624'-9" 593'-6" 593'-6" 23-27 A-B _6. 8 Ilectric Chain ll.G.L _ Standby Cas I'llters 1 566'-6" 546'-U" 23-27 A-B 1,8 Electric Omin II.G.T-124 ~St6'-0" j 126 ffilV (thtloard) Clearance hill p-41'-6" 532'-0" 532'-0" 21-25 E-F 2,8,11 Stuvial time PtilV (Infoard) - Fhintenance (4) 5 544 '- 63/8 " - - 22-19 D 2,13 fame thain ll.G T. 203 Diesel Generator Ingine (6) 1 544' 0" 525'-7" 5258-7" 12-14 F- L 2,8 Mumial Diesel Cencrator I:ngine 525'-7" 13-14 F- L _2,8 bhrmaal 204 (3) 5 54 4 ' - O 52 5 ' - 7 11 2 Service Water hanps (2) 8 48b'-5 2" 435'-U"- 466'-5 2' 2-5 A-C J, l_ Electric _ 1%R 117 SN. henp Mitors I A 6 IH thint. 3 450'-l 4" 435'-0" 435'-0" 2 B 16 tbne Iy G7,0 Q 4 SW. henp thtors IC 4 ID thint. 3 450'-lk' 135'-0" 435'-0" 3 B 16 Mme By 0;6E l - 3' M e gg ; eam W7' ac, r.4 b r"
{j Ta ] 2 (^) MAIN RF)LTOR BUILDING'CPANE - 110 TON 1100K LG\D IDENTIFICATION 10AD WGT (TONS) DESIGNATED LIFFING DEVICE CONTROLLING DOCLMENT Reactor Cavity Shield Plugs (6) 90 21/4" IhRC 3 legged bridle sligg bE.RFP.402 Dryer Separator Pit (3) 40 (2) 2" shackles hE.RFP.402 Plugs (1) 44 (1) 2 legged bridle sling, 2" IWRC Fuel Pool Shield Plugs (4) 12 (1) 13/8" shackle, (1) 1 3/8" IhRC sling hE.RFP.402 Drywell Head 65 RPV head strong back, (4) 2.75" turnbuckle, (4) 2.5" shackles hE.RFP. 401 RPV licad Insulation ME.RFP.403 Rx Head Stud Tensioner 4 Stud Tensioner Strongback FE.RFP.404 Reactor ifead 65 RPV head strongback, (4) 2.75" turnbuckles, (4) 2.5" shackles ME.RFP.404 Steam Dryer 38 Dryer /Seperator Strongback,1 1/2" IhRC 4 legged bridle sling (4) 2.5" turnbuckles FE.RFP.303 Steam Separator 51 Dryer / Separator Strong back, 1 1/2" IWRC 4 legged bridle sling, (4) 2.5" turnbuckles FE.RFP.304 Fuel Pool Gates (1) 5.5 (2) 1 1/2" shackles, 2" IhRC 2 legged bridle (1) 3.5 sling bE.RFP.405 Dryer / Separator Pool Gate 23.5 (2) 2" shackle 2" IhRC 2 legged bridle sling FE.RFP.406 Shipping Cask Storage Pit Gate 4.0 (2) 1.5" shackles 2" IhRC 2 legged bridle sling hE.RFP.407 Reactor Service Platform 6.0 5/8" 3 legged bridle sling hE.RFP.408
I, _ MAIN REACTOR BUILL ; CPANE - 10 'IDN llc 0K ( . _ . IDAD IDENTIFICATION LDAD WGT (TONS) DESIGNATED LIFTING DEVICE CONTROLLING DOLU.!ENT New Fuel Shipping Crate 1.0 3/4" 4 legged bridle sling NE. HIP.03, 04, 06 3/4" 2 legged upending sling Removable 1/2 Ton Jib Crane 4.0 1 3/8" shackle, 1 3/8" sling ME . K"' ' O' I Q l
n go ~ (v, gj e) ITB1 118 Low Pressure Core Spray Ptm:p 4.0 Ton Load Identification Load lieight Ptrnp !btor 3.5 Ton Plunp Impeller 3.0 Ton Floor Slabs (2) 3.0 Ton ITD! 119 Residual Heat Removal Pumps (3) 4.0 Ton Load Identification Load Ifeight Floor Slabs (2) 3.0 Ton Pump bbtor 2.0 Ton linnp Impeller 2.5 Ton ITDI 128 hSIV's Inboard 5.0 Ton Load Identification Load Weight
, SSIV Air Cylinder 1.0 Ton Complete SSIV 5.0 Ten o
, ITB! 417 6 Service Water Pumps 3.0 Ton 418 Load Identification Load Weight Pump Upper Shell <2.0 Ton
<2.0 Ton
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x.) V C* ITB!105 Relief and Safety Valve Maintenance 2 Ton Load Identification Load Weight Main Steam Relief Valves 2900 lbs. ITDI 108 Main Steam flatch Slabs and Isolation Valves 20 Ton Load Idantification Load Weight (4) Stenm llatch Slabs 18.5 Tons MSIV Air Cylinder 1.0 Ton Complete MSIV 5.0 Ton ITB! 109 Reactor Recirculation Pump Motor 24.45 Tons Load Identification Load Weight Pump 5btor 23.8 Tons ' ITD! 111 Ilatch Slabs and RCIC hhintenance 15 Ton load Identification Load Weight I (3) llatch Slabs 1 Ton RCIC Pump 2 Ton RCIC Turbine 1.5 Ton Ibd Drive Pump 0.75 Ton Rod Drive Pump Motor 1.5 Ton ITDI 112 RBCCN (IA) lleat Exchanger 20 Ton Load Identification Load Weight Tube Bundle 7 Ton ITB1114 Drywell Valve Maintenance 2.5 Ton Lov.d Identification Load Weight Shutdown Cooling Suction - Valve Bonnet 1 Ton Recirculation Flow Control Valve Actuator 0.5 Ton ITD! 116 Drywell Access flatch Cover 6.0 Ton Load Identification Load Weight flatch Cover 5.0 Ton
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, NUCLEAR REGULATORY COMMISSION y ~, . %. j. - WASHINGT ON. D. C. 20555 . .
\ .' ,',', , December 22, 1980 L)in W_ I 1 >>Fl' TO ALL LICEtiSEES OF OPERATir4G PLAllTS AND I _.
APPLICANTS FOR OPERATING LICEllSES AND I HOLDERS OF CONSTRUCTI0fl PERMITS
- I Gentlemen:
Subject:
Control of Heavy Loads
- In January 1978, the NRC published NUREG-0410 entitled, "f!RC 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 -
,m Resolution of TAP A-36." This report contains several recommendations U to be implemented by all licensees and applicants to ensure the safe handling of heavy loads.
The purpose of this letter is to request that you review your controls for the handling of heavy loads to determine the extent to which the guidelines of Enclosure 1 are presently satisfied at your f acility, and to ioentify the changes and modifications that would be required in order to fully satisfy these guidelines. To expedite your compliance with this request, we have enclosed the following: NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" (Enclosure
. 1). .
Staff Position - Interim Actions for Control of Heavy Loads (Enclosure 2). Request for Additional Information on Control of Heavy Loads (Enclosure 3). . l
*With the exception of licensees for Indian Point 2 and 3, Zion 1 and 2 and Three Mile Island 1 (These were previously sent a letter) l
, - c 4 j .
. - - - .- - . -. - - - ~ - . - -
h December 22, 1980 L) You are requested to implement 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 fiRC to determine whether operating licenses should be modified (10 CFR 50.54(f)), operating reactor licensees are requested to provide the following:
- 1. Submit a report documenting the results of your review and the required changes and modifications. This report should include the information identified in Sections 2.1 through 2.4 of Enclosure 3, on how the guidelines of ttuREG-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 months from the date of this letter. Submit the Sections 2.2, 2.3 and 2.4 information within nine months. p 2. Furnish confirmation within six months that implementation of V those changes and modifications you find are necessary will , commence as soon as possible without waiting on staff review, so that all such changes, beyond the above interim actions, will be completed within two years of submitital of Section 2.4 for the above report.
- 3. Furnish justification within six months for any changes or modifications that would be required to fully satisfy the guidelines 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 requested by item 1 above and to meet the same schedule of implementation as indicated in 2 above. Any item for which the implementation date is prior to the expected 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. I O l
This request for information was approved by GA0 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,
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Darrel M G E'isenhut, Director Division o Licensing
Enclosures:
- 1. NUREG-0612
- 2. Staff Position
- 3. Request for Additional '
Information ec: w/o Enclosure (1) Service List r 9 9 3 e
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