ML17256A529

Forwards Supplemental Response to NRC 820819 Technical Evaluation Rept, Control of Heavy Loads - NUREG-0612. Part 2 Response Will Be Submitted 830201.Util Will Develop Load Handling Procedures for 10 Sys within NUREG Scope

ML17256A529
Person / Time
Site:	Ginna
Issue date:	03/02/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR GL-81-07, GL-81-7, NUDOCS 8303080333
Download: ML17256A529 (68)

Text

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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER TEI.EPHOHE Vice Prosldont AREA CODE 7le 546-2700 March 2, 1983 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch 55 U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

"Control of Heavy Loads" Supplemental Report Addressing Techni'cal: Ev'a1ua'tio'n'eo'rt', Dat'ed'u ust9','982

Dear Mr. Crutchfield:

Enclosed please find our response to your letter of August 19E 1982E "Control of Heavy Loads NUREG 0612."

A part two response, "NRC Request for Additional Information on Control of Heavy Loads," will be submitted December 1, 1983.

AVery truly yours, E. Maier 8303080333 P~R ~D~C 05000244 PDR'-,',;.'.,-

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SUPPZEMENTAL REPORT ON CONTROZ OF HEAVY LOADS RESPONSE TO THE DRAFT TECHNICAL EVALUATION REPORT PREPARED BY FRANKLIN RESEARCH CENTER CONCERNING CONTROL OF HEAVY LOADS NUREG 0612 AT R. E. GINNA NUCZEAR POWER STATION REFERENCED LETTERS NRC GENERIC LETTER 81-07 DATED DECEMBER 22~'980

2. NRC GENERIC LETTER 81-07 DATED FEBRUARY 3, 1981

'3. LETTER TO MR. DARRELL G. EISENHUT (NRC)

FROM MR. JOHN E. MAIER (RG&E)

DATED FEBRUARY 1, 1982 LETTER TO MR. JOHN E. MAIER (RGScE) FROM MR. DENNIS M. CRUTCHFIELD (NRC)

DATED AUGUST 19~ 1982 (TECHNICAL=EVALUATIONREPORT)

R. E. GINNA NUCLEAR POWER STATION ROCHESTER GAS AND EZECTRIC CORPORATION DOCKET NO. 50-244 MARCH 1, 1983 MF3A

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INTRODUCTION AND BACKGROUND On February 1, 1982 Rochester Gas and Electric Corporation submitted a report stating the extent. of compliance with general load-handling policies and procedures at the R. E. Ginna Nuclear Power Plant with NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants", Section 5.1.1.

A Technical Evaluation Report (TER) was prepared and returned to Rochester by the NRC and its consultants. Enclosed in this report are responses to open items in this TER, schedules for implementation of procedures and training programs to assure compliance with NUREG-0612 and justification for exceptions taken to NUREG 0612.

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RESPONSE TO THE DRAFT TECHNICAL EVALUATION REPORT PREPARED BY FRANKLIN RESEARCH CENTER CONCERNING "CONTROL OF HEAVY LOADS - NUREG 0612" AT R. E. GINNA NUCLEAR POWER STATION TER Section 2.1.lc "Overhead Hea Load Handlin S stems" Conclusions and Recommendatxons The Licensee should identify overhead handling systems excluded from compliance with NUREG-0612 and verify that such exclusion was based on one or more of the following:

1. No safety-related equipment or irradiated fuel is located in close proximity or sufficient physical separation exists.

2. The systems are sole-purpose systems and are used only when the equipment is out of service.

3. Heavy loads are not carried by the excluded system. (A heavy load for R. E. Ginna Nuclear Power Station is taken as 1500 lbs.)

RG&E Res onse In response to "Conclusions and Recommendations" listed for this section RG&E has provided an enclosed list of all Overhead Handling Systems 'at R. E. Ginna Nuclear Power Station (Attachment 1). The list of overhead handling systems within the scope of NUREG-0612 provided in RG&E's February 1, 1982 submittal has been reduced by using the exclusion criteria shown above.

Attachment 2 shows the physical location of each overhead handling system identified.

TER Section 2.1.2 "Safe Load Paths Guideline 1, NUREG-0612, Sects.on 5.1.1 1 Conclusz.ons and Recommendatxons The Licensee partially complies with Guideline 1 for the Ginna plant. In order to comply fully with the criteria of this guideline, the Licensee should perform the following:

Provide suitable visual aids to assist the crane operator in the areas where loads. are handled by all equipment that. is not excluded from compliance with NUREG-0612, as specified in 2.1.1.c.

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2. Define all safe load paths in procedures.

3. Incorporate safe load paths into equipment layout drawings.

Verify that deviations from established load paths require written alternatives to be approved by the plant safety review committee.

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RG&E Res onse In response to "Conclusions and Recommendations" listed for this section RG&E will: 1) define specific heavy load safe load paths, 2) define "generic" heavy load safe load paths, 3) incorporate safe load paths into load handling procedure A-1305, 4) establish

'a deviation of safe load path control procedure, 5) provide suitable visual aids to assist crane operators properly handle heavy loads where practical.

The above procedures will be implemented for the following Overhead Handling Systems:

Crane No. Overhead Handlin S stem 7 100(2) Ton O.H. Crane in CTMT 29 40(5) Ton O.H. Crane Auxiliary Bldg.

32 7 1/2 Ton Screenhouse Crane (East)

The remaining 7 overhead handling systems within the scope of NUREG-0612 (Attachment 1, Page 6 of 6) are restricted by the physical capabilities of the system and therefore require no additional work regarding safe load paths.

RG&E will have these procedures in place by September 1, 1983.

TER Section 2.1.3 "Load Handlin Procedures" Guideline 2, NUREG-0612, Section 5.1.1 2 Conclusions and Recommendations The Ginna plant does not comply with Guideline 2. Load-handling procedures should clearly identify inspection and acceptance criteria, steps, and proper sequence, and clearly define the safe load paths for the various heavy loads listed.

RG&E Res onse In response to "Conclusions and Recommendations" listed for this section RG&E will develop Load Handling Procedures for the 10 Load Handling Systems within the scope of NUREG 0612. The program will identify specific and "generic lifts", insure the proper equipment is utilized for the lift and that the load is handled properly. This development of Load Handling Procedures will be done in administrative procedure A-1305 accompanied by a qualifying rigger program.

RG&E will have these procedures in place by December 31, 1983.

TER 2.1.5 "S ecial Liftin Devices" Guideline 4, NUREG-0612 Section 5.1.1 4 Conclusions and Recommendations A conclusion regarding compliance with this guideline must be deferred until the Licensee completes the analysis of their special lifting devices. However, this analysis should address the specific items identified in this independent evaluation.

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A comparison analysis for the Special Lifting Devices used at R. E. Ginna Nuclear Power Plant to determine the compliance with NUREG-0612 has been completed by Westinghouse Corp. This analysis encompasses the following special lifting devices:

Reactor Head Lifting Rig, The Upper and Lower Internals Lifting Assembly and The Reactor Coolant Pump Motor Sling. The evaluation shows that the stress limit criteria of ANSI N14.6-1978 associated with certain stress design factors for tensile and shear stresses are adequately satisfied.

Enclosed is justification for dynamic load factors considered in the analysis of these special lifting devices. (Attachment 3)

RG&E has implemented an inspection,, testing and maintenance program to insure continued compliance with ANSI N14.6-1978.

This program will require visual inspections annually (not to exceed 15 months, consistent with permissible extensions for Technical Specification surveillance). Nondestructive examination of critical welds will also be done every ten years.

At. this time the analysis is based on the original design drawings. During our spring outage 1983 "as built," sketches of any modifications or additions to the special lifting devices will be made, reviewed and analyzed to determine if the evaluation performed is effected. RGGE will submit this information by August 1, 1983.

TER 2.1.6 "Liftin Devices" Not S eciall Desi ned Guideline 5, NUREG-0612 Section 5.1.1 5 Conclusions and Recommendatxons Determination of compliance with Guideline 5 must be defer'red until RG&E provides specific information concerning:

1. Installation and use of slings (in accordance with ANSI B30.9-1971)

2. Selection of slings (base'd upon the sum of the static and maximum dynamic loads)

3. Sling markings and sling restrictions, where appropriate In response to "conclusions and recommendations" listed for this section RGSE will implement a rigger qualification program to insure that slings are selected and used in accordance with ANSI B30. 9-1971.

At this time sling selection and use at R.E. Ginna Station is the responsibility of each individual rigger. The "Handbook for Riggers" by W. G. Newberry, Calgary, Alberta, Canada is currently used and believed to be equivalent to ANSI B30.9-1971.

All slings used at Ginna Station have load ratings marked on them.

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RG&E believes that adding additional factors to consider dynamic loads above the 5:1 safety factors for slings already considered is impractical and provides no justifiable cushion of safety. Dynamic loads are negligible and only static loads are considered.

RG8E will have the qualified rigger program in place by December 31, 1983.

TER 2.1.7 "Cranes" Ins ection, Testin and Maintenance Guideline 6, NUREG-0612, Section 5.1.1 6 Conclusions and Recommendations The Ginna plant will comply with Guideline 6 upon implementation of proposed revisions to inspection, testing, and maintenance programs.

RGSE Res onse Revisions are being made to the existing RGSE inspection, testing, and maintenance programs listed in the February 1, 1982 submittal to insure full compliance with ANSI B30.2-1976, Chapter 2 2 ~

Additional programs are being developed for jibs and monorails to insure that inspection, testing, and maintenance procedures comply with ANSI B30.11-1980 "Monorails and Underhung Cranes" Chapter 11-2. All procedures will be in place by September 31, 1983.

In response to a question concerning the Auxiliary Building overhead crane and a "rated load test", the February 1, 1982 submittal stated that this crane was load tested prior to lifting a spent fuel cask in 1973. This is correct. The 40 ton auxiliary crane was load tested using a 40 ton test load.

TER 2.1.8 "Crane Desi n" Guideline 7, NUREG 0612, Section 5.1.1 7 Conclusion The Ginna Auxiliary Building crane complies with Guideline 7.

The Reactor Building substantially complies with this guideline; however, the Licensee should be ready to provide suitable documentation to justify the location and moment of inertia of the actual longitudinal stiffeners.

RG&E Res onse Justification for the location and moment of inertia of the longitudinal stiffeners used on the crane bridge of the Containment.

Overhead Crane is provided in Attachment 4.

In response to a question concerning the horsepower rating for the main hoist of the 100 ton containment overhead crane it is a 5 H.P. motor. This capacity was omitted in error in the February 1, 1982 submittal.

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TER Interim Protection Measures Conclusions and Recommendations Insufficient information has been provided to clearly determine compliance with this interim measure. The Licensee should review and determine whether current, technical specifications meet, the intent of this guideline.

RG&E Res onse RG&E has reviewed the technical specifications which limit travel of the Auxiliary Building overhead crane over the spent fuel area and has found them to be adequate interim protection.

No other overhead handling systems can physically move over the spent fuel area except the spent fuel manipulator crane. This crane has undergone analysis for a single spent fuel assembly handling accident and has been deemed not to require further evaluation.

TER S ecial Review for Hea Loads Handled Over the Core Interim Protection Measure 6 NUREG-0612, Section 5.3 6 Evaluation Conclusion and Recommendatz.ons The Licensee has made no statements or conclusions regarding this interim protection measure. The Licensee should report the completion of the special review identified in ths interim measure.

RG&E Res onse Safe load paths for heavy load lifts made Ginna Station are physically restricted.

in containment at Procedure A-1305 is currently the controlling load-handling procedure, the crane is inspected according to ANSI and the crane operators are trained according to ANSI. Further analysis of handling of heavy loads in this area is required to satisfy NUREG-0612 and shall be included in the load-drop analysis submittal.

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g I ATTACHMENT 1 TOTAL LIST OF OVERHEAD HANDLING SYSTEMS AT R. E. GINNA NUCLEAR POWER STATION No. ~Bui1 din Overhead Handlin S stem 1 Containment 3 Ton Jib 2 Containment, 1 Ton Jib (E) 3 Containment 1 Ton Jib (W)

Containment 1 1/2 Ton Fuel Manipulator Bridge Containment Aux. Trolley on Fuel Manipulator Bridge Containment, 10 Ton Jib Containment 100(20) Ton Overhead Crane Containment, 2 Ton Jib Containment 1/4 Ton Jib on Overhead H Crane, 10 Containment", 3 Monorail Hoists'on Reactor Head Monorail'-'ib 11 'ontainment.

on Overhead 12 I 13 Turbine (2) Monorails Over. Feed-water Pumps (Basement)-

Turbine 2 Ton Jib -- Turbine Oil Part 15,16,17 Turbine (3) Monorails-Condenser Parts 18 Turbine (1) Monorail Feed-water Heater Parts 19,20,21,22 Turbine (4) Monorails -- Moisture Separator Parts 23 Turbine Turbine Overhead 125 Ton (25 Ton) 24 Turbine 3 Ton Movable Gantry 25,26 Auxiliary (2) Nonorails RHR Pit (Basement) 27 Auxiliary (1) Monorail (Basement) 28 Auxiliary 2 Ton Spent Fuel Crane 29 Auxiliary 40(5) Ton Overhead Crane 30 Auxiliary 5 Ton Drumming Crane 31 *Screenhouse 7 1/2 Ton Screenhouse (W) 32 *Screenhouse 7 1/2 Ton Screenhouse (E) 33 Service 2 Ton -- Steamfitting Shop 34 Service 2 Ton -- Hot Shop 35 Service 5 Ton -- Machine 6 Elect.

36 Service 2 Ton --Shop Machine S Elec. Shop 37 Service 2 Ton -- Meter Shop MF3B Page 1 of 6

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.No. B~nildin Overhead Handlin S stem 38,39 Intermediate (2) Monorails -- MDAFWP 40 Intermediate (1) Monorail -- TDAFWP 41 Intermediate (1) Monorail -- M.S. Header 42 Intermediate 3 Ton Monorail Upper Level 43 Intermediate (1) Monorail A F.W. Line 44 Standby Auz (1) Monorail F.W. Pump Bldg.

45 Diesel Gen. (1) Monorail DG1 46 Diesel Gen. (1) Monorail.DG2, 47 AVT Bldg. 1 Ton Stairwell Monorail 48 Oil Storage Monorail '1)

Building Plant 18 Ton Mobile Crane Exterior 50 Containment Reactor Vessel Stud Cleaning Crane 51 Containment Base Mounted Pillar Jib Crane 52 Containment Jib at Equipment Hatch (On Wall)

• Screenhouse crane is classified as two different cranes, however, there is only one crane for two areas which are separated by a track switch MF3B Page 2 of 6

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OVERHEAD HANDLING SYSTEMS EXCLUDED FROM 'COMPZ IANCE WITH NUREG 0612 BASED ON >>NO SAFETY-RELATED E UIPMENT OR IRRADIATED FUEL IS ZOCATED IN CLOSE PROXIMITY OR'SUFFICIENT PHYSICAL SEPARATION EXISTS No. ~Buildin Overhead Handlin S stem 12, 13 Turbine (2) Monorails Over Feed-water Pumps (Basement)

Turbine 2 Ton Jib -- Turbine Oil Part 15,16,17 Turbine (3) Monorails--

Condenser Parts 18 Turbine (1),Monorail -- Feed-

,i water Heater Parts',

19,20,21,22 Turbine,.. (4) Monorails Moisture e Separator Parts 23 Turbine 125(25) Turbine O.H. Crane 24 Turbine 3Ton,,Gantry 30 Auxiliary 5 Ton Drumming'Crane 31 Screenhouse 7 1/2 Ton Screenhouse (W) 33 Service 2 Ton -- Steamfitting Shop 34 Service 2 Ton -- Hot Shop 35 Service 5 Ton Machine 6 Elect. Shop 36 Service 2 Ton Machine 6 Elec. Shop 37 Service, 2 Ton -- Meter Shop 47 AVT Bldg. 1 Ton Stairwell Monorail 48 Oil Storage (1) Monorail Building Plant 18 Ton Mobile Crane Exterior 50 Containment Reactor Vessel Stud Cleaning Crane TOTAL = 24 MF3B Page 3 of 6

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OVERHEAD HANDLING SYSTEMS EXCLUDED FROM COMPI IANCE WITH NUREG 0612 BASED ON: "SOLE PURPOSE SYSTEMS AND ARE USED ONLY WHEN THE E UIPMENT IS OUT OF SERVICE" No. ~Buildin Overhead Handlin S stem 10 Containment (3) Monorail Hoists on Reactor Head Monorail 25, 26 Auxiliary (2) Monorails RHR Pit Basement 38, 39 Intermediate -(2) Monorails -- K)AFWP 40 Intermediate (1) Monorail -- TDAFWP 41 Intermediate Monorail Over Main Steam Header Intermediate Monorail Over "A" F.W. Line Standby Aux (1) Monorail F.W. Pump Bldg.

Diesel Gen. (1) Monorail Bldg. A Diesel Gen. ,(1) Monorail Bldg. B TOTAL = 11 All of the above overhead handling systems are used only when the safety related equipment below them or within their proximity is out of service. Each monorail will be posted to prohibit its use while the systems below are in operation and each will be locked to insure that this restriction is adhered to.

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OVERHEAD HANDLING SYSTEMS EXCLUDED FROM COMPLIANCE WITH NUREG 0612 BASED ON: "HEAVY LOADS ARE NOT CARRIED BY THE EXCLUDED SYSTEM" (A HEAVY LOAD AS DEFINED BY NUREG 0612 FOR R. E. GINNA STATION IS 1500 LBS.)

No. ~Buildiu Overhead Handlin S stem Containment 1 Ton Jib (E)

Containment 1 Ton Jib (W)

Containment ,

Aux.,Trolley on Fuel

. Manipulator Bridge Containment 1/4 Ton Jib on Overhead Crane 11 Containment Jib on Overhead CTMT Crane 51* Containment Base Mounted Pillar Crane 'ib 52 Containment Jib at Equipment Hatch (On Wall)

TOTAL = 7

• Designed, not installed, on hold.

All of the overhead handling systems above will be derated and posted so as to prevent. the lifting of any heavy loads.

(>1500 lbs.)

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Total identified Overhead Handling Systems 52 Total eliminated by "Physical Separation" 24 Total eliminated by "Sole Purpose" 11 Total eliminated by "No Heavy Load Lifted" 7 TOTAL OVERHEAD HANDLING SYSTEMS THAT MUST COMPLY WITH NUREG 0612 10 No. ~Bnildin Overhead Handlin S stem Containment 3 Ton Jib Containment 1 1/2 Ton Fuel Manipulator Bridge 6 Containment '10 Ton Jib 7 Containment 100(20) Ton O.H. Crane 8 Containment '2 Ton Jib 27 Auxiliary (1) Monorail (Basement) 28 Auxiliary 2 Ton Spent Fuel Crane 29 Auxiliary 40(5) Ton O.H. Crane 32 Screenhouse 7 1/2 Ton Screenhouse (E) 42 Intermediate 3 Ton Monorail Upper Level Total = 10 MF3B Page 6 of 6

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I I ~ 1 Attachment 3 1/2 SPECIAL LXPTING DEVICES ITEM 1= STRESS DESXGN FACTOR PROM NUREG 0612 The stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on character-istics of the crane which will be used. This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) of the load and of the intervening components of the special handling device.

DISPOSITION OP DYNAMIC LOADS XN WESTINGHOUSE ANALYSIS OP LIFTING DEVXCES I

It can be inferred from this factors specified in Section paragraph that the stress design 3.2.1.1 of ANSI N14.6 (3 and 5) are not all inclusive. Also, it can be inferred that the specified ANSI N14.6 stress, design factors should be increased by any amount based on the crane dynamic characteristics. The dynamic characteristics of the crane would be based on the main hook and associated wire ropes holding the hook. Most, main use sixteen (16) or more wire ropes to handle the load.

containment'ranes Should the crane hook suddenly stop during the lifting or lowering of a load, a shock load could be transmitted to the connected device. Because of the elasticity of the sixteen or more wire ropes, the dynamic factor for a typical containment crane is

not much larger than 1.0. The maximum design factor that is recommended by most design texts 7, 8, 9j is a factor of 2 I

for loads that are suddenly applied. The stress design factors required in Section 3.2.1.1 of ANSI N14.6 are:

3 (weight) < Yield Strength 5 (weight) < Ultimate Strength The factor of 3 specified, certainly, includes consideration of suddenly applied loads for cases where the dynamic impact factor may be as high as 2.0 Thus, we feel that the use of

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CMAA f70 IMPACT LOAD CRXTERIA 3~3 ~2~1 ~ 1.3 Impact Allowance: For cranes operating on runways as described'n Section 1.4, the impact allowance of the rated capacity shall be taken as 1/2%

of the load per foot per minute of hoisting speed, but not less than 158 nor more than 50%, except for bucket and magnet cranes for which the impact value shall be taken as 50% of the rated capacity.

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RG&E DISPOSITION Since all three of our special lifting devices are operated only with the main hoist of the containment, overhead crane, which has a hoist speed of 3"/min., the following maximum impact load has been calculated:

Rated Capacity = 100 Tons Hoist Speed= 3 inches/minute Impact Allowance = I I = 1/2S (100 tons)/3 inches per minute I = 4000 or 2% (158 equals 30,000 lbs.)

Westinghouse has determined that the three special lifting devices analyzed are within the 3 and 5 strength factors for static loading. Based on this analysis, the nature of the crane used with these devices, and their actual impact allowance we have determined that pur special lifting devices conform to NUREG 0612.

ATTACHMENT 4 CRANE DESIGN CTMT OVERHEAD ITEM 1: LONGITUDINAL STIFFENERS FROM NUREG 0612 SECTION 5.1.1 (7)

The crane should be designed to meet the -applicable criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, "Overhead and Gantry, Cranes" and of CMAA-70, "Specifications for Electric Overhead Travelling Cranes." An alternative to a specification in ANSI B30.2 or CMAA-70 may be accepted in lieu of specific compliance if the intent of the specification is satisfied.

CRANE COMPARISON ANALYSIS RESULTS A comparison analysis was done on the containment overhead crane to determine its extent of compliance to CMAA-70. The longitudinal stiffeners are not located as specified in CMAA-70.

When two longitudinal stiffeners are used, they shall be located as stated in Section 3.3.3.1.$ .2 of CMAA-70. Each shall have a moment of inertia of 2407 in. (calculated) the existing moments of .inertia are .68 in. as stated in the "Whiting" crane comparison analysis.

TECHNICAL EVALUATION REPORT COMMENTS Although not in verbatim compliance, with CMAA-70 requirements concerning location and moment, of inertia, the use of longitudinal stiffeners, in the containment, building crane is judged to meet the intent of this guideline. Longitudinal stiffeners are used, in conjunction with transverse stiffeners or diaphragms, to allow the use of thin web plates (i.e., web plates with large h/t ratios where h = web depth, and = web t thickness.) CMAA-70 allows for h/t ratios of up to 188 for girders with no longitudinal stiffener, and of up to 376 for girders with a single longitudinal stiffener. Were such a single stiffener used, in the Ginna containment crane, a moment of inertia about the web face of approximately 1.8 in. would be required. The Ginna design employs two longitudinal stjffeners, each with a moment of inertia of approximately 0.46 in. about the web face, in conjunction with a web h/t ratio of 236.

Although judged to meet the intent of this guideline, the Licensee should provide suitable documentation to justify the location and moment of inertia of the installed stiffeners.

RGScE DISPOSITION The location of the installed stiffeners in the containment building crane are shown on a Westinghouse Shop Drawing, U-55964 which is a permanent RGB record; (See attached sketch for stiffener location).

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Calculations for the moment of inertia of the stiffeners are shown on pages 15 and 16 of the Whiting Comparison Report.

(February 1, 1982 submittal, Attachment 5).

The crane girder was designed under EOCI-Cl specifications using sound engineering practices. There is simply'o indication that the crane is in jeopardy of structural failure or any overstress due to the location and size of the existing longitudinal stiffeners.

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PAGE of EVVR No DATE 42 ~ 60 REV. 2/77

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