Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: 05000344/LER-1978-020, Forwards LER 78-020/03X-3, 05000344/LER-1978-020-03, /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced, ML19207C007, ML19209A322, ML19209A323, ML19209A336, ML19209A363, ML19209A432, ML19209A435, ML19209B063, ML19209B180, ML19209B241, ML19209D051, ML19209D056, ML19225A294, ML19241A963, ML19241A969, ML19241C194, ML19242B129, ML19242B972, ML19247B146, ML19248C628, ML19248C934, ML19249D678, ML19250C450, ML19253C727, ML19254D131, ML19254F178, ML19256F544, ML19256F546, ML19256F990, ML19256F993, ML19260C591, ML19261A687, ML19261D547, ML19261D820, ML19263E970, ML19267A290, ML19267A296, ML19269D190, ML19270E836, ML19270G402, ML19270H454, ML19271A997, ML19275A272, ML19282A785, ML19289C608, ML19289F192, ML19290C976, ML19294B198... further results
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MONTHYEARML19209A3631974-02-25025 February 1974 Burn Tests on Silastic Rubber-Coated Glass Drop Cloths. Prof Qualifications of Ew Edwards Encl Project stage: Other ML19256F5461974-06-30030 June 1974 Miscellaneous Paper C-74-12,Pullout Resistance of Reinforcing Bars Embedded in Hardened Concrete, Prepared by Engineer Waterways Experiment Station Project stage: Other ML20195C3451978-04-28028 April 1978 Informs That Structure of Walls in Control Bldg Does Not Meet Seismic Criteria for Sar.Reanalysis Confirms Control Bldg Will Maintain Structural Integrity & Plant Will Retain Functional Capability Under Design Loads Project stage: Other ML20195C3641978-05-26026 May 1978 Clarifies Items 2 & 3 of DG Eisenhut 780502 Memo Re Proposed Mod to Plant Spent Fuel Storage Rack Proceedings.Design Engineer Activities in Fuel Bldg Design Should Be Considered Supporting Role Project stage: Other ML18004B9711978-06-0202 June 1978 Addresses Pipe Support Base Plate Problem.Discusses Review of Support Redesigns & Capability of Anchor Bolts to Withstand Cyclic Loadings Project stage: Approval ML20195C3511978-06-29029 June 1978 Forwards Affidavits of CM Trammell & LC Shao Re Safety Significance of Control Bldg Design Deficiencies & NRC Findings Concerning Significant Hazards Considerations Project stage: Other ML20195C3851978-06-29029 June 1978 Affidavit of Chales M. Trammel,Iii.* Staff Concluded That an Amendment Authorizing Operation of Trojan Nuclear Power Plant Pending Upgrading of Seismic Capability of Control Bldg Walls Would Constitute a Decrease in Safety Margin Project stage: Other ML20195C4001978-06-29029 June 1978 Affidavit of LC Shao Re Control Bldg Design Errors Resulting in Substantially Weaker Walls than Intended by Original Design criteria.As-built Structure Has one-half of Seismic Capacity & Safety Margin Project stage: Other ML20195C3741978-06-30030 June 1978 Forwards Proposed Schedule of Actions to Bring Plant Control Bldg Into Substantial Compliance Ww/Requirements & Intended Design Margins.Detailed Description of Actions,Design Changes & Mods Will Be Submitted Prior to 780901.W/o Encl Project stage: Other 05000344/LER-1978-020-03, /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced1978-07-21021 July 1978 /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced Project stage: Other ML20195C4581978-08-19019 August 1978 Forwards NRC Questions & Licensee Responses,780804-17 Based on Info Provided by Bechtel Re Control Bldg.All Walls Except 1B,2 & 3 Have Dowel Capacities Exceeding Shear Capacities Controlled by Either Shear or Bending Project stage: Other ML20195C4621978-08-21021 August 1978 Forwards Final NRC Responses to Questions 6 & 10 Re Control Bldg Mods,Based on Info Provided by Bechtel.Equipment in Structure Should Continue to Be Capable of Resisting Seismic Loadings Resulting from Real Earthquakes Project stage: Other ML20195C5331978-08-22022 August 1978 Responds to Re Amendment Permitting Temporary Operation of Plant Independent of Public Hearing.Law Requires Hearing to Be Held in Connection W/Amend to OL Project stage: Other ML20150A6081978-08-30030 August 1978 Forwards Request for Addl Info Re Control Bldg Per Seismic Nonconformance Project stage: RAI ML20150A6141978-09-0101 September 1978 Forwards Preliminary Results of Stardyne Finite Element Analysis of Trojan Control-Auxiliary-Fuel Bldg Complex & Assessment of Seismic Load Resistance of Bldg as Presented at 780828 Meeting. Lic. NPF-1 Project stage: Meeting ML20195C1431978-09-0707 September 1978 Responds to Commissioner Davis Addressed to Commissioner Bradford & Expressing Concerns Re non-conformance to Specs of Control Bldg at Plant & Effect of Facility Shutdown on Rate Payers Project stage: Other ML20147C2411978-09-12012 September 1978 Forwards Corrected Supplementary Info Transmitted by Ltr Project stage: Supplement ML20150A6441978-09-20020 September 1978 Forwards Final Results of Rev & Evaluation of Recent Stardyne Finite Element Analysis for Existing Control Bldg of Subj Facil.Suppl Structural Evaluation Response to Specified SSE Event,& Response to Questions Encl Project stage: Other ML20150A6651978-09-20020 September 1978 Responds to Specified SSE Event.Stardyne Dynamic Analysis Was Used to Determine Structural Capacities & Forces. Concludes That Control Bldg Can Withstand SSE Event Safely Project stage: Other ML20150A6581978-09-21021 September 1978 Order Re Responses to NRC Interrogatories by Coalition for Safe Pwr & Consolidation.Cfsp Must:Respond W/In 14 Days to S1,S2,E1,G1,G2,G3,G8 & All Other Interrogatories;Clarify the Status of Spokesmen.Motion for Reconsideration Is Denied Project stage: Approval ML20062B9611978-09-28028 September 1978 Forwards 780628 Memo to R Mattson Re Info on Failures of safety-related Pipe Supports at Millstone 1 & Design Deficiencies on Similar Equipment at Shoreham.Aslb Notified of Pipe Support Base Plate Design Project stage: Approval ML20062A5471978-09-29029 September 1978 Notifies That Staff Is Unable to File Testimony on Interim Oper of Subj Facil Before 781013 Re Finite Element Analysis. Urges That ASLB Commence Hearing on 781018 or 781023 Project stage: Request ML20147E6401978-10-0303 October 1978 Transcript of SR Christensen Testimony Re Description of Seismic Instrumentation & Engineering Investigations to Be Conducted Following Earthquake Project stage: Other ML20147E6321978-10-0303 October 1978 Transcript of Dj Broehl Testimony Re Plant History, Chronology of Events Since Apr 1978 & Summary of Licensee Efforts to Ensure Safe Interim Operation of Control Bldg Project stage: Other ML20148A0601978-10-0606 October 1978 Direct Testimony of Harold Laursen Re Assignment to Eval Ability of Subj Facil Bldg Shear Walls to Resist Seismic Loading.Determined Shear Walls Can Withstand .25g Safe Shutdown Earthquake Project stage: Other ML20062C1421978-10-11011 October 1978 Notice of Evidentiary Hearing on Issue of Interim Operation & Limited Appearance.Hearing to Determine Whether Interim Operation Should Be Permitted Prior to Mods Required by Order Will Be Held on 781023 & 1030-1101 Project stage: Other ML20148C0251978-10-13013 October 1978 Responds to NRC 781011-13 Questions Re Supplemental Structural Evaluation of Control Bldg,Particularly Shear Wall Capacity.Certificate of Svc Encl Project stage: Supplement ML20062B2751978-10-13013 October 1978 Forwards Ks Herring Testimony on Structural Adequacy of Trojan Control Bldg for Interim Operation & RT Dodds & Je Knight Testimony on Seismic Features Relevant to Facility Safety Project stage: Other ML20062B2791978-10-13013 October 1978 Testimony Verifying That Reasonable Assurance Exists That Shear Walls Will Withstand SSE or Obe.Original Intended Margins of Safety Reduced & Should Be Restored Project stage: Other ML20062B2821978-10-13013 October 1978 Testimony Describing Insp of Humboldt Bay Following 5.4 Richter Magnitude Earthquake on 750609 & Std Insp Procedures After Seismic Event.Procedures to Be Followed During Earthquake Detailed Project stage: Other ML20062B2861978-10-13013 October 1978 Testimony Responding to ASLB Questions Re Effects of Seismic Event on Plant Features Important to Maintaining Safety of Facility.Certificate of Svc Encl Project stage: Other ML20147F0961978-10-16016 October 1978 Licensees Testimony on Capability of Subj Facil to W/Stand Seismic Events.Statements of Qualifications,Ref & Append Are Attached.Description of Affected Structure & Deficiencies Such as Amount & Arrangement of Reinforcing Steel Provided Project stage: Other ML20147F0891978-10-16016 October 1978 Testimony of Bart Withers,As Superintendent of Subj Facil W/Statement of Qual Attached.Describes Capability of Plant to Function & Plant Staff to Respond Properly Immediately Following a Seismic Event Project stage: Other IR 05000344/19780201978-10-16016 October 1978 IE Inspec Rept 50-344/78-20 on 780905-29 During Which No Items of Noncompliance Were Noted.Major Areas Inspec Incl: Plant Opers,Maint,Surveillance Test,Facil Security & Licensee Event Followup Project stage: Request ML20062B4191978-10-16016 October 1978 Forwards Ks Herring Testimony Re Suppl to Stardyne Analysis & Effect on Structural Capacity of Control Bldg.Certificate of Svc Encl Project stage: Other ML20062B4251978-10-17017 October 1978 Testimony Re Suppl to Stardyne Analysis & Effect of Structural Capacity of Control Bldg.Structure Can Withstand SSE & Less Severe Obe,But Suppl Info Alters Earthquake Level Requiring Plant Insp Project stage: Other ML20062B9591978-10-19019 October 1978 Forwards Recent Memoranda Re Certain Problems Experienced in Connection W/Pipe Support Base Plate Design.Staff Determining If Problems Have Generic Implications for Operating Facilities.Aslb Will Be Kept Informed Project stage: Other ML20062C6271978-10-27027 October 1978 Forwards Further Response to NRC Staff Tech Questions Re Stardyne Analysis & Review.Includes Description of Criteria & Procedures Used & Explanation of Dev of New Acceleration time-history.Cert of Svc Encl Project stage: Other ML20062D3481978-11-0606 November 1978 Cross-examination or Testimony Re Analysis & Review by Licensee Poge of safety-related Matls in Control-Auxiliary- Fuel Bldg Complex Will Be Taken at 781211 Hearing.Nrc Given Time to Reply to Interrogs.Proposed Findings Due 781120 Project stage: Other ML20197D4801978-11-22022 November 1978 Forwards Suppl Documentation in Support of Floor Response Spectra Provided in 781027 & 781102 Responses to NRC Info Requests.W/Cert of Svc Encl Project stage: Other ML20197D4691978-11-22022 November 1978 Forwards Suppl Document Supporting Floor Response Spectra Provided in 781027 & 781102 Submittals to NRC in Response to Request for Additional Info Project stage: Request ML19305A0701978-12-11011 December 1978 Limited Appearance Statement by Rd Pollard of Ucs to Explain the Kind of Inquiry Possible,Yet Untapped,W/Respect to Any Person of Pollards Competence & Commitment in Field of Nuclear Plant Licensing Project stage: Other ML19305A0631978-12-18018 December 1978 Forwards Limited Appearance Statement by Rd Pollard of Ucs. W/Encls Project stage: Other ML19270E8361978-12-21021 December 1978 Partial Initial Decision Re Whether Operation of Facility Should Be Permitted in Spite of Identified Design Deficiencies in Control Bldg & Prior to Mod.Decision Is to Allow Interim Operation Project stage: Other ML19267A3021978-12-22022 December 1978 Notice of Issuance of Amend 35 License NPF-1 Project stage: Approval ML19267A2901978-12-22022 December 1978 Forwards Partial Initial Decision,Amend 35 to License NPF-1 & Notice of Issuance Project stage: Other ML19267A2961978-12-22022 December 1978 Amend 35 to License NPF-1.Modifies Waiver Portions of Tech Specs & FSAR Criteria Which Have Not Been Followed Due to Design Deficiency in Control Bldg Shear Walls Project stage: Other 05000344/LER-1978-020, Forwards LER 78-020/03X-31978-12-26026 December 1978 Forwards LER 78-020/03X-3 Project stage: Other ML19308A2121978-12-26026 December 1978 Reportable Occurrence on 780622: Piping Penetrations Not Designed to Be Solidly Grouted Were Found to Be Solidly Grounted.During Subsequent Design Review,Excessive Support or Pipe Stresses Found on 11 Isometrics. Probable DELETE-RO Project stage: Other ML20150F0221979-01-0303 January 1979 FOIA Request for 20 Documents Listed Re ECCS Performance Calculations & Calculational Errors Identified by Westinghouse & Portland GE, & on Pipe Cracks in Containment Vessel of Trojan Plant Project stage: Request 1978-04-28
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March 28, 1979 Trojan Nuclear Plant Docket 50-344 License h7T-1 Director of Nuclear Reactor Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Eir:
Attached are our responses, prepared by Bechtel Power Corporation, to the NRC Staff technical questions of G
March 8,1979, concerning the Trojan Control Building design modifications. We have forwarded 3 signed and 40 copies of this letter.
This letter and attachnent are being served on the Atomic Safety and Licensing Board (ASLB) and all parties to the Control Building proceeding.
Sincerely, X,
1 JWD 4,
g W. # _5TJ
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4.taa Vice President Engineering-Construction WJL/CAZ/4gah2A6 Attachment G
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5 RESPONSES TO NRC QUESTIONS DATED MARCH 8, 1979 9
1.
Describe the distance between the diesel fuel lines in the area to be excavated as described in Section 5.3.3 of PGE-1020.
The distance betvean the centerlines of the two diesel fuel lines in the area to be excavated is 1 f t 3 in.
2.
Describe the location of all shutof f and cross-connection valves in the fuel oil lines for the diesel generators.
The location of shutoff and cross-connection valves in the fuel oil lines for the diesel generators (shown on FSAR Figure 9.5-3) are as follows:
West Emergency Diesel Generator Room (Turbine Building)
Valve No Location D0005 9 ft vest of column line Y, D0007 12 in. off north wall D0011 at Elevation 47 f t 6 in.
MO-4903A D0017 4 ft east of column line Z, D0019 3 ft 6 in north of colu=n line 47 at Elevation 45 ft 6 in.
D0023 6 in. vest of column line X, 6 in. off north wall at Elevation 45 f t 6 in.
D0008 12 in. east of column line X, 6 in. off north wall at Elevation 49 ft.
D0025 5 f t 3 in. east of column line Z, D0027 9 f t 6 in. south of column line 47 at Elevation 47 f t 9 in.
D0029 10 ft east of column line X.
D0031 9 f t 6 in. south of column line 47 at Elevation 47 f t 9 in.
0 USM$7*
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t East' Emergency Diesel Generator Room (Turbine Building)
Valve No.
Location D0009 3 ft east of column line W',
6 in. off north wall at Elevation 49 f t.
D0010 3 f t east of column line W',
6 in. off north wall at Elevatlon 47 f t 6 in.
D0006 7 f t east of column line W',
6 in, off north wall at Elevation 47 f t.
N04903B 3 ft east of column line W',
3 ft off north wall at Elevation 47 f t 6 in.
D0018 7 ft east of column line W',
D0022 4 f t 6 in. of f north wall at Elevation 45 f t 5 in.
[
D0024 1 f t 3 in east of column line W',
~
D0026 9 ft 6 in. south of column line 47 i
at Elevation 47 f t 5 in.
D0030 4 f t east of column line T, D0028 9 f t 6 in. south of column line 47 at Elevation 47 f t 5 in.
i Vicinity of Stc, rage Tanks (Yard Area East of Fuel Building) i, l
Valve No.
Location D0001 D. O. Transfer punp A discharge l
D0003 109 ft east of column line A.
L 65 f t south r,f column line $5.
r P
D0002 D. O. Transfer pump B discharge D0004 125 f e east of column line A.
l 65 ft east of column line 55.
- t l
.}
s Diesel Auxiliary Feed Pump Room (Turbine Building) valve No.
I.ocation D0021 2 f t 5 in. south of column line 65, i
27 ft 9 in. east of column line S at Elevation 49 f t 5 in.
D0032 2 f t 5 in. south of column line 65, 24 ft 6 in. east of column line S at Elevation 49 f t 6 in.
D0033 4 ft 11 in. south of column line 65, 30 f t 5 in. east of column line S at Elevation 58 f t 4 in.
D0034 6 fe 6 in. south of column line 65, 26 ft east of column line S at Elevation 58 f t 4 in.
MO-4907A 3 ft 8 in. south of column line 65, 31 f t 5 in. east of column line S at Elevation 58 f t 4 in.
HO-4907B 5 ft south of column line 65, 26 i.e east of column line S e
at Elevation 58 f t 4 in.
3.
Identify and discuss the area and depth to be excavated by hand when uncovering diesel fuel lines.
The conventional backfill surrounding the diesel fuel lines will be removed by light hand tools, such as shovels, until sound rock is l
encountered.
If removal of any rock is required, light power tools vill be used.
4.
Describe measures to be taken to protect diesel f uel lines when hoisting steel plates and the fire protection measures to be taken in event of a line rupture by either hand tool damage or by drop-ping the steel plate.
The construction sequence is planned such that hoisting of the plates will not occur wSile the fuel lines are exposed. The excavation will be refilled and the concrete floor replaced before hoisting of the steel plate sections above this area is perforned. Thus, the fuel lines will be protected f rom any potential harm by approximately 5 ft of earth and the s a crete floor.
Hand-cperated chain hoists and the auxiliary hook of the overhead crane in the Turbine Building will be used to raise or lower plate sections into position.
pull redundancy will be provided for each lifting device needed (e.g., if two hoists are needed to lift a plate section, four hoists will be utill ed). _
1 The holsts and crane hook will have a safety factor of five times the required capacity.
In case of the failure of one hoist, the remaining hoisting device vill still have the capacity to carry the entire weight 0
of the plate sections and thus preclude their dropping.
The fire protection provided during the excavation around the diesel fuel oil lines and during other construction activities consists of administra-tive procedures, the permanent sprinkler system 'B' and hand-held fire extinguishers.
Should one of the lines be damaged, the amount of fuel oil vould be limited to that contained in the piping, thus, the combus-tion loading would be minimal. This section of piping is isolated f rom the fuel oil day tanks by normally closed, motor-operated valves and
]
check valves. Oil f rom the underground storage tanks is supplied through l
these sections of piping only during operation of a diesel oil transfer i
pump which will be controlled during excavation.
1 During the excavation around the fuel oil lines, a fire watch will I
be added that will remain at his station for at least 30 min af ter com-pletion of work to ensure that the pipes are not leaking. During the entire modification program, including excavation, local hand-held fire extinguishers will be provided in this area.
I i
5.
Describe the effect of dropping the steel plate on the duct banks
{
described in Sections 5.3.3 and 5.3.9.
khat protection is af forded against damage to safety-related cables?
As with the diesel fuel lines, the duct banks vill not be exposed during hoisting of the' plate sections since they are located below grade and vill be covered by backfill and.the concrete slab at grade.
6.
Describe measures to be taken to protect cables when hoisting plates above trays over to the guides as discussed in Section 5.3.11.
l l
The equipment that will be used to hoist the plates above trays sill l
be as described in the response to Question 4 The lower plates vill be secured in place first, thereby providing a lower limit stop to arrest downward motion of the upper plate section. Vertical steel guides af fixed to the lover plates will ensure that the upper sections will come to rest on the lower previously installed plate section.
Since the lower plate will arrest the downward motion of the upper plate, contact with the cable trays should not be possible.
7.
Describe measures to protect these cables f rom damage by the hoisting equipment.
The holsts will be installed above Elevation 93 ft.
The cables will be protected f rors the holsts by the floor sisb at Elevation 93 f t 0 in.
Guides will be installed to prevent any contact between the hoisting equipment and the cable trays.
t 8.
What equipment vill be used to raise / lower the plate (s) into position?
This equipment is described in the response to Question 4.
9.
As described in PGE-1012, "Trojan Nuclear Plant Fire Protection Review" (Page F-5), Plant safety procedure PS-7 requires that all immoveable combustible material below and within a 35-f e radius dere velding, cutting, grinding, or open flame work is performed be protected by asbestos curtains, metal guards or flame-proof covers.
In this regard, state the material composition of the protective blankets and velding screens discussed in Section 5.3.11 of PCE-1020.
The material is Claremont Weld Shield Style No. 800-24, manufactured by Claremont Company, Inc., 82 Camp Street, Meriden, Connecticut. or equivalent material. The material is described in Attachment 1.
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gn, 1,71 RESPONSES TO NRC STAFF i
TEQINICAL QUESTIONS DATED MARCH 8,1979 ATIAODDT 1
. PACE 1 of 2 Weld Fhield Fabrics Cla remont Weld Shictd fab'rics have been designed for difficult and demandin service conditions.
Under normal welding and acetylene cutting conditions Cla remont Weld Shield fabrics will give many times the use and wear itfe expticted of conventional welding cloth.
_ Con s t ruc tion Weld shield fabrics are made of special glass fabrics designed for high strength and flex resistance.
The incombustible cha racteristics of glass are then enhanced with a speelally enmpounded Neoprene coating.
The resulting fabric provides high abrasion resistance, tear snd puncture resistance, easy sewing and will shed molten metal splash in a good many applications.
Advanta ce s Most conventional fabrics used for welding or acetylene cutting protection can become quite flammable if contaminated with oils or grease, Weld Shield products do not readily absorb any liquid and surfaces can generally be wiped clean increasing the life and safety of the fabric.
in a fabrie make it clean to use-no lint or dust to contaminate immediate orTh adjacent a reas.
Feld shield fabrics a re lightweight and strong permitting easy sewing of curtains, pads and clothing.
Apnlications Prntection vf equipment, protection of personnel, flameproof curtains for eye protection (nf chippers, sanders and welders).
Weld Shield can be used to direct acetylene cutting drop to desired areas, all purpose protection during heavy construction where weldt:ig, cutting, abrasion and flame a re present.
Weld Shield fabrics can be used for Safety Clothing applications such as aprons, coats, shoulder patches, spats, pants, etc. based on the hazard and conditions, r
9
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DATE:
June 1-71 RESPONSES TO NRC STA F TECHNICAL QUESTIONS DATED MARCH 8, 1979 AITACHMENT 1 B ASE FABRIC DATA AG 2
Style Number 24 32 Dose Fab ric Cla s s W cave Glass Plain Ccnst. WXT Plain 19 x 10 W cht, o:/ yd, ",
2s : 10
- 8. 8 16.3 Std. Width 38"-50" 38" FINISHED FAB RIC PHYSICA LS Coating F. R. N eoprene F. R. Neopr ene Method FTMS 191 Cclo r Green #239 Green #239 Coating Deposit Balanced Finish B ala nc ed
.Te.nured T e.tu r ed Wght o:/yd.
22+2 3 2,+ 2 Thickne s s -Mils.
33-35 38-40 nsile: Warp 230 230 Fill 90 5102 280 Tea r:
Warp 15 5102 20 Fill 12 5970 20 5970 Finme Re sistance Flame out (s ec. )
.O to 2. O Max.
.O to 2. O M ax 5903 A f ter Clow (sec. )
.O to 2. O Ma.%
.O te2. O Max 5903 Char Length (in. )
1-2 1-2 5903 Roll SI::e s 50-100 yds.
50-100 yds.
F. O. B.
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