Rev 0 to Technical Note 51187, Procedures for Repairing Prefabricated Panel & Preshaped Conduit Section Fire Barriers Installed at PlantML20076H283 |
Person / Time |
---|
Site: |
Turkey Point ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
---|
Issue date: |
05/31/1987 |
---|
From: |
THERMAL SCIENCE, INC. |
---|
To: |
|
---|
Shared Package |
---|
ML20076E803 |
List: |
---|
References |
---|
FOIA-93-230 51187, NUDOCS 9410210143 |
Download: ML20076H283 (7) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17352A3821993-12-28028 December 1993 Third Ten-Yr ISI Interval IST Program for Pumps & Valves. ML17353A7621992-12-28028 December 1992 Pre-fire Plan Guidelines & Safe Shutdown Manual Actions. ML17349A7491992-12-0808 December 1992 Revised Odcm. ML17349A3711992-05-21021 May 1992 Rev 10 to Procedure PT-51-WS, Solidification Process Control Procedure. ML17349A2511992-03-27027 March 1992 Rev 0 to Pc/M 91-128, 480 Volt Undervoltage Protection Scheme Mod for Unit 3 ML17348B4121991-10-22022 October 1991 Health Physics Procedure 0-HPS-042.8, Dewatering Controls for Radwaste Liners. ML17348A2801990-05-31031 May 1990 Rev 1 to Emergency Power Sys Enhancement Project Testing Rept. ML17348A5381990-02-13013 February 1990 Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17347B4891989-12-18018 December 1989 Administrative Procedure AP 11550.92,Health Physics Procedure HP-92, Emergency Radiation Team Response - Offsite. W/891218 Ltr ML17347B3681989-10-0202 October 1989 Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves, Rev 2 ML17347B2851989-08-17017 August 1989 Change a to Rev 1 to JNS-PTN-200, Second Ten-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17347B2951989-03-21021 March 1989 Procedure 3-EOP-ECA-0.1, Turkey Point Nuclear Plant Unit 3 Loss of All AC Power. ML17348B4131988-03-10010 March 1988 Rev 8 to Procedure PT-51, Solidification Process Control Procedure. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17342A9971987-10-26026 October 1987 Procedure 0-ADM-019, Mgt on Shift. ML17342B0191987-10-24024 October 1987 Procedure 0-ADM-019, Mgt on Shift (Mos), Weekly Summary Rept for Wk Starting 871024 ML17342A8141987-07-24024 July 1987 Draft Revs to Procedures Generation Package. ML20076H2831987-05-31031 May 1987 Rev 0 to Technical Note 51187, Procedures for Repairing Prefabricated Panel & Preshaped Conduit Section Fire Barriers Installed at Plant ML17347A3081987-01-26026 January 1987 Emergency Procedure EP 20109, Criteria for & Conduct of Local Evacuations. ML17347A3071987-01-26026 January 1987 Emergency Procedure EP 20107, Fire/Explosion Emergencies. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17342A9111986-11-18018 November 1986 Off-Normal Operating Procedure 3208.1, Malfunction of RHR Sys. ML20215L8241986-09-23023 September 1986 RCS Pressure Boundary Check Valves 4-874A & B Leak Test, for Unit 4 ML20215L7031986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-3-750 &/Or MOV-3-751 Leak Test, for Unit 3 ML20215L7881986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 3 ML20215L7791986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-4-750 &/Or MOV-4-751 Leak Test, for Unit 4 ML20215L8001986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 4 ML20215L8191986-09-23023 September 1986 RCS Pressure Boundary Check Valves 3-874A & B Leak Test, for Unit 3 ML20076H4411985-11-0606 November 1985 Rev 4 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4491985-10-11011 October 1985 Rev 3 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Precedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4531985-09-20020 September 1985 Rev 2 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20199E4531985-08-23023 August 1985 Off-Normal Operating Procedure 9408.2, Energizing 4 Kv Buses Using Cranking Diesels Bus Tie Lines or Startup Transformer from Opposite Unit ML20199E4611985-08-23023 August 1985 Off-Normal Operating Procedure 7308.1, Malfunction of Auxiliary Feedwater Sys ML20199E4111985-08-22022 August 1985 Operating Procedure 7201.1, Standby Steam Generator Feedwater Sys - Operating Instructions. Related Info Encl ML20199E4321985-08-22022 August 1985 Off-Normal Operating Procedure 9408.3, Loss of Voltage to 'C' 4,160 Volt Bus ML20076H4611985-03-28028 March 1985 Rev 1 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4721985-03-15015 March 1985 Rev 0 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Powecorp,Turkey Point Npp ML17346A8291985-02-0404 February 1985 Procedures Generation Package. ML17346A6701984-12-31031 December 1984 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents. ML17346A5621984-09-26026 September 1984 Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation package.W/841001 Ltr ML17346A5391984-09-0101 September 1984 Emergency Plan Implementing Procedure 1107, Duties of Emergency Planning Supervisor,Offsite Emergency Organization. ML17346A5401984-09-0101 September 1984 Emergency Plan Implementing Procedure 1211, Activation & Use of Emergency News Ctr (Turkey Point),Offsite Emergency Organization. 1998-08-27
[Table view] |
Text
.
..:1.l" $ f APPENDIX III TO THERMAL SCIENCE, INC.'S RESPONSE TO THE UNITED STATES NUCLEAR REGULATORY COMMESION'S LETTER DATED 10 SEPTEMBER 1991 Enclosure 28 TSI Technical Note 51187 Procedures For Repairing Prefabricated Panel and Preshaped Conduit Section Fire Barriers Installed At The Turkey Point Nuclear Plant REV O May 1987 0.. , n 0 0 0 I N le l
9410210143 930830 )
PDR FOIA
, LAMBREC93-230 PDR
O a
TSI TECHNICAL NOTE 51187 PROCEDURES FOR REPAIRING PREFABRICATED PANEL AND PRESHAPED CONDUIT SECTION FIRE BARRIERS INSTALLED AT THE TURKEY POINT hTCLEAR PLANT I
l 1
i DATE OF ISSUE: 7 MAY 1987 l THERMAL SCIENCE, INC. + 2200 CASSENS DR.
- ST. LOUls. MO 63026 .(314)349-1233 Telex: Domestic 44-2384
- Oversecs 209901+ Telecopier (314 ) 349 1207
o
)
TS1 TECHNICAL NOTE 51187 PROCEDlfRES FOR REPAIRING PREFABRICATED PANEL AND PRESHAPED CONDUIT SECTION FIRE BARRIERS INSTALLED AT THE TURKEY POINT NUCLEAR PLAh'T INTRODUCTION These repair procedures set forth the sequential steps involved in making required sealing and drainage corrections ** the THERMO-LAG 330 Fire Barrier System Materials installed at Florida Power and Light Corporation's Turkey 4 Point Nuclear Power Generating Plant. These corrections are required to enhance the stability of the system when exposed to intensive rain, followed by direct exposure to heat by the sun.
The program of corrective action is fourfold. It involves removing water damaged fire barrier sections and replacing them with new sections. It involves 1) removing all defective caulking material and then resealing the seams and joints with the THERMO-LAG 260 Sealistic Rapid Curing Elasto=eric Caulk, 2) installing drainage holes everywhere that an inv,erse change occurs in the fire bctrier system and where ponding water is apt to occur, and 3) the removal of cracked, pinholed or otherwise damaged topcoat , and then applying a dual topcoat system comprised of an initial coat of the THERMO-LAG 350-2000 Topcoat, followed by a second coat of the THERMO-LAG 350-5000-10 Topcoat.
The following paragraphs highlight the detailed procedural steps involved in implementing these corrections to the fire barriers previously installed at Turkey Point Nuclear Power Generating Plant.
6 1.0 REMOVAL AND REPLACEMENT OF WATER DA'dAGED FIRE BARRIER SECTIONS 1.1 Procedure Description The repair of damaged sections of THERMO-LAC 330 Fire Barrier System Materials is accomplished by identifying and removing the damaged prefabricated panels and preshaped conduit sections, replacing them with new material, caulking the edges and joints, and applying a dual topcoat which is impermeable to water vapor.
1.2 Procedure Steps 1.2.1 Identify all fire barrier sections which show any abnormalities such as soft and spongy material, leaching, or other visual evidence of weathering effects. Use an indentation measurement of 150 mils obtained with a Chatillon Push Gauge set at 25 pounds to identify fire barrier sections which need to be removed.
1.2.2 Cut the tie wires or steel bands fastening the water damaged fire barrier sections together and remove the damaged material back to solid dry material.
1.2.3 Removal all foreign matter from the exposed substrate surfaces resulting from removing the damaged material.
1.2.4 Cut or form replacement sections from prefabricated panels or-preshaped conduit sections.
1.2.5 Mount the replacement sections in the spaces created by the removal of the water da= aged material, using approved stainless steel tie wire or stainless steel banding material. The recommended maximum spacing between the tire vires or steel banding should not exceed 12 inches.
2
, , - -- , , . , , a ,.,n,,. ,. 4 , - - . v-m. p
J 1.2.6 Fill in all edges and joints with a bead of THERMO-LAG 269 Sealistic Rapid Curing Elastomeric Caulk. The minimum cross-sectional thickness of the bead shall be 0.500 inches for a one hour fire barrier and 1.00 inches for a three hour fire barrier.
1.2.7 After the elastomeric caulk has hardened to touch, apply the THERMO-LAG 350-2000 Topcoat by brush or roller in multiple passes or criss-cross techniques, at a spread rate of 50 square feet per gallon.
1.2.8 After the THERMO-LAG 350-2000 Topcoat has hardened to touch, apply the THERMO-LAG 350-5000-10 Topcoat by brush or roller in multiple passes or criss-cross techniques, at a spread rate of 50 square feet per gallon.
2.0 REM 0 VAL AND REPLACEMENT OF Dr.FECTIVE CAULKING MATERIAL 2.1 Procedure Description The removal and replacement of defective caulking material is acco=plished by
- removing ali- caulking unterial that has cracked or receded from the edges or "
joints of the fire barriers and then resealing these edges and joints, using the THERMO-LAG 269 Sealistic Rapid Curing Elastomeric Caulk.
2.2 Procedure Steps 2.2.1 Remove all cracked or receding caulking material from the edges and joints of the fire barriers by means of cutting, scraping, and grinding methods.
2.2.2 Brush all foreign matter from the edges and joints.
3
e 4
3.2.2 Cut the tie wires and steel bands fastening the prefabricated panels or preshaped conduit sections together and remove the fire barrier from the raceway or structural steel entity.
3.2.3 Drill 1/2 inch holes at three (3) inch spacing along the bottom of all sections of the barrier where water may accumulate and pond.
3.2.4 Select the required number of 1/4 inch plastic tubes and butter them with the THERMO-LAG 330-1 Subliming Catalyzed Material - Trowel Grade.
3.2 5 Insert the plastic tubes in the drilled holes and tap them into place.
3.2.6 Reassemble the fire barrier sections using approved stainless steel tie wire or stainless steel banding material. The recommended maximu= spacing between the tie v!-e or steel banding should not exceed 12 inches.
3.2.7 Fill in the edges and joints with a bead of the THERMO-LAG 269 Sealistic Rapid Curing Elastomeric Caulk. The minimum cross-sectional thickness of the bea= shall be 0.500 inches for a one hour fire barrier and 1.00 inches for a three hour fire barrier.
3.2.8 After the elastomeric caulk has hardened to touch, apply the THERMO-LAG 350-2000 Topcoat by brush or roller in multiple passes or criss-cross techniques, at a spread rate of 50 square feet per gallon.
3.2.9 After the THERMO-LAG 350-2000 Topcoat has hardened to touch, apply the THERMO-LAG 350-5000-10 Topeoat by brush or roller in multiple passes or criss-cross techniques, at a spread rate of 50 square feet per gallon.
5
1 s 1 4.0 RDf0 VAL AND REPLACEMENT OF CRACKED OR OTHERWISE DAMAGED TOPCOAT 4.1 procedure Description The removal and replacement of cracked or otherwise damaged topcoat is accomplished by removing all defective topcoat by wire brushes or sanding, and then apply a dual topcoat system which is impermeable to water vapor.
4.2 procedure Steps 4.2.1 Visually inspect the existing topcoat for cracking, peeling and/or pinholes.
4.2.2 Remove any damaged topcoat by wire brushing or sanding methods.
4.2.3 Brush away all foreign matter.
4.2.4 Apply a coating of the THERMO-LAG 350-2000 Topcoat by brush or roller in multiple passes or criss-cross techniques, to replace the topcoat removed in Step 4.2.2, at a spread rate of 50 square feet per gallon.
n .m 4.2.5 After the THERMO-LAG 350-2000 Topcoat hat., hardened to touch, apply the THERMO-LAG 350-5000-10 Topcoat by brush or roller in multiple passes or criss-cross techniques, at a spread rate of 50 square feet per gallon.
I h
6 k
____ _ __