Document dan6Evq4Mdx5OMBKrEp0eBX8R

< (conoco) Interoffice Communication To Distribution From J. H. McCulley, Jr. Data May 7, 1982 Subject EPA VCM Standard Information Exchange Meeting A PVC plant VCM standard information exchange meeting will be held in Aberdeen on Friday, May H. The meeting agenda is attached. You will note that the agenda seems impossibly long. Hopefully a number of the items listed can be covered quickly. It is important to cover all the items under the relief discharge prevention heading. If necessary, some of the items may best be resolved in another meeting. Chief Process Engineer Chemicals Division Process Engineering Department pjc Enc CC: JF:CRM:PEM:RAF(2):SJV RAC:AWS:JPW:JH:JL:RJR File P--47-2 DTH 000070893 EPA VCM STANDARD INFORMATION EXCHANGE MEETING Objectives: 1. Discuss prevention of VCM relief discharges. 2. Discuss controls in other areas of the standard as time permits. 3. Share information. To this end I am designating a plant to take the lead in discussing their controls in each area. The other plant's representative would then discuss their differences, if any. Meeting Date: May 14, 8:00 a.m. at Aberdeen PROPOSED AGENDA Relief Discharge Prevention 8:00- 9:30 V/fl --&QF ABD A. Rupture Discs 1. Review recent history of premature failures and suspected causes. PED 2. Potential causes for premature disc failure. ABD 3. Ordering specifications. , 15,1 -4. Preinstallation testing and inspection. ^ X 5. Installation--procedures, daskei\, tail pipe support. 6. Post installation testing--hydro test, visual. 7. Testing after removal and review of recent results. 8.VPlan for analyzing discs that fail prematurely. 9. BS&B's new Energy Absorbing Disc 10. Future testing plans. t/3 ****** DTH 000070894 Proposed Agenda Page 2 Relief Discharge Prevention (Continued) 9:30-10:15 B. Relief Valves PED 1. Potential causes for valve opening below set pressure or remaining open too long. a <TPiV V^ Cjreu abd abd abd 2. Reactor relief valve relief experiences. 3. Installation. A. Testing. 10:15-11:30 C. Process Upsets that can Cause a Relief Discharge OKC I (L/e/n OKC y 1. Known causes. 2. Controls for preventing each cause. PED \/ BM ABD 3. Proposed additional controls. k. Status of and plans for reactor level alarm study. 11:30- 1:00 D. Emergency Killing okc tfcnx l. Experience with AMS system including fouling of top head port. 2. Experience with NO system. p/y] 3. AMS quality control. k. Testing emergency kill system. OKC - p6/*1 pem `jtB./y) ABD E. Emergency Procedures l. Power failure. 2. Loss of instrument air. OKC fW ^ Q. Rfn ABD &y\ ABD OKC 0AM ABD F**1 3- Loss of agitation. k. Loss of cooling. 5. Fire. 6. Severe weather. DTH OOOC 7. Manual venting of a reactor to the atmosphere. ABD 8. Equalization between reactors. Proposed Agenda Page 3 I. Relief Discharge Prevention (Continued) F. Auxiliary Systems 1. Backup power. 2. Backup instrument air. 3. Backup cooling water. G. Training 1. Operators--emergency response. OKC 2. Rupture discs--mechanics. OKC RApfow 3. VCM standard in general. 3:45- 4:00 H. Incident Investigation PED OKC PED 4:00- 5:00 1. Immediate--Try to find out what really happened, accurate calculations.--=> ^^ /*rv- S'* i 2. Dejayed--Importance of good filing system. ^-- p<jr{.s . <= <- (Z,V>^-- COf><^ / aJ /z^>.Jrfc,4 3. Guidelines for making and evaluating suggest ions y~D --(yu P >JC\ 7-C- f 11 Other I terns ; /t, /^> 77" g_* A. Sampling Reactor Slurry ^ T-IS- TfSSl >S3 A} B. vjf Q VCM Valve Leakage Pump Seals l^tr d. Incinerator Operation j fZ <0 Aj > <3-0 /^-r \J A--z-~'S<Z_j% --- i//^" Z'fe-JS 7" oCrL- i f~rt 'S&- /hRsz. $T^ c y-//z^r3 (/. <3 A~g?xbr--;J<'^'-r , r*J<.'Z.. <Z- St y AiAA^r TTWii, *** ci 7-y*r+J ^co,? DTH 000070896