ML20214R377
| ML20214R377 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/21/1986 |
| From: | Guzman G MEXICO, GOVT. OF |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20214R357 | List: |
| References | |
| RTR-NUREG-0797, RTR-NUREG-797 NUDOCS 8612050447 | |
| Download: ML20214R377 (4) | |
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instituto nacional de investigaciones nucleares OhTOBER 21,1986.
L I
HEAD OF THE DIVISION OF LICENSING OFFICE OF NUCLEAR REGULATION U.S. NUCLEAR REGULATORY COMMISSION, WA'SHINGTON,'D.C. 20555 U.S.A.
TO WHOM IT MAY CONCERN:
WITH RESPECT TO THE U.S. REGULATORY ACTION FOR THE COMAN-CHE PEAK PROJECT BASED ON THE FINAL SAFETY ANALYSIS. REPORT
( NUREG-0797-SUPPL.9, MARCH 1985 ) TO ELIMINATE THE COMMITMENT THAT C0ATINGS INSIDE THE CONTAINMENT BUILDING BE QUALIFIED.FOR UNITS 1 AND 2, I WOULD LIKE TO ASK THE FOLLOWING QUESTIONS i.
1.
SHOULD THE STAFFS OF THE NRC AND TUEC HAVE NOT TAKEN INTO ACCOUNT THE APPROVAL OR OPINION OF THE ASTM COMMITTEE D-1 AND D-33 ?
2.
SHOULD " THE COST OF SAFETY RELATED C0ATED SYSTEMS AND THE REDUCE LEVEL OF THE NEW PLANT CONSTRUCTION AND THEREFORE ORDERS FOR C0ATING BE AN IMPORTANT OR DECISIVE FACTOR IN -
LOWERING OR NOT USING THE C0ATING QUALIFICATION STANDARDS AND THEREFORE THE QUALITY ASSURANCE PROGRAM" ?
~
3.
WOULD YOU CONSIDER THAT A THEORETICAL ANALYSIS OF WHAT IS OR IS NOT LIKELY TO HAPPEN DUE TO PAINT DEBRIS INSIDE THE NUCLEAR POWER STATION, CAN SUBSTITUTE FOR ACTUAL TESTING DR OK 5
5
.2-instituto nacional de investigaciones nucleares 0F BLOCKAGE IN SUMPS OR FLOW PASSAGES DURING A DBA AND POST-DBA CONDITIONS ?
4.
SHOULD THE CONTAMINATION AND DECONTAMINATION OF A C0ATING FROM FISSION PRODUCTS, NOT BE CONSIDERED AS PART OF NUCLEAR SAFETY AND THEREFORE FOR QUALITY ASSURANCE PROGRAM AND QUALIFICATION TESTS ?
5.
SHOULD NUCLEAR PLANT MANAGEMENT BE WELL ADVISED TO FOLLOW
" THE PATTERN USED AT COMANCHE PEAK.TO EVALUATE THE~ SAFETY SIGNIFICANCE.0F CONTAINMENT FAILURE.." ?
i 6.
DOES THE DIVISION OF LICENSING OF THE US NRC CONSIDER THAT
[
A C0ATING IS SUFFICIENTLY QUALIFIED UPON COMPLYING ONLY i
WITH THE REQUIREMENTS OF THE REGULATORY GUIDE NRC RG 1,54 AND THE STANDARD ANSI 101.2 ?.
WHAT IMPORTANCE SHOULD BE GIVEN TO ELEMENT UNMENTIONED IN 4
THE AB0VE SUCH AS THE FOLLOWING :
6.1 MANUAL OF C0ATING WORK FOR LIGHT-WATER NUCLEAR POWER PLANT PRIMARY CONTAINMENT AND OTHER - RELATED FACILITIES ASTM, 1979.
j.
6.2 GUIDE FOR SELECTION OF IESTING COATINGS USED IN LIGHT WATER NUCLEAR POWER PLANTS, ASTM D 3842 - 80 4
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instituto nacional de investigaciones nucleares G&&
6.3 AGEING :
6.3.1 LIGHT AND TEMPERATURE : ASTM D 822-60 6.3.2 WEAR AND MECHANICAL STRESS ASTM G 14-77 FTMS 141 6.3.3 GAMMA RADIATION, ANSI N 512-74 6.3.4 CHEMICAL RESISTANCE OF COATINGS USED IN LIGHT WATER NUCLEAR POWER PLANTS, ASTM D 3912-80.
6.4 DBA 6.4.1 RADIATION IEST : ANSI N 512-74 6.4.2 STEAM IEST: ' EVALUATING COATINGS USED IN LIGHT WATER NUCLEAR POWER PLANTS AT SIMULATED TOSS OF COOLANT ACCIDENT ( LOCA ) CONDITIONS" ASTM D 3911 - 80.
6.5 POST-DBA 6.5.1 "ETERMINATION OF THE DECONTAMINABILITY OF COATINGS USED IN LIGHT-WATER NUCLEAR POWER PLANTS" ASTM D 4256, 7.
SHOULD SEQUENCE OF THE TESTS MENTIONED ABOVE " FOLLOW A SPECIFIC PATTERN ?
8.
WHEN DO YOU CONSIDER THf.T A C0ATING IS OUALIFIED AND WHEN IT IS NOT NECESSARY. ?
,.. ~
instituto nacional de investigaciones nucleares 9.
WHAT.IS THE PROCEDURE OR THE REQUIREMENTS TO UPDATE THE.
REGULATORY GUIDE NRC RG 1.5f4.?
WHILE PERHAPS, THE STUDIES CARRIED OUT AT THE COMANCHE i
PEAK, HAVING BEEN CONVINCINGLY JUSTIFIED IN THEIR PARTICULAR i
CIRCUNSTANCES, HERE, WHERE NUCLEAR ENERGY IS JUST BEING INITIATED, THEY HAVE PROV0KED GREAT CONFUSION, DOUBTS AND CONTROVERSY-ABOUT THE IMPORTANCES OF QUALITY ASSURANCE AND EQUIPMENT -AND MATERI AL QUALIFICATION -FOR A NUCLEAR POWER STATION FOR THAT REASON I WOULD GREATLY' APPRECIATE AN ANSWER TO THIS LETTER.
IN AUGUST 1986 I DIRECTED FSSENTIALLY THE SAME INQUIRY TO MR VINCENT S. N0ONAN WHO I NOW UNDERSTAND WAS NOT THE PERSON TO WHOM THE LETTER SHOULD HAVE BEEN SENT.
HOPING TO RECEIVE YOUR KIND CONSIDERATION TO MY INQUIRY AT AN EARLY DATE.
SINCE3EL-Y YOIJRS7 UI RMO 4N GERE CI A DE MATERIALES COPY TO :
- ASTM COMMITTEE D-1 AND D-33:
AMERICAN SOCIETY FOR TESTING AND MATERI ALS,1916 RACE ST., PHILADELPHI A, PA.19103, U.S. A.
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