ML17206A539
| ML17206A539 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point, Saint Lucie  |
| Issue date: | 11/24/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Robert E. Uhrig FLORIDA POWER CORP. |
| References | |
| NUDOCS 7812040308 | |
| Download: ML17206A539 (6) | |
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Xn Reply Refer To:
RII:JPO 50-335j 50-389 50-250, 50-251 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTASTREET, N.IN.
ATLANTA,GEORGIA 30303 OWI NOV 34 g78 SS'7 Florida Power and Light Company Advanced Systems and Technology Attn:
Dr. R. E. Uhrig, Vice President P. 0.
Box 529100 Miami, Florida 33152 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facility(ies) with an operating license or a construction permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, mes P. O'Reilly D rector
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 VS>2040 SCZ
Florida Power and'ight Company cc w/encl:
N. Weems, Assistant QA Manager P. 0.
Box 128 Ft. Pierce, Florida 33450 C. M. Wethy, Plant Manager St. Lucie Plant P. 0.
Box 128 Ft. Pierce, Florida 33450 H. E. Yaeger, Plant Manager Turkey Point Plant P. 0.
Box 013100 9250 West Flagler Street Miami, Florida 33101
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 24, 1978 IE Bulletin No. 78-'12A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 3.978, and the two documents should be considered together.
Bulletin 78-12 described the use of weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels.
Use of the atypical weld material in vessel weldments causes them to have higher than normal nil-ductility transition temperature characteristics whi,ch. in turn requires more conservative pressure/tempera-ture operating limits.
Bulletin 78-3.2 was issued for the purpose of verifying that similar atypical weld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication.
Recognizing that the scope of the record review required is extensive and time consuming, and to assure that responses provided are meaningful, the requirements of Bulletin 78-3.2 are being modified.
Action To Be Taken By Licensees and Permit Holders For all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical weld materia11:
The twelve nuclear units identified as having possible atypical pressure vessel weldments are:
Three Mile Island Unit Nos.
1 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No. 1, Oconee Unit No. 3, Rancho Seco Unit No. 1, Midland Unit No. 1, Quad Cities Unit No. 2, Browns Ferry Unit No. 3., Turkey Point Unit No.
4 and Zion Unit Nos. 1 and 2.
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IE Bulletin No.78-12A November 24, 1978 1.
Provide all information available on weld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items lc, ld, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.)
This information may be provided to NRC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.
2.
Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time.
(Last sentence of Xtem 2c, Bulletin 78-Z2 ~
)
- However, each licensee is required
'o yerify that the weld materials information provided to the NRC under Item D.does in fact cover each reactor vessel for which the lj;censee is responsible.
3.
Responses to item 1 above shall be submitted in writing within
&20 days of the date of this Bulletin supplement.
Reports should
'be submitted to the Director of the appropriate NRC Regional Office and y, copy should be forwarded to the U.S. Nuclear Regulatory Coned,ssgon, Office of Inspection and Enforcement, Division of gepctor Construction Inspection, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic p'oblems.
2 Weld material information submitted will be evaluated by NRC.
Requests for further information will be dependent upon results of these evalua-tions.
Additfonal requests or instructions will be issued following these evaluations.
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November 24'978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject No.
Date Issued Issued To 78-Oz 78-O2 Flammable Contact-Arm Retainers in G.E.
CR120A Relays Terminal Block Qualification 1/Z6/78 1/30/78 All Pover Reactor Facilities with an OL or CP All Paver Reactor Facilities with an OL or CP 78-O3 78-O4 78-O5 78 O6 78-O7 Potential Explosive Gas Mixture Accumula-tions Associated with BWR Qffgas System Operations Environmental Quali-fication of Certain
/tern Mounted Limit Switches Inside Reactor Containment Malfunctioning of Circuit Breaker Auxi;lunary Contact gechanism-General Model CR105X Defective Cutler-
- Hammer, Type M Relays With DC Coils Protection afforded by Air-Line Respirators and Supplied-Air Hoods 2/8/78 2/21/78 4/Z4/78 5/31/78 6/32/78 All BWR Power Reactor Facilities with an OL or CP All Power Reactor
'Facilities vith an OL or CP All Power Reactor Facilities vith an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities vith an OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities vith an OL, and all Priority 3.
Material Licensees Enclosure 3.
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IE Bulletin No.78-12A November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject No.
Date Issued Issued To 78-08 Radiation Levels from
'Fuel Element Transfer Tubes 6/12/78 All Power and Research React or Facilities vith a Fuel Element transfer tube and an OL.
78 09 BWR Dryvell Leakage Paths Associated vith Xnadequate D~ell Closures 6/z4/78 All BWR Power Reactor Facilities with an OL or CP 78-3.0 Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coils Examination of Bark I Containment Torus Welds 6/27/78 7/21/78 All BWR Power Reactor Facilities with an OL or CP BWR Po~er Reactor Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee Atypical Weld Material 9/29/78
$n Reactqr Pressure gessel Welds Failures in Source Heads 30/27/78 of Kyy-Ray, Xnc,, Gauges Models 7050,
- 7050B, 7051 7051B, 7060, 7060B, 7061 and 7061B All Power Reactor Facilities vith an OL or CP All General and Specific Licensees with Key-Rey Gauges Enclosure
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