ML20062E337
| ML20062E337 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/24/1978 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Shalla L OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 7812060264 | |
| Download: ML20062E337 (1) | |
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UNITED STATES o
'o NUCLEAR REGULATORY COMMISSION LPDR REGION IV TIC
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E 611 RYAN PLAZA ORIVE, SUITE 1eco NSIC AR LINGTCN, TEXAS 76011
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November 24, 1978 Docket No. 50-285 Omaha Public Power District ATTN: Mr. L. C. Shalla Group Manager, Operations 1623 Harney Street Omaha, Nebraska 68102 Gentlemen:
Enclosed is a supplement (IE Bulletin f.o.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facility with an operating license or a construction pennit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, W
4<
Karl V. Seyfrit Director
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 7 819 0 g a c p f k
t UNITED STATES NUCLEAR REGULATORY C0 GtISSION OFFICE OF INSPECTION AND ENFORCEMENT UASHINGTON, D.C.
20555 IE Bulletin No.78-12A Date: November 24, 1978 Page 1 of 2 ATYPICAL UELD MATERIAL IN REACTOR PRESSURE VESSEL MELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on Septcmber 29, 1978, 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 velds of twelve identified reactor pressure vassels. Use of the atypical weld naterial in vessel weldments causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure / tempera-ture operating limits.
Culletin 78-12 was issued for the purpose of verifying that similar atypical weld material was not also supplied to other vessel manufacturers and used in re3Ctor pressure vessel fabrication.
Reccgnizing that the scope of the record review required is extensive and time consuming, and to assure that responses provided are meaningful, the requirements of Sulletin 78-12 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 material 1/:
1/ ine ts/sTve nuclifr7nTfs identified as having possible atypical pressure vessel weldrents are: Three Mile Island Unit Nos. I and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Uni t No. 3, Rancho Seco Unit No.1, Midland Unit No.1, Quad Cities Unit No. 2, ?rtans Ferry Unit No. 1, Turkey Point Unit No. 4 and Zion Unit Nn. I a d 2.
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I IE Bulletin No.78-12A Date: November 24, 1978 Page 2 of 2 1.
Provide all infornation available on weld naterials used for each reactor vessel primary boundary ferritic weluz.ent. 2/ (Items ic, Id, 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.
j 2.
Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time.
(Last sentence of item 2c, f;ulletin 78-12. ) However, each licensee is required to verify that the weld materials information provided to the URC under item 1 does in fact cover each reactor vessel for which the licensee is responsible.
3.
Responses to item 1 above shall be submitted in writing within 120 days of the date of this Bulletin supplement.
Reports should be submitted to the Director cf the appropriate NRC Regional Of fice and a copy should be f orwarded to the U.S. Nuclear Regulatory Commis; ion, Office of Inspection and Enforcement, Division of Reactor Construction Inspection, '.lashington, D.C.
20555.
Approved by GAO, B180225 (R3072); clearance expires 7/31/80. Approval was given under a blanket cleac3 ace specifically for identified generic problems.
- t 2/ Welo material informatico submitted will be evaluated by NRC. Requests for furth3r information will be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following these evaluations.
i IE Bulletin f o.78-12A Date: November 24, 1978 LISTING 0F IE BULLETINS ISSUED Ifi 1978 Bulletin Subject Date Issued Issued To Go.
70-01 F13 arable Contact 1/16/78 All Pcwer Reactor Arn Retainers in G.E.
Facilities with an CR120A Relays Operating License (OL) or Construc-tion Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an Operating License (0L) or Construc-tion Permit (CP) 78-03 Potential Explosive 2/8/78 All BWR Pcwer Gas Mixture Accumula-Reactor Facilities tions Associated with with an Operating BWR Offgas System License (OL) or Operations Construction Permit (CP) 73-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem tounted Limit Operating License Switches Inside (0L) or Construc-Reactor Containment tion Permit (CP) 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mair. ni s 1 - General (CL) er Ccnstruc-Electric Model tion Permit (CP)
CR105X 73-C$
Defective Cutler-5/31/78 All Power Reactor Har.rer, Type ti Relays Facilities with an With CC Coils Operating License (0L) or Construc-tion Permit (CP)
Enclosure Page 1 of 3
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-l IE Bulletin !:o.78-12A Date: NovemSer 24, 1978 73-07 Protection Afforded 6/12/73 All Power Reactor l
by Air-Line Facilities with an j
nespirators and Operating License (OL) and Supplied-Air all class C and F j
Hoods Research Reactors with an OL, all Fuel
)
Cycle Facilities with an OL, and all Priority 1 Material Licenseas t
78-0J Radiation Levels from C/12/73 All Power and j
Fuel Element Transfer Research Reactor i
Tubes I
Facilities with a Fuel Element Trans-1 fer Tube and an Operating License (0L) 1 78-09 BUR Drywell Leakage 6/14/78 All BWR Power i
Paths Associated with Reactor Facilities
]
Inadequate Drywell with an Operating Closures License (OL) or Construction Per-mit (CP) 1 73-10 Ce rge.i-Pa te rson 6/27/78 All BUR Power Hydraulic Shock Reactor Facilities i
Suppressor Accumulator with an Operating Soring Coils License (0L) or Construction Per-mit (CP) 7S-11 Examination of Mark i 7/21/78 BWR Power Reactor Cantiinrent Torus Facilities for 2
helJs action: Peach Botton 2 and 3, Quad Cities 1 and
- 2. Hatch 1 Monti-cello and Vennent Yankee
)
Enclosure Page 2 of 3
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November 24, 1978 73-12 Atypical '.-l eld Miterial 9/26/78 All Power Reactor j
in Reactor Pressure Facilities with an j
Vessel ;;elJ:
Operating License i
(0L) or Construc-i i
tion Permit (CP) l l'
78-13 Failures in Source 10/27/78 All General and
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I Enclosura l
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