ML20141K778
| ML20141K778 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 05/22/1997 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | NRC |
| References | |
| REF-PT21-97-401 NUDOCS 9705300006 | |
| Download: ML20141K778 (3) | |
Text
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4 NRC Operations Center U. S. Nuclear Regulatory Commission Washington, D. C.
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l Attachment to Siemens Power Corooration 10 CFR Part 21 Report IFuel Cvele and Event Notification Worksheet) of May 22.1997 l
10 CFR 21 Notification of Defect in Critical Heat Flux (CHF) Data Base Range a
During NRC Engineering Inspection 9990081/97-01, the NRC determined that the CHF data base for the ATRIUM
-9 fuel design and other 9x9 fuel designs with internal water cnannels was not extensive enough to adequately estimate the 4
uncertainties for the additive constants used in SPC's CHF correlation. A statistical 4
4 treatment of the existing relevant CHF data was developed to estimate the l
uncertainties beyond the original CHF data ranges. These estimated uncertainties
)
are larger than the original additive constant uncertainties. Revised safety limit calculations with the larger additive constant uncertainties indicate that certain plants may have operated with incorrect safety limits.
The affected licensees have been informed of the increase in additive constant uncertainties and of the possibility that previously calculated safety limits may have been impacted by the larger uncertainties. Safety limit calculations for current reactors with ATRIUMm-9 fuel design and other 9x9 fuel designs with internal water channels have been performed with the inclusion of projected higher additive constant uncertainties.
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FUEL CYCLE FACILITY EVENT NUMBER:
32379 FACILITY: SIEMENS POWER CORPORATION NOTIFICATION DATE: 05/22/97 RXTYPE: URANIUM FUEL FABRICATION NOTIFICATION TIME: 17:13 [ET]
COMMENTS: LEU CONVERSION (UF6 to UO2)
EVENT DATE:
05/22/97 FABRICATION & SCRAP RECOVERY EVENT TIME:
00:00[PDT]
COMMERICAL LWR FUEL LAST UPDATE DATE:
05/22/97 CITY: RICHLAND REGION: 4 COUNTY: BENTON STATE: WA NOTIFICATIONS LICENSE #: SNM-1227 AGREEMENT: Y DOCKET: 07001257 NRC NOTIFIED BY:
L. MAAS RAMSEY NMSS j
j HQ OPS OFFICER:
BOB STRANSKY HODGE NRR 3
EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:
CDEG 21.21(c) (3) (i)
DEFECTS / NONCOMPLIANCE
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i j
j EVENT TEXT CRITICAL HEAT FLUX DATABASE USED FOR 9x9 FUEL DESIGNS DOES NOT ADEQUATELY ESTIMATE UNCERTAINTIES.
THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE VENDOR:
"DURING NRC ENGINEERING INSPECTION 9990081/97-01, THE NRC DETERMINED THAT THE CHF [ CRITICAL HEAT FLUX] DATA BASE FOR THE ATRIUM-9 (TM) FUEL DESIGN AND OTHER 9x9 FUEL T'* TONS WITH INTERNAL WA'ER CHANNELS WAS NOT EXTENSIVE ENOUGH TO ADEQUATELY ESTIMATE THE UNCERTAINTIES FOR THE ADDITIVE CONSTANTS USED IN SPC's CHF CORRELATION. A STATISTICAL TREATMENT OF THE EXISTING RELEVANT CHF DATA WAS DEVELOPED TO ESTIMATE THE UNCERTAINTIES BEYOND THE ORIGINAL CHF DATA RANGES. THESE ESTIMATED UNCERTAINTIES ARE LARGER THAN THE ORIGINAL ADDITIVE CONSTANT UNCERTAINTIES. REVISED SAFETY LIMIT CALCULATIONS WITH THE LARGER ADDIf1Vs CONSTANT UNCERTAINTIES INDICATE THAT CERTAIN PLANTS MAY HAVE OPERATED WITH INCORRECT SAFETY LIMITS.
THE AFFECTED LICENSEES HAVE BEEN INFORMED OF THE INCREASE IN ADDITIVE CONSTANT UNCERTAINTIES AND OF THE POSSIBLITY THAT PREVIOUSLY CALCULATED SAFETY LIMITS MAY HAVE BEEN IMPACTED BY THE LARGER UNCERTAINTIES. SAFETY LIMIT CALCULATIONS FOR CURRENT REACTORS WITH ATRIUM-9 FUEL DESIGN AND OTHER I
9x9 FUEL DESIGNS WITH INTERNAL WATER CHANNELS HAVE BEEN PERFORMED WITH THE i
INCLUSION OF PROJECTED HIGHER ADDITIVE CONSTANT UNCERTAINTIES."
A LIST OF AFFECTED FACILITIES WAS NOT PROVIDED. THE VENDOR WILL CONTACT NRC REGION IV REGARDING THIS ISSUE.
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l My -Ny-97 13:37 P.O2 l r l
PAGE 1 OF 2
' NRC FOkW 361 A t
U S, NUCLE AR REGULATORY COMMISSION LICENSE NUMBER-i cm SNM-1227 FUEL CYCLE AND MATERIALS (NRC Docket EVENT NOTIFICATION WORKSHEET No. 70-1257)
R& PORT TWE FACILffY OR ORGAMZATION NAuJ CE CALLER CALLSACM TELEPtONE NLAd8EM j
Siemens Power Corp, - ND L. J. Flaas (iO9) 375-8537 fyEWV TWE EVENT DATI LOCADON OF EVENT ONCLUDE COLMTV AND 6 TATE)
PORTION OF PLANT AFpf CTEC N/A 3 /20 / 97 Richland, Benton County, 'fA N/A EVENT CLASSIFICATICHS EVENT TYPES INCOENT REPORTS (30 50,40 60,70.50) l GENERAL EME AGENCY
- X FUEL CYCLE V
- 20.2201 LOSS / THEFT (a)
E O SITE AAEA EMERGENCY ME0tCAL / ACADEMIC 20.2202 fvt IDI I'I
^"7NAT@
X AE AM ALEAT T RANSPORTATION 20 2202 g (b)(2)
" ^
ILU E NOTIFICATION OF DEF6.CT /
MEDICAL TREATMENT e
WAM GEMENT X
2@
l UNUSUAL EVENT NONCOMPLIANCE IDIII)
WITH CONTAMIN ATION X
INCIDENT REPORT INDUST AIAL / COMME AC1 AL 26 73 FITNESS FOR DUTY (b)(4) FIRE / EXPLOSION TRANSPOATATION EVENT FOREIGN EVENT 35.33 MISADMINISTRATION 70 52 C AITICAUTY / SNM LOST INFOAMATON ONLY OTHE A (Speesty) 36 83 IRA ADI ATOA EVENT 70 62 AC n / ATTEMPTED g py OTME A (SpeaM AUPTUAEO WELL CRITICALITY CONTROL + 4MOUR 3e 77 LOGGING SOURCE (BULLETIN 9141)
IRAETRIE'/ABLE WELL CRITICALITY CONTROL +24+OUR 3* II LOGGING SOUACE fBULLETIN 91-01) e NY UNDER OLD 1961 ORDER 40 26 OTHE A NON-CFA AECU'AEMENT T
ASTE OA YES NO 8
ANYTHING UNUSUAL OR YES MWew)
NRC REGION 7 l
X NOT UNOERST0001 X
NO STATE 7 OID ALL SYSTEMS FUNCTION y
AS REQUIRED 7 i
90 gg,ew e,en; OTHER GOVERNMENT AGENCIES 7 X
ADOITIONAL INFORMATION X
YES i
1 ON BACK7 (attached)
PRESS RELEASE 7
( X l
NO EVEMT oEscRIPTION (Consnue on separate sheet of necessary)
See attach:d summ.,j of defect in critical heat flux (CHF) data uase for specific SPC fuel designs. As noted, this issue was raised during an NRC inspection and has been fully communicated to impacted utility licensees.
NRC 80RM M A (t ulM)