ML20217Q044
| ML20217Q044 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 03/06/1998 |
| From: | Passwater A UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-3761, NUDOCS 9803110328 | |
| Download: ML20217Q044 (7) | |
Text
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U baf/:ctric one Ameren Plaza 1901 Chouteau Avenue PO Box 66149 i
St. louis, MO 63166-6149
.m sir..tzr March 6, 1998 U.S. Nuclear Regulatory Commission A'ITN: Document Control Desk Mail Station PI-137 Washington, D.C. 20555 ULNRC-3761 Gentlemen:
MI/
DOCKET NUMBER 50-483 Dr/Aggfpff CALLAWAY PLANT UNION ELECTRIC COMPANY 10CFR50.46 ANNUAL REPORT-ECCS EVALUATION MODEL REVISIONS There are no reponable peak cladding temperature (PCT) changes or ECCS Evaluation Model revisions for Callaway during the time period from March 1997 to March 1998. Attachment 1 provides an ECCS Evaluation Model Margin Assessment which shows the same total PCTs (licensing basis PCTs plus margin allocations) as provided in Reference 11. References 1-11, listed below, include prior 10CFR50.46 repons.
Should you have any questions regarding this letter, please contact us.
Very tnily yours, l[l Alan C. Passwater Manager-Licensing & Fuels GGY/jdg Attachments
/
References:
- 1) ULNRC-2141 dated 1-19-90
- 7) ULNRC-3087 dated 10-19-94
- 2) ULNRC-2373 dated 2-28-91
- 8) ULNRC-3101 dated 11-23-94 l
- 3) ULNRC-2439 dated 7-19-91
- 9) ULNRC-3295 dated Il-22-95
- 4) ULNRC-2664 dated 7-16-92
- 10) ULNRC-3499 dated Il-27-96
- 5) ULNRC-2822 dated 7-15-93
- 11) ULNRC-3552 dated 3-21-97
- 6) ULNRC-2892 dated 10-22-93 l
9803110328 980306 P
PDR hlllllllllll0.lllh.ll0.lll*{lll.l PDR ADOCK 05000483 a subsibery of Amorea Corporation
cc:
M. H. Fletcher l
Professional Nuclear Consulting, Inc.
19041'Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive i
Suite 400
' Arlington, TX 76011-8064 l
Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 i
Barry C. Westreich (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 I
I
_J
ULNRC-374 i ATTACILMENT OXE ECCS EVALUATION MODEL MARGIN ASSESSMENT FOR CALLAWAY Page 1 of 5
LARGE BREAK LOCA A.
ANALYSIS OF RECORD PCT = 2014*F B.
1989 LOCA MODEL ASSESSMENTS
+ 10*F (refer to ULNRC-2141 dated 1-19-90)
C.
1990 LOCA MODEL ASSESSMENTS
+ 0*F (refer to ULNRC-2373 dated 2-28-91)
D.
1991 LOCA MODEL ASSESSMENTS
+ 10*F (refer to ULNRC-2439 dated 7-19-91)
E.
1992 LOCA MODEL ASSESSMENTS, MARGIN
+ 29'F ALLOCATIONS, AND SAFETY EVALUATIONS (refer to ULNRC-2664 dated 7-16-92 and ULNRC-2892 dated 10-22-93)
F.
1993 LOCA MODEL ASSESSMENTS.
- 65'F (refer to ULNRC-2822 dated 7-15-93 and ULNRC-2892 dated 10-22-93)
{
G.
1994 LOCA MODEL ASSESSMENTS
- 6*F (refer to ULNRC-3087 dated 10-19-94 and j
ULNRC-3101 dated 11-23-94)
H.
1995 LOCA MODEL ASSESSMENTS
+ 39'F (refer to ULNRC-3295 dated 11-22-95) j I.
1996 LOCA MODEL ASSESSMENTS
+ 0*F (refer to ULNRC-3499 dated 11-27-96)
J.
1997 LOCA MODEL ASSESSMENTS
+ 15*F (refer to ULNRC-3552 dated 3-21-97)
K.
CURRENT LOCA MODEL ASSESSMENTS -
+ 0*F MARCH 1998 LICENSING BASIS PCT + MARGIN ALLOCATIONS 2046*F
=
ABSOLUTE MAGNITUDE OF MARGIN ALLOCATIONS 0*F i
=
SINCE LAST LBLOCA 30-DAY REPORT (ULNRC-3552)
Page 2 of 5
SMALL BREAK LOCA A.
ANALYSIS OF RECORD PCT
= 1528'F B.
1989 LOCA MODEL ASSESSMENTS
+ 229'F (refer to ULNRC -2141 dated 1-19-90)
C.
1990 LOCA MODEL ASSESSMENTS
+ 0*F (refer to ULNRC-2373 dated 2-28-91)
D.
1991 LOCA MODEL ASSESSMENTS
+
0*F' (refer to ULNRC-2439 dated 7-19-91)
E.
1992 LOCA MODEL ASSESSMENTS AND SAFETY
+ 0*F EVALUATIONS (refer to ULNRC-2664 dated 7-16-92) 2 F.
1993 LOCA MODEL ASSESSMENTS 13*F (refer to ULNRC-2892 dated 10-22-93)
G.
1993 SAFETY EVALUATIONS
+
4*F' (refer to ULNRC-2822 dated 7-15-93)
H.
BURST AND BLOCKAGE /TIMEIN LIFE
+
0*F' (This PCT assessment is tracked separately since it will change depending on future margin allocations.)
4 I.
1994 LOCA MODEL ASSESSMENTS
- 282*F (refer to ULNRC-3087 dated 10-19-94 and ULNRC-3101 dated 11-23-94)
J.
1995 LOCA MODEL ASSESSMENTS
+ 0*F (refer to ULNRC-3295 dated 11-22-95) 4 Page 3 of 5
SMALL BREAK LOCA (cont.)
1 K.
1996 LOCA MODEL ASSESSYJ.NTS -
+ 40*F*
(refer to ULNRC-3499 dated 11-27-96)
L.
1997 LOCA MODEL ASSESSMENTS -
+ 0*F (refer to ULNRC-3552 dated 3-21-97)
M.
CURRENT LOCA MODEL ASSESSMENTS -
+ 0*F MARCH 1998 LICENSING BASIS PCT + MARGIN ALLOCATIONS
= 1506*F ABSOLUTE MAGNITUDE OF MARGIN ALLOCATIONS 30*F*
=
SINCE LAST SBLOCA 30-DAY REPORT (ULNRC-3101)
Per Section 3.5 of WCAP-13451, intentional changes to plant input parameters evaluated per 10 CFR 50.59 (such as the +10*F penalty for the reduced feedwater temperature evaluation) are not tracked against the 10 CFR 50.46 reportmg i
requirements related to a significant change (i.e., > 50*F).
Page 4 of 5
NOTES:
- 1. See Attachment I to ULNRC-3101. The 1991 assessments have been eliminated as a result of the new SBLOCTA calculation. The Small Break Burst and Blockage penalty is a function of the base PCT plus margin allocations and has been reduced to 0*F since the total PCT has been reduced to a value below that at which burst would occur.
- 2. Addendum 2 to WCAP-10054 has been submitted to NRC. It refemnces the improved condensation model (COSI) described in WCAP-11767 and provides justification for application of this model to small bmak LOCA calculations. Union Electric tracks the Peak Cladding Temperature (PCT) change reported in ULNRC-2892 (+150*F/-150*F) as a pennanent change to Callaway's calculated PCT. See WCAP-10054, Addendum 2,
" Addendum to the Westinghouse Small Brer.k ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken 140p and COSI Condensation Model,"
I August 1994.
- 3. +4.0*F Cycle 6 CRUD Deposition penalty will be carried until such time as it is
)
detennined to no longer apply.
- 4. Based on the limiting case clad heatup reanalysis with axial offset reduced from 30% to 20%, as discussed in ULNRC-3101.
i i
Page 5 of 5