ML20196A477
| ML20196A477 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/30/1988 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 GL-88-11, ULNRC-1867, NUDOCS 8812060016 | |
| Download: ML20196A477 (4) | |
Text
E-4 1901 Gratet Street lbst Offwe Box 149 St. Louis. Alissoun63166 p4eran2 i
Umon Etecruicn November 30, 1988 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C.
20555 Gentlemen:
ULNRC-1867 DOCKET NO. 50-483 CALLAWAY PLANT
, RADIATION EMBRITTLEMENT OF REACTOR VESSEL MATERIALS Roference: NRC Generic Letter 88-11, dated-July 12, 1988 Generic Letter 88-11 requested Licensees to use the j
methodc described in Revision 2 to Regulatory G' tide (R.G.) 1.99 to predict the offect of neutron raciation I
on reactor vessel materials.
In addition, a technical j
analysis was required to be performed and a schedule of proposed actions was to be submitted within 180 days of i
the offectivo date of R.G.
1.99, Revision 2.
i-1 Union Electric currently utilizos the Draft j
Revision 2 to R.G.
1.99 methodology to predict the offect of neutron radiation on reactor vessel matorials.
This l
methodology was used to reviso the Callaway Plant Reactor Coolant System (RCS) hoatup and cooldown rates, l
the Cold Overpressure Mitigation System (COMS) setpoints and associated Technical Specifications and was approved in Amendment 36 to the callaway Operating License.
4 i
A review of the differences between the Draft l
Revision 2 and the Revision 2 muthodologies has been performed.
The Draft Revision 2 methodology utilizes a more conservativo fluence factor to calculate the change in RT at any location in the vossol wall (e.g., at 1/4T$9T3/4T locations).
Calculating the fluence factor j
using the Revision 2 methodology would lower tho predicted RT values allowing for an improved pressure-tenhEfaturewindowforlowtemperature k00
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I operations and Low Temperature Overpressure Protection Setpoints.
Therefore, a re-analysis of the RCS heatup and cooldown rates, COMS setpoints, and associated Technical Specifications is not necessary at this time.
Future analyses submitted per 10 CPR 50 Appendix G will utilize R.G.
1.99, Revision 2.
If you have any questions concerning this information, please contact me.
Very truly yours,
(
Donald F.
Schnell WEK/ dis
i
]
~
STATE.J MISSOURI )
)
Donald F.
Schnelle of lawful age, beir.g first duly sworn upon oath says that he is Senior Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
/
By I)onald F.~ Schnell Senior Vice President Nuclear SUBSCRIBED and sworn to before me this N day of 198[
fkkw 9 hul BAR9ARd PFAFf V 8 N1tAAY PUSUC, STATE OF MISSM1 Nf COMMIS$10N EXPtRES APR!L 22.1933 t
ST.LOUl$ COUNTY 1
s t
- n cc:
Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N.
Street, N.W.
Washington, D.C.
20037 Dr. J. O. Cermak CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg, MD 20879 R. C. Knop Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road 2
Glen Ellyn, Illinois 60137 Bruce Little
- )
Callaway Resident Office U.S. Nuclear Regulatory Commission 4
RRil Steedman, Missouri 65077 4
Tom Alexion (2)
Office of Nuclear Reactor Regulation j
U.S. Nuclear' Regulatory Commission Mail Stop 316 l
7920 Norfcik Avenue Bethesda, MD 20014 l
Manager, Electric Department Missouri Public Service Commission i
P.O. Box 360 j
Jefferson City, MO 65102 U.S. Nuclear Regulatory Commission f
ATTN:
Document Control Desk l
Washington, D.C.
20555
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