ML20101K526
| ML20101K526 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/24/1992 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M82504, TAC-M82505, NUDOCS 9207060003 | |
| Download: ML20101K526 (3) | |
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DALTIMORE GAS AND ELECTRIC 1650 CALVERT CUFFS PARKWAY
- LUSBY, MARYLAND 20657 4702 GEORot C CRttL Vict PREnfotNt NVC4( AR ENthov June 24,1992 wioi..o..se U. S. Nuclear Regulatory Commission Washington, DC 20555 ATI'ENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Pressurized Thermal Shock Rule, Supplemental Response to NRC Request for Additional Information, dated hiarch 31,1992 (TAC Nos. h182504 andh182505)
REFERENCES:
(a) letter from hir. O. C. Creel (BG&E) to NRC Document Control Desk, dated hiay 22,1992, Response to NRC Request for Additional information (b) letter from hir. D. O. hicDonald, Jr. (NRC) to hir O. C. Creel (BG&E), dated hiarch 31.1992, Request for Additional Information (c)
Letter from hir. O. C. Creel (BG&E) to NRC Documer.t Ccmtrol Desk, dated December 13, 1991, Response to the 1991 Pressurized Thermal Shock Rule l
Gentlemen:
During a telephone conference call on June 16, 1992, hir. B. J. Elliot (NRC) requested that we respond to Question No. 2 of Reference (b) as it pertains to plate materials in the Unit 1 and 2 reactor vessels.
Accordingly, the requested information is provided in Attachment (1), and supplements Reference (a).
Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, 7
(
m OCC/BSht/bsm/dlm
Attachment:
(1)
Surveillance Test Results for Reactor Vessel Plate Af aterials, Units 1 & 2 92070gggy hhobi7 PDR PDR r-m UGU P
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.. ~.
Document Control Desk
' June 24,1992
,Page 2 cc:
D. A. Brune, thquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC B. J. Elliot, NRC T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. II. Walter, PSC l
i l
l 1
l l
ATI'ACllMENT (1)
, SURVEILIANCETEST RESU1/rs icOR REACTOR VESSEL P! ATE MATERIALS, UNITS 1 & 2 We reviewed measured RT ur shift results for plates in the Calvert Cliffs Reactor Vessel N
Surveillance Program (Table 1). 'these test results indicate the values of ART ns calculated using i
the methodology specified in the PTS Rule bound the surveillance measurements.
TABLE (1)
SURVEILLANCE TEST RESULTS Measured Shift l'redicted Shift Suneillance Chemistry Fluence
(@ 30 ft.. lbs)
(l'TS Hule) -
Plate Cu%
Ni%
Factor x10" "/cm2 (e r)
(, y)
Calvert Cliffs 1 D7206-3,
,12
.64
-- 84
.61o 60 e
e d
72
- 11SST 01 MY,
.18g
.66f 136
.61o -
8So 117 (Reference Plate)
Calvert Cliffs 2 D8907 2 I4
.66 102
.806, 84, 96 b
e e
IISST01 MYb 18f
.66r 136
,806,
- 128, 128 (Reference Plate)
REFERENCES a)
" Summary Report on hianufacture of Test Specimens and Assembly of Capsules for Nradiation Surveillance of Calvert Cliffs Unit #1 Reactor Vessel hiaterials," Combustion Engineering, CENPD 34, February 1972 b)
" Summary Report on hianufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Calvert Cliffs Unit #1 Reactor Vessel hiaterials," Combustion Engineering, CENPD-48. August 1972 c)
Creci, O.C., letter dated December 13,1991, " Response to the 1991 Pressurized Thermal Shock Rule" d)
Perrin, J.S., E.O. Fromm, D.R. Farmelo, R.S. Denning, and R.G. Jung, "Calvert Cliffs Unit #1 Nuclear Plant Reactor Pressure Vessel Surveillance Program Capsule 263," Battelle Columbus Laboratories, December 1980 -
c)
Norris, E.B., " Reactor Vessel hiaterial Surveillance Program for Calvert Cliffs Unit #2 Analysis of 263
- Capsule," SwRI-7524, September 1985 f)
NUREG/CR 4947," Analysis of the A302B and A533B Standard Reference hiaterials in Surveillance Capsules of Commercial Power Reactors," F.W. Stallman, January 1988 8
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