ML20043A744
| ML20043A744 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/17/1990 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-11, TAC-71475, TAC-71476, NUDOCS 9005230072 | |
| Download: ML20043A744 (3) | |
Text
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BALTIMORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 Gromot C. CartL viet Passior.a Nucitan reatmov 400 een eans May 17,1990 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Response to Request for Additional Information - Generic Letter 88-11 (TAC No. 71475. Unit l' TAC No. 71476. Unit 2) 2
REFERENCES:
(a) Letter from D. G. Mcdonald (NRC) to G. C. Creel (BG&E), dated April 17, 1990, Request for Additional Information Proposed Technical Specification Amendments in
Response
to Generic Letter 88-11 Gentlemen:
As requested in the referenced letter, BGAE is providing additional information concerning the 16 EFPY LTOP Technical Specification amendment request.
The information provided is a clarification to the technical information provided previously.
It does not affect the significant hazards determination presented previously.
Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, D
1 G. C. Creel Vice President - Nuclear Energy GCC/ PSF /bjd -
Attachment h
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e Document Ccntr:1 Desk -
May 17,1990 Page 2 a
cc:
D. A. Brune, Esquire J. E.
Silberg, Esquire R. A.Capra,NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC L. E. Nicholson R. I.McLean, DNR P
t a
i l
l 1
l RESPONSE TO REQUEST FOR ADDITIONAL INFORMA110N 16 EFPY LTOP TECIINICAL SPECIFICATION e
Ouestion i Verify that nil-ductility transition reference temperature (RTNDT) for reactor vessel 0
0 closure flange is -20 F for Unit I and -10 F for Unit 2.
Resnonse The limiting RT f r the flange area of the reactor vessels are:
NDT 0
-10 F for Unit I
+30 F for Unit 2 Ouestion 2 Provide the Unirradiated Upper Shelf Charpy impact Energy for welds 2-203 A, B, C in Unit I and weld 2-203 A, B, C in Unit 2.
Resnonse The Unitradiated Upper Shelf Charpy impact Energy (USE) is typically not available for welds in the beltline unless the weld material was used in the Surveillance Program. The weld materials identified by the NRC are not in our original Surveillance Program. Ilowever, the same material used for Unit I welds 2-203 A, B, C was also used as the Surveillance weld material for Duke Power Company's McQuite Unit I and the reported USE for this material is 112 ft-lb.
There is currently no USE information available for welds 2-203 A,
B, C in Unit 2.
The weld materials and procedures used for welds 2-203 A, B, C in Unit 2 are similar to those used for the 9-203 welds in both Units and the 2-203 A, B, C welds in Unit 1.
The weld materials in our original Surveillance Programs are same as the weld materials used for weld 9-203 in Unit I and Unit 2. The USE for the weld materials in 9-203 is 160 ft-lb for Unit I and 140 ft-lb for Unit 2. Therefore, we expect the USE value for welds 2-203 A, B, C in Unit 2 to be greater than 100 ft-lbs and that no potential exists for low upper shelf toughness problems over the operating life of the plant for these welds.
Ouestion 3 Verify that the Pressure-temperature limit curves for Unit 2 in the October 27, 1989 submittal will be used in the Technical Specification change. The curves are effective for '6 EFPY.
Resnonse The Unit 216 EFPY heatup and cooldown curves submitted in the October 27, 1989 letter are proposed to replace Unit 2 Technical Specification Figures 3.4-2b and 3.4-2c. This proposed replacement was not clearly identified in the text.
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