HL-5310, Elaborates Response to NRC RAI Re P/T Submittal of 960918
| ML20134L003 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/31/1997 |
| From: | Woodard J GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-5310, NUDOCS 9702180110 | |
| Download: ML20134L003 (7) | |
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Georgia Power Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-3195 Malling Address -
40 invemess Center Parkway 4
Post office Box 1295 Birmingham Alabama 3520t Telephone 205 868-5086 3
J. D. Woodard the southern electnc system Senior Vice President 1
5 January 31, 1997 l
Docket Nos. 50-321 HL-5310 i
i 50-366 i
U.S. Nuclear Regulatory Commission
. ATTN:: Document Control Desk I
Washington, D.C. 20555 3
Edwin I. Hatch Nuclear Plant 3
Response to Request for Additional Information on Technical Specification Revision Request:
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Pressrire-Temperatrire Limits Gentlemen:
C This letter elaborates on our response to an NRC request for additional information concerning our pressure / temperature submittal of September 19,1996. Our response was submitted on January 23,1997. You have since verbally asked for an elaboration on the.
. response to question C; it is provided in the enclosure.
Additionally, the attachment contains the welding material qualifications for two heat numbers of Weld 1-313.
j Sincerely, t
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. Woodard i
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Enclosure:
AdditionalInformation on Technical Specification Revision:
Pressure-Temperature Limits F
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Attachment:
' Welding Material Qualifications for. Weld 1-313, Tt Heat Number 33A277/0091 Flux 3977 Lot and
-l Heat Number 90099/0091 Flux 3977 Lot 9702100110 970131 PDR ADOCK 05000321 p
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'Georg'ia Power 1 4
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U. S. Nuclear Regulatory Commission Page 2 January 31, 1997 cc: Georgia Power Company Mr. H. L. Sumner, Nuclear Plant General Manager NORMS j
U.S. Nuclear Repilatorv Commission. Washington. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U.S. Nuclear Repolatory Commission. Region 11 Mr. L. A. Reyes, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector - Hatch I'
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Enclosure i
Edwin I. Hatch Nuclear Plant Response to Request for Additional Information on Technical Specification Revision Request:
Pressure-Temperature Limits Ouestion:
Please provide supporting information to document the initial RTer of-50 F for Weld 1-313 with heat and lot number 33 A277/0091 flux 3977 and why -10 F was previously used for Weld 1-313.
Response
In NEDC-30997, "Edwin I. Hatch Nuclear Power Plant, Unit 1, Reactor Pressure Vessel Surveillance Materials Testing and Fracture Toughness Analysis", dated October,1985 only the weld material with the limiting initial RTer was reported in Tables 3-2 and 3-4, 4
even though the data was available for the other welds (for example, the chemistry for 33 A277 as well as 90099 are reported in Table 3-1). Therefore, in NEDC-30997, the limiting weld initial RTmr of-10 F was used for all welds. This was an unnecessary conservative assumption. Subsequently, Reg. Guide 1.99 was revised and the NRC issued Generic Letter (GL) 88-11. In Georgia Power Company's response to GL 88-11 the unnecessary conservatism was removed by reporting the -50 F initial RTmr for 33 A277.
3 Later, in the Georgia Power response to GL 92-01, we made the following statement in response to NRC question 2.b in referring to beltline weld materials, "The unirradiated i
RTer was determined from the procedure as the higher of either (T3or - 60 F) or -50 F.
Accordingly, initial RTxm values used in the Appendix G analysis were 10 F for plate and
-10 F for weld." Again, only the data for the limiting weld initial RTer was reported.
As described in our January 23,1997 letter, when the NRC asked Plant Hatch to confirm the data for the reactor vessel integrity database (RVID), in which the initial RTer for heat numbers 90099 and 33A277 were both reported as -10 F, we failed to notify you that a
the correct number for heat 33A277 was -50 F.
In the current PT submittal under review by the NRC, the evaluation was performed consistent with the GL 88-1I submittal.
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J HL-5310 E-1
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- Enclosure Pressure-Temperature Limits i
i Attached is the Welding Material Qualification for heat number 33A277/0091 e
flux 3977 lot to support the calculation ofinitial RTer.
For heat number 33 A277, since the Charpy tests at 10 F are all above 50 fl-lbs, the initial RTer is the higher of the NDT or the (CVN 50 f1-lb - 60 F).
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(CVN 50 fi-lb)- 60 F = 10 F - 60 F = -50 F In the absence of NDT data, RTer shall not be lower than -50 F. Therefore, the
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initial RTer is -50 F.
Also, for comparison purposes, the Welding Material Qualification for heat number l
90099/0091 flux 3977 lot is attached.
For heat number 90099, since the lowest Charpy tests value at 10 F is 30 fi-Ibs, the CVN 50 fi-lb is calculated as follows:
CVN 50 ft-lb = (50 ft-lb -30 fi-lb) x 2 F/fl-lb + 10 F = 50 F.
Initial RTmr is the higher of the NDT or the (CVN 50 fi-lb - 60 F)
(CVN 50 ft-lb)- 60 F = 50 F - 60 F = -10 F.
Therefore, the initial RTer is -10 F.
As presented, the initial RTer for Weld ID l-313 with heat.iumber 90099/0091 flux 3977 lot is -10 F and for Weld ID 1-313 with heat number 33 A277/0091 flux 3977 1
- lot is -50 F. Please revise the RVID to reflect that -50 F is the correct initial RTwr for Weld ID l-313 with heat number 33 A277/0091 flux 3977 lot.
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Attachment d
Welding Material Qualifications for Weld 1-313, Heat Number 33A277/0091 Flux 3977 Lot and Heat Number 90099/0091 Flux 3977 Lot 4
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-- om Welding Material Qualification Mr. R. E. Lorentz, Jr.
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Mr. S. A. LewisSection III Chattanooga Mr. S. R. Lewis A-32255 Mr. J. E. Brasfield 810560 October 7,1970 The.following test data is for 3/16" diameter bare wire, type B-4, heat number 33A277, flux type 0091,.lo..t. n. u.m. _ber 3977 A weld depostt was made using the above heat of wire and lot of flux. Weld was done in accordance with C. E. Welding Procedure specification B-4 SA The completed weldment was given a post weld heat treatment of 1150*F
- for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*F.
Charov V-Notch Imoacts Test Code P.
- Pt/Lbs. @ + 10 F
__ Recuirements BB 111, 106, 113 20 Ft/Lbs @ +10*F All Weld Metal.505 Tensile Yield Strength Ultimate
- ensile Elongation in Reduction of KSI Strencth KSI
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67.7 81.3 31.0 70.2 t
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Mr. R. E. Lorentz, Jr.
Section III Chattanooga Mr. S. A. Lewis A-32255 Mr. S. R. Lewis 810560 October 7,1970 Mr. I. E. Brasfield i
The following test data is for 3/16" diameter bare wire, type B-4. heat number 90099, flux type 0091, lot numbe-3977.
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A weld deposit was made using the above heat of wire and lot of flux. Welding l
was done in acecrdance with C. 2. Welding Procedure Specification SAA-33 L(1).
The completed weldment was given a post weld heat treatment of 1150*F *25'F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*F.
Charov Y-Notch Impacts Test Code Pt/I,bs. @ + 10_'F Recuirements f
A SC 56, 30, 52 30 Ft/Lbs @ +10'F All Weld Metal.505 Tensile Yield Strength Ultimate Tensile Elongation in Reduction of XSI Strencth KSI_
2" %
Area %
77.0 89.5 25.0 68.6 1
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