ML20024J086
| ML20024J086 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/21/1994 |
| From: | Saccamando D COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024J087 | List: |
| References | |
| NUDOCS 9409270074 | |
| Download: ML20024J086 (4) | |
Text
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1400 Opus P. ace Downers G ove. ll no s 60515 September 21,1994 W~~v -- m.,-n Mr. William Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk 1
Subject:
Byron Station Unit 2 Analysis of Capsule W from the Reactor Vessel Radiation Surveillance Program and Evaluation of Pressurized Thermal Shock NPF-66; NRC Docket No. 5_0-455__ __
References:
- 1. WCAP-14064, " Analysis of Capsule W from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program," July 1994
- 2. WCAP-14054, " Evaluation of Pressurized Thermal Shock for Byron Unit 2," August 1994
Dear Mr. Russell,
The enclosed technical report, WCAP 14064, " Analysis of Capsule W from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program", is being submitted to you pursuant to 10 CFR 50, Appendix H, " Reactor Vessel Material Surveillance Program Requirements"Section III of Appendix H, " Report of Test Results", requires a summary technical report to be submitted within one year after capsule withdrawal. Capsule W was withdrawn from the Unit 2 reactor vessel on September 23,1994.
Byron Technical Specification Surveillance Requirement 4.4.9.1.2 also states that the reactor vessel material irradiatior, specimens shall be removed and examined to determine changes in the material properties as required by Appendix H, in accordance with the schedule in Technical Specification Table 4.4-5.
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Mr. William Russell 2
September 21,1994 WCAP 14054 summarizes the testing, data obtained and data analysis as performed by Westinghouse Electric Corporation for Commonwealth Edison Company (CECO). Please note that it is permissible to distribute this report as necessary since it has been classified as non-proprietary by Westinghouse.
CECO's ISI/ Materials Group and System Material Analysis Department have reviewed the report and found it acceptable based on the criteria in NRC Regulatory Guide 1.99, " Radiation Embrittlement of Reactor Vessel Materials,"
Revision 2. The material exhibited adequate upper-shelf energy for continued plant operation in accordance with 10CFR50, Appendix G, and are projected to maintain an adequate upper-shelf energy through 32 Effective Full Power Years.
Also enclosed, please find technical report, WCAP-14054, " Evaluation of Pressurized Thermal Shock for Byron Unit 2". This report is being submitted to you pursuant to 10 CFR 50.61. Based on the evaluation in WCAP-14054, the Byron Unit 2 RTns values will remain below the 10 CFR 50.61 screening values through the projected 32 EFPY fluence. The calculations were performed using both 10CFR50.61 and Reg Guide 1.99, Rev. 2, Position 2 methodologies.
Please address any further comments or questions regarding this matter to this office.
Sincerely,
(
Denise M. Saccomando Nuclear Licensing Administrator
Enclosures:
- 1. WCAP-14054
- 2. WCAP-14064 G. F. Dick, Byron Project Manager - NRR cc:
H. Peterson, Senior Resident Inspector - Byron B. Clayton, Branch Chief-Region III Oflice of Nuclear Facility Safety -IDNS k: \\nla \\ byron \\byrpvi \\ 2
August 31, 1994 To: Mr. K.L.
Dhaese Station Support Engineering Byron Station
Subject:
WCAP-14054, Evaluation of Pressurized Thermal Shock for Byron Unit 2, August 1994 The subject document has been reviewed for technical content and found acceptable by SMAD-Metallurgy and NETS-Materials personnel.
The document should be submitted to the NRC as required by 10CFR50.61.
Summary Updated Unit 2 PTS evaluations were performed to include material data obtained from the analysis of reactor vessel surveillance capsule W (WCAP-14064, July 1994).
The calculated RTPTS values will remain well below the 10CFR50.61 screening values through the projected 32 EFPY fluence.
The calculations were performed using both 10CFR50.61 and Reg.
Guide 1.99, Rev.
2, Position 2 methodologies.
Girth weld WF447 is the limiting beltline material.
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Chynoweth SMAD-Metallurgy
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NETS-Materials cc. Station Manager, Byron D.E.
St. Clair, Byron 94 LOO 200.M
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1 August 23, 1994 To:
K.
L.
Dhaese System Engineering Byron Station
Subject:
RPV Materials Surveillance Program I
Byron Unit 2, Capsule W Ref: WCAP-14064, Analysis of Caosule W from the Commonwealth Edison Comoany Byron Unit 2
Reactor Vessel Surveillance Proaram, July 1994.
i The referenced document has been reviewed for technical content and l
found acceptable by SMAD-Metallurgy and NETS-Materials personnel.
The document should be submitted to the NRC as required Dy 10CFR50-Appendix H.
1 Caosule W Summary L
The Byron Unit 2 Capsule W specimens were irradiated to 1.211E+19 2
l n/cm (E > 1. 0 MeV).
All 30 ft-lb transition. temperature shif ts are considered acceptable in accordance with NRC Regulatory Guide 1.99, l
Rev.
2.
The limiting beltline weld metal exhibited a 30 ft-lb transition temperature increase of 40*F.
I 1
The measured upper shelf energy decreases for the surveillance capsule materials are less than Regulatory Guide 1.99, Rev.
2 l
predictions, which is considered acceptable. - The materials exhibit i
adequate toughness for continued safe plant operation, and are projected to maintain an upper shelf energy greater than 50 ft-lb l
through 32 EFPY in accordance with 10CFR50 Appendix G.
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- 4. M. Chynownth SMAD Metallurgy A~, D T.D.
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i NETS cc. Station Manager, Byron D.
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St. Clair, Byron 94 LOO 114.M
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