ML091390368
| ML091390368 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/21/2009 |
| From: | David M Plant Licensing Branch III |
| To: | Pardee C Exelon Nuclear |
| david marshall NRR/DORL 415-1547 | |
| References | |
| TAC MD8515, TAC MD8516, TAC MD8517, TAC MD8518 | |
| Download: ML091390368 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 r'1ay 21, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - CORRECTION PAGES TO AMENDMENT NOS. 158 AND 163 (TAC NOS. MD8515, MD8516, MD8517, AND MD8518)
Dear Mr. Pardee:
On March 26, 2009, the Nuclear Regulatory Commission (NRC, the Commission) issued Amendment No. 158 to Facility Operating License No. NPF-72 and Amendment No. 158 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2 (Braidwood), and Amendment No. 163 to Facility Operating License No. NPF-37 and Amendment No. 163 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2 (Byron), respectively.
The amendments revised Technical Specifications (TSs) 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program," and 5.6.8, "Tendon Surveillance Report," for consistency with the requirements of Title 10 Code of Federal Regulations (10 CFR) Section 50.55a, "Codes and standards," paragraph (g)(4) for components classified as American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class CC, by replacing the reference to the specific ASME Code year for the tendon surveillance program with a requirement to use the applicable ASME Code and addenda as required by 10 CFR 50.55a.
Your staff recently informed us that TS 5.5.6 for Braidwood, and TS 5.5.6 for Byron, were issued with an error. Specifically, the references to Surveillance Requirement (SR) 3.0.2 had not been removed from these TSs as requested in your application dated April 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081010540), as supplemented by letter dated October 1, 2008 (ADAMS Accession No. ML082750420). In its Safety Evaluation for Amendment Nos. 158 and 163, the NRC staff had found the removal of the references to SR 3.0.2 from TS 5.5.6 for Braidwood, and TS 5.5.6 for Byron to be acceptable.
Therefore, we are issuing the enclosed corrected TS 5.5.6 for Braidwood, and TS 5.5.6 for Byron.
C. Pardee
- 2 We apologize for any inconvenience this may have caused.
Sincerely,
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I Mars all J Davi~
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Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Corrected TS page 5.5-5 for Braidwood
- 2. Corrected TS page 5.5-5 for Byron cc w/encls: Distribution via ListServ
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure conta"inment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC.
Determining pre stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990.
The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.
BRAIDWOOD - UNITS 1 &2 5.5 - 5 Amendment 158
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC.
Determining pre stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990.
The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.
BYRON - UNITS 1 &2 5.5 - 5 Amendment 163
C. Pardee
-2 We apologize for any inconvenience this may have caused.
Sincerely, IRA!
Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Corrected TS page 5.5-5 for Braidwood
- 2. Corrected TS page 5.5-5 for Byron cc w/encls: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsN rrLATHarris Resource RidsNrrPMBraidwood Resource RidsNrrPMByron Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDeEmcb Resource RidsOgcRp Resource GThomas, NRR GHill,OIS ADAMS Accession No. ML091390368 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME MDavid THarris CGoodwin for RGibbs DATE 5/21/09 5/20/09 5/21/09 OFFICIAL RECORD COpy