ML13225A296
| ML13225A296 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  (NPF-009, NPF-017) |
| Issue date: | 08/19/2013 |
| From: | Jason Paige Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Paige J, NRR/DORL 415-5888 | |
| References | |
| TAC MF1166, TAC MF1167 | |
| Download: ML13225A296 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 19, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST MC-SRP-ND-01 (TAC NOS. MF1166 AND MF1167)
Dear Mr. Capps:
By letter dated February 27,2013, Duke Energy Carolinas, LLC (Duke, the licensee), submitted its Inservice Testing Program for the Fourth Ten-Year Interval at the McGuire Nuclear Station.
Included in the submittal is proposed relief request MC-SRP-ND-01 for review and approval.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On August 12, 2013, the Duke staff indicated that a response to the RAI would be provided within 45 days of the date of this letter.
If you have any questions, please call me at 301-4. -5888.
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son C. Paige, roject Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST MC-SRP-ND-01 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 By letter dated February 27,2013. Duke Energy Carolinas, LLC (Duke, the licensee), submitted its Inservice Testing Program for the Fourth Ten-Year Interval at the McGuire Nuclear Station.
Included in the submittal is proposed relief request MC-SRP-ND-01 for review and approval.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that the following additional information is needed in order to complete our review:
RAI MC-SRP-ND-01-1 Relief request MC-SRP-ND-01, under "Alternate Testing," contains a heading "Group A I Comprehensive Tests." Is the licensee requesting relief for Group A tests, Comprehensive Tests, or both? The licensee states in relief request MC-SRP-ND-01, page 2, that "the instrumentation used to measure suction and discharge pressure is more accurate than ASME Code requirements. (0.5% vs. 2%)." This statement is true for the accuracy requirements for Group A tests in ASME OM Code Table ISTB-351 0-1. The licensee also states that the code allowable actual instrument error is "6% (2*690/230)." This is also true for Group A tests as per ASME OM Code Table ISTB-3510-1. However, for comprehensive tests, ASME OM Code Table ISTB-3510-1 requires an accuracy of 0.5%. If a gauge that meets the three times the reference value criteria is used, the code allowable reading error is therefore 0.5%
- 3 = 1.5%
for comprehensive tests.
The licensee states that "the actual reading error at test pressure due to the process instrument is 2.2%." If the licensee is seeking relief for comprehensive testing, please justify how the instrumentation provides acceptable measurement accuracy as an alternative to the requirements listed in ASME OM Code Table ISTB-3510-1 for comprehensive tests.
Relief request MC-SRP-ND-01, page 1, states that there are two suction pressure gauges installed with ranges of 0-60 psig and 0-600 psig. Relief request MC-SRP-ND-01, page 2, states that the typical values for NO (residual heat removal) suction range from 48-81 psig. Since the 0-60 psig gauge cannot read values exceeding 60 psig, the 0-600 psig gauge must be relied upon for suction pressure measurements ranging from 60 - 81 psig. For this range, the most conservative reading error is therefore 0.5% * (600/60) = 5%. If suction pressure is obtained from the 0-600 gauge only, the most conservative reading error would be 0.5%*(600/48) = 6.25%, which is greater than the reading error that the licensee states is acceptable by code requirements (6%). Please justify how the test procedures and instrumentation implemented will ensure that an acceptable level of accuracy is achieved for the measurement of suction pressure.
Enclosure
August 19, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST MC-SRP-ND-01 (TAC NOS. MF1166 AND MF1167)
Dear Mr. Capps:
By letter dated February 27,2013, Duke Energy Carolinas, LLC (Duke, the licensee), submitted its Inservice Testing Program for the Fourth Ten-Year Interval at the McGuire Nuclear Station.
Included in the submittal is proposed relief request MC-SRP-ND-01 for review and approval.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On August 12, 2013, the Duke staff indicated that a response to the RAI would be provided within 45 days of the date of this letter.
If you have any questions, please call me at 301-415-5888.
Sincerely, IRA!
Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 RlF RidsAcrsAcnw _MaiICTR Resource RidsNrrDorlLpl2-1 Resource RidsNrrDeEpnb Resource RidsNrrPMMcGuireResource (hard copy)
RidsNrrLASFigueroa Resource RidsRgn2MailCenter Resource ADAMS Accession No. ML13225A296
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