ML12200A102
| ML12200A102 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  (NPF-042) |
| Issue date: | 08/08/2012 |
| From: | Beltz T Plant Licensing Branch IV |
| To: | Matthew Sunseri Wolf Creek |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC MD9470 | |
| Download: ML12200A102 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 8, 2012 Mr. Matthew W. Sunseri President and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATION STATION - CORRECTION TO TECHNICAL SPECIFICATION PAGE ISSUED WITH AMENDMENT NO. 183 REGARDING TECHNICAL SPECIFICATION 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION" (TAC NO. MD9470)
Dear Mr. Sunseri:
On July 30,2009, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 183 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091700296) to the Wolf Creek Generating Station (WCGS). The amendment revised Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
Instrumentation," to extend the Surveillance Frequency on selected ESFAS slave relays from 92 days to 18 months, and changed the Renewed Facility Operating License, in response to your application dated August 14, 2008 (ADAMS Accession No. ML082350072).
Following issuance of Amendment No. 183, the NRC staff was informed by WCGS Licensing staff of an error in the approved TSs. On page 3.3-48, Table 3.3.6-1, footnote (c), the value of "9" mRlh was missing. The footnote was issued as follows:
(c)
Trip setpoint concentration value (J.1CilcmJ) is to be established such that the actual submersion rate would not exceed mRih in the containment building.
Amendment No. 123 was the previous amendment affecting Table 3.3.6-1. This amendment was issued on March 31, 1999 (ADAMS Legacy Accession No. 9904070150), and was associated with the WCGS conversion to Improved Technical Specifications. Table 3.3.6-1 did include the specified value of "9 mRlh" in footnote (c). The footnote was issued as follows:
(c)
Trip setpoint concentration value (J.1CilcmJ) is to be established such that the actual submersion rate would not exceed 9 mRih in the containment building.
The value of "9" was omitted from the proposed TS page revision submitted with your license amendment application dated August 14, 2008, and the NRC subsequently approved and issued Amendment No. 183 with this omission. Furthermore, Table 3.3.6-1 was located on page 3.3-49 in Amendment No. 123, and on page 3.3-48 in Amendment No. 183. Therefore, another possible contributor to this error of omission was the repagination of TS Section 3.3.
M. Sunseri
- 2 The NRC staff concludes that this omission was inadvertently introduced in the license amendment request, that the error is entirely administrative in nature, and that the erroneous change was not the subject of the amendment or the associated notice to the public.
Accordingly, this error of omission may be corrected by a letter in accordance with the NRC's policy established by SECY-96-238 (ADAMS Accession No. ML003754054).
Please find enclosed the replacement page 3.3-48 for Amendment No. 183. This correction does not change any of the NRC staff's conclusions in the safety evaluation associated with the amendment.
If you have any questions regarding this matter, please call me at (301) 415-3049.
Sincerely, Terry A. Beltz, Senior Project Manager Plant licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As stated cc w/encl: Distribution via ListServ
ENCLOSURE WOLF CREEK GENERATING STATION DOCKET NO. 50-482 REPLACEMENT TECHNICAL SPECIFICATION PAGE 3.3-48 FOR AMENDMENT NO. 183
Containment Purge Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Purge Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIRED CHANNELS REQUIREMENTS TRIP SETPOtNT
- 1.
Manual Initiation 1,2,3,4, (a),(b) 2 SR 3.3.6.4 NA
- 2.
Automatic Actuation Logic and Actuation Relays (BOP ESFAS) 1,2,3,4, (a),(b) 2 trains SR 3.3.6.2 SR 3.3.6.6 NA
- 3.
Containment Atmosphere Gaseous Radioactivity 1,2,3,4, (a),(b)
SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.5 (c)
- 4.
Containment Isolation Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a, for all initiation functions and requirements.
(a)
During CORE ALTERATIONS.
(b)
During movement of irradiated fuel assemblies within containment.
(c)
Trip setpoint concentration value (J.lCl/cm') is to be established such that the actual submersion rate would not exceed 9 mRlh in the containment building.
Wolf Creek - Unit 1 3.3-48 Amendment No. ~,183 \\
Please find enclosed the replacement page 3.3-48 for Amendment No. 183. This correction does not change any of the NRC staff's conclusions in the safety evaluation associated with the amendment.
If you have any questions regarding this matter, please call me at (301) 415-3049.
Sincerely, IRA!
Terry A Beltz, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As stated cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC Lpl4 Reading RidsAcrsAcnw _MaiICTR Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMWolfCreek Resource RidsOgcRp Resource RidsRgn4MailCenter Resource RecordsAmend Resource ADAMS Accession No. ML12200A102 OFFICE NRRlLPL43-1/PM NRR/LPL4/LA NRRlLPL4/BC NRRlLPL3-1/PM NAME TBeltz JBurkhardt MMarkley TBeltz DATE 8/3/12 8/2/12 8/7/12 8/8/12