ML110940452
| ML110940452 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/04/2011 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Hooper D Wolf Creek |
| Hall, J R, NRR/DORL/LPL4, 301-415-4032 | |
| References | |
| TAC ME5742 | |
| Download: ML110940452 (2) | |
Text
From:
Hall, Randy Sent:
Monday, April 04, 2011 2:32 PM To:
Hooper Diane M Cc:
Wideman Steve G; Burkhardt, Janet; Lent, Susan
Subject:
Acceptance of License Amendment Request for Wolf Creek Re: Changes to Technical Specifications (TSs) 3.3, 3.7, and 3.8 - TAC ME5742 April 4, 2011 Diane M. Hooper Licensing Supervisor Wolf Creek Generating Station Wolf Creek Nuclear Operating Corporation
Dear Diane,
By letter dated February 23, 2011 (Letter No. WO 11-0008), Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request for Wolf Creek Generating Station (WCGS). The proposed changes will revise Technical Specifications (TSs) 3.3.7, "Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation," 3.3.8, "Emergency Exhaust System (EES) Actuation Instrumentation," 3.7.10, "Control Room Emergency Ventilation System (CREVS)," 3.7.11, "Control Room Air Conditioning System (CRACS)," 3.7.13, "Emergency Exhaust System (EES)," 3.8.2, "AC Sources - Shutdown," 3.8.5, "DC Sources - Shutdown," 3.8.8, "Inverters - Shutdown," and 3.8.10, "Distribution Systems -
Shutdown."
Specifically, this amendment will:
Delete MODES 5 and 6 from the Limiting Condition for Operation (LCO) Applicability for the CREVS and its actuation instrumentation (TS 3.7.10 and TS 3.3.7, respectively). The event that heretofore required these LCOs to be applicable in MODES 5 and 6 (waste gas decay tank rupture) requires no mitigation at WCGS in order to meet General Design Criteria (GDC) 19.
Delete the Required Action from TS 3.7.10 and TS 3.7.11 that requires verifying that the OPERABLE CREVS/CRACS train is capable of being powered by an emergency power source.
Revise TS 3.7.13 by incorporating a 7-day Completion Time for restoring an inoperable EES train to OPERABLE status during shutdown conditions (i.e., during movement of irradiated fuel assemblies in the fuel building).
Adopt NRC-approved traveler TSTF-36-A for TSs 3.3.8, 3.7.13, 3.8.2, 3.8.5, 3.8.8, and 3.8.10. This change will add an exclusion from LCO 3.0.3 that recognizes that irradiated fuel movement in the fuel building is independent of reactor operation in MODES 1 through 4 and defaulting to LCO 3.0.3 would force an unnecessary plant shutdown.
Add a more restrictive change to the LCO Applicability for TSs 3.8.2, 3.8.5, 3.8.8, and 3.8.10 such that these LCOs apply not only during MODES 5 and 6, but also during the
movement of irradiated fuel assemblies regardless of the MODE in which the plant is operating.
The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov