ML042170380
| ML042170380 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/04/2004 |
| From: | Donohew J NRC/NRR/DLPM/LPD4 |
| To: | Muench R Wolf Creek |
| Donohew J N, NRR/DLPM,415-1307 | |
| References | |
| TAC MB8763 | |
| Download: ML042170380 (4) | |
Text
August 4, 2004 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - CORRECTION LETTER FOR AMENDMENT NO. 154 ON TECHNICAL SPECIFICATIONS 3.8.1 AND 3.8.4, AC AND DC SOURCES (TAC NO. MB8763)
Dear Mr. Muench:
By letter dated July 12, 2004, the Commission issued Amendment No. 154 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS). The amendment revised several surveillance requirements in Technical Specification 3.8.1 on alternating current sources for plant operation to adopt in part the staff-approved TSTF-283, Revision 3.
The amendment was in response to your application dated April 30, 2003 (WO 03-0009).
It has been determined that on page 14 of the safety evaluation for the amendment there was an incorrect reference to Callaway instead of to WCGS. Enclosed is the corrected page with the correction identified by a vertical line on the right hand side of the page. This page should replace the page in the safety evaluation issued in the letter dated July 12, 2004. The error does not change the conclusions in the safety evaluation. We regret any inconvenience caused by the error.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Corrected Page to Safety Evaluation cc w/encl:
See next page
Wolf Creek Generating Station cc:
Jay Silberg, Esq.
Shaw Pittman, LLP 2300 N Street, NW Washington, D.C. 20037 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Vick L. Cooper, Chief Air Operating Permit and Compliance Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Site Vice President Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Superintendent Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 U.S. Nuclear Regulatory Commission Resident Inspectors Office 8201 NRC Road Steedman, MO 65077-1032
August 4, 2004 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - CORRECTION LETTER FOR AMENDMENT NO. 154 ON TECHNICAL SPECIFICATIONS 3.8.1 AND 3.8.4, AC AND DC SOURCES (TAC NO. MB8763)
Dear Mr. Muench:
By letter dated July 12, 2004, the Commission issued Amendment No. 154 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS). The amendment revised several surveillance requirements in Technical Specification 3.8.1 on alternating current sources for plant operation to adopt in part the staff-approved TSTF-283, Revision 3.
The amendment was in response to your application dated April 30, 2003 (WO 03-0009).
It has been determined that on page 14 of the safety evaluation for the amendment there was an incorrect reference to Callaway instead of to WCGS. Enclosed is the corrected page with the correction identified by a vertical line on the right hand side of the page. This page should replace the page in the safety evaluation issued in the letter dated July 12, 2004. The error does not change the conclusions in the safety evaluation. We regret any inconvenience caused by the error.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION PUBLIC GHill (2)
Enclosure:
Corrected Page to Safety Evaluation PDIV-2 Reading RidsNrrDlpmPdiv(HBerkow) cc w/encl:
See next page RidsNrrPMJDonohew RidsNrrLAEPeyton RidsOgcRp RidsAcrsAcnwMailCenter RidsRegion4MailCenter (D. Graves)
TBoyce ACCESSION NO.: ML042170380 NRR-106 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME JDonohew:sp EPeyton SDembek DATE 8/4/04 8/4/04 8/4/04 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML042170380.wpd OFFICIAL RECORD COPY
- 4.
No maintenance or testing that affects the reliability of the train not associated with the EDG being tested will be conducted during testing of the EDG in Modes 1 and 2 connected to the offsite power supply. If any testing or maintenance of the train must be performed at this time, then a 10 CFR 50.65(a)(4) evaluation will be performed prior to the EDG testing connected to the offsite power supply.
In the licensees email dated February 25, 2004 (ADAMS Accession No. ML040701115, dated March 10, 2004), the licensee stated that the restrictions listed above are encompassed by its discussion in its application and supplemental [[letter::WO 03-0062, Response to RAI for the Revision to Technical Specifications 3.8.1, AC Sources - Operating and 3.8.4, DC Sources - Operating|letter dated December 18, 2003]].
In its letter dated April 13, 2004, the licensee stated that upon implementation of the amendment it would add information to the TS Bases for SR 3.8.1.14 that encompasses the statements made above. The NRC staff reviewed what would be added to the TS Bases for SR 3.8.1.14 and agrees that it encompasses the statements made above.
Based on the above evaluation, the NRC staff also concludes that the licensee's management of risk for testing the EDG in additional modes and the commitments given above are reasonable and sufficient for the amendment.
4.3 Conclusions The design of the onsite and offsite electric power systems for WCGS to permit the functioning of structures, systems, and components that are important to safety is not being changed by the proposed amendment. Further, the amendment does not change the testing of the EDG, only the modes in which the testing is conducted. Therefore, the plant continues to meet GDC 17.
The ability to inspect and test the safety-related electric power systems for WCGS, which must l
be designed to permit appropriate periodic inspection and testing, are not being changed by the amendment. Therefore, the plant continues to meet GDC 18.
For the reasons discussed in Sections 4.1 and 4.2 above, the NRC staff concludes that the proposed changes to SRs 3.8.1.10 through 3.8.1.14 and SRs 3.8.1.16 through 3.8.1.19, to allow testing the EDG in Modes 1 and 2 and for SR 3.8.1.16 in Modes 3 and 4, are acceptable.
Therefore, based on this, the NRC staff also concludes that the proposed changes to TS 3.8.1 meet 10 CFR 50.36(c)(3).
Based on the evaluation given above and because the proposed amendment meets GDC 17, GDC 18, and 10 CFR 50.36(c), the NRC staff concludes that the proposed amendment to SRs 3.8.1.10 through 3.8.14 and SRs 3.8.1.16 through 3.8.1.19 for AC power sources is acceptable.
4.4 Changes to the TS Bases The licensee presented the changes to the TS Bases for the proposed amendment in to its application and in the letters dated December 19, 2003, and April 14, 2004.
The NRC staff has reviewed the changes to the TS Bases for TS 3.8.1 and has no