ML042300415
| ML042300415 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/12/2004 |
| From: | Michael Webb NRC/NRR/DLPM/LPD4 |
| To: | Hinnenkamp P Entergy Operations |
| Webb M, NRR/DLPM, 415-1347 | |
| Shared Package | |
| ML042330124 | List: |
| References | |
| TAC MC1093 | |
| Download: ML042300415 (10) | |
Text
August 12, 2004 Mr. Paul D. Hinnenkamp Vice President - Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REMOVAL OF MODE RESTRICTIONS FOR SURVEILLANCE TESTING OF THE DIVISION III BATTERY (TAC NO. MC1093)
Dear Mr. Hinnenkamp:
The Commission has issued the enclosed Amendment No. 141 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 21, 2003.
The amendment removes MODE restrictions that prevent performance of Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division III direct current electrical power subsystem while in MODES 1, 2, or 3. These surveillances verify that the battery capacity is adequate to perform its required functions. The changes allow the performance of SR 3.8.4.7 and SR 3.8.4.8 during normal plant operations rather than only during refueling outages.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Michael K. Webb, Senior Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. Amendment No. 141 to NPF-47
- 2. Safety Evaluation cc w/encls: See next page
August 12, 2004 Mr. Paul D. Hinnenkamp Vice President - Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REMOVAL OF MODE RESTRICTIONS FOR SURVEILLANCE TESTING OF THE DIVISION III BATTERY (TAC NO. MC1093)
Dear Mr. Hinnenkamp:
The Commission has issued the enclosed Amendment No. 141 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 21, 2003.
The amendment removes MODE restrictions that prevent performance of Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division III direct current electrical power subsystem while in MODES 1, 2, or 3. These surveillances verify that the battery capacity is adequate to perform its required functions. The changes allow the performance of SR 3.8.4.7 and SR 3.8.4.8 during normal plant operations rather than only during refueling outages.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Michael K. Webb, Senior Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. Amendment No. 141 to NPF-47
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsOgcRp PDIV-1 Reading RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiv (HBerkow)
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Accession No.: ML042300415 Nrr-058
- No major changes to SE input.
TS Pages: ML Nrr-100
- No legal object w/comments.
Package No.: ML OFFICE PDIV-1/PM PDIV-1/LA EEIB*
OGC**
PDIV-1/SC NAME MWebb DBaxley RJenkins RWeisman RGramm DATE 8/12/04 8/12/04 6/24/04 26 July 2004 8/12/04 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML042300415.wpd OFFICIAL RECORD COPY
ENTERGY GULF STATES, INC. **
AND ENTERGY OPERATIONS, INC.
DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 141 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated October 21, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and
- Entergy Operations, Inc. is authorized to act as agent for Entergy Gulf States, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
- Entergy Gulf States, Inc., has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc., was the surviving company in the merger.
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 141 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.8-26 3.8-26 3.8-27 3.8-27
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 141 TO FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458
1.0 INTRODUCTION
By application dated October 21, 2003 (ADAMS Accession No. ML033030535), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for the River Bend Station, Unit 1 (RBS). The proposed changes would remove MODE restrictions that prevent performance of Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division III direct current (DC) electrical power subsystem while in MODES 1, 2, or 3. These surveillances verify that the battery capacity is adequate to perform its required functions. The changes would allow the performance of SR 3.8.4.7 and SR 3.8.4.8 during normal plant operations in conjunction with a high pressure core spray (HPCS) system outage rather than only during refueling outages. According to the licensee, this will help to reduce the complexity of work and testing activities during refueling outages.
2.0 REGULATORY EVALUATION
RBS began commercial operation on June 16, 1986. Therefore, the General Design Criteria (GDC) of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A and the SRP are applicable to the RBS.
GDC 17, Electric power systems, requires, in part, that the onsite electric power supplies, including the batteries, shall have sufficient independence, redundancy, and testability to perform their safety functions, assuming a single failure GDC 18, Inspection and testing of electric power systems, requires, in part, that electric power systems important to safety shall be designed to permit appropriate periodic inspection and testing to assess the continuity of the systems and the condition of their components.
3.0 TECHNICAL EVALUATION
The 125 volt DC (VDC) electrical power system of the RBS consists of three independent Class 1E DC electrical power subsystems, Division I, II, and III. Each subsystem consists of a battery, associated battery charger(s), and all associated control equipment and interconnecting cabling. The DC electrical power system is designed to have sufficient independence, redundancy, and testability to perform its safety functions, assuming a single failure.
The Division III 125 VDC power system function is to provide a reliable, continuous, and independent 125 VDC power source of control and motive power as required for the HPCS system logic, HPCS Diesel Generator (DG) set control and protection, and all Division III related controls. A battery charger is provided for the battery. The Division III 125 VDC system is independent of all other divisional batteries and there is no manual or automatic connection to any other battery.
The Division III DC power source is required for HPCS DG field flashing, control logic and control and switching function of 4.16 kiloVolt breakers. In accordance with SRs 3.8.4.7 and 3.8.4.8, the Engineered Safety Features divisional batteries are required to be service tested and performance discharge tested periodically. However, as currently stated, there is a NOTE in SR 3.8.4.7 and SR 3.8.4.8 stating that This surveillance shall not be performed in MODE 1, 2, or 3....
The licensee proposes to modify NOTE 2 for SR 3.8.4.7 and the NOTE for SR 3.8.4.8 that currently read This surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR. to state This surveillance shall not be performed in MODE 1, 2, 3 (not applicable to Division III). However, credit may be taken for unplanned events that satisfy this SR.
The licensee stated that the current TS allows the Division III HPCS DG and HPCS system to be removed from service to perform scheduled maintenance while in MODES 1, 2, or 3. The TS change is desired to allow Division III battery tests to be performed in conjunction with these scheduled system outages. The change will allow the Division III battery service test required by SR 3.8.4.7 and the Division III battery performance test required by SR 3.8.4.8 to be performed in MODES 1, 2, or 3 in conjunction with HPCS system outage or for unplanned events. The TS allows 14 days of HPCS inoperability if the Reactor Core Isolation Cooling system is operable.
The licensee stated that the time needed to perform the battery testing is approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The testing period is within the period of time that the HPCS system would be out of service for planned maintenance. The battery test does not increase unavailability of the supported system or represent any change in risk above the current practice of planned system maintenance outages as currently allowed by the TS. In addition, RBS has a Configuration Risk Management Program in place in accordance with RBS commitments for compliance with 10 CFR 50.65, Monitoring the Effectiveness of Maintenance to provide assurance that risk-significant plant equipment configurations are precluded or minimized when plant equipment is removed from service.
3.1 Technical Conclusion Based on the above, the NRC staff concludes that the licensees proposed changes to the TS associated with the Division III DC electrical power system do not change the ability of the DC electrical power system to meet GDC 17 and are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (68 FR 68662 dated December 9, 2003). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Saba Date: August 12, 2004
June 2004 River Bend Station cc:
Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager - Licensing Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775 Senior Resident Inspector P. O. Box 1050 St. Francisville, LA 70775 President of West Feliciana Police Jury P. O. Box 1921 St. Francisville, LA 70775 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Ms. H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, LA 70806 Mr. Michael E. Henry, State Liaison Officer Department of Environmental Quality Permits Division P.O. Box 4313 Baton Rouge, Louisiana 70821-4313 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205 Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 General Manager - Plant Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775 Director - Nuclear Safety Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775 Vice President - Operations Support Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Attorney General State of Louisiana P. O. Box 94095 Baton Rouge, LA 70804-9095 Brian Almon Public Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, Texas 78701-3326