ML030310075
| ML030310075 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  (NPF-057) |
| Issue date: | 01/30/2003 |
| From: | George Wunder NRC/NRR/DLPM/LPD1 |
| To: | Keiser H Public Service Enterprise Group |
| Wunder G, NRR/DLPM, 415-1494 | |
| References | |
| TAC MB6617 | |
| Download: ML030310075 (9) | |
Text
January 30, 2003 Mr. Harold W. Keiser Chief Nuclear Officer & President PSEG Nuclear LLC-X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE:
REVISION TO TECHNICAL SPECIFICATION 6.12, HIGH RADIATION AREA (TAC NO. MB6617)
Dear Mr. Keiser:
The Commission has issued the enclosed Amendment No. 142 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station. This amendment consists of a change to the Technical Specifications (TSs) in response to your application dated October 23, 2002. The amendment revises TS 6.12, High Radiation Area, to be consistent with the Standard TS, General Electric Plants (NUREG-1433, Rev. 2).
A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Amendment No. 142 to License No. NPF-57
- 2. Safety Evaluation cc w/encls: See next page
Hope Creek Generating Station cc:
Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Hope Creek Resident Inspector U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. David F. Garchow Vice President - Operations PSEG Nuclear - X10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Gabor Salamon Manager - Nuclear Safety and Licensing PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038
Mr. Harold W. Keiser Chief Nuclear Officer & President PSEG Nuclear LLC-X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE:
REVISION TO TECHNICAL SPECIFICATION 6.12, HIGH RADIATION AREA (TAC NO. MB6617)
Dear Mr. Keiser:
The Commission has issued the enclosed Amendment No. 142 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station. This amendment consists of a change to the Technical Specifications (TSs) in response to your application dated October 23, 2002. The amendment revises TS 6.12, High Radiation Area, to be consistent with the Standard TS, General Electric Plants (NUREG-1433, Rev. 2).
A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Amendment No. 142 to License No. NPF-57
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION JClifford OGC GMeyer, RGN-I KGibson SRichards PUBLIC GWunder ACRS Wbeckner RDennig PDI-2 Reading LCox RTaylor GHill (2)
Accession Number: ML030310075
- See previous concurrence OFFICE PDI-2/PM PDI-2/PM PDI-2/LA IEHB/SC*
OGC PDI-2/SC NAME RTaylor GWunder LCox KGibson BSmith VNerses for JClifford DATE 01/06/03 01/06/03 11/20/02 11/21/02 01/16/03 01/27/03 OFFICIAL RECORD COPY
PSEG NUCLEAR LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the PSEG Nuclear LLC dated October 23, 2002, 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, 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 142, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by VNerses for/
James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 30, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 142 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 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 6-24 6-24 6-24a 6-24b
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 142 TO FACILITY OPERATING LICENSE NPF-57 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354
1.0 INTRODUCTION
By letter dated October 23, 2002, PSEG Nuclear LLC (PSEG, or the licensee), submitted an application to amend a Technical Specification (TS) for the Hope Creek Generating Station.
The licensee requested that the U.S. Nuclear Regulatory Commission (NRC) review and approve a revision to Hope Creek TS 6.12, High Radiation Area. This revision would make the Hope Creek TS consistent with the Standard Technical Specifications, General Electric Plants (NUREG-1433, Rev. 2).
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, Technical Specifications, specifies the categories of items to be included in the plant TSs. These include safety limits, limiting safety system settings, limiting control settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. In addition, 10 CFR Part 20 and Appendix I of 10 CFR Part 50 provide requirements for radiological control.
Over the years, the NRC staff published a number of guidance documents regarding TSs requirements related to radiological control. These include the following:
Regulatory Guide 8.38, Control of Access to High and Very High Radiation Areas in Nuclear Power Plants,
Generic Letter (GL) 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual (ODCM) or to the Process Control Program,
NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors (GL 89-01, Supplement No. 1), and
GL 95-01, Relocation of Selected Technical Specification Requirements Related to Instrumentation.
In addition to these, the NRC staff issued guidance to improve TSs. This guidance is located in NUREG-1433, Standard Technical Specifications, General Electric Plants, BWR/4.
The licensee has previously implemented much of the guidance described above. On September 8, 1999, the NRC issued Amendment No. 121 to the Hope Creek operating license.
Amendment No. 121 relocated the procedural details of the RETS to the ODCM and the procedural details associated with solid radioactive waste to the Process Control Program.
Additionally, the Administrative Controls section was revised to incorporate programmatic controls for radioactive effluents and environmental monitoring consistent with the guidance provided in GL 89-01.
3.0 TECHNICAL EVALUATION
The licensees amendment request proposes to adopt wording for TS Section 6.12, High Radiation Area, that is consistent with NUREG-1433, Rev. 2. The proposed change includes capping dose rates to differentiate a high radiation area from a very high radiation area, additional requirements for groups entering high radiation areas, and clarification of the need for communication with, and control of, workers in high radiation areas. The alternate controls relate to the protection of plant personnel from radiation hazards during normal plant operations and as such, the proposed change has no impact on the protection of the public from the consequences of any design basis accident or transient.
The NRC published 10 CFR 20.1601(c) to provide licensees a means for implementing alternative methods for controlling access to high radiation areas. Additionally, the NRC published the guidance contained in Regulatory Guide 8.38, Control of Access to High and Very High Radiation Areas in Nuclear Power Plants, which describes methods acceptable to the NRC staff for meeting the requirements. The licensees submittal conformed to Regulatory Guide 8.38; therefore, the NRC staff finds the proposed change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New Jersey State Official was notified of the proposed issuance of the amendment. The state official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes 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 amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 75884). Accordingly, the amendment meets 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 amendment.
6.0 CONCLUSION
The NRC staff 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 regulation, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. Taylor Date: January 30, 2003