ML20126H962
| ML20126H962 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/21/1992 |
| From: | Stephen Dembek Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126H965 | List: |
| References | |
| NUDOCS 9301050377 | |
| Download: ML20126H962 (5) | |
Text
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,1 NUCLEAR REGULATORY COMMISSION o,
,a WASHINoToN. D.C. 20565 PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No.56 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The applications for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated June 4, 1992 and July 8, 1992, as supplemented by letters dated September 1, 1992, October 6, 1992, and November 16, 1992, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's ru.es 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:
(1) 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 ccaducted in compliance with the Commission's 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 Commission's 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:
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. (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No, 56, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G 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 of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0 %ds Akbbs Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Neember 21, 1992
ATTACHMENT TO LICENSE AMENDMENT NO. s6 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Overleaf page provided to maintain document completeness.*
Remove Insert 6-5 6-5*
6-6 6-6
4 TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION SIKGLE UNIT FACILITY POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 SNSS*
1 1
NSS*
1 None NCO 2
1 E0 2
1 STA 1
None RPT 1
1 TABLE NOTATION SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator license on the Unit NSS
- Nuclear Shift Supervisor with a Senior Reactor Operator license on the Unit NCO
- Nuclear Control Operator with a Reactor Operator license on the Unit EO
- Equipment Operator STA
- Radiation Protection Technician Except for the Senior Nuclear Shift Supervisor, the shift crew composition may be one less than the minimum requirements of Table 6.2.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the-shift crew compo-sition to within the minimum requirements of Table 6.2.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shif t crewman being late or absent.
During any absence of the Senior Nuclear Shift Superviste from the control room while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual with a valid Senior Reactor Operator license shall be designated to assume the control room command function.
During any absence of the Senior Nuclear Shift Supervisor from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Reactor Operator license or Operator license shall be designated to assume the control room command function.
"In cases where an individual has a Senior Reactor Operator's license on the unit, is a qualified STA, and has a Professional Engineers License by virtue of successful completion of the Professional Engineers examination or a bachelor's degree in a scientific, engineering, or engineering technology discipline from an accredited institution, the individual can serve in a dual role capacity as either the SNS$/STA or NSS/STA.
(Note:
For those individuals with a bachelor's degree in a scientific or engineering technology discipline, course work must have included physical, mathematical,-or engines.'ing science.)
Otherwise, there shall be a qualified STA as well as a SNSS and NSS on-shift.
l Amendment ygg g g
5 HOPE CREEK 6-5
i ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Adsisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI /ANS 3.1-1981 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the individual designated as the operations manager who shall meet or exceed the minimum qualifications of ANSI /ANS 3.1-1981 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10 CFR Part 55.
6.3.2 The Operating Engineer, Senior Nuclear Shift Supervisors, and Nucl' ear l
Shift Supervisors, shall hold a senior reactor operator license.
The Nuclear Control Operators shall hold a reactor operator license.
6.3.3 The Operations Manager shall meet one of the following:
(1) Hold a senior reactor operator license, or (2) Have held a senior reactor operator license for this or a similar unit (BWR).
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall:
- 1) be maintained under the direction of the Manager-Nuclear Training, 2) shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI /ANS 3.1-1981 for all affected positions except licensed optrators, and 3) comply with the requirements of 10 CFR Part 55 for licensed operators.
. 4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the require-ments of the SRP (NUREG-00^0) Section 13.2.2.II.6, 10 CFR 50 Appendix R and Branch Technical Position CMEB 9.5.1, Section C.3.d.
6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC)
FUNCTION 6.5.1.1 The SORC shall function to advise the General Manager - Hope Creek Operations on all matters related to nuclear safety.
HOPE CREEK 6-6 Amendment No. 56
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