ML17251A114
| ML17251A114 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/31/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A116 | List: |
| References | |
| NUDOCS 8806130131 | |
| Download: ML17251A114 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
G AMEN R PLANT ENSE Amendment No.
28 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated December 28, 1987 as clarified on May 5, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will oper ate 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 Commission's regulations; 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.
DPR-18 is hereby amended to read as follows:
PDR ADOCK 0500024<4 P
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2g, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications'.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technica1 Specifications Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II Date of Issuance:
~qy 31 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATIN(~ LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT ll 6.2-1 6.2-2 6.2-3 6.2-4 6.2-5 6.2-6 6.2-7 11
- 6. 2-1 6.2-2*
6.2-3 6.?-4
- No change - repositioned on page
TABLE OF CONTENTS (cont'd) 4.8 4.9 4.10 4.11 4.12 4.13 4.14 4.15 4.16 Auxiliary Feedwater System Reactivity Anomalies Environmental Radiation Survey Refueling Effluent Surveillance Radioactive Material Source Leakage Test Shock Suppressors (Snubbers)
Fire Suppression System Test Overpressure Protection System Pacae 4.8-1 4.9-1 4.10-1 4.11-1 4.12-1 4.13-1 4.14-1 4.15-1 4.16-1 5.0 DESIGN FEATURES 5.1 5.2 5.3 5.4 5.5 Site Containment Design Features Reactor Design Features Fuel Storage Waste Treatment Systems 5.1-1 5.2-1 5.3-1 5.4-1 5.5-1 6.0 ADMINISTRATIVECONTROLS 6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.8 6.9 6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17 Responsibility Organization 6.2.1 Onsite and Offsite Organization 6.2.2 Facility Staff Station Staff Qualification Training Review and Audit 6.5.1 Plant Operation Review Committee (PORC) 6.5.2 Nuclear Safety Audit and Review Board (NSARB) 6.5.3 Quality Assurance Group Reportable Event Action Safety Limit Violation Procedures Reporting Requirements 6.9.1 Routine Reports 6.9.2 Unique Reporting Requirements Record Retention Radiation Protection Program (Deleted)
High Radiation Area (Deleted)
Offsite Dose Calculation Manual Process Control Program Major Changes to Radioactive Waste Treatment Systems 6.1-1 6.2-1 6.2-1 t
6.2-2 6.3-1 6.4-1 6.5-1 6.5-1 6.5-5 6.5-11 6.6-1 6.7-1 6.8-1 6.9-1 6.9-1 6.9-3 6.10-1 6.11-1 6.13-1 6.15-1 6;16-1 6.17-1 Amendment No.
p, p8
6.2 ORGANIZATION 6.2.1 Onsite and Offsite Orcranization An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all Plant management positions.
Those relationships shall be documented and
- updated, as appropriate, in the form of organization charts.
These organization charts will be documented in the UFSAR and updated in accordance with 10CFR50.71.
b.
The Senior Vice President, Production and Engineering, shall have corporate responsibility for overall Plant nuclear
- safety, and shall take any measures needed to assure acceptable performance of the staff in operating, maintaining, and providing technical support in the Plant so that continued nuclear safety is assured.
- c. The Ginna Station Superintendent shall have responsibility for overall unit operation and shall have control over those resources necessary for safe operation and maintenance of the Plant.
6.2-1 Amendment No.,
28
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d.
The persons responsible for the training, health physics and quality assurance functions may report to an appropriate manager onsite, but shall have direct access to responsible corporate management at a level where action appropriate to the mitigation of training, health physics and quality assurance concerns can be accomplished.
6.2.2 Facilit Staff The Facility organization shall be subject to the following:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2=1.
b.
At least one licensed Operator shall be in the control room when fue1 is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recover from reactor trips caused by transients or emergencies.
d.
All core alterations shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
e.
An individual qualified 'in radiation protection pro-cedures shall be on site when fuel-is in the reactor.
- 6. 2-2 Amendment Ng; 28
f.
A Fire Brigade of 5 members shall be maintained on site at all times.
This excludes the two members of the minimum shift crew necessary for safe shutdown.
g.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions including senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.
Changes to the guidelines for the administrative procedures shall be submitted to the NRC for review.
Fire Brigade composition may be less than the minimum requirements 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 /> to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to the minimum requirements.
Amendment No. gP, gP, 28 6.2-3
Table'.2-1 MINIMUMSHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION RCS Above Cold Shutdown Cold Shutdown 6 Refueling SS SRO RO AO STA 1
None 1
1 None SS - Shift Supervisor with a Senior Reactor Operators License SRO Individual with a Senior Reactor Operators License RO Individual with a Reactor Operators License AO Auxiliary Operator STA Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 Composition to within the minimum requirements of Table 6.2-1., This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is above Cold Shutdown, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function.
During any, absence of the Shift Supervisor from the Control Room while the unit is in Cold Shutdown or Refueling, an individual with a valid SRO or RO license shall be designated to assume the Control Room command function.
6.2-4 Amendment No., JP, fP, 28