ML17056C216
| ML17056C216 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/05/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056C215 | List: |
| References | |
| NUDOCS 9301130079 | |
| Download: ML17056C216 (6) | |
Text
~g RECT P0
~
Cy A0O
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 t
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
137 TO FACILITY OPERATING LICENSE NO.
DPR-63 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT NO.
1 DOCKET NO. 50-220
- 1. 0 INTRODUCTION By letter dated October 28,
- 1992, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit No.
1, Technical Specifications (TS).
The requested changes would revise TS 6.2.2.f.
and TS Table 6.2-1 to be consistent with current NRC requirements regarding supervision and performance of core alterations.
The current Nine Mile Point Unit 1
TS require that core alterations be supervised by a licensed Senior Reactor Operator and that a licensed Reactor Operator manipulate the controls of all fuel handling equipment except movement of new fuel from receipt through dry storage.
The proposed amendment would require that all core alterations be performed by qualified personnel and be supervised by a Senior Reactor Operator or by a Senior Reactor, Operator Limited to Fuel Handling.
- 2. 0 EVALUATION The staffing requirements during fuel movement and core alterations are specified in TS 6.2.2.f and TS Table 6.2-1.
The current TS requires that a
licensed Senior Reactor Operator shall be responsible for the movement of new and irradiated fuel within the site boundary.
The current TS also specify that only a licensed Reactor Operator may operate the controls of fuel handling equipment except for movement of new fuel from receipt through dry storage.
The proposed change would allow a licensed Senior Reactor Operator Limited to Fuel Handling as well as a licensed Senior Reactor Operator to supervise all core alterations.
The proposed change would also delete the requirement that only licensed Reactor Operators may operate the controls of fuel handling equipment; trained and qualified nonlicensed personnel would be permitted to operate the fuel handling equipment under the supervision of a licensed Senior Reactor Operator Limited to Fuel Handling or a licensed Senior Reactor 0'perator.
(
930ii30079 930i05 PDR ADOCK 05000220 P
n S
Senior Reactor Operators Limited to Fuel Handling have the same qualifications, skills, and receive the same training relative to fuel handling as licensed Senior Reactor Operators.
Their training includes appropriate areas of nuclear theory, plant systems, and plant procedures.
They are licensed in accordance with 10 CFR Part 55.
The Code of Federal Regulation at 10 CFR 50.54(m)(2)(iv) requires that a person holding a Senior Reactor Operator license or a Senior Reactor Operator Limited to Fuel Handling license directly supervise core alterations and shall not be assigned other duties during this time.
The proposed change also requires another Senior Reactor Operator to be in the control room during core alternations.
The proposed change for having Senior Reactor Operators or Senior Reactor Operators Limited to Fuel Handling supervise core alterations at NMP-1 meets the requirements of 10 CFR 50.54(m)(2)(i) and 10 CFR 50.54(m)(2)(iv) and is, therefore, acceptable.
Personnel designated to operate the fuel handling equipment in accordance with the proposed change will be skilled and qualified technicians who have been trained to use NMP-1 fuel handling equipment and procedures.
The Code of Federal Regulations at 10 CFR 55. 13(b) does not require a Reactor Operator license for individuals who, under the direction and in the presence of a licensed senior operator, manipulate the controls of fuel handling equipment.
The proposed change permitting nonlicensed personnel to operate the NMP-1 fuel handling equipment meets the requirements of 10 CFR 55. 13(b) and is, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendment relates to changes in administrative procedures and requirements.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
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.
e
'0
- 5. 0 CONCLUSION The Commission has concluded, based on the considerations discussed
- above, that:
(I) 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 Commission's regulations, 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:
D. Brinkman Date: january 5, 1993
C a