ML20101H763
| ML20101H763 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 06/24/1992 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20101H736 | List: |
| References | |
| NUDOCS 9206300181 | |
| Download: ML20101H763 (3) | |
Text
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l C311-92-2060 I.
TECHNICAL SPECIFICATION CHANGE RE0 VEST (TSCR) N0. 215 GFUN requests that the attached revised page replace page 6-la of the THI-l Technical Specifications, 11.
Reason for the Chanae This request involves an :.dministrative change to Technical Specifications which designates the supervisory requirements for fuel loading and transfer which conform to 10 CFR 50.54 (m)(2)(iv).
Presently, TMI Technical Specification Section 6.2.2.2.f requires two licensed Senior Reactor Operators (SR0s), one in the Reactor Building and one in the Fuel Handling Building, to accomplish refueling activities.
This change deletes the wuirement for an SR0 to directly supervise fuel handling evolutions in the Fuel Handling Building but maintains the requirement for a licensed SR0 or SR0 Limited to Fuel Handling to directly supervise alterations in core geometry. Other fuel handling operations which may take place at the same time in the Fuel-Handling Building do not require the physical presence of another person with.the same degree of training.
SR0's, as defined in 10 CFR 55.4, are required to be present to direct any evolution that involves manipulating a control of the facility which affects the reactivity or power level of the reactor. The evolution that is relevant in this case is the manipulation of fuel in the core which directly effects the reactivity of the reactor; an evolution for which an SR0 is required.
Fuel handling operations in the Fuel Handling Building do not involve manipulating the controls of a reactor as defined in 10 CFR 55.4.
The fresh or irradiated fuel which is stored and moved in the Fuel Handling Building cannot affect the reactivity of the reactor and its handling and movement'is nct considered.a refueling operation.
III. Safety Evaluation Justifyina the Pronosed T.S. Chanae The proposed revised Technical Specification Section 6.2.2.2.f is consistent wii.h the regulatory requirement stated in 10 CFR 50.54 (m)(2)
(iv). The requirement is based on the need for the presence, during core alterations, of a dedicated person whose training exceeds the minimum requirements for a reactor operator in the areas of: conditions and limitations in the facility license, the facility's technicai specifications, procedures and limitations involved in core alterations, and fuel handling facilities and procedures. The THI Technical Specifications uses an alternate defined term " REFUELING OPERATIONS" instead of the equivalent term " core alterations" which is used in the Standard Technical Specifications.
9206300181 920624 PDR ADOCK 0S000289
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C311-92-2060
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i The effect of the proposed change would be to provide a level of supervision for REFUELING OPERATIONS and fuel movement activities which is consistent with present regulations.
This change will eliminate an unnecessary burden without compromising safety or safe plant operation.
TMI-l presently exceeds regulatory requirements but no apparent additional safety m;rgin is realized by the additional staffing position, l
IV.
No Sianificant Hazards Consideration Operation of the facility in accordance with the proposed amendment will have no adverse effect on nuclear safety or safe plant operations. The elimination of the requirement for a separate licensed SR0 to directly supervise irradiated fuel handling and transfer activities on site, and tha retention of the requirement for a licensed SR0 to directly supervise Rt. FUELING OPERATIONS is consistent with regulatory requirements.
GPUN has determined that this Technical Specification change request poses no significant hazards as defined by 10 CFR 50.92. Operation of the facility in accordance with proposed amendment will have no adverse effect on nuclear safety or safe plant operations as evaluated below.
1.
Operation of the facility in ac rdance with the proposed amendment w M d not involve a significant increase in the-probability of (ccureence or consequence of an accident previously evaluated.
De Rt' n of the requirement for a separate licensed SR0 to directly supervise irradiated fuel handling and transfer activities at locations other than.the Reactor Building is an administrative change which is consistent with regulatary requirements noted in 10 CFR 50.54 (m)(2)(iv).
2.
Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident'from any accident previously evaluated. The proposed amendment does not modify plant hardware operation or methods of handling fuel. The facility will continue to be operated within the limits of the existing accident analyses and margins of safety.
3.
Operation of the facility in accordance with the proposed amendment would not involve a significant. reduction in a margin of safety since the change contained in the proposed amendment does not change any existing safety margins.
V.
IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon issuance. -
At least two licensed Reactor Operators-shall be.
c.
t
-present in the control room during reactor:startup,-
i scheduled reactor shutdown and during recovery from j
d.
The Shift Supervisor or Shift Foreman #'shall be:in the control room at-all times other than cold shutdown conditions (T,,, < 200*F) when he shall be onsite.
e.-
An individual ## qualified _ pursuant to 6.3.2 in radiation protection procedures shall be on site when fuel is in the reactor.
f.
All REFUELING OPERATIONS shall be observed and directly supervised by either a licensed Senior Reactor ';,,erator or Senior Reactor Operator Limited to-Fuel Handling who has no-other concurrent responsibilities during.this operation.
1 g.
A Site Fire Brigade ## of at least 5 members shall'be i
maintained onsite at all-times. The Site Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit and any-personnel required for other essential _ functions l
during a fire emergency.
i h.
The Shift Technical Advisor shall' serve in an-advisory.
capacity to the Shift Supervisor on matters pertaining to i
the engineering. aspects assuring: safe operation of the.
unit.
i 6.2.2.3 Individuals who train tt e operating st ff i.nd those who carry out the health physics and quality assurance function shall have sufficient-i organizational freedom to be independent frc; operating = pressures, however they may report to the appropriate manager on site..
- The individual of item 6.2.2.2e and the Fire Brigade' composition may be less than the minimum requirements = for a period of time not-to exceed 2 hot;rs -
in order to accomn.odate unexpected absence provided immediate action is taken to fill the required. positions.
6-la l
Amendment JJ, H, 77, 139 2
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