ML20246K565
| ML20246K565 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/13/1989 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20246K544 | List: |
| References | |
| NUDOCS 8907180208 | |
| Download: ML20246K565 (4) | |
Text
[. _.
- q. * :.;g.
L----------
[
M TROPQ ITAN' EDISON COMPANY JERSEY CENTRAL: POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY l-
~
.GPU NUQ. EAR THREE MILE IS.AND NUQ_ EAR STATION UNIT II-
- Operating License No. DPR,. Docket No. 50-320 Technical Specification Change Request No. 62, Supplement f The Technical Specification Change Request is submitted in' support of Licensee's request to change Operating License No. DPR-73 for Three Mile Is' land Nuclear Station Unit 2.
As'a part of this request, proposed replacement pages for Appendix A are also included.
GPU NUQ. EAR is By Director, TMI-2 Sworn and ' subscribed to me this 13th day of July
, 1989.
)
t) 1 V
h-Notary Public NOTARIAL SEAL ERIN MICHELLE LEBo, NOTARY PUBLIC i ~
LONDoNDERRYTWP., DAUPHIN COUNTY MYCOMMISSioN EXMES SEFT.11.1989 u
Memt*,Pennsylonia Assoontonof Notaries H
8907180200 890713 PDR ADOCK 05000320 P
PNU g
/
.uA___--------.-'__----
...aI._
UNITED STATES OF AMERICA NUQ EAR REGU ATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-320 LICENSE NO. DPR-73 GPU NUQ_ EAR This is to certify that a copy of Technical Specification Ctiange Request No. 62, Supplement 1, to Operating License DPR-73 for Three Mile Island Nuclear Station Unit 2 has been filed with the U.S. Nuclear' Regulatory Commission and served to the chief executives of 1) Londonderry Township, Dauphin County, Pennsylvania; 2) Dauphin County, Pennsylvania; and 3) the designated official of the Commonwealth of Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Jay.H. Kopp, Chairman Ms. Sally Klein, Chairperson Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, PA 17057 Harrisburg, PA 17120 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection PA Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 GPU NUO. EAR By Director, TMI-2 July 13,1989 Date l
l
m, y
s jg l
},
l
'Three Mile Island Nuclear Station, Unit:2'_(TMI-2) 4 Operating License DPR-73 4
E Docket No. 50-320L ly :,1 LTechnical Specification Change ReQJestl(TSCR) No.'62, Supplement 1 GPU Nuclear requests that attached _Page 6-11 of the TMI-2 Technical
. Specifications-(Tech._ Specs.) replace existing Page 6-11 of the Tech. Specs.
This proposal supplements the changes' requested by TSCR No. 62 (reference GPU Nucleal letter.4410-883-L-0191, dated December 27, 1988). 'The attachment'also
- reflects a change. submitted by-TSCR No.~ 60.
[
- Description of Change The proposal adds tihe following note to Tech. Specs. 6.8.3.1.b, "(Note:.The requirement.for' a' Senior Reactor Operator's License applies during Model1.
.only)."
Reason for Change l_
. Tech.-Specs. 6.8.3.1.b specifies that a condition for making temporary changes to procedures of! Tech. Specs. 6.8.1 is:
"For those procedures which affect the operational status of unit systems or equipment,.the change is approved by
- two members of.the unit management staff, at least one'of which holds a. Senior Reactor.: Operator's License." Following the completion of Mode 1-(i.e., end of-defueling) licensed operators will no longer be required at TMI-2.Thus, the requirement-of Tech. Specs. 6.8.3.1.b which pertains to a senior licensed operator _will no longer apply following the completion of Mode.l.
Itlis' noteworthy'that the. initial submittal of TSCR No.L 62 proposed a similar type change to Tech., Specs. 6.3.1 to. note:an-exception for licensed operators following the completion of Mode 1.
Thus, the attached change is consistent'
-with the initial' submittal of TSCR No. 62.'
~
Justification of. Change The proposed change _is consistent with the current TMI-2 Tech. Specs, as approved by NRC License Amendment No. 30 dated May 17, 1988. This amendment
- modified. Tech. Spec. 6.2.2 such that licensed. operators are no longer required
.at:TMI-2 following Mode 1.
The safety. evaluation attached to this license amendment ~ states, "The requirements for licensed operators are specified in 10 CFR 50.54 for fueled' nuclear power plants. _Upon transition from Mode 1, the facility will.no longer be considered fueled and these requirements will no longer apply. The staff finds the proposed change acceptable." Thus, the attached change, to delete the requirement for a Senior Reactor Operator to approve certain procedure changes, is administrative in nature to ensure consistency.within the TMI-2 Tech. Specs.
It is also noteworthy that this change does not affect the other requirements for making temporary changes to procedures including the requirement for a supervisory person within the
' department having cognizance of the procedure being changed to approve the
-change.
x -
No Significant Hazards Consideration 10 CFR 50.92'provides the criteria.which the Commission uses to evaluate a No Significant; Hazards Consideration. 10 CFR 50.92 states that an amendment to a facility license involves No Significant Hazards if operation of the facility in accordance with the proposed amendment would not:
1.
Involve a significant increase in~the probability or consequences of an accident previously evaluated, or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated, or 3.
Involve a significant reduction in a margin of safety.
The proposal is an administrative change to ensure consistency within the current TMI-2 Tech. Specs. During Modes 2 and 3, the current requirements of Tech. Specs. 6.8.3.1.b for making temporary changes to procedures required by Tech. Specs. 6.8.1 will continue to apply with the exception that the requirement for approval by a Senior Reactor Operator will not apply.
The requirements of Tech. Specs. 6.8.3.1 are primarily intended for operating power reactors. During Modes 2 and 3, TMI-2 will continue to be in a stable, shutdown condition. Fuel will have been removed to the extent practicable and the remaining fuel will be in a geometric configuration that precludes criticality. Thus, the proposed change does not involve a significant increase in the probability or consequence of an accident, create the possibility of a new or different kind of accident, or involve a significant reduction in the margin of safety since fuel-related accidents, for which licensed operator training is considered necessary to ensure an adequate response, are no longer possible. Based on the above, GPU Nuclear concludes that No Significant Hazards is involved in the proposed change.
t
. - _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ - - _ _ - _ _ _ _