ML20116C718
| ML20116C718 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 10/28/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20116C717 | List: |
| References | |
| NUDOCS 9211050004 | |
| Download: ML20116C718 (5) | |
Text
. - - - - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMi'ANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE 'SLAND NUCLEAR S1ATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 222 This icchnical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for lhree Mile Island Nuclear Station, Unit 1.
As a part of this request, a proposed replacement page for Appendix A is also included.
GPU NUCLEAR CORPORATION b-BY:
Vice Presiddit and Director, THI-l Signed and sworn before me this 28th day of October
, 1992.
'/?[/[g/hs'/('Mt16tl[c-Notary Public (N
7 L 1",Nm
% (c.a men L.;u 3A 9 21, ton Wnbar, Punrc/ada /emm of Wrres 9211050004 921028 PDR ADOCK 05000289 j-P PDH
e UNITED STATES Of AMERICA NI' CLEAR REGUL ATORY COMMISSION IN THE MATTER Of DOCKET NO. 50-289 GPU NUCLEAR CORPORATION LICENS" NO. UPR-50 CERTlflCATE OF SERVICE This is to certify that a copy of Technical St.ecification Change Request No. 222 to Appendix A of the Operating Licensa for 'ihree Mile Island Nuclear Station Unli 1 has been filed on the date given below with the executives of Londonderry Township, Dauphin County, Penn ylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Er.vironmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kapp, Chairman Mr. Russell L. Sheaffer, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Mr. William P. Dornsife, Director PA. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 liarrisburg, PA 17120 GPU NUstEA" CORPORATION BY:
Vice President 0and Director, THI-l DATE:
10/28/92
1 C311-92-2134 1.
TECHNICAL TPElflCATION CHANGfl00EST fTSCR) NO 222 GPUN requests that the attached n vised page replace 3-22 of the THI-l l
Technical Specifications.
)
Reason for the Change This requested change to the Technical Specifications (TS) will eliminate the requirement to place the plant in the COLD SHUTDOWN cond.i. ton when ona train of an affected system included in TS 3.3.1 is not restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following initiation of maintenance activities while the plant is operating. The more appropriate course of action when one train of an affected system is determined to be inoperable and the reactor is critical is to place the plant in the 110T SHV100WN condition; i.e., the first lower operating plant condition with the reactor sub-critical, in accordance with TS 3.0.1, if system (s) included in TS 3.3.1 are determined to be inoperable for any reason, the plant shall be placed in HOT STANbBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and il0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Deleting the current requirement in TS 3.3.2 to place the plant in COLD SHUTDOWN and substituting a requirement to take action in accordance with TS 3.0.1 will make the system inoperability requirements in TS 3.3.1 and 3.3.2 consistent.
Additionally, paragraph 3.3.2 has been changed to specify reactor operation vice power operatinn te be consistent with TS 3.3.1.
111.
Safety Evaluation Justifyino the Proposed T.S. Chance The THI-l Technical Specification (TS) for ECC Systems operability is in effect when the reactor is critical.
The reactor is critical in only three conditions: POWER OPERATION, REACTOR CRITICAL and HOT STANDGY.
The first lower operating condition where tht: reactor is not critical is the HOT SHUTDOWN condition.
When a component becomes inoperable and cannot be returned to OPERABLL status within the required completion time, the plant must be brought to a condition in which the LC0 does not apply. This is the basis for TS 3.0.1.
In the specific case of TS 3.3.1, where ECC systems must be operable for the reactor to be made critical, the first_ condition where the LC0 does not apply is the HOT SHUIDOWN condition. The LC0's for equipment and components included in TS 3.3.1 are specified in TS 3.0.1 and TS 3.3.2 depending on the circumstances involved. LC0 3.0.1 requires, in the case of 1S 3.3.1, that the plant be placed in HOT SHUTDOWN when one redundant train / component is inoperable. TS 3.3.2 requires the plant to be placed in COLD SHUTDOWN if the specified systems cannot ce restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This is not consistent with TS 3.0.1 which requires HOT SHUTDOWN for inoperability of a given redundant train of ECC systems..
{
C311-92-2134 i
Additionally, for the Decay Heat Removal Systems, it is not advisable to place the plant in COLD SHUTDOWN with only one operable train, as would be required by current TS if maintenance was being conducted and a problem occurred requiring a determination of inoperability.
The Decay Heat Systems are the primary means of plant cooling when the reactor is at less that 200 degrees F.
Requiring near term entry into a plant condition where a single train of a redundant component or system may be recuired to safely and reliably maintain plant temperatura woulc not be the best option.
This would be the case if the plant were placed in COLD SHUTDOWN with one train of Decay Heat Removal inoperable.. TS 3.4.2 also recognizes that both Decay Heat Rer40 Val trains may be needed to safely maintain plant temperature when the plant is cooled down to less than 250 degrees F.
IV.
No Sianificant Hazards Consideration Operation of the facility in accordance with the proposed amendment will have no 3dverse effect en nuclear safety or safe plant o, erations. The i.11mination of the requirement to place the plant in COLD SHUTDOWN when e given train of an ECC system is declared inoperable during mairitenance activities is consistent with the requirements specifieo in Section 3.0.1 of the Technical Specifications (TS).
The reactor will be required to be shutdown and placed in the HOT SHUTDOWN condition which is consistent with the FSAR accident analysis.
The basis of the revised Standard Technical Specifications for the ECCS Operating condition, required actions, also references this situation.
GPUN has determined that this Technical Specification change Request poses no significant hazards as defined by 10CFR-50.92. Operation of the-facility in accordance with the proposed amendment will have no adverse effect on nuclear safety or safe plant operation as evaluated below:
)
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequence of an accident previously evaluated. At least two trains of ECC systems and-equipment will continue to be required to be operable when the reactor is critical.
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 previously evaluated. The-requirement to place the plant in HOT SHUTDOWN is consistent with the actions required due to inoperability of-any ECC System, independent of the initiating circumstances.
3.
Operation of the facility 1:1 accordance with-the proposed amendment would not involve a significant reduction in the margin of safety since the change contained in the proposed amendment-does not change any existing safety margins.. - -
8 a
C311-92-2134 1&_LiMENTAT10N It is requested that the amendment authorizing this change become effective upon issuance, W
3. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. _ -_ -