ML20248H261
| ML20248H261 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/04/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20248H255 | List: |
| References | |
| NUDOCS 8910110237 | |
| Download: ML20248H261 (6) | |
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. METROPOLITAN EDISON COMPANY p
JERSEY CENTRAL POWER & LIGHT COMPANY-7 AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating' License'No. DPR-50 Docket No. 50-289-Technical Specification Change Request No.196 ThisL echnical Specification Change Request is submitted in support of Licensee's T
request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.-
As a,part of this request, proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION.
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BY:
h ViEe President & Director, TMI-1 Sworn'and Subscribed to'before me this MA day of &cie /w,1989.
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sMHD Notary Public Shamn P
. Notary Pubic bJuly1 1
M Member, PemsyMna Assocuson of M l
8910110237 891004 PDR ADOCK 00000289 P-PDC
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f UNITED STATES '0F AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO.~50-289 LGPU NUCLEAR-CORPORATION' LICENSE NO.' DPR-50 CERTIFICATE OF SERVICE e
-This is to' certify that'a copy of. Technical Specification Change Request No. 196
-to-Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has,'on the date given'below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit.in the United States mail, addressed as follows:
Mr. Kenneth E. Witmer, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County 25 Roslyn Road Dauphin' County Courthouse
.Elizabethtown, PA' 17022 Harrisburg, PA 17120 Mr. Thomas Gerusky, Director
-PA. Dept.gof Environmental Resources Bureau of Radiation Protection
- P.O. Box 2063 Harrisburg, PA 17120; GPU NUCLEAR CORPORAT i
j BY:
Vi~ce Pre &ident & Director, TM1-1 DATE:
October 4, 1989 1
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TECHNICAL 5PECIFICATONCHANGEREQUEST(TSCR)NO.196 GPUN requests that the following changed replacement pages be inserted into the existing Technical Specifications:
Revised pages: 3-16, 3-20, 3-34a, 3-45 Revised figure: 3.5 - 2M These pages are attached to this change request.
II. REASON FOR CHANGE The moderator temperature coefficient specified in Technical Specification Section 3.1.7.2 and Bases is revised to utilize margin previously described in the TMI-1 FSAR which will provide additional flexibility for future cycle core designs. The_ Bases are also revised to delete reference to the correction factor verification performed on earlier B&W reactors which is no longer appropriate.
l Technical Specification Section 3.2 Bases is administrative 1y changed to include a bounding value for BWST water volume required for an emergency shutdown.
Technical Specification Section 3.5.2.4.f is administratively changed to clarify which tilt limit (maximum) in the Core Operating Limits Report (COLR) shall be used to comply with the specification.
Technical Specification Section 3.8 Bases is administratively changed to remove reference to an example value for the refueling boron concentration.
Technical Specification Figure 3.5-2M is revised to increase the 2-foot elevation Allowable Linear Heat Rate (LHR) limits from 14.0 to 14.5 kw/ft for 0-1000 MWD /MTU and from 15.0 to 15.5 kw/ft after 1000 MWD /MTU.
III. SAFETY EVALUATION JUSTIFYING CHANGE The moderator temperature coefficient (MTC) specified in Technical Specification Section 3.1.7.2 is revised from < 0.5 x 10-"Ak/k/F to < 0.9 x 10-*ok/k/F. This change is made to utilize existing margin in the~
1 TMI-1 FSAR accident analyses, and will provide additional flexibility for future cycle core designs. The Startup Accident is the most limiting accident analysis for accidents which are sensitive to the Beginning-of-Cycle MTC.
For this accident, the existing FSAR Chapter 14 provides a sensitivity study which examines the effects of changes in the MTC from -0.6 x 10-* to +1.0 x 10-*Lk/k/F. Over this range of MTC, the peak thermal power varied only 15% of full power and remained well below the design thermal overpower and RCS peak pressure acceptance criteria for this accident. Therefore, the proposed MTC increase from +0.5 x 10-* to
+0.9 x 10-*ak/k/F is considered bounded by the existing FSAR Chapter 14 Startup Accident analysis, and the existing accident analysis acceptance criteria and margins of safety are maintained.
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i Deletion of the Bases statement references of the correction factor verification performed on earlier B&W reactors is purely an editorial change since this statement is historical and is no longer appropriate.
Technical Specification Section 3.2 Bases is revised to change the boric acid solution volume in the Borated Water Storage Tank for emergency shutdown requirements (BWST) from 32,112 gallons to a bounding value of 40,000 gallons. The required volume varies slightly as the core reactivity parameters vary from cycle to cycle. The value is provided in the Technical Specification Bases for information only and is not related to any. existing Technical Specification requirement.
Existing Technical Specification Section 3.3.1.1 bounds this value by specifying that the BWST shall contain a minimum volume of 350,000 gallons of water having a minimum concentration of 2270 ppm boron. Therefore, the proposed change is administrative.
Technical Specification Section 3.5.2.4.f is revised to clarify that the
" maximum" tilt limit defined in the COLR shall be used to comply with this specification. This clarification was omitted when the tilt limits were removed from the Technical Specifications and placed into the COLR.
Existing Cycle 7 Reload analyses support use of the term " maximum".
No change to the COLR is required since the tilt values in the COLR remain the same. Prior to the COLR, the same tilt values were specified in the Technical Specification and were utilized as " maximum" values. Therefore, the proposed change provides additional clarification and is administrative.
Technical Specification Section 3.8 Bases is revised to remove the reference to 1800 ppm refueling boron concentration. The method for calculating the refueling boron concentration referenced in Technical Specification Section 3.8.4 is presented in the existing Technical Specification Section 3.8 Bases. The calculational method remains unchanged. This value does not provide the basis for the existing specification. Therefore the proposed change is administrative.
Technical Specification Figure 3.5-2M is revised to reflect an increase in the Allowable LHR limits at the 2-foot elevation from 14.0 to 14.5 kw/ft for 0-1000 MWD /MTU and from 15.0 to 15.5 kw/ft after 1000 MWD /MTU. This change causes the LHR limits at 1000-2600 MWD /MTU and for After 2600 MWD /MTU to be the same, thereby allowing the later burnup window to be eliminated; The change from 14.0 kw/ft to 14.5 kw/ft for 0-1000 MWD /MTU is based on a standard ECCS licensing calculation that was performed at the 2-foot core elevation, beginning-of-life (BOL), for a 50 psi reduction in fuel rod pre-pressure. This analysis was performed generically for the B&W lowered loop configuration plant Mark-B4 fuel rod design using the BAW-2 critical heat flux correlations. The results of the analysis are reported in BAW-2001P, (reference Attachment 3). The BOL results were then extrapolated to the next burnup window allowing this value also to be increased by 0.5 kw/ft.
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3 The effects of Mark-BZ fuel and the BWC critical heat flux correlation on the results of the ECCS analysis described in BAW-2001P have been evaluated. This evaluation concluded that the increase in core pressure drop due to the Zircaloy spacer grids in the Mark-BZ design would not affect the thermal hydraulic conditions at the 2-foot elevation and thus not affect the LOCA limits established for the Mark-B4 fuel. The change in CHF correlation from the BAW-2 to the BWC correlation has no effect on the predicted time of DNB at the 2 foot core elevation for the B&W lowered loop configuration plants. The proposed change preserves the existing ECCS acceptance criteria required by 10 CFR 50.46, as demonstrated in BAW-2001P.
The existi~ng FSAR References listed on the above affected Bases Sections of Technical Specification Sections 3.1.7,3.2, and 3.B are revised to indicate "UFSAR" rather than "FSAR."
UFSAR is the proper title for reference to the TMI-1 Updated Final Safety Analysis Report. This change in nomenclature is purely editorial.
IV. NO SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this Technical Specification Change Request poses no significant hazards as defined by NRC in 10 CFR 50.92.
1.
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated. The proposed revisions to the MTC, and Allowable LHR limits preserve the existing acceptance criteria for the design basis accidents of concern and maintains the existing ECCS acceptance criteria.
Therefore, operation in accordance with the proposed amendment does not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
2.
Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of 1
accident from any previously evaluated. The proposed amendment ensures the plant will be operated in accordance with limits that maintain existing accident analysis and ECCS acceptance criteria and margins of safety, and is unrelated to the possibility of creating a new or different kind of accident.
3.
Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety. The proposed revisions to the MTC and the Allowable LHR limits preserve j
the existing margins of safety defined in the TMI-1 FSAR Chapter 14 Accident Analyses and Technical Specification Bases. Therefore, it 1
is concluded that operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety.
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' The Comission has. provided guidelines pertaining to the application of the three standards by listing specific examples in 48 FR 14870. The proposed amendment is considered to be in the same category as example (i) of amendments.that are-considered not likely to involve significant hazards consideration in that the proposed change is an administrative change _to the Technical Specification to allow operation at revised MTC and Allowable LHR limits.which maintain the acceptance criteria of original safety analyses and preserve the ECCS acceptance criteria; and to incorporate other purely editorial revisions. Thus, operation of the facility.in
.accordance with the proposed amendment involves no significant hazards considerations.
V.
IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon issuance.
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