ML17164A961
| ML17164A961 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/17/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17164A960 | List: |
| References | |
| NUDOCS 9902230100 | |
| Download: ML17164A961 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATIONBYTHE OFFICE OF NUCLEAR REACTOR REGULATION RELATINGTO AMENDMENTNO.
TO LICENSE NO. NPF-22 PENNSYLVANIAPOWER AND ELECTRIC COMPANY SUS UEHANNASTEAM ELECTRIC STATION UNIT2 DOCKET NO. 50-388
1.0 INTRODUCTION
By letter dated August 4, 1998, as supplemented by letters dated December 16, 1998,
'anuary 12, 1999, and January 28, 1999, PP8L, Inc. (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station (SSES), Unit 2, Technical Specifications (TSs). The requested changes include the Minimum Critical Power Ratio (MCPR) safety limits for ATRIUM'-10 fuel which is consistent with Siemiens Power Corporation (SPC) 9X9-2 fuel.
The SSES-2 Cycle 10 core has 764 fuel assemblies, which consist of 280 fresh ATRIUM'-10 assemblies, 312 once-burned ATRIUMTM-10assemblies, 168 twice-burned 9X9-2 assemblies and 4 twice-burned GE-12 lead use assemblies (LUAs). The December 16, 1998, January 12, 1999, and January 28, 1999, letters provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 EVALUATION The licensee requested a change to the SSES-2 Cycle 10 TSs in accordance with 10 CFR 50.59, 50.90, and 2.101. The proposed revision of TSs 2.1.1.2, 5.6.5 and the associated Bases 2.1.1.1, 2.1.1.2, and 3.2.2 is described below.
2.1 TS 2.1.1.2 The following changes are proposed for TS 2.1.1.2 Safety LimitMCPR (SLMCPR):
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- 1) Delete Figures 2.1.1.2-1 and 2.1.1.2-2 including the footnote indicating that the MCPR Safety Limitis only approved for Unit 2 Cycle 9, and
- 2) Single value MCPR Safety Limits of 1.11 for two recirculation loop operation or 1.12 for single recirculation loop operation are proposed to replace the flowdependent MCPR Safety Limitwhen the reactor steam dome pressure is greater than or equal to 785 psig and core flowis greater than or equal to 10 million Ibm/hr.
For the Cycle 10 SLMCPR analyses, the licensee has used the approved ANFB-10 correlation forATRIUM'-10 fuel and the ANFB correlation for SPC 9x9-2 fuel to support the TS changes.
Based on our review of the licensee's submittals, the staff finds that the proposed TS changes for the SLMCPR of 1.11 for two recirculation loop and 1.12 for single recirculation loop in 9902230100 9902i7 PDR ADQCK 05000388 PDR Cycle 10 operation are acceptable.
The basis of the staff's acceptance is that boiling transition is predicted. using approved critical power correlations and a minimum critical power ratio value is specified such, that at least'99.9% of the fuel rods'are expected to avoid boiling transition during normal or anticipated operational occurrences.
The flowdependent MCPR Safety Limits are replaced by single value SLMCPRs using the approved ANFB-10 correlation. Therefore, the deletion of Figures 2.1.1.2-1 and 2,1.1.2-2, which are no longer applicable to SSES-2 Cycle 10 operation, is acceptable.
2.2 TS Bases 2.1.1.1, 2.1.1,2, and 3.2.2 The proposed changes to the Bases are merely to reflect the use of the ANFB-10 correlation for ATRIUM-30fuel and to update its associated approved methodology in the references.
The range of the applicability of the ANFB-10 correlation is valid for pressures greater than 571 psi and bundle mass fluxes greater than 0.115x10'Ib/hr-ft'. Therefore, the proposed changes are acceptable.
2.3 TS 5.6.5 Core Operating Limits Report The staff has reviewed the proposed changes to the list of approved methodologies in TS 5.6.5.b and found them acceptable.
These changes revise the list of methodologies to delete references that are no longer directly related to the generation of Core Operating Limits and to add two NRC-approved ANFB-10 topical reports to the list of approved methodologies.
These two new topical reports, used in the Cycle 10 specific operating limits, are EMF-1 997 (P)(A)
Revision 0, "ANFB-10 Critical Power Correlation," July 1998, and EMF-1997 (P)(A) Supplement 1 Revision 0, "ANFB-10 Critical Power Correlation: High Local Peaking Results," July 1998, both listed as number 19, in the list of app'roved methodologies.
The use of these NRC-approved methodologies, which are appropriate for use at SSES-2, will ensure that values for cycle-specific parameters are determined such that all applicable limits of the plant safety analyses are met.
Based on the review, we conclude that the proposed TS revisions are acceptable for SSES-2, Cycle 10 application.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State officialwas notified of the proposed issuance of the amendment.
The State Official had no comments.
4.0 ENVIRONMENTALCONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves,no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 48262). The'amendment also relates to changes in recordkeeping, reporting, or
administrative procedures or requirements.
Accordingly, the arriendment meets the eligibility criteria for categorical exclusions set forth in 10 CFR 51.22(c)(9) and (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.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assu'rance that the health and safety of the public willnot be endangered by operatioh in the proposed manner, (2) such activities willbe conducted in compliance with the Commissio'n's regulations, and (3) the issuance of the amendment willnot be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
T. Huang Date: February 17, 1ggg