ML20128L022
| ML20128L022 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/11/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128L004 | List: |
| References | |
| NUDOCS 9302190076 | |
| Download: ML20128L022 (3) | |
Text
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UNITED TTATES
[-
g NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.168 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY l
JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-289
1.0 INTRODUCTION
By letter dated August 9, 1991 and October 29, 1992, the GPU Nuclear Corporation (the licensee) submitted two requests for changes to the Three Mile Island Nuclear Station, Unit No.1 (TMI-1) Technical Specifications (TS). The requested changes would revise the Technical Specifications Bases addressing the minimum borated water storage volumes with respect to the loss of coolant accident (LOCA) linear heat rate (LHR) allowable limits.
Figure 3.5-2M, "LOCA Limited Maximum Allowable Linear Heat Rate," is revised to reflect the Babcock & Wilcox (B&W) re-evaluations of generic linear heat rate limits. The second requested change would remove Figure 3.5-2M from the TS and incorporate it into the THI-l Core Operating Limits Report (COLR).
2.0 EVALUATION By letter dated August 9,1991, the licensee requested a change that would revise TMI-l TS to reflect the B&W re-evaluation of the generic LOCA linear heat rate (LHR) allowable limits and to administratively update the Bases discussion associated with the minimum borated water storage volumes to ensure adequate shutdown margin.
To assure preservation of 10 CFR 50.46 acceptance criteria over entire core life, the licensee developed new LOCA LHR limits using NRC approved B&W emergency core cooling system (ECCS) evaluation model and fuel perfomance computer codes (TS section 6.9.5.2 new references 9 through 12). From the analysis, LOCA LHR are required to be reduced at the 6 o.
foot core evaluation from 16.5 to 16.1 Kw/ft at the beginning of core life (0
,@g to 1000 MWD /MTU*) and from 18.0 to 16.1 Kw/ft for above 1000 MWD /MTV.
To
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assure that internal fuel rod pressure does not exceed reactor coolant system E8 (RCS) pressure, the LHR limits are reduced at all core levels ae. a function of pg maximum rod average fuel burnup from 36,375 to 60,000 MWD /MTU.
Re-evaluation of the peak clad. temperatures at various fuel elevations using NRC approved M
analytical methods determined that peak centerline temperature (PCT) values meet the acceptance criteria using the new LHR limits. These re-evaluations 04 for the revised generic allowable LOCA LHR for BGW 177A lowered-loop plants 5
confirm the preservation of the acceptance criteria. These changes are 88 reflected in the revised Figure 3.5-2M.
o n.a
- Megawatt-days per metric ton of uranium
el I Application of B&W Topical Report BAW-1016P-A " TACO-3 Fuel Pin Thermal Analysis Computer Code" causes a new restriction on~ the end-of-life LOCA LHR limits. Accordingly, in order to maintain fuel rod internal pressure below RCS pressure for higher burnups, the allowable end-of-life LOCA !HR limits for all fuel assembly elevations are reduced based on the burnup of the limiting fuel rods.
Figure 3.5-2M incorporates a diagonally decreasing limit as a function of maximum rod average burnup from 36,37S to 60,000 MWD /MTV.
TS Section 3.2 Bases is revised to change the boric acid solution volume in the Borated Water Storage Tank (BWST) for emergency shutdown requirements from 40,000 gallons to a bounding value of 60,000 gallons. The required volume varies slightly as the core reactivity parameters vary from cycle to cycle.
The value is provided in the TS Bases for information only and is not related to any existing TS.equirements.
Existing TS 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.
By letter dated October 29, 1992, the licensee requested a change that would remove THI-1 Figure 3.5-2M from the TS and incorporate it into the COLR. The licensee's proposed changes to the TS are in accordance with the guidanco provided by Generic Litter 88-16, which allows the removal of cycle-specif'c parameter limits from TS. All changes in cycle-specific parameter limits are to be documented in the COLR before each reload cycle or remaining part of a reload cycle and submitted to the NRC prior to operation with the new parameter limits.
On the basis of the review of the above items, the NRC staff concludes that the licensee has provided an acceptable response to those items as addressed in the NRC guidance in Generic letter 88-16. Because plant operation continues to be limited in accordance with the values of-cycle-specific parameter limits that are established using NRC approved methodologies, the NRC staff concludes that this change is administrative in nature and there is no impact on plant safety as a consequence. Accordingly, the staff finds that the proposed changes are acceptable.
As part of the implementation of Generic Letter 88-16, the staff has also reviewed a sam)le COLR that was provided by the licensee. On the basis of this review, t1e staff concludes that the format and content of the sample COLR are acceptable.
3.0 STATE CONS!)LTATION In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
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 amendment also relates to changes in recordkeeping, reporting, or administrative procedures or requirements. 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 exporure. 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 (57 FR 34583 and 57 FR 58246). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (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 assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Francis Young Date:
February 11, 1993
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