ML20236X117
| ML20236X117 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/01/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236X116 | List: |
| References | |
| NUDOCS 8712080431 | |
| Download: ML20236X117 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
5 fj WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT-NO.135 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289
1.0 INTRODUCTION
By letter dated March 5, 1987 (Ref. 1), General Public Utilities (GPU) Nuclear Corporation (the licensee) made application to amend the license of the Three Mile Island Unit 1 (TMI-1) plant. The proposed. amendment would raise the reactor protection system (RPS) high reactor coolant system (RCS) pressure trip setpoint from 2,300 psig to 2,355 psig. -Also, the arming threshold for the Anticipatory Reactor Trip (ART) on turbine trip would be raised from the current'20% reactor power level to a level of 45%. These proposed' changes were to improve the operational performance of the plant.
.The licensee, in providing justification'for the requested changes, referred to studies made in 1985'by.the Babcock and Wilcox Owners Group (B&WOG). As part of the Transient Assessment Program the B&WOG had studies performed to improve operational safety and performance through a reduction in the frequency of reactor trips. This effort resulted in two reports submitted for review to the NRC. These reports are:
(1)
" Justification for Raising Setpoint for Reactor Trip on Pressure,"
BAW-1890, September 1985 (Ref. 2).
Turbine Trip," BAW-1893, October 1985 (Ref. 3)patory Reactor Trip on (2)
" Basis for Raising Arming Threshold for Antici The staff accepted the two above listed reports by evaluations issued on April 22, 1986 (Ref. 4) and April 25, 1986 (Ref. 5), respectively.
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2.0 EVALUATION The staff was assisted in the evaluation of the THI-1 Technical Specification changes by their consultants at EG&G. The EG&G evaluation included a review of the GPU Nuclear Corporation request for changes (Ref. 1) and comparison with 8712080431 871201 l
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~2-l the B&WOG reports (Refs. 2 and 3) which were approved by the staff (Refs. 4'and 5). Additional supporting information was requested by the staff.
The-evaluation of the above information was prepared by EG&G and is presented in.
The staff agrees with the EG8G evaluation which concludes that adequate. justification has been provided to verify that NRC requirements for the number of PORY openings and the probability of a small-break loss of coolant from PORY failure have been met. Also, it-was found that'the accidents analyzed in the FSAR for TMI-1 bound the 3roposed Technical Specification changes. The staff therefore concludes t1at the RCS high pressure trip j
setpoint can be increased from 2,300 psig to 2,355 psig and that the arming j
threshold'for anticipatory reector trip on turbine trip can be raised from 20%
l reactor power to 45% reactor. power without adverse effect on safety.
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3.0 TECHNICAL SPECIFICATION CHANGES The Technical Specification changes for TMI-1 are as follows:
1.
TS 2.2 Bases, Page 2-4.
Safety Limits. Reactor System Pressure. The-value of the setting for the reactor high pressure trip is changed from 2,300 psig to 2,355 psig as found acceptable.in Section 2 above. Also the reference to the setting of the pressurizer electromatic relief valve is deleted as no credit is taken for it in the safety analysis.
2.
TS 2.2 Bases.Page 2-7.
Reactor Coolant System Pressure. Parts of two paragraphs were modified for better grammatical and historical background information. Also a new paragraph was added to refer to the B&W analysis made in September 1985 (BAW-1890) which justified raising the setpoint
-for reactor trip on high pressure. -This is acceptable.
3.
TS 2.2, Page 2-8.
The B&W report " Justification for Raising Setpoint for Reactor Trip in'High Pressure," BAW-1890, Rev. O, Babcock and Wilcox, September 1985, is added as a reference.
4.
Table of-Reactor Protection System Trip Setting Limits, Page 2-9.
The value for the high reactor coolant system pressure was changed from 2,300 psig to 2,355 psig and is acceptable as explained in Section 2 above.
5.
Figure 2.3 Protection System Maximum Allowable Setpoints. The reactor coolant pressure was raised from 2,300 psig to 2,355 psig. This is acceptable as explained in'Section 2 above.
6.
TS 2.2, Pace 3-28. The value shown for the arming threshold for the anticipatory reactor trip (ART) was changed from 20% reactor power to 45%
reactor power. This is acceptable as explained in Section 2 above.
Also, a reference to B&W report,
- Basis for Raising Arming Threshold for Anticipatory Reactor Trip on Turbine Trip," BAW-1893, Rev. O, Babcock and
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Wilcox, October 1985, was added.
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7.
Table 3.5-1, Page 3-30.
Instruments Operating Conditions. The value shown for the arming threshold for the ART was changed from 20% reactor power to 45% reactor power. This is acceptable as explained in Section 2 above.
8.
Table 4.1-1, Page 4-7.
The value shown for the arming threshold for the ART was changed from 20% reactor power to 45% reactor power. This is acceptable as explained in Section 2 above.
The staff with assistence from EG&C has reviewed the proposed changes to TS 2.2 and Table 3.5-1 for TMI-1. The preansed changes would (1) increase the setpoint for trip of the reactor on hig1 pressure in the reactor coolant system from 2,300 psig to 2,355 psig; and (2) increase the arning threshold for ART on turbine trip from 20% of full power to 45% of full power. As discussed in Section 2, the proposed enanges meet the NRC positions established in the review of the B&W topical reports and therefore meet the applicable regulatory guidance and requirements and are, therefore, acceptable.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to the installation or use of e facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no I
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 signif-icant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eli criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)gibility Pursuant to 10 CFR 51.22(b), no (.avironmental impact statement or environmental assess-j ment.need be prepared in connection with the issuance of this amendment.
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6.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) there l
is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
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' 7.0~ REFERENCES;
' 1..
Letter from H.'D. Hukill, GPU Nuclear Corporation, to U.S. Nuclear-Regulatory' Corporation, dated March 5,.1987.
2.
. Justification for Raising Setpoint for Reactor Trip on High Pressure,"
BAW-1890, September'1985.
3.
" Basis for Raising Arming Threshold for Anticipatory Reactor Trip on Turbine Trip," BAW-1893, October 1985.
~ 4.
Letter from D.,M.'Crutchfield, NRC, to~J. H. Taylor, Babcock'and Wilcox Company, April 22, 1986.
5.
Letter from D. M. Crutchfield, NRC, to J. H. Taylor, Babcock and Wilcox Company, April. 25, 1986.
Enclosure:
EG&G' Evaluation Dated: December 1, 1987 Principal Contributor:
1' H. Balukjian 1
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