ML20084Q325
| ML20084Q325 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/22/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084Q313 | List: |
| References | |
| NUDOCS 9506080566 | |
| Download: ML20084Q325 (4) | |
Text
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- t, UNITED STATES 2
S NUCLEAR REGULATORY COMMISSION 1
1I WASHINGTON. D.C. 3086&4001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.166 TO FACILITY OPERATING LICENSE NO. DPR-20 CONSUMERS POWER COMPANY PALISADES PLANT DKKET NO.10-255
1.0 INTRODUCTION
By letter dated October 20, 1992, the Consumers Power Company (the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. DPR-20 for the Palisades Plant.
The proposed amendment would revise TS 5.3.la to reflect changes being made to the Palisades Final Safety Analysis Report (FSAR) Section 4.2.
The proposed FSAR changes correct and clarify the cyclic design load descriptions resulting from the replacement of the Palisades steam generators.
2.0 EVALUATION The proposed FSAR changes to Section 4.2 are described below:
1.
In FSAR Section 4.2.2, Item 3, the design load of 15,000 power change cycles with a ramp load change of 15% of full load per minute, is being deleted since the replacement steam generators were not analyzed for this load change rate.
2.
In FSAR Section 4.2.2, Item 5, a statement is being added to reflect the I
relationship between the allowable temperature and maximum primary to secondary pressure differential as referenced in Combustion Engineering Report, " Specification for Steam Generator Assemblies for Consumers Power Company."
3.
In FSAR Section 4.2.2, Items 6 and 7, changes to primary leak testing design load are being added to show the assumptions used in the design analysis.
4.
In FSAR Section 4.2.2, in the middle of page 4.3-6 following Item 8, the i
edition of the American Society of Mechanical Engineers (ASME) Code is deleted since the replacement steam generators are not built to Section i
III, Class A of the 1965 edition.
FSAR Section 4.2.4 describes the applicable Code edition.
5.
In FSAR Section 4.2.2, a change is being made to better define the abnormal transient loads. The description of one cycle of loss of secondary system pressure is also clarified.
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6.
FSAR Section 4.2.2, Items I through 8 are being renumbered to reflect the deletion of Item 3.
Ebanae No. 1 This change deletes one of the design cyclic transients which were used in the fatigue analysis of the original steam generators.
Specifically, the transient for 15,000 power change cycles over the range of 50% to 100% of full load with a ramp load change of 15% of full load per minute, is being deleted, as it does not apply to the replacement steam generators that were installed at Palisades in late 1990.
This change does not affect plant operation 4
because there is no design or licensing requirement that the plant be capable of 15% per minute load changes.
In addition, by deleting the 15% per minute e
load change rate from the FSAR, the operation of the plant is unaffected because the 5% per minute limit on load rate change transient (FSAR Section 4.2.2, Item 2) is more limiting.
Furthermore, the staff previously reviewed the steam generator replacement design change in Amendment 135.
Chanae No. 2 This change adds the reference for assumptions on steam generator differential pressure. The reference that was added is a Combustion Engineering Report,
" Specification for Steam Generator Assemblies for Consumers Power Company, Specification No.19377-PE-120." This specification was used in the design of the replacement steam generators and is added to account for limits on differential pressure to avoid steam generator tube degradation.
Chance No. 3 I
This change is being made to add changes to the primary leak testing design to show the assumptions used in the design analysis. This change simply adds design information used in the replacement steam generators.
Chanae No. 4 This change deletes the specific edition of the ASME Code because the replacement steam generators are not built to Section III, Class A of the 1965 edition.
FSAR Section 4.2.4 describes the applicable edition.
The design of the replacement steam generators to the 1977 ASME Code was addressed by the staff in Amendment 135 to the Palisades TS.
Chanae No. 5 This change adds clarifying information to better define the abnormal transient loads during a loss of secondary system pressure for the replacement steam generators.
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Chance No. 6 This change renumbers Items 1 through 8 in FSAR Section 4.2.2.
Because of the deletion of Item 3 in Section 4.2.2, the design cyclic loads will be numbered I through 7.
Conclusion With the exception of Change No. 1, the proposed changes to FSAR Section 4.2 are editorial in nature and serve to clarify the existing information in FSAR Section 4.2 following replacement of the steam generators.
Changes 2 through 6 are, therefore, acceptable.
The deletion of the 15,000 power change cycles over the range of 50% to 100%
of full load with a ramp load change of 15% of full load per minute does not apply to the Palisades' replacement steam generators. The replacement steam generators were not designed to meet this cyclic load transient and are not required to do so.
Based upon the fact that there is no license requirement and no NRC requirement to meet this design load, the change to delete it is acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The Michigan State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The 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 (60 FR 18624). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
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.
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5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
3 (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:
J. Kennedy Date:
May 22, 1995
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