ML20035H159
| ML20035H159 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/23/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035H157 | List: |
| References | |
| NUDOCS 9305030218 | |
| Download: ML20035H159 (4) | |
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'4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.162 TO FACILITY OPERATING tICENSE NO, DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By letter dated September 9, 1992, the Nebraska Public Power District (the licensee) submitted a request for changes to the Cooper Nuclear Station (CNS)
Technical Specifications (TS). The requested changes modify TS Table 3.1.1, Reactor Protection System Instrumentation Requirements, to indicate that the Main Steam Line Isolation Valve (MSIV) Closure trip is only required while the plant i., in the RUN mode of operation. Also, the amendment adds bases for the instrument settings for the Core Spray and the Low Pressure Coolant Injection (LPCI) mode of the Residual Heat Removal (RHR) systems to the TS Bases section for the Core Standby Cooling System (CSCS). The amendment also changes TS Limiting Condition for Operation (LCO) 3.12.A.2.c to clarify that only one emergency bypass fan exists in the Control Room Emergency Filter system.
Finally, minor editorial changes and typographical error corrections are made to TS pages iii, 48, 63, 78, 87, 206, 209a, 215, 215a, 215d, 215e, and 215f.
The specific changes made to the TS are as follows:
(1) On page 29, Table 3.1.1, Reactor Protection System Instrumentation Requirements, is revised by deleting the "X" and its associated footnotes indicating that the MSIV closure trip is applicable while the plant is in the STARTUP mode.
The modified table indicates that this trip is applicable only when the mode selector switch is in the RUN position.
(2) On page 85, the following Bases for the Core Spray and RHR (LPCI mode) instrument settings are added:
" CORE SPRAY i
Initiation and control instrumentation settings ensure that the Core i
Spray system operates to ensure that peak fuel element cladding temperatures do not exceed 2200*F during a design basis LOCA. The i
basis for the settings is discussed in USAR [ Updated Safety Analysis Report] Section VII-4.
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RESIDUAL HEAT REMOVAL (LPCI MODE)
Initiation and control instrumentation settings ensure that the LPCI mode of the Residual Heat Removal system operates to ensure that i
peak fuel element cladding temperatures do not exceed 2200"F during a design basis LOCA [ Loss-of-Coolant Accident). High drywell pressure and reactor water level instrumentation also allow injection water to be diverted for containment spray. The basis for the settings is discussed in USAR Section VII-4."
(3) On pages 215 and 215f, the term " Reactor Building Closed Cooling Water System" is replaced by the term " Reactor Equipment Cooling System." This change clarifies the existing TS requirements by utilizing a new term that is consistent with the terminology used in Amendment No.152.
l (4) On pages 111, 48, 63, 78, 87, 206, 209a, 215, 215a, 215d, and 215e, the terms Main Control Room Ventilation Isolation System," " Main Control Room Ventilation System," and " Control Room Air Treatment System" are replaced by the term " Control Room Emergency filter System." This change clarifies the existing TS requirements through the use of a single term for this system that is consistent with the system descriptions given in CNS USAR Section X-10.3.6.5 and in the Standard Technical Specifications.
(5) On page 215a, LCO 3.12.A.2.c has been revised to clearly identify that this LCO is applicable to the emergency bypass fan, as opposed to each fan. This change clarifies in the previous wording, which implied that more than one fan exists. The change correctly reflects the current configuration of the plant. There are no changes to the configuration of the Control Room Emergency Filter system associated with this change.
(6) On page iii, a page reference pertaining to Section 3.12.A is changed and the subsection headings associated with Section 5.0 are moved to their proper location.
i (7) Or, page 48, parentheses are removed from LCO 3.2.D.5.b.
(8) On page 63, the term " Isolation (4)" is moved under the first column and parentheses are removed from the term "RMV-RM-1.*
(9) On page 78, the comma is removed from the term "RMP-RM-251 A, B, C & D."
(10) On page 206, a Surveillance Requirement is renumbered from "3.10" to "4.10."
(11) On page 215a, Surveillance Requirement 4.12.A.2.d is appropriately numbered, the referenced specification is changed to "3.12.A.3" in LC0 3.12.A.), and in LC0 3.12.A.3, the spelling of " succeeding" is corrected.
(12) On page 215f, the term " Service Water is capitalized.
(13) To improve clarity, all of the LCOs under 3.12.A and the associated surveillance requirements under 4.12A are moved to page 215a. For similar reasons, a portion of BASES 3.12.C is moved from page 215e to page 215d.
2.0 EVALUATION With regard to the change in TS Table 3.1.1, the licensee stated that Amendment No. 83 to the CNS operating license authorized the changes to the TS needed for the implementation of a plant modification which added the Low Low Set function to the safety relief valves. This plant modification is described in the licensee's letters to the NRC dated December 17, 1982, and February 15, 1983. The licensee stated that, 'during a recent operator licensing examination, it was noted that these changes failed to include the modification performed to the circuitry which bypasses the MSIV Closure trip when the reactor mode selector switch is not in the RUN mode.
Prior to Amendment No. 83, this trip was applicable when the mode selector switch was also in the STARTUP position, with bypass controlled by four pressure switches. The function of these pressure switches was reassigned to the Low Low Set function by the Low Low Set plant modification, and the MSIV Closure trip circuitry in the STARTUP mode eliminated. However. Table 3.1.1 was not updated to reflect the changes to the MSIV Closure trip circuitry which were approved by Amendment No. 83. The changes made by this amendment correct this oversight made by the licensee in proposing the TS changes associated with Amendment No. 83, and make the Table 3.1.1 consistent with the plant modifications previously approved by Amendment No. No. 83. On this basis the NRC staff finds the proposed changes to TS Table 3.1.1 to be acceptable.
The licensee also stated that the changes to the TS Bases that were made in Amendment No. 83 included Bases section for the new Low Low Set instrumentation settings. However, the changes proposed by the licensee and implemented by Amendment No. 83 erroneously indicated that the settings for the Core Spray and RHR (LPCI mode) system instruments had "No Basis." The change made by this amendment adds appropriate bases for the Core Spray and RHR system instrumentation. The licensee proposed that the Bases for the instrument tables for these two systems reference Updated Safety Analysis i
Report (USAR) Section VII-4, which describes the Core Spray and RHR (LPCI mode) system initiating and control instrument settings, and that operation of the systems ensures that fuel cladding temperatures will not exceed 2200*F during design basis loss-of-coolant accidents. Based on its review of the proposed new Bases, the staff finds them acceptable because they correct an error made at the time Amendment No. 83 wu requested.
The other changes have been reviewed by the NRC staff and found acceptable because they are administrative changes that improve the consistency of the TS and correct a variety of minor errors.
In summary, the NRC staff has reviewed the changes made by this amendment and finds that all the changes are administrative in nature and are made to i
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clarify the TS, to make the 1S consistent with the plant configuration, to make the TS internally consistent, and to correct minor errors in the TS. On this basis the staff finds them acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comment.
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 and changes in surveillance 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 exposure. The Commission has previously issued a pro-posed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 61114).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 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.
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:
H. Rood Date:
April 23, 1993
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