ML20113H301
| ML20113H301 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/15/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20113H297 | List: |
| References | |
| NUDOCS 9207290158 | |
| Download: ML20113H301 (3) | |
Text
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UNITED STATES n
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SAFETY LYALVAUON BY THIEJRE OF NUCLEALIKAC1011LOUL ATI_03 Ef1AI1D_lk.AM.[MPlQi_T NO,15010 FA[1L111_011RATU[G LICENSE ILO, ORp-LO
[.ORSUMERS PQWER COMPAq fjLLSfaQES Pt ANT DOCKET NO. SQ.tM 1.0 1111BRDM,qlJfB By letter dated February 3,1992, the Consumers Power Company (CPC or the licensee) submitted a request for changes to the Technical Specifications (TS).
The requested changes would delete footnote (4) from TS Table 4.1.1
" Minimum frequencies for Checks, Calibrations and Testing of Reactor Protective System." This footnote addresses the testing of the low flow trip set noints for non-operating reactor coolant pump combinations.
Additionally, changes were proposed to TS Section 2.0, " Safety Limits and Limiting Safety System Settings." This section would administratively be revised to enhance clarity and consistency with other sections of the TS.
The licensee previously submitted proposed changes (May 30, 1991 and November 1, 991) for Safety limits and Limiting Safety System Settings for Variable High Power set point and associated Cycle 10 reload. Thess changes were separately reviewed and are not included in this evaluation, in addition, a revised Basis for TS, Section 2.0 was also submitted to correct an error and clarify the discussions dealing with three pump operatior.
2.0 EVALVATION 2.1 Reactor Protection System (RPS) medificaticn The original design of the RPS provided a single flow set point selector switch (FSSS) that allowed proper selections of the high pour and low flow set points for the three available primary coolnt pump % des of operations (2, 3, or 4 operating pumps).
The trip set point for di.ferent modes was selected by turning the switch to the appropriate position, thereby electronically aligning to the proper potentiometer for each channel.
Other set points and pump modes could not be independently selected and verified for surveillance testing without causing the reactor to trip.
Footnote (4) in TS Table 4.1.1 was needed to ensure the low flow trip set points for non-operating reactor coolant pump combinations could be verified when shut down and within a specified time af ter ruuming operation with a different pump combirstion.
in 1988, lhe NRC approved (Amendment No. 118) the licensee's request to install a variable high power trip to the RPS system.
The variable high power trip set point selections were removed frcm the FSSS.
The non-operating pump 9207290150 920715 l
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I 2-J combination (three-pumps) for low flow trip settings were then conservatively set at the greater than four-pumps operating value (e.g., 110 percent flow) to prevent inadvertent selection of the FSSS, The reactor trip would occur due l
to a flow mismatch between an actual measured flow and flow set point for three. pumps setting, if the TSSS was moved from the four-pumps position.
This act:on ensured that a loss of flow protection was not compromised.
During the recently completed refueling outage, the licensee implemented a design change to replace aging components for the RPS. The RPS modifications were performed under a 10 CFR 50.59 Safety Evaluation and consisted of replacing all four channels of the RPS power assemblies, trip unit assemblies, interconnection modules, bistable trip units, and auxiliary trip units as well as the incorporation of trip tester functions into the RPS power supply assemblies.
The Rps component upgrades were based on analog-to-analog and were form-fit-functien replacement with newer design.
The RPS power supply I
front panni combines the functions that were previously contained in the trip tester unit with the indications currently found on the front panel.
The test functions on the trip tester unit were implemented in a similar manner to that used in the original design.
Changes made included the rewiring of the Thermal Margin / Low Pressure (IM/LP) selector switch and the removal of the unnecessary FSSS switch.
The TM/LP switch and Trip Test switr.h are functionally unchanged. As a result of the recent RPS modification, the licensee will continue to perform surveillance testing for normal operating pump mode and also has the capability to independently verify preset trip and trip set points at trip unit bistables for other non-orerating pump combinations while the reactor is critical.
Removal of the iSSS eliminates the potential of inadvertent selection of other than operating pump combination during power operation, thus preventing an inadvertent react 7e trip.
Therefore, footnote (4) in 15 Table 4.1.1 was no longer needed 13e staff has reviewed the CPC submittal and has found the changes are acceptacle, i
2.2 Technical Specifications (TS) Section 2.0, " Safety Limits and Limiting 5efety System Sett.ngs" format rearrangement and Basis revised.=
The licensee administratively rearranged the TS Section 2.0 format to enhance clarity and consistency witii other sections of the TS.
Specifications 2.1, 2.2 and 2.3 were rewritten in the format: Specification - Application -
Action.
information in the existing " Objective" statements was moved to the
- Basis, lhe licensee incorporated the Standard Technical Specifications, NUREG-0212, format for the " Action" statements for failure to meet a limiting Safety System Setting.
l The'Dasis section for TS Sections 2.1, 2.2, and 2.3 were grouped together and placed in appropriate location following the specifications section.
The j
departure from nucleate boiling (DNB) safety limits have been moved from the Basis and were incorporated into the specification section and the TM/LP-trip setting equations were moved to Table 2.3.1, with the rest of the set points l
limits.
w,,p= = w w, y yy..,.m-+= w ---"ee m-e m e -- r i w n-wwe e w w w m e t -* e-we w ep*W-=e-w+
n w e.w -e =surv e r e-mwn eem aw-
-ewww--v--=-+,w*-w--%w.we-~~
m--e-+ww----r e--r-eav w w-r- me-t -- w= e 9 '
t
' footnote 1, 2, 3, and 4 from Table 2.3.1, were deleted to reduce redundancy with other TS.
The staff has reviewed the Consumers Power Company, P311sedes Plant submittal and has found that the proposed deletion of the surveil h nce requiremer.t Footnote (4) in Table 2.3.1 and the administrative change to TS Section 2.0 format and the associated Basis to enhance clarity and consistency are acceptable.
3.0 STATE CONSULTATIOH In accordance with the Commission's regulation:
the Michigan State Official tas notified of the proposed issuance of the amendment.
The State Official had no comments.
4.0 D VIRONMENTAL CONSIDERATION The' amendment changes a requirement with respect to the installation or nse of
-a_ facility component-located within the restricted area as defined in 10 CFR Part 20 and a chrnge in a surveillance requirement.
The staff has detarmined 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 accumulative 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 (57 FR 9441).
Accordingly, this 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 this arendment.
5.0 (DNCLUSION We have 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) issuance of this amendment will not be inimical to the health and safety of the public.
Principal Contributor:
Date: July 15, 1992 l
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