ML20070D772
| ML20070D772 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/20/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070D771 | List: |
| References | |
| NUDOCS 9103010161 | |
| Download: ML20070D772 (7) | |
Text
_-
i
+
o, UNITED STATES
[
NUCLEAR REGULATORY COMMISSION I
W ASHING TON, D. c. rous
./
1, SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO CYCLE 9 RELOAD i
CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
By letters dated August 31, (Ref. 1), and September 19, 1990, as amended October 3, and December 28, 1990 (Ref. 2), Consumers Power Company (CPC) submitted proposed Technical Specification (TS) changes to Facility Operating License DPR-20 for Cycle 9 operation of the Palisades Plant.
The October 3 and December 28, 1990, submittals provided additional information and a revised Technical Specification page, and did not change the determination of no 4
significant hazards or alter the proposed action.
The evaluation of the changes for Cycle 9 operation is provided by the Advanced Nuclear Fuels Corporation (ANF) safety analysis report and evaluation of Standard Review Plan (SRP), Chapter 15 events (Refs. 3 and 4).
2.0 EVALUATION 2.1 Palisades Cycle 9 Safety Analysis Report The results of the safety evaluation for Cycle 9 of the Palisades nuclear plant are presented in ANF-90-076 (Ref 3).
The Palisades Cycle 9 reload will consist of 52 Reload M assemblies at an average enrichment of 2.69 /o U-235.
Twenty of the Reload M assemblies will each contain 12 gadolinia-bearing fuel rods containing 6.0 w/o Gd 8 f the M assemblies will each contain 8 rods 3,f the H assemblies will each contain 4 rods containing 4.0 w/o Gd o
containing 4.0 w/o Gd 3, and 8 of the M assemblies will each contain an asymmetric loading of rods each containing 4.0 w/o Gd 0.
The fuel assembly design for Reload M is similar to the four Reload L Hig YhermalPerformance
)
(HTP) assemblies loaded in Cycle 8.
Reload M fuel rods differ from those of the Reload L design primarily in enrichment.
The fuel pellet density and pellet diameter are slightly increased for Reload M.
The Reload i HTP design is similar to the Reload H extended burnup design.
Cycle 9 uses a low radial leakage loading plan similar to the design developed for Cycle 8.
This Cycle 9 plan differs in-its use of hafnium inserts in selected peripheral assemblies, rather than assemblies reconstituted with stainless steel rods.
This use of the hafnium combined with the low radial leakage design reduces the neutron fluence on critical pressure vessel welds.
Cycle 9 of the Palisades nuclear plant-is designed to operate at 2,530 MWt.
I 9103010161 910220 i
ADOCK050gg5 PDR P
U
i 2
Plant safety analyses, both LOCA and non-LOCA, ha've been performed to support Palisades Cycle 9 operation.
These analyses support full power operation with:
4 The new steam generators with up to 15% tube plugging A
An F limit f 1.57 (216 rods / assembly) and 1.48 (208 rods / assembly) r T
An F limit of 1.92 for all assemblies 7
T The F limit replaces the current FAH Technical Specification r
limit r
16 assemblies with hafnium inserts The increase in the radial peaking is required to support the low radial leakage reload pattern.
Palisades Cycle 8 has been chosen as the reference neutronics cycle due to the close resemblance of the overall neutronic characteristics of Cycle 9 and Cycle 8.
The results contained in ANF-90 076 show that operation at a power level of 2,530 WL with the increased radial peaking can be safely achieved.
A comparison summary of the Cycle 9 plant parameters to the core license limits are given in Table 2.1 (Ref. 3).
Analyses to support increased burnup levels for ANF fuel have also been performed and a summary of the Cycle 9 maximum pellet exposures is shown in Table 2.2 (Ref. 3) and is compared to the exposure limits of these analyses.
The staff has reviewed these analyses and has determined that they were performed with NRC approved ANF methodology and are acceptable.
Also, The use of hafnium inserts in the low power Reload I fuel is acceptable for Cycle 9.
2.2 Transient ar Accidents - Analysis of Standard Review Plan Chapter 15 Events ANF-90-078 (Ref 4) documents the results of a FSAR Chapter 14 plant transient analysis performed in support of Palisades Cycle 9 operatio: with up to 15.0%
steam generator tube plugging.
The events were selected in accordance with Chapter 15 of the Standard Review Plan (SRP) and Advanced Nuclear Fuels (ANF)
Corporation methodology (Ref. 5 & 6).
The basis for event selection is documented in the Disposition of Events report (Ref. 7) and the events analyzed are shown in Table 1.
ANF 90-078 presents the conditions employed in the event analyses and the results of these event analyses.
It includes a tabular list of the disposition of events and analysis of record for Palisades, Chapter 15 events, with a cross reference between SRP_ event numbers and the Palisades Updated FSAR.
The staff has reviewed these analyses and finds them to be acceptable.
A bounding MONBR analysis was performed for Cycle 9 that is based on the radial peaking factors given in Table 15.0.3-1 (Ref 4).
The bounding analysis
t j
4.
i consisted of evaluating the HDNBR's for Reload L fuel with standard bi-metallic spacers and radial peaking factors of 1.66 and 2.03 for the assembly and teak rod, respectively.
The MONBR's for the standard bi-metallic spacer fuel (Reload L) were evaluated with the XNB critical heat flux correlation.
Confirmatory MDNBR calculations were performed for Reload M fuel with HTP spacers and radial peaking factors of 1.57 and 1.92 for the assembly and peak rod, respectively.
The MDNBR's for the HTP specer fuel (Reload M) were evaluated with the ANFP critical heat flux correlation.
The Cycle 9 Technical Specifications on radial peaking for both Reload L and M fuel will be limited to 1.57 and 1.92 for the assembly and peak rod, respectively.
This is acceptable to the staff.
TABLF 1 EVENTS REQUIRING REANALYSIS Increase in Heat Removal by the Secondary System 15.1.3 Increase in Steam Flow Decrease in Heat Removal by the Secondary System 15.2.1 Loss of External Load Decrease in Reactor Coolant 53 stem _F_ low 15.3.1 Loss,of Forced Reactor Coolant flow 15.3.3 Reactor Coolant Pump Rotor Seizure Reactivity and Power Distributjon Anomalies 15.4.1 Uncontrolled Control Rod Bank Withdrawal from a Subtritical or Low Power Startup Condition 16.4.2 Uncontrolled Control Rod Bank Withdrawal at Power 15.4.3 Control Rod Misoperation (1) Dropped Control Rod / Bank (4) Statically Misalignea Control Rod / Bank (5) Single Control Rod Withdrawal (6) Core Barrel Failure 15.4.6 CVCS Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant 15.4.8 Spectrum of Control Pod Ejection Accidents Decreases in Reactor Coolant Inventory 15.6.1 Inadvertent Opening of a PWR Pressurizer Pressure Relief Valve 15.6.3 Radiological Consequences of Steam Generator Tube failure
~4-2.3 Technical Specification Changes The proposed amendment would modify the Palisades Plant Technical $pecifications (TS) as follows:
In TS Section 1.1, the definition of " Interior fuel Rod" is deleted since it is no longer used.
Accordingly, all references to " interior" are deleted from thedefinitionof{TotalInteriorRodRadialPeakingFactor".
Total Rod Radial Peaki g Factor "F
" is renamed "F T" and a " local peaking" definition is added 9
to F forclarification r
r In TS Section 2.1, basis and references, a sentence is added stating that the analysis is performed in accordance with the added references 6.
This change is necessary since Cycle 9 has a mixed core arrangement and a new Minimum Departure fror.: Nucleate Boiling Ratio (MDNBR) analysis is required.
The "P
" tiquation in TS section 2.3 is revised to reflect the update to the constaM[fortheThermalMargin/LowPressure(TM/LP)equationforCycle9.
In the basis, the Variable High Power Trip (VHPT) setpoint is changed from "112% to "115%" as a result of the uncertainty on the VHPT setpoint being increased from 5.5% to 8.5% for Cycle 9.
The references 1, 4, 8 and 11 are replaced with an updated Cycle 8 basis report and the reference 12 is deleted.
TS Section 3.1, and its associated basis and references, is change to incorporate a new primary coolant pump measured flowrate in order to reflect the associated lower assumed tube plugging ratio of the replacement steam The T equation, and the associated basis, is changed to generators.
reflectthisincrejQgtmargin.
Also Figure 3-0, "ASI LC0 for T Function",
isreplacedwithant.pdatedfigureduetoanexpandedAxialShah)fbdex(ASI)
Limitirig Condition for Operation (LCO) operating window between 70% and 25%
power.
Finally, references 4 and 5 are replaced with one Cycle 9 specific references.
TS Section 3.10, basis and references, and TS Section 3.12, references, have been revised with the appropriate references to reflect the changes in the Cycle 9 analysis.
TS Tables 3.23-2, TS Section 3.g.2 and i}s associated basis, and TS Section 4.19.2.1, similarly replaced F with F for the reasons listed above.
- Also, r
in TS Table 3.23-2, the radial peaking f5ctor limits are revised with values consistent with the cycle 9 analysis.
Finally, a paragraph is added in the basis of Section 3.23-2 explaining the Loss of Coolant Accident Analysis Limits.
The majority of the Technical Specification Changes proposed for Cycle 9 are either editorial in nature or are made to support Cycle 9 operation according to previously staff approved ANF methodology and, therefore, are acceptable.
The following two changes do not fall into these categories and the staff focused on these changes as part of the review:
1.
The licensee proposed to replace the INCA method of analyzing in-core power detector data with their new PIDAL software.
--c-
2.
The licensee proposed to extend the previously approved ANFP DNB correlation for High Thermal Performance Fuel in Palisades Reactor (Ref. 1 & 8).
4 The staff is currently performing an in-depth review of the PIDAL Code which will not be completed in time for the start up of Cycle 9 operation.
Therefore, the staff will require that the previously approved INLA methodology be continued during Cycle 9 operation.
ANF-89-192(P) demonstrates that the ANFP DNB correlation may be used to predict the ONB heat flux in the 15x15 High Thermal Performance (HTP) fuel design for Palisades.
The Palisades design is similar to those represented in the ANFP correlation data base in most key design characteristics, but differs in having a shorter heated length and no interior guide tubes.
The ANFP correlation is shown to predict low ONB heat fluxes for ANF DNB Tests 56 and 57, which together represent these two special features of the Palisades design.
Use of the ANFP correlation thus results in a conservative estimation of the ONB heat flux for the Palisades design.
For both tests, the data presented in ANF-89-192(P) indicate that on average the prtdicted heat flux at which DNB occurs is less than that measured.
This is conservative.
Also, the talerance limits lie below the 1.154 safety limit of the ANFP correlation.
Hence, the ANFP correlation and its associated safety limit of 1.154 provide a conservative assessment of the ONB performance for
- Tests 56 and 57 and its use for analyses of the Palisades Cycle 9 reload core is acceptable to the staff.
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 State official had no comments.
4.0
SUMMARY
The staff has reviewed the proposed modifications to the Palisades Technical Spetifications and reload fuel configuration for Cycle 9 operation and finds them acceptable provided that the INCA method of analyzing in-core power detector data is retained.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Fart 20 and a change in a surveillance requirement.
The staff hat 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 of fsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued e proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this 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
- 6-environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
The staff 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 Conmission'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.
The staff, therefore, concludes that the proposed changes are acceptable.
Principal Contributors:
B. Holian G. Schwenk Date: February 20, 1991
REFERENCES 1.
Letter, G. B. Slades (CP) to NRC,
- Palisades Plant - Technical Specifications Change Request - DNB Correlation," dated August 31, 1990 2.
Letters, G. B. Slade (CP) to NRC " Palisades Plant - Cycle 9 Technical Specification Change Requests," dated September 19, October 3 and December 28, 1990.
3.
K. C. Segard, " Palisades Cycle 9 Safety Analyses Report,"
ANF-90-076, dated September 19, 1990.
4 T. R. Lindquist, " Palisades Cycle 9:. Analysis of Standard Review Plan Chapter 15 Events," dated September 25, 1990.
5.
" Advanced Nuclear fuels Corporation Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events " ANF-84-73(p).
Revision 4. Appendix B, Advanced Nuclear fuels Corporation, August 1989.
6.
Letter, Mr. Ashok C. Thadani (USNRC) to Mr. R. A. Copeland ( ANF),
dated July 13, 1990. " Acceptance for Referencing of Topical Report ANF-84 73(P), Revision 4. Appendix B, ' Advanced Nuclear Fuels Corporation Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events.'"
l 7.
" Disposition of Standard Review Plan Chapter 15 Events for Palisades Cycle 9 "ANF-90-041. Revision 2. Advanced Nuclear fuels Corporation, Septenter 19, 1990.
8.
F. T. Adams, " Justification of the ANFP DNB Correlation for High Thermal Performance Fuel in the Palisades Reactor," dated January 17, 1990.
l