ML17158C115
| ML17158C115 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/23/1997 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9705010301 | |
| Download: ML17158C115 (55) | |
Text
jt LICENSEE:
FACILITY:
SUBJECT:
Pennsyl van ~ower and Light Company
( PPLL )
April 23, 1997
/
Susquehanna Steam Electric Station (SSES),
Unit 2 MEETING WITH PPKL STAFF TO DISCUSS A PROPOSED AMENDMENT TO AUTHORIZE THE USE OF ATRIUM-10 FUEL IN SSES, UNIT 2.
On March 26,
- 1997, PPSL and NRR staff met to discuss key issues related to the review.of the licensee's proposed amendment related to the use of ATRIUM-10 fuel in SSES, Unit 2.
Enclosure 1 is a list of the staff who attended the meeting.
The licensee discussed key aspects of the proposed amendment and provided an overview of the Siemens Power Corporation Report, EMF-97-010, Revision 1, that addresses the staff's concern with the ANFB correlation between flow and power levels.
In addition, a series of staff questions were discussed related to the supporting analysis and performance of the fuel. 'hese discussions are reflected in Enclosure 2,
a set of slides provided by the licensee.
It was agreed during the meeting that subsequent teleconferences would be conducted as the staff's review continued as necessary.
It was also noted that PPKL should note in the revision to the technical specifications that the ATRIUM-10 change is cycle-specific in nature.
Finally PP&L committed to providing both proprietary and non-proprietary versions of the responses to the staff's questions discussed in the meeting.
Docket No. 50-388 (Ori,ginal signed by)
Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Meeting Attendees 2.
Licensee Handouts cc w/encls:
See next page DISTRIBUTION
~Nard Co w/Enclosure Doc~ket FFTilI
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- PUBLIC
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- CPoslusny 1 (*w/Enclosures 1
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NAME CPoslusny:rb THuang SMatthews TAttard GGolub JLyons NO
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 23, 1997 LICENSEE:
Pennsylvania Power and Light Company (PP&L)
FACILITY:
Susquehanna Steam Electric Station (SSES),
Unit 2
SUBJECT:
MEETING WITH PP&L STAFF TO DISCUSS A PROPOSED AMENDMENT TO AUTHORIZE THE USE OF ATRIUM-10 FUEL IN SSES, UNIT 2.
On March 26,
- 1997, PP&L and NRR staff met to discuss key issues related to the review of the licensee's proposed amendment related to the use of ATRIUM-10 fuel in SSES, Unit 2.
Enclosure 1 is a list of the staff who attended the meeting.
The licensee discussed key aspects of the proposed amendment and provided an overview of the Siemens Power Corporation Report, EMF-97-010, Revision 1, that addresses the staff's concern with the ANFB correlation between flow and power levels.
In addition, a series of staff questions were discussed related to the supporting analysis and performance of the fuel.
These discussions are reflected in Enclosure 2,
a 'set of slides provided by the licensee.
1 It was agreed during the meeting that subsequent teleconferences would be conducted as the staff's review continued as necessary.
, It was also noted that PP&L should note in the revision to the technical specifications that the ATRIUM-10 change is cycle-specific in nature.
Finally PP&L committed to providing both proprietary and non-pr'oprietary versions of the responses to the staff's questions discussed in'he meeting.
cg~
Chester
- Poslusny, Senior Project Manager Project'irectorate I-2
'ivision of Reactor Projects -.I/II Office of Nuclear Reactor Regulation Docket No. 50-388
Enclosures:
1.
List of Meeting Attendees 2.
Licensee Handouts cc w/encls:
See next page
~
~
~
Mr. Robert G.
Byram Pennsylvania Power
& Light, Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 h
Bryan A. Sn'app, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania
.. 18101 Mr. K. Jenison Senior Resident Inspector U.
S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P.
O.
Box 8469 Harrisburg; Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Mr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. George Kuczynski Plant Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
'Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Chairman Board of Supervisors 738 East Third Street
- Berwick, PA 18603
LIST OF ATTENDEES USE OF ATRIUM-10 FUEL SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 MARCH 26 1997 NAME C. Poslusny T.
Huang S. Matthews T. Attard G. Golub D. Jaffe J.
Lyons E. Kendrick L. Phillips G. Jones J. Kulick J.
Kenny G. Miller J.
Spadaro C.
Lehmann J.
Nordahl D. Cuset J.
Ingham T. Keheley J.
Caren'RGANIZATION NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR
.NRC/NRR NRC/NRR NRC/NRR PP&L PP&L PP&L PP&L PP&L PP&L Siemens Power Corporation Siemens Power Corporation Siemens Power Corporation Siemens Power Corporation Brookhaven National Lab.
ENCLOSURE 1
C
Introduction
+ Key aspects ofproposed amendment
+ Review ofrevision to proposed amendment
+ Overview ofEMF-97-010, Rev.
1 methodology
+ Response to NRC questions
+ Summary Pennsylvania Power 4 Lightcompany Page l
.MCMSURE 2
0
Key Aspects
+ Proposed amendment addresses NRC issues Development ofAdditive Constants Flow bias ofANFB LPF > 1.30 Applicabilityto 1'ow flowconditions
+ Short term solution
+ Long term solution is to re-correlate Pennsylvania Power 8h Light company Page 2
Key Aspects
+ Flow dependent MCPRSL protects fuel rod cladding integrity
+ Flow dependent MCPRSL does not affect operator interface with the plant
+ MCPROLs established to maintain conservative margin to the MCPRSL
+ Does not affect any plant monitoring systems or the process computer Pennsylvania Power dh Light company Page 3
Review ofRevision to Proposed Amendment
+ Core flowdependent MCPR Safety Limits
+ Inclusion ofa Siemens Power Corporation methodology topical report in Section 6.9;3.2 Pennsylvania Power 8h Light company Page 4
II
Reason for the Change
.+ NRC issues regarding application ofthe ANFB Critical Power Correlation to ATRIUM-10.
+ Short Term Solution - SPC developed-a conservative MCPR methodology to support use ofANFB.
+ Long Term Solution - Recorrelate ANFB correlation to better model upskew data Pennsylvania Power 8t Light company Page 5 "
Overview ofKMF-97-010, Rev. 1 Methodology
+ Derivation ofAdditive Constants for ATRIUM-10
+ Flow dependence in Critical Power prediction
+ Extension in range ofvalidityfor Local Peaking Factors > 1.30 Pennsylvania Power 4 Lightcompany Page 6
Derivation ofAdditive Constants KMF-97-Q10, Rev. 1, Ch. 2 - 5
+ Used Conservative Subset ofCosine Axial Shape Test Data
+ Resulting Increases in Additive Constants Penalized MCPR 7 70
+ Very Conservative forDownskew and Center Peaked APDs
+ Results Showed Flow Dependence
- Needed to Be Addressed Pennsylvania Power 4 Light company Page 7
P
Flow Dependence in Critical Power Prediction
+ Correlation Becomes'Non-Conservative at Low Flows (Upskew APD)
+ Derived Correlation Non-Conservatism from Upskew APD Data
+ Derived Correlation Uncertainty (Additive
.Constants) from Upskew APD Data
+ Conservative Extension ofDependence to Low Flows
+ Derived Parameters Used in Safety Analysis Methods Pennsylvania Power 4 Light company Page 8
a
Extension ofRange ofValidi for Local Peaking Factors > 1.30
+ ATRIUM-10Tested Up to 1.34
+ Data shows no Significant Effect on Additive Constants (i.e., correlation)
+ Data Exists for Same Peaking Pattern and Different LPFs
+ Data Used to Derive Conservative Uncertainty for LPFs > 1.30
+ Extra Uncertainty Applied in MCPR SL for LPFs > 1.30 Pennsylvania Power 8h Lightcompany Page 9
t 4
Provide details on the calculation oftransient h,CPRs incorporating the flow dependence.
Explain why the adjustment ofACPR described in EMF-97-010, Rev. 1 is acceptable as opposed to re-running the transients and directly calculating a h.CPR which accounts for the flow dependence.
Discuss the impact on anticipated operational occurrences and MCPR related accidents.
Pennsylvania Power 4 Light company Page l0
Response to uestion 1
+ h,CPRs calculated such that MCPR SL is not exceeded for AOOs
+ PPAL Performs Reload Transient Analyses
+ NRC Approved Methods (PL-NF-90-001-A)
+ LimitingEvents / Plant Specific Analyses o Loss ofFeedwater Heating o Feedwater Controller Failure o Generator Load Rejection &Turbine Trip w/o Bypass o Rod Withdrawal Error.
o Recirculation Flow Controller Failure o Mislocated &Rotated Bundle Pennsylvania Power 4 Light company Page ll
Response to uestion 1 Cont.
+ 0 tion 1: Direct Approach
+ Put Flow Dependence of CPR into Codes and Re-analyze
+ Use Table 6.2 ofEMF-97-010, Rev.
1 Except ifECPR < 1.0 use ECPR = 1.0
+ Adjusted h,CPR Directly Calculated Pennsylvania Power A Light company Page 12
Response to uestion 1 Cont.
+ 0 tion 2: "Off-line"Approach
+ Uses Existing Transient Analysis Results
+ Conservative h.CPR.adjustment based on Transient Flow Decrease Pennsylvania Power dh Light company Page 13
Response to uestion 1 Cont.
+ Single Loop Pump Seizure Accident
+ Adjusted h,CPR Calculated - Large Adjustment for Flow Decrease
+ Safety LimitAnalysis to Calculate Number ofPins in Boiling Transition - Includes. flow dependence and increased uncertainty on LPF
+ Result is < small fraction of 10CFR100 Pennsylvania Power dh Lightcompany Page 14
Describe the details of the new methodology for computing the flow dependent MCPR Safety Limit. How is the process different from the standard methodology (non-flow dependent limit)? Describe how the flow bias is incorporated into the calculation
'Pennsylvania Power 8h Lightcompany Page 15
7
MCPR Safety LimitMethods
+ Calculate MCPR such that 99.9% pins not expected to be in boiling transition
+ Statistically Combines Uncertainties, including MCPR correlation
+ Core Wide Analysis
+ Cycle Specific PcnnsyNania Power 4, Light company Page 16
MCPR SL Inputs - Previous Method
+ The Point ofBoilingTransition assumed to be constant
+ Analysis at Rated Conditions
+ Single Value for Correlation Uncertainty.
(AdditiveConstants)
Pennsylvania Power 4, Light company Page 17
t
'r t
~
MCPR SL Inputs - Revised Method
+ BoilingTransition corresponds to MCPR as a function ofFlow
+ Increases as Flow Decreases
+ Applied to AllATRIUM-10Bundles Regardless ofAPD
+ Analyses at Various Core Flows
+ Increased Uncertainty for LPFs > 1.30 Pennsylvania Power 4 Light company Page 18
Adjustment to ACPR for AOOs
+ Accounts for Flow Dependence in Critical Power Prediction
+ Increased h,CPR ifBundle Flow Decreases
+ Added to Flow Dependent MCPR SL corresponds to MCPR OL Pennsylvania Power 4 Lightcompany Page 19
4
Conclusions
+ MCPR Safety Limits'and Operating Limits specified such that 99.9% offuel rods expected to avoid boiling transition during normal operation and AOOs.
+ Revised methodology is conservative for developing MCPR SLs and OLs.
Accounts for flow dependence in ATRIUM-10critical power test data.
Increased correlation uncertainty for high local peaking factor rods.
)I Pennsylvania Power dh Lightcompany Page 20
Provide the technical bases for the uncertainties for local peaking factors > 1.30. Also provide the technical bases for the flow dependent uncertainties used.
Pennsylvania Power 4 Light company Page 21
Response to uestion 3
+ Used ATRIUM-10Data with Different LPFs
+ 95'/o Confidence X2 Value for Additive Constant Uncertainty Derived =.013
+ Conservatively Assumes Entire Uncertainty Attributable to LPF Changes Pennsylvania Power dh Light company Page 22
Response to uestion 3 Cont.
+ Applied in Safety LimitAnalysis for rods with LPF>1.3
+ + = SQRT (s Additive constant+ 'O 3 )
Pennsylvania Power 4, Light company Page 23
Describe how the flow dependent MCPR Safety Limit affects plant monitoring and protection systems.
Speciflc items to consider are the process computer, RBM, APRM scram and rod block. In addition, consider the impact Qn the Susquehanna Steam Electric Station power/flow map.
Are the bases for any of these items affected?
Pennsylvania Power R Light company Page 24
Response to uestion 4
+ Reviewed Tech Spec Monitoring and Protection Systems, and Power/Flow Map
+ Methodology Changes and Flow Dependent MCPR SLs have no impact Pennsylvania Power 8h Lightcompany Page 25
Response to uestion 4 Cont.
+ Rod Block Monitor o Prevent violation ofthe MCPR SL for Rod Withdrawal Error o b,CPR Adjusted for Flow Dependence o No Credit Taken for RBM at SSES
+ Control Rod Program Controls o RSCS and RWM o Limits Reactivity for Control Rod Drop (< 20% power) o Analysis ofCRDA does not use ANFB Pennsylvania Power &,Lightcompany Page 26
lI'
Response to uestion 4 Cont.
+ Control Rods o Maintain Shutdown Margin o Insertion Times for Transient Analyses (input to analysis) o No impact from flowdependent MCPR.SL
+. APRM Flow Biased Rod Block k, Scram o Rod Block Defines Allowable Region ofOperation o Region Unaffected by MCPR Limits o Allowable Region is an Input to Analyses o APRM Flow Biased Scram not Credited for Analyses - Backup Trip Pennsylvania Power A Light company Page 27
~t
Response to uestion 4 Cont.
+ Core Monitoring System o Monitors Core Performance vs. Operating Limits o Input is MCPR OL, Safety Limitis not monitored o Combination ofOLs and Monitoring System willprevent Safety Limits violations for AOOs
+ Power/Flow Map o Based on Measured Data and Plant Setpoints (APRM Rod Block) o MCPR Limits do not alter Power/Flow Map o Allowed Operating Space is input to Safety Analyses (not affected by output)
Pennsylvania Power dh Light company Page 28
0
~ yI l~ I 4
uestion 5:
Explain in detail "the process used to extend the ATRIUM-10upskew axial-power distribution data to the lower flow range (bundle flows less than.05 Mlb/hr).
Pennsylvania Pown A Lightcompany Page 29
0
~ $
/
ik
Response to uestion 5
+ Cosine APD Data Exists for Bundle Flows to.01 Mlb/hr
+ Upskew Critical Powers = 0.821 (+.012) x Cosine Critical Powers (Constant Sub cooling)
+ 0.821 Factor Used to Extend Upskew.
Critical Power Data Pennsylvania Power 4 Light company Page 30
Response to uestion 5 Cont.
+ Barnett Correlation Predictions Indicate Extension is Conservative
+ Larger Uncertainty Used at Lower Flows (<
.05 Mlb/hr)
Pennsylvania Power 8h Light company Page 31
Summary
+ Proposed amendment addresses NRC issues Development ofAdditive Constants Flow bias ofANFB LPF > 1.30 Applicabilityto low flowconditions
+ Short term solution
+ Long term solution is to recorrelate Pennsylvania Power 4 Light company Page 32
Summary
+ Flow dependent MCPRSL protects fuel rod cladding integrity
+ Flow dependent MCPRSL does not affect operator interface with the plant
+ MCPROLs established to maintain conservative margin to the MCPRSL
+ Does not affect any plant monitoring systems or the process computer Pennsylvania Power 8t Light company Page 33