ML20236A627

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Summary of 870924 Meeting W/Util Re Thermal Hydraulic Stability Tests for End of Second Fuel Cycle & Reduced Min Control Power Ratio Margins for Third Fuel Cycle.Related Info Encl
ML20236A627
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/15/1987
From: Kintner L
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8710220451
Download: ML20236A627 (29)
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Mp 'kg T October 15,:1987: ,

9 f,$ h; f.J ." t' 'T,y, W6 deket No. 50-416 DISTRIBUTION o6d9 h6m- L .

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NRC & Local-PDRs:- 1

. System.Eneray Res'ources, Inc.-

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FACILITY: Grand Gulf Nuclear Stationj,; Unit 1 L. Kintner ff ,

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SUMMARY

SUBJECT:

. OF SEPTEMBER 24,g987 MEETING E. ilordan -

REGARDING-REACTOR THERMAL lAND HYDRAULIC LIMITS NRC Participants-

! v  % .8. Troskoski

- ', The. purpose: of the meeting was f o ~ discuss possible thermal hydraul.ic. stability f// L k MM tesis for the' end ~of the second fuel cycle and possible' reduced. minimum control:

,l .povsv ratio (MCPR)'marginsJfor the third fuel cycle. The licensee'was repre- t' w sented by.Y. Balas.<and.I. NJr. Participants for NRC were'L. Phillips and .

r; :L. Kintner. Enc 1 & re 1 1sla handout prepared by the licensee: Sheets 1~-13 h

3p

concern potectini nydraulicisidbility tests and.use of the results' to enlarge

, , it% opefating region isthe' power-flow map; and Sheets 14-26 concern potential

% q~ " improvements in operating flexibility by refined analyses of MPCR and other R: thennal limits. Resulty of GGNS Unit 1 stability tests at the beginning of fueP cycle;(800) So. S are compared with RETRAN analysis results in Sheet 5 of' i u

'! I, Enclosure 1 showing tha,t  !

for the range of decay ratios tested, RETRAN conser-O' vatively, predicts decay ratio.) The licensee estimates that the maximum achie-vable decay ratio. during 'cyclej was at mid-cycle (0.70) and. that the.~end of e

4 g 'dyc b (E00),dw ay ratio will be 0.65. The licensee expects the highest decay y i ratilfor anrehilibrium cwe. The staff commented that while the comparison.

of the GGNS UnitL 1 RETRAN eMpulation with 80C test. data 2 indicates the calcu-lation method 'is. reasonably accurate for low decay ratios, a calculation bench mark fodecay ratios ~ equal to oCgreater than'0.8. should.be obtained because previous calculation methnds have'shown large inaccuracies for high decay ratios. ; A' submittal.requestYng expansion of the operating region in the low coolant ficw reghte should iricluda analysis for flows close to those of test point No. 6 and for an. equilibrium ~ core. In addition, calculation of the worst case core. decay ratios at' the intersection of the natural circulation flow and rod block line would be required.. Any extension of the allowable power-flow

  1. operating region without stability monitoring would need to be .iustified based on calculation results. Approval of the claimed RETRAN uncertainty for predic- -l tion of Grand Gulf core stah111ty will require a description of the model and 1 appropriate benchmarking to plant measurements.

A tape of plant data.obtained during mid-cycle operation at low flow-high power

-conditions has been provided to ORNL for use in LAPVR benchmarking and for Jossible use in support of future applications for changes to the allowable

. HQrating conditions.in Technical Specifications. It is anticipated that addi- j E- '

th4t1 p pes will be obtained for high decay ratio operating conditions near 16e:end of cycle. Such tapes icill also be provided to ORNL.

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The calculated MCPR and MAPFAC factors based on new analyses are shown on- I Sheets 25 and 26, respectively. Operating limits with the recirculation pumps. d in automatic control (auto flux) and manual control show a large margin is available when using the manual control mode. ,

The licensee said it planned to submit requests for improved thermal. hydraulic l stability and MCPR operating limits with appropriate . justification and bases in the first quarter of 1988.

Lester L. Kintner, Project Manager Project Directorate II-2 Division of Reactor Proiects-1/II

Enclosure:

As stated ,

cc w/ enclosures:

See next page P: DII-? 0;Nff22

) LA:PDII-2 DMiller LKintner:bg H8erifow 10/1j/87 10// /87 10/pf/87 l

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Mr. Oliver D. Kingsley,.Jr.

System Energy Resources, Inc. Grand Gulf Nuclear Station (GGNS) l- 'CC '

L -Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager.

and Support. System Energy Resources, Inc.

System Energy Resources, Inc. Post Office Box 756 Post Office Rox 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39005 Robert R. McGehee- Esquire

, The Honorable William J. Guste Jr.  !

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 3UO5 State of Louisiana Raton Rouge, Louisiana 7080a' Nicholas S. Reynolds, Esquire

. Bishop. Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi I?00 17th Street, N.W. Jackson, Mississippi 39201 Washington, D. C. 20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality. Assurance Jackson, Mississippi 39?05 Middle South Utilities System Services,'Inc.

P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management ,

Mississippi Department of Natural  !

Mr. John G. Cesare Resources Director, Nuclear Licensing and Safety Bureau of Pollution Control System Energy Resources, Inc. Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39?09 Jackson, Mississippi 39205 Alton B. Cobb, M.D.

Mr. R. W. Jackson, Pro.iect Engineer State Health Officer Bechtel Power Corporation State Board of Health )

15740 Shady Grove Road P.O. Box 1700 1 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2, Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 303?3 l j

Mr. James E. Cross l GGNS Site Director  !

System Energy Resources, Inc. i P.O. Box 756 Port Gibson, Mississippi 39150 1

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ENCL 9SURE!

. ..,4 EOC2 STABILITY TEST.

Supportina Information Estimated maximum ~~ achievable DR during' Cycle 2:

Cycle Exposure- Max DR BOC 0.60 MOC 0.70 EOC* 0.65 ,

  • Assumed EOC conditions:

100% rod line 39% core flow line LHGR 5 LHGR limit Rated equilibrium Xe J14 MISC 87092104 - 5 /

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GRAND GULF CORE STABILITY

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ANALYTICAL-CONSIDERATIONS j

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'o' 'B002 Test Results k l

Methodology Deficiencies / Uncertainties-4

-*' RETRAN Methodology

' - GGNS Unit 1 Cycle 2 Results

- GGNS Unit 1 Equilibrium Cycle Approach  ;

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  • : Methodology Uncertainties  ;

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ll 0 l 100 1 103 ll 0.18 1 0.11-0.22 ll 11 I I li I I  :

1I I I II I Il l1 1 l 52 1 39 ll 0.31 l 0.25-0.37 l  !

II l l 11 1 I II I i 11 I il ll 2 l 62 l 45 ll 0.32 l 0.27-0.37 'l 11 1 I il I i ll l l ll l lll ll 4 l 59 l 39 ll 0.32 l 0.31-0.33ll 11 1 I il l I II I I II I  !!

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C*HiftltedLMinVolvePosn 0 Il odLine 3g3 8 18 28 36 40 50 H 70 et 90 101 Percent Core flu Figure VI-l Stability Test Points Power / Flow Conditions 1

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ll I I 11 ll 0 l 100 l 103 ll 0.18. l 0.11-0.22 l 0.19 ll ll l l ll l 1 11 Il i I 11 I I 11 ll 1 1 52. l 39 ll 0.31 l 0.26-0.37 l 0.35 ll ll l l ll l .I II II I I II I I II i l 2 1 62 l 45 ll 0.32 l 0.27-0.35 1 0.36 Il  !

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- EVALUATION OF ANF's .

, METHODOLOGY / ANALYSIS RESULTS' l

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*; ~ Analysis Region Attainability i

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RETRAN METHODOLOGY Le .' Based on EPRI Developed Approach

  • :- ' Core, Vessel and Recirculation Loop Modeling RETRAN'Model Benchmarked Against Cycle 1 Startup Tests
  • . Time and Frequency Domain Solut. ion.
  • - Model Qualific'ations Sensitivity' Evaluations Benchmarks to B0C2 Test Results P M e p in 1. f rad: c.4 s'a ns
  • Equilibrium Cycle Analysis Approach i

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. Sensitivity Analyses Paramet'er-Conclusion

1. Core Power Sensitive
2. Core Flow Sensitive
3. Axial Power: Shape Sensitive
4. Fuel-Clad Cap Conductivity Sensitive
5. Moderator Density (Void) Sensitive Reactivity Coefficient
6. Delayed Neutron Fraction Sensitive
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9. GE vs ANF Fuel Geomett y Insensitive i

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. METHOD UNCERTAINTY

  • .RETRAN results agree well with ORNL test results.
  • All RETRAN results are consistently more conservative than ORNL results.
  • To allow for additional conservatism establish surveillance procedures for 1,0 i: DRRETRAN > 0.9 and restrict operations for DRRETRAN > 1. 0 J14 MISC 87092104 - 4

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-, GGNS-1 T/S OPERATING LIMITS IMPROVEMENT PROGRAM

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  • Current Limits

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.- ~MAPLHGR I

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Scope of Analysis In Progress.

-~ Generic RWE

-Limiting Transients (GLR, FWCF)

Two pump flow increase event One, pump flow increase event )

Other events as necessary Both rated and'off-rated events will be considered.

SCHEDULE

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  • Complete margin improvement package - first quarter of 1988 i

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