ML17328A702

Forwards Summary of 900419 Meeting W/Util Re Cycle 8 Reload Analysis.List of Attendees & Slides Encl

ML17328A702
Person / Time
Site:	Cook
Issue date:	05/04/1990
From:	Giitter J Office of Nuclear Reactor Regulation
To:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
References
NUDOCS 9005160226
Download: ML17328A702 (36)

Text

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Docket Nos.

50-315/316 May 4, 1990 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Mr. Milton Alexich Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

SUBJECT:

MEETING WITH INDIANA MICHIGAN POWER COMPANY TO DISCUSS CYCLE 8 RELOAD ANALYSIS FOR D.

C.

COOK UNIT 2.

On April 19, 1990, the staff met with Indiana Michigan Power Company (IMPC) to discuss the proposed Technical Specification (TS) amendments related to the D.

C.

Cook Unit 2 Cycle 8 reload.

A list of attendees is provided as Attachment l.

A copy of the slides (all non-proprietary) is provided as.

IMPC has submitted three technical specification amendment applications to support Cycle 8 for D.

C.

Cook Unit 2:

(1) an amendment that reflects revised accident analyses for Cycle 8, (2) an amendment that would allow receipt of fuel assemblies with higher enrichment into the spent fuel pool and new fuel storage vault, and (3) an amendment that would allow cycle specific parameters to be removed from technical specifications and placed in a Core Operating Limits Report.

The staff informed IMPC that safety evaluations for items 2 and 3 were complete and that TS should be issued within the next month.

IMPC currently estimates. that Unit 2 will enter a refueling outage toward the beginning of July and commence Cycle 8 at the end of August.

The transition core designed for Cycle 8 wi 11 include 77 new Westinghouse 17 x 17 Vantage 5

fuel assemblies plus 116 of the previously utilized Advanced Nuclear Fuels 17 x 17 fuel assemblies.

Changes from previous analyses include revised set points or response times for some reactor protection system and engineered safety features actuations, a

decrease in shutdown margin (to 1.6X),

an increase in minimum boric acid storage tank volume, an increase in allowable rod drop time, and relaxed accumulator volume and pressure limits.

The proposed amendment would also modify some current transition mode requirements.

For example, shutdown margin requirements would be added for modes 4 and 5 such that an operator would have sufficient time (at least 15 minutes) to respond to a postulated boron dilution transient.

9005160226 900504 PDR AXIOCK 05000315 P

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I INPC still plans to submit information related to incomplete modelling of the feedwater regulating valves, in addition to some corrected TS pages and other information requested by the staff.

INPC requested HRC response relative to the shutdown margin requirement in mode 4 and 5 by June 29th and approved TS hy August 15th.

S incere ly, Attachments:

As stated e p G. Giitter, Project tlanager Project Directorate III-I Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation cc:

See next page

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~ ll IMPC still plans to submit information related to incomplete modelling of the feedwater regulating valves, in addition to some corrected TS pages and other information requested by the staff.

IMPC requested NRC response relative to the shutdown margin requirement in mode 4 and 5 by June 29th and approved TS by August 15th.

Sincerely, Attachments:

As stated cc:

See next page DISTRIBUTION

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/90 I /90 Original signe4 gy Joseph G. Giitter, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation (A)D/PD31:DRSP DDiIanni 05/3 /90

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Mr. Milton Alexich Indiana Michigan Power Company Donald C.

Cook Nuclear Plant CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C. Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nucleai Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 Mr. S.

Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

ATTACHHENT 1 HEETING WITH D. C.

COOK TO DISCUSS UNIT 2 CYCLE 8 RELOAD ANALYSIS APRIL 19, 1990 Thomas A. Georgantis Vance Vanderburg Steve Brewer Shamul Abedin Donald H. Behuki Juan H. Nieto Bert Svensson Doug Halin Harry Balukjian Daniel Fieno Joseph G. Giitter Laubros Lois Scott R. Griffith Hichael A. Emery Bernard W. Gergos Hark Caruso Dominic DiIanni AFFILIATION AEPSC-NF&A AEPSC-NF&A AEPSC-NS&L Westinghouse/NS Westinghouse/Nuc Sof AEPSC-NS&L Indiana Hichigan Power AEPSC-Nuclear Fuels NRR/RSB NRR/SRXB NRR/DRSP NRR/DST Westinghouse/Nuc Safety Westinghouse/Nuc Safety Westinghouse/CNFD NRR/SRXB NRR/DRSP TITLE Engineer Scientist Hanager Sr'. Engineer Sr. Engineer Sr. Engineer Lic. Coord.

Hanager Reactor Engineer Sr. Reactor Physicist Project Hanager Sr. Nuclear Engineer Engineer Engineer Sr. Engineer Section Chief Acting Project Director

Attachment 2

DONALD C. COOK NUCLEAR PLANT UNIT 2 CYCLE 8 Presentation to NRC Staff April 19, 1990

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DONALD C. COOK NUCLEAR PLANT UNIT 2 CYCLE 8 Currently Projected Outage Schedule End of Cycle 7......... 29Jun90 Mode 5 Cycle 8....... 22Aug90 Mode 4 Cycle 8....... 27Aug90 Transition Core 77 Westinghouse 17 x 17 V-5 Assemblies 116 Advanced Nuclear Fuels 17 x 17 Assemblies

~ Vantage 5 Fuel Integral Fuel Burnable Absorber

- Intermediate Flow Mixers Reconstitutable Top Nozzle Extended Burnup Axial Blankets Debris Filter Bottom Nozzle APRIL 19, 1990:NRC419AA

Cycle 8 Submittals

~ Unit 2 Cycle 8 Reload Analyses (AEP:NRC:1071E,1071H)

~ Unit 2 Cycle 8 Criticality Analyses (AEP:NRC:1071F,10716)

~ Unit 2 Core Operating Limits Report (AEP:NRC:1077A)

April 19, 1990:NRC419A

UNIT 2 CYCLE 8 RELOAD ANALYSES

~ Unit 2 Licensing Basis

~ Proposed TiS Changes

PURPOSES OF CYCLE 8 T/S CHANGES

~ Support Mixed Core Operation ANF 17x17 Fuel Westinghouse 17x17 V-5 Fuel

~ Gain Operational Flexibility

~ Remove Non-Standard Transition Mode Requirements

~ Similar Changes to Unit 1 Where Justifications Are Similar

ORGANIZATION OF CYCLE 8 RELOAD ANALYSES SUBMITTAL

~ Cover Letter

~ Eleven Attachments

Attachments Description and 50.92 Evaluation 2.

Proposed T/S Changes 3.

Summary 4.

Westinghouse Analyses and Evaluations 5.

Westinghouse Analysis of M&E Release inside Containment 6.

Westinghouse Evaluation to Support Pressurizer Operability at 92% Level 7.

Draft Cycle 8 COLR 8.

Unit 2 Licensing Basis 50.92 Evaluation 9.

Letter from NRC Staff Discussing Previous Cycle 8 Meeting

10. Part B of WCAP 10217-A, Fq Surveillance Technical Specification f1. Major Analytical Assumptions from WCAP 11908, "Containment integrity Analysis for Donald C. Cook Plant Units 1 and 2"

Page 5

ATTACHMENT 3 TO AEP:NRC:1071K

SUMMARY

DESCRIPTIONS FOR DONALD C.

COOK NUCLEAR PLANT UNIT 2 CYCLE 8 PROPOSED T/Ss Pa e

Section Descri tion Remarks 3/4 1-3b Figure 3.1-3 2

033 Remove Figure 3.1-3 The shutdown margin requirements for Mode 4 and Mode 5 when operating on RHR were added to the Unit 2 T/Ss by Amendment 82.

This requirement ensures the operator has adequate time to respond to dilution transients when operating on RHR.

We propose to address this concern administratively.

See Attachment 1; T/S Change Group 2b 3/4 1-16 3.1.2.8 1

034 Item al; the required volume of the 20,000 ppm boration source is increased to 7715 gallons The new value is a value which is expected to accommodate uprating to a core thermal power of 3588 MWt, fuel of increased enrichment for increased cycle

length, and changes in vendor methodology.

This change is indicated in Attachment 4, Table 6.1 and Attachment 4, Appendix A.

4 035 Mathematical symbols replaced with words Administrative change 3/4 1-23 3.1.3.4 1

036 The rod drop time requirement is changed to less than or equal to 2.7 seconds The pressure drop is larger in V5 than other fuel types requiring an increase in rod drop time to 2.7 seconds.

See Attachment 4, Section 5.1.2;, Appendix B, Section B.2.4; and Attachment 4, Appendix C, Table C.3.2-1.

4 037 Mathematical symbols Administrative change replaced with words

1 NEW ANALYSES FOR UNIT 2 CYCLE 8

~ Uncontrolled RCCA Bank Withdrawal From A Subcritical Condition

~ Uncontrolled RCCA Bank Withdrawal At Power

~ Rod Cluster Control Assembly Misalignment

~ Rod Cluster Control Assembly Drop

~ Uncontrolled Boron Dilution

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NEW ANALYSES FOR UNIT 2 CYCLE 8 (CONTINUED)

~ Loss of Forced Reactor Coolant Flow (including Locked Rotor)

~ Loss of External Electric Load or Turbine Trip

~ Loss of Normal Feedwater

~ Excessive Heat Removal Due to Feedwater System Malfunctions

~ Excessive Load Increase

~ Loss Of Offsite Power to the Station Auxiliaries

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NEW ANALYSES FOR UNIT 2 CYCLE 8 (CON T IN UE D)

~ Rupture of a Steamline

~ Rupture of a Control Rod Drive Mechanism Housing

~ Major Rupture of Main Feedwater Pipe

~ Large Break LOCA

~ Small Break LOCA

~ Post LOCA Long Term Cooling

~ Combined Seismic LOCA Analysis

TlS CHANGE GROUPS

~ Changes Based on Analyses

~ Transition Mode Requirements

~ Changes Previously Made for Unit 1

~ Administrative

~ Delta Flux Surveillance

~ Parallel Changes to Unit 1 T/S

CHANGES FROM ANALYSES

~ New Safety Limit Curves

~ New OPDT/OTDT Setpoints

~ Increase Design Flow to to 91,600 gpm/loop

~ Decrease SDM to 1.6%

~ Increase Minimum BAST Volume

~ Increase Allowable Rod Drop Time to 2.7 Seconds

~ New Mode 1 Operating Window:

643.9oF

< Tavg

< 578.7oF Pressurizer Pressure

> 2200 psig RCS Total Flow

> 366,400 gpm Note: Design Flow

= 366,400 gpm / 4

CHANGES FROM ANALYSES (Continued)

~ Revise Fp Penalty

~ Add Protection Response Time

- Pressurizer Level

~ Relax Response Times Pressurizer

Pressure, Low and High Low Flow, One and Two Loops Steam Generator Level, Low-Low

- Undervoltage RCPs

~ New High Steam Flow Setpoints

~ Add Safeguards

Response

Times

- Containment Pressure High Steam Generator Level, High-High

CHANGES. FROM ANALYSES (Continued)

~ Relax Accumulator Volume and Pressure Limits 921 to 971 Cubic Feet 585 to 658 psig

~ Relax Permissible Sl and RHR Pump Degradation

~ Relax Boron Injection Flow Imbalance

~ Related Bases Changes

TRANSITION MODE REQUIREMENTS

~ SDM in Modes 4 & 5 for Boron Dilution Transient

~ Protection for Increased Steam Load Transient in Mode 3

~ DNB Protection in Modes 2,3,48 6

~ 8 Footnote for Steam Generator High-High Level Safeguards Actuation

PROPOSED UNIT 2 T/S CHANGE PREVIOUSLY APPROVED FOR UNIT 1

~ OPERABILITY LEVEL FOR PRESSURIZER

PROPOSED UNIT 1 CHANGES SIMILAR TO PROPOSED UNIT 2 CHANGES

~ SDM In Modes 4 & 5 For Boron Dilution Transient

~ Delta Flux Surveillance

~ Sl and RHR Pump Degradation

DELTA FLUX SURVEILLANCE AFTER RESTORING MONITOR OPERABILITY

~ 24 Hour Monitoring Requirement Based on Inability to Update Time Out of Target Band

~ Not Needed lf Known Delta Flux Not Out of Target Band

FEEDWATER SYSTEM MALFUNCTION ZERO POWER CASE

~ One Open Item Remains from AEP:NRC:1071E Submittal:

Incomplete Modelling of Feedwater Regulating Valve in Original Analysis

~ Analysis Redone

~ All Acceptance Criteria Are Met

~ NRC Submittal:

May 1990

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COLR PARAMETERS

~ MTC: -38.0 pcm/oF for HFP Tavg 574.0oF

~ 300 ppm Acceptance Criterion:

Approximately -32 pcm/oF (1)

~ ARO: 228 Steps

~ Rod Insertion Limits

~ Delta Flux Wings

~ F(Q):

2.33 for Westinghouse Fuel 2.10 for ANF Fuel

~ K(Z)

~ F Delta H:

1.56 for Westinghouse Fuel 1.49 for ANF Fuel

~ v(z)

(~)

(1):

To Be Calculated Unit 2 Cycle 8 Reload Submittal Assumes COLR Submittal Approval

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CONCLUSIONS

~ Standard Westinghouse Fuel Product in Westinghouse NSSS

~ No Challenge to Health, Safety, and Welfare of the Public

~ Reviewed Submittal with NRC

~ Unit 2 COLR - Under Staff Review

~ Unit 2 Criticality - Under Staff Review

~ AEP to Provide Final Documentation for Feedwater Malfunction in May

~ Need NRC Response to Modes 4 8 5 SDM by June 29

~ Need NRC Final Approval by August 35

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