ML20217P009
| ML20217P009 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/21/1997 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | Schopfer D SARGENT & LUNDY, INC. |
| References | |
| NUDOCS 9708260412 | |
| Download: ML20217P009 (5) | |
Text
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Mr. Don Schopf:r, V:rificati:n Team M: nager Atrjust 21,1997 S;rgent & Lundy 55 E. Monroe Street Chicago,IL 60603
Dear Mr. Schopfer:
On June 30,1997, you submitted for NRC review and approval, the critical characteristics for the accident mitigation systems discussed in Chapter 15 of the Millstone Unit 3 Final Safety Analysis Report (FSAR). The staff has completed its review of these critical characteristics.
The enclosure provides the results of the NRC's review. The NRC has identified additional system parameters that are important to the safety analysis in Chapter 15 of the FSAR. You are requested to incorporate the additional system parameters into your Independent Corrective Action Verification Program (ICAVP) Tier 2 review of Millstone Unit 3 and to provide the NRC with an update to the critical characteristics that identifies where each of the additional parameters were incorporated. For these identified system parameters, you should verify that the values assumed in the safety analysis are accurately reflected in Chapter 15 of the FSAR and are supported by the plant design data and test data with measurement uncertainties. For the parameters that used limiting values in the analysis, you should verify that the values are bounded by Technicol Specifications limits or by the operating limits specified in the core operating limits report.
The NRC did not ide6fy any critical characteristics in your June 30,1997, submittal that do not require your review. As such the set of critical characteristics in your June 30,1997, submittal are conditionally approved for the ICAVP Tier 2 review. Following incorporation of the additional parameters as described above, the NRC will provide final approval of the critical characteristics that you are required to review to complete the ICAVP Tier 2 review.
The staff has also reviewed the generic methodology you proposed in Attachments 3 through 6 of your June 30,1997, submittal. The NRC staff determined that the generic methodologies you proposed are acceptable and approves them for use during the ICAVP Tier 2 review of the accident mitigation systems at Millstone Unit 3.
If you have any questions or comments please contact me at (301) 4151490 or e-mail EXI@NRC. GOV.
Sincere vgfist._...,.,p ty.
Eugene Imbro, Deputy Director ICAVP Oversight Special Projects Office Office of Nuclear Reactor Regulation
Enclosure:
As stated i
cc w/ encl: See next page h'
DISTRIBUTION:
Docket Files (Docket 50-423)
PUBLIC WTravers JAndersen SPO R/F PMcKee
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EVimbro DATE Y lb/97
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ADDITIONAL SYSTEM PARAMETERS IMPORTANT TO SAFETY ANALYSIG FOR MILLSTONE UNIT 3 1.
System Parameters Aeolicable to All Accident Anaivseg Rod Cluster Control Assembly (RCCA) position versus drop time (FSAR Figure a.
15.0-3).
b.
RCCA reactivity worth as a function of RCCA insertion (FSAR Figures 15.0-4 and 5).
c.
Reactor Coolant Pump (RCP) coastdown flow rate.
2.
Decrease in Feedwater Temoerature Event a.
The maximum decrease in the feedwater temperature (35 'F) assumed for loss of one train of feedwater heater.
3.
Steam Line Break a.
RCP coastdown flow, b.
Reactor Protection System (RPS): Reactor trip setpoints and trip delay times.
c.
High Pressure Safety injection (HPSI) actuation: Setpoints, delay time, safety injection (SI) flow with and without a loss of offsite power, and Si boron concentrations, d.
Main Steam System: Isolation valve actuation setpoint, delay time, and isola'slon valve closure time, e.
Main Feedwater System: Flow rate, temperature, termination of feedwater flow with and without a loss of offsite power, delay time, and isolation valve closure
- time, f.
Auxiliary Feedwater System (AFWS): Actuation time of AFWS with and without a loss of offsite power, flow rate, temperature, isolation actuation setpoints, delay time, and isolation valve closure time.
4.
Turbine Trio a.
Pressurizer spray: Operability, actuation setpoint, flow rate, and fluid temperature.
S.
A Loss of Normal Feodwater a.
RCP coastdown flow following the RCP trip that results from a loss of offsite power.
Enclosure
l Northeast Nuclear Energy Company Millstone Nuclear Power Station Units 2 and 3 cc:
Lillian M. Cuoco, Esquire Citizens Regulatory Commission Senior Nuclear Counsel ATTN: Ms. Susan Perry Luxton Northeast Utilities Service Company 180 Great Neck Road P. O. Box 270 Waterford, Connecticut 06385 Hartford, CT 06141-0270 Mr. F. C. Rothen Mr. Kevin T. A. McCarthy, Director Vice President Nuclear Work Services Monitoring and Radiation Division Northeast Niiclear Energy Company Department of Environmental P.O. Box 128 Protection Waterford, CT 06385 7g Elm Street Hartford, CT 06106 5127 Charles Brinkman, Manager Wash!ngton Nuclear Operations Mr. Atlan Johanson, Assistant Director ABB Combustion Engineering Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 Policy Development and Planning Rockville, MD 20852 Division 450 Capitol Avenue MS 52ERN Mr. D. M. Goebel P. O. Box 341441 Vice President Nuclear Oversight Hartford, CT 061341441 Northeast Nuclear Energy Company P. O. Box 128 Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. M. L. Bowling, Jr.
King of Prussia, PA 19406 Millstone Unit No,2 Nuclear Recovery Officer First Selectmen Northeast Nuclear Energy Company Town of Waterford P. O. Box 128 Hall of Records Waterford, CT 06385 200 Boston Post Road Waterford, CT 06385 Senior Resident inspector Millstone Nuclear Power Station Deborah Katz, President c/o U.S. Nuclear Regulatory Commission Citizens Awareness Network P. O. Box 513 P. O. Box 83 Niantic, CT 06357 Shelburne Falls, MA 03170 Mr. J. K. Thayer Mr. Wayne D. Lanning Recovery Officer - Nuclear Deputy Director of Inspections Engineering and Support Special Projects Office Northeast Nuclear Energy Company 475 Allendale Road P. O. Box 128 King of Prussia, PA 19406-1415 Waterford, CT 06385 Mr. M. R. Scully, Executive Director Burlington Electric Department Connecticut Municipal Electric clo Robert E. Fletcher, Esq.
Energy Cooperative 271 South Union Street 30 Stott Averue Burlington, VT 05402 Norwich, CT 06360
?
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unita 2 and 3 cc:
Mr. William D. Meinert Mr. John Buckingham Nuclear Engineer Department of Public Utility Control Massachusetts Municipal Wholesale Electric Unit i
Electric Company 10 Liberty Square P. O. Box 426 New Britain, CT 06051 i
Ludlow, MA 01056 Mr. James S. Robinson Ernest C. Hadley, Esq.
Manager, Nuclear Investments and 1040 B Main Street Administration P. O. Box 54g New England Power Company West Wareham, MA 02576 25 Research Drive Westborough, MA 01582 Joseph R. Egan, Esq.
Egan & Associates, P.C.
Mr. B. D. Kenyon 2300 N Street, NW President and Chief Executive Officer Washington, D.C. 20037 Northeast Nuclear Energy Company P. O. Box 128 The Honorable Terry Concannon Waterford, CT 06385
- Co-Chair Nuclear Energy Advisory Council Mr. M. H. Brothers Room 4035 Vice President - Millstone Unit 3 Legislative Office Building Northeast Nuclear Energy Company Capitol Avenue P. O. Box 128 Hartford, Connecticut 06106 Waterford, CT 06385 Mr. Evan Woollacott Mr. John C. Markowicz Co-Cnair Nuclear Energy Advisory Council
- Nuclear Energy Advisory Council 9 Susan Terrace 128 Terrys Plain Road Waterford, CT 06385 3515 Simsbury, CT 06070 Mr. Daniel L. Curry Ms. P. Loftus Project Director Director Regulatory Affairs for Millstone Project Millstone Station Parsons Power Group Inc.
Northeast Nuclear Energy Company 2675 Morgantown Road P. O. Box 128 Reading, PA 19607 Waterford, CT 06385 Mr. N. S. Carns -
Senior Vice President and Chief Nuclear Officer Northeast Nuclear Energy Company P. O. Box 128 Waterford, CT 06385
Mr. Don Sch:pf;r, V rific:ti:n Tcim M: nager Sargent & Lundy 55 E. Monroe Street Chicago,IL 60603
Dear Mr. Schopfer:
On June 30,1997, you submitted for NRC review and approval, the critical characteristics for the accident mitigation systems discussed in Chapter 15 of the Millstone Unit 3 Final Safety Analysis Report (FSAR). The staff has completed its review of these critical characteristics.
The enclosure provides the results of the NRC's review. In the enclosure, the NRC has identified additional system parameters that are important to the safety analyses described in Chapter 15 of the FSAR. You are requested to incorporate the additional system parameters into your independent Corrective Action Verification Program (ICAVP) Tier 2 review of Millstone Unit 3 and to provide the NRC with an update to the critical characteristics that identifies where each of the additional parameters were incorporated. For the system parameters within the scope of the Tier 2 review, you should verify that the values input to the analyses described in Chapter 15 of the FSAR are consistent with those stated in Chapter 15 of the FSAR and the Technical Specifications, and are supported by the plant design data and test data including measurement uncertainties.
The NRC did not identify any critical characteri tics in your June 30,1997, submittral that do not require your review. The set of critical characteristics in your June 30,1997, submittal as supplemented by the enclosure to this le}ter are approved for the ICAVP Tier 2 review.
The staff has also reviewed the generic methodology you proposed in Attachments 3 through 6 of your June 30,1997, submittal. The NRC staff determined that the generic methodologies you proposed are acceptable and approves them for use during the ICAVP Tier 2 review of the accident mitigation systems at Millstone Unit 3.
If you have any questions or comments please contact me at (301) 415-1400.
Sincerely, a
Eugene Imbro, Deputy Director ICAVP Oversight Special Projects Office Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ encl: See next page DLS.TRIBUTION:
Docket Files (Docket 50-423)
PUBLIC WTravers JAndersen SPO R/F PMcKee
- See previous concurrence page, f o receive a copy of th's document. Indicate in the hos "C" a Copy without attacNenci *E" e Copy with ettacNonct "N" s No copy OFFICE ICAVP/SPO E
LA ICAVP/SPO ICAV.'/SPO NAME JANakosk
- LBerry*
SReynolds*
EVimbro DATE 8/ S /97 8/ S/97 8 /5 /97
/ /97 OFFICIAL RECORD COPY i