ML20212G808
| ML20212G808 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/28/1997 |
| From: | Andersen J NRC (Affiliation Not Assigned) |
| To: | Carns N, Loftus P NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M99502, NUDOCS 9711070105 | |
| Download: ML20212G808 (7) | |
Text
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Mr. Neil S. Carns Senior Vics Presidsnt October 28, 1997 and Chief Nuclast Officer Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED REVISION TO THE MILLSTONE UNIT 3 TECHNICAL SPECIFICATIONS DATED AUGUST 29,1997 (TAC NO. M99502)
Dear Mr. Carns:
By letter dated August 29,1997, Northeast Nuclear Energy Company (the licensee) submitted a proposed revision to the Millstone Unit 3 Technical Specifications (TS). Based on a review and subsequent calculations of the cold overpressurization protection (COPS) enabling temperature and the emergency core cooling systern (ECCS)/chargi5 lystem mode 3 requirements, you proposed to reduce the COPS enabling temperature. As a result, you proposed the following TS changes: new heatup and cooldown pressure /
temperature limit curves and their associated requirements; new power operated relief valve (PORV) setpoint curves and their associated requirements; revisions to the reacter coolant loops and coolant circulation, ECCS, boration systems, and COPS to incorporate the lower enabling temperature and new restrictiom: for cold overpressure protection system, PORV undershoot, and residual heat removal (RHR) rellof valve bellows; addition of a footnote to allow a reactor coolant pump to substitute for an RHR pump during heatup i
from Mode 5 to 4, which is consistent with the improved standard technical specification (STS); rewording 3/4.4.P.3 and its Bases section to be consistent with the improved STS:
and revision of the affected Bases sections to be consisten,t with the proposed changes-i The NRC staff has reviewed the proposed changes and in order to support further staff r
evaluation, you are requested to provide the staff with answer,s to the enclosed questions.
Please respond to this request for additionalinformation expeditiously in order for the staff to complete its review in a timely manner.
4 Sinc ely rke t Manager Ja Ad n
Special Projects Office Licensing Office of Nuclear Reactor Regulation i}
Docket No. 50-423 ll I
Enclosure:
As stated N
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WASHINGTON, D.C. 30M64001 October 28, 1997 Mr. Neil S. Carns Senior Vice President and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Ms. Patricla A. Loftus Director - Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED REVISION TO THE MILLSTONE UNIT 3 TECHNICAL SPECIFICATIONS DATED AUGUST 29,1997 (TAC NO. M99502)
Dear Mr. Carns:
By letter dated August 29,1997, Northeast Nuclear Energy Company (the licensee) submitted a proposed revision to the Millstone Unit 3 Technical Specifications (TS). Based on a review and subsequent calculations of the cold overpressurization protection (COPS) enabling temperature and the emergency core cooling system (ECCS)/ charging system mode 3 requirements, you proposed to reduce the COPS enabling temperature. As a result, you proposed the following TS changes: new heatup and cooldown pressure /
temperature limit curves and their associated requirements; new power operated relief valve (PORV) setpoint curves and their associated requirements; revisions to the reactor coolant loops and coolant circulation, ECCS, boration systems, and COPS to incorporate the lower enabling temperature and new restrictions for cold overpressure protection system, PORV undershoot, and residual heat removal (RHR) relief valve bellows; addition of a footnote to allow a reactor coolant pump to substitute for an RHR pump during heatup from Mode 5 to 4, which is consistent with the improved standard technical specification (STS); rewording 3/4.4.9.3 and its Bases section to be consistent with the improved STS; and revision of the affected Bases sections to be consistent with the proposed changes.
The NRC staff has reviewed the proposed changes and in order to support further staff evaluation, you are requested to provide the staff with answers to the enclosed questions.
Please respond to this request for additional information expeditiously in order for the staff to complete its review in a timely manner, Sincerely, s
b w
or,.
James W. Andersen, Pro ct Manager Special Projects Office Licensing Office of Nuclear Reactor Regulation Docket No. 50 423
Enclosure:
As stated cc w/ encl: See next page
i DISTRIBUTION:
Docket file PUBLIC SPO-L Reading SP0 Reading WTravers PHcKee LBerry JAndersen THarris (e-mail SE only TLH3)
BEQUEST FOR ADDITIONAL INFORMATION CONCERNING PROPOSED REVISION TO TECHNICAL SPECIFICATIONS l
DATED AUGUST-29.1997 Mlj,LSTONMUCLEAR POWER STATION, UNIT 3 TAC M99502 1.
Provide the 10 CFR Part 50, Appendix G, pressure / temperature (PR) limits to which the cold overpressure protection system (COPPS) are designed to protect against (i.e., PR limits under steady state reactor operation, the isothermal curve).
2.
Provide a modified Figure 3.4 4a and 'J.4 4b (power operated relief valves (PORVs) setpoints) with instrumentation uncertainties incorporated.
3.
Provide a tabulation to list PORV setpoint, transient pressure overshoot, instrumentation uncertainties, PR limit, and margin under various temperature conditions below the COPPS enable temperature (5 or 6 points including highest and lowest temperature which need COPPS). This data should show that the value of the PORV setpoint plus translent precure increase plus instrumentation uncertainties is still below the PR limit with sufficient margin at each temperature within the area of protection.
4.
Provide data to show that the value of the residual heat removal (RHR) relief valve setpoint plus transient pressure overshoot plus instrumentation uncertaintbs is still below the PR limit with sufficient margin at each temperature within the area of protection and that they are also below the maximum allowable RHR system pressure.
5.
Discuss the major assumptions used in your mass addition and energy addition transients in supportin ur design of the COPPS. Identify the assumptions that are different from t esented in WCAP 14040 and justify them, 6.
The enable temperature is defined in NRC branch technical position (BTP) RSB 5 2 as the water temperature corresponriing to a metal temperature of at least RTndt +
90 degrees F at the beltline location (1/4t or 3/4t). Provide values of the RTndt, Instrumentation uncertainties, and the temperature difference between the reactor coolant and the metal at 1/4t due to the temperature gradient between the vessel wall to demonstrate that the proposed enable temperature of 275 degrees F is properly determined with sufficient margin.
7.
Discuss the standard used for determining the instrum6ntation uncertainties applied in the design of COPPS.
I Enclosure
i
-l 2-8.
Discuss the technical bases to support the following proposed TS:
- a. items a and c of proposed TS 3.4.1.3 footnote
- b. Item b.1 of proposed TS 3.4.1.4.1 footnote
- c. Item a and b.1 of proposed TS 3.4.1.4.2 footnote * * *
- d. Footnote of proposed TS 3.4.9.3 9.
Provide a specific method used to assure the charging or safety injection pumps incapable of injecting water to the reactor coolant system when the restriction is needed during low temperature operation. The method should be single failure proof.
J
N:rtheast Nucl:ar Energy Company Millstone NucI:ar P;wer Station Unit 3 cc:
Lillian M. Cuoco, Esquire Mr. William D. Meinert Senior Nuclear Counsel Nuclear Engineer Northeast Utilities Service Company Massachusetts Municipal Wholesalo P. O. Box 270 Electric Company Hartford, CT 061410270 P. O. Box 426 Ludlow, MA 01056 Mr. Kevin T. A. McCarthy, Director Monitoring and Radiation Division Joseph R. Egan, Esquire Department of Environmental Protection Egan & Associates, P.C.
79 Elm Street 2300 N Street, NW Hartford, CT 06106 5127 Washington, D.C. 20037 Regional Administrator, Region 1 Mr. F. C. Rothen U.S. Nucisar Regulatory Commission Vice President Nuclear Work Services 475 Allendale Road Northeast Nuclear Energy C,ompany King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmen Town of Waterford Ernest C. Hadley, Esquire Hall of Records 1040 B Main Street 200 Boston Post Road P. O. Box 549 Waterford, CT 06385 West Wareham, MA 02576 Mr. Wayne D. Lanning Mr. John Buckingham Deputy Director of Inspections Department of Public Utility Control Special Projects Office Electric Unit 475 Allendale Road 10 Liberty Square King of Prussia, PA 19406 1415 New Britain, CT 06051 Michael H. Brothers Mr. James S. Robinson Vice President Millstone Unit 3 Manager, Nuclear Investments and Northeast Nuclear Energy Company Administration P. O. Box 128 New England Power Company Waterford, CT 06385 25 Research Drive Westborough, MA 01582 Mr. M. R. Scully, Executive Director Connecticut Municipal Electric Mr. D. M. Goebel Energy Cooperative Vice President Nuclear Oversight 30 Stott Avenue Northeast Nuclear Energy Company Norwich, CT 06360 P. O. Box 128 Waterford, CT 06385 Mr. David Amerine Recovery Officer Nuclear Engineering and Support Northeast Nuclear Energy Company P. O. Box 128 Waterford, Connecticut 06385
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 fic:
Debort. Katz, President Mr. B. D. Kenyon Citizens Awareness Network President and Chlef Executive Officer P. O. Box 83 Northeast Nuclear Energy Company Shelburne Falls, MA 03170 P. O. Box 128 Waterford, CT 06385 Senior Resident inspector Millstone Nuclear Power Station Mr. Daniel L. Curry c/o U.S. Nuclear Regulatory Project Director Commission Parsons Power Group Inc.
P. O. Box 513 2675 Morgantown Road Niantic, CT 06357 Reading, Pennsylvanla 19607 Mr. Atlan Johanson, Assistant Director Mr. Don Schopfer Office of Policy and Management Verification Team Manager Policy Development and Planning Division Sargent & Lundy 450 Capitol Avenue MS# 52ERN 55 E. Monroe Street P. O. Box 341441 Chicago, Illinois 60603 Hartiord, CT 061341441 Citizens Regulatory Commission ATTN: Ms. Susan Perry Luxton 180 Great Neck Road Waterford, Connecticut 06385 The Honorable Terry Concannon Co Chair Nuclear Energy Advisory Council Room 4035 Legislative Office Building Capitol Avenue Hartford, Connecticut 06106 Mr. Evan W. Woollacott Co Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, Connecticut 06070 Little Harbor Consultants, Inc.-
Millstone ITPOP Project Office P. O. Box 0630 Niantic, Connecticut 06357 0630
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