ML20141H876
| ML20141H876 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/30/1997 |
| From: | Andersen J NRC (Affiliation Not Assigned) |
| To: | Carns N, Loftus P NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M99262, NUDOCS 9708010248 | |
| Download: ML20141H876 (5) | |
Text
,. -
Mr. Neil S. Carns Senior Vice President July 30, 1997 and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT 3 - CHANGE TO TECHNICAL SPECIFICATION BASES SECTION 3/4.9.7 (TAC N0. M99262)
Dear Mr. Carns:
Qy letter dated July 14, 1997, Northeast Nuclear Energy Company submitted changes to Technical Specification (TS) Bases Section 3/4.9.7, Crane Travel -
Spent Fuel Storage Areas.
The change modifies TS Bases Section 3/4.9.7 to be consistent with the revised impact load analysis for the spent fuel racks.
The change to the Bases, along with the July 1, 1997, revision to the Millstone Unit 3 Final Safety Analysis Report (FSAR), _ removes inconsistencies between the TS and the FSAR regarding load limits.
The NRC staff has reviewed the changes and has no objection to the wording. A copy of revised Bases page B 3/4 9-2 is enclosed.
Sincerely, Original signed by:
4 James W. Andersen, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Revised Bases page B 3/4 9-2 cc w/ encl:
See next page DISTRIBUTION:
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41 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION
,o*g WASHINGTON. D.C. 20066 0001 July 30, 1997
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Mr. Neil S. Carns Senior Vice President and Chief Nuclear Officer 1
Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs J
P.O. Box 128 Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT 3 - CHANGE TO TECHNICAL j
SPECIFICATION BASES SECTION 3/4.9.7 (TAC NO. M99262)
Dear Mr. Carns:
By letter dated July 14, 1997, Northeast Nuclear Eaergy Company submitted changes to Technical Specification (TS) Bases Section 3/4.9.7, Crane Travel -
Spent Fuel Storage Areas. The change modifies TS Bases Section 3/4.9.7 to be consistent with the revised impact load analysis for the spent fuel racks.
The change to the Bases, along with the July 1,1997, revision to the Millstone Unit 3 Final Safety Analysis Report (FSAR), removes inconsistencies between the TS and the FSAR regarding load limits.
The NRC staff has reviewed the changes and has no objection to the wording. A copy of revised Bases page B 3/4 9-2 is enclosed.
j Sincerely, J nes W. Andersen, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Revised Bases page B 3/4 9-2 j
cc w/ encl:
See next page
. =,
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 cc:
Lillian M. Cuoco, Esquire Mr. William D. Meinert i
Senior Nuclear Counsel Nuclear Engineer Northeast Utilities Service Company Massachusetts Municipal Wholesale 1
P. O. Box 270 Electric Company Hartford, CT 06141-0270 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 I Mr. F. C. Rothen U.S. Nuclear Regulatory Commission Vice President - Nuclear Work Services 475 Allendale Road Northeast Nuclear Energy Company King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmon 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 Raad 10 Liberty Square Kiig 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. 60ebel Energy Cooperative Vice President - Nuclear Oversight 30 Stott Avenue Northeast Nuclear Energy Company Norwich, CT 06360 P. O. Box 128 Waterford, CT OF385 Mr. Mr. K. Thayer 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 cc:
Deborah Katz, President-Mr. Daniel L. Curry Citizens Awareness Network Project Director P. O. Box 83 Parsons Pow r Group Inc.
Shelburne Falls, MA 03170 2675 Morgantown Road Reading, Pennsylvania 19607 Senior Resident Inspector Millstone Nuclear Power Station Mr. Don Schopfer c/o U.S. Nuclear Regulatory Verification Team Manager Commission Sagent & Lundy P. O. Box 513 55 E. Monroe Street Niantic, CT 06357 Chicago, Illinois 60603 i
Mr. Allan Johanson, Assistant Director Office of Policy and Management i
Policy Development and Planning Division 450 Capitol Avenue - MS# 52ERN P. O. Box 341441 1
Hartford, CT 06134-1441 Citizens Regulatory Commission ATTN: Ms. Susan Perry Luxton 180 Great Neck Road i
Waterford, Connecticut 06385 The Honorable Terry Concannon Co-Chair Nuclear Energy Advisory Council j
Room 4035-Legislative Office Building Capitol Avenue Hartford, Connecticut 06106 Mr. Evan W. Wocllacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road
$1msbury, Connecticut 06070 Little Harbor Consultants, Inc.
Millstone - ITPOP Project Office P. O. Box 0630 Niantic, Connecticut 06357-0630 Mr. B. D. Kenyon President and Chief Executive Officer Northeast Nuclear Energy Company P. O. Sox 128 Waterford, CT 06385 I
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i REFUELING OPERATIONS I
BASES e
l 3/4.9.6 REFUELING MACHINE j
The OPERABILITY requirements for the refueling machine ensure that:
(1) refueling machines will be used for movement of drive rods and fuel assem-i blies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from j
excessive lifting force in the event they are inadvertently engaged during i
lifting operations.
t 5
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS i
i The restriction on movement of loads over fuel assemblies in the storage pool ensures that in the event the load is dropped:
(I) the activity release will be less than the activity release assumed in the design basis fuel handling accident, and (2) the resulting geometry will not result in a critical j
array.
k 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION I
j 314.9.8.1 HIGH WATER LEVEL
{
BACKGROUND j
' The purpose of the Residual Heat Removal (RHR) System in MODE 6 is to remove 1
decay heat and tensible heat from the Reactor Coolant System (R.CS), as required 4
l by GDC 34, to provide mixing of borated coolant and to prevent boron stratification. Heat is removed from the RCS by circulating reactor coolant through the RHR heat exchanger (s), where the heat is transferred to the Reactor Plant Component Cooling Water System. The coolant is then returned to the RCS via the RCS cold leg (s). Operation of the RHR system for normal cooldown or decay heat removal is manually accomplished from the control room. The heat removal is manually accomplished from the control room. The heat removal rate is adjusted by controlling the flow of reactor coolant through the RHR heat exchanger (s) and the bypass. Mixing of the reactor coolant is maintained ey this continuous circulation of reactor coolant through the RHR system.
APPLICABLE SAFETY ANALYSES If the reactor coolant temperature is not waintained below 200*F, boiling of the reactor coolant could result. This could lead to a loss of coolant in the reactor vessel. Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to boron plating out on components near the areas of the boiling activity. The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is fission product barrier.
One train of the RHR system is required to be operationa' in MODE 6, with the water level 123 ft above the top of the reactor vessel Gange to prevent this challenge. The LCO does permit deenergizing the RHR pump for short darations, MILLSTONE - UNIT 3 B 3/4 9-2 Revised by NRC Letter esn dated 11, vt 1907