ML20217G660
| ML20217G660 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/29/1997 |
| From: | Andersen J NRC (Affiliation Not Assigned) |
| To: | Carns N, Lotfus P NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M99643, NUDOCS 9710140120 | |
| Download: ML20217G660 (4) | |
Text
Mr. Neil S. Carns Senior Vice President-Sephrtvr 29,1997 and Chief Nuclear-Officer
-Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs P.O. Boy 128 Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT 3 - CHANGE TO TECHNICAL SPECIFICATION BASES SECTION 2.2 (TAC N0. M99643)
Dear Mr. Carr,
s:
By letter dated September 18, 1997, Northeast Nuclear Energy Company (NNECO) submitted a change to Technical Specification (TS) Bases Section 2.2.1, Reactor Trip System Instrumentation Setpoints.
The change clarifies the function of the P-6 interlock for increasing as well as decreasing reactor power. The P-6 interlock is a permissive which, on increasing power during reactor startup, becomes active above the interlock allowable value specified
-in TS Table 2.2-1 to allow the manual block of the source range high flux reactor trip, and deenergizes the high voltage to the source range detectors.
On decreasinc power during reactor shutdown, the P-6 interlock deactivates to reinstate the source range high flux trip, and the source range detectors are reenergized.
The Millstone Unit 3 Plant Operating Review Committee approved the revision to Bases Section 2.2.1 on September 12, 1997.
The Bases section now includes a statement that the P-6 deactivation will occur at a value below its activation value and may be calibrated to occur below the P-6 interlock allowable value to prevent overlap and chatter based u)on the expected bistable drift.
The NRC staff has reviewed the change and 1as no objection to the wording. A copy of revised TS Bases page 2-7 is enclosed.
I L
Sincerely, g
$Dft DO N osooN23 James Y Yn e n Project Manager P
PDR Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No.
50-423-
Enclosure:
Revised TS Bases page 2-7' cc w/ encl:
See next page h
DISTRIBUTION:
'f Docket File PUBLIC-SP0-L Reading
/\\
SP0 Reading-WTravers
- 0/
PMcKee en -
US gM (MM %f8y LBerry JAndersen-
.c43 GHill (2)
.ll[ [" l ff l.f l-ll,l'
.i 0GC ACRS
- '*c JDurr, RI D0t.dMENT NAME: G:
/
t..i...p,.iihie oo.om.\\ANDERSEN\\M99643.LTi nt,indcate in the bot'. 'C' = Copy without attac%fnq e
'E' = Copy with attachment / enclosure
- N* = No copy 0FFICE SP0-L:PM A SPO-L:LA (! 0(3 SP0/L/.UD /
l SRXS
,l N MsC3 E
NAME JAndersen@
' LBerry
)(f 7 PMdKee
'T Cc// d Wt/
l 0 ATE 09/uS/97 09/B597 1
49/4,/97 49/4 /97 09/$/97 hb
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 j
cc:
1 Lillian M. Cuoco, Esquire Mr. William D. Meinert Senior Nuclesr Counsel Nuclear Engineer Northeast Utilities Service Company Massachusetts Municipal Wholesale P 0.-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 Ragional 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 Selectmen L
Town of Waterford Ernest C. Hadley, Esquire L
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
- '.4 nager, 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 Cocperative Vice President - Nuclear Oversight 30 Stott Avenue.
Northeast Nuclear Energy Company-Norwich, CT 06360 P 0.-Box 128 4
Waterford, CT 06385 Mr. David Amerine Recovery Officer - Nuclear Engineering and Support Northeast Nuclear Energy Company P. O. Box 128 Waterford,-Connecticut 06385
'I
Northeast Nuclear Energy Company Millstone Nuclear Power Station j
Unit 3 i
CC:
Deborah Katz, President Mr. B. D. Kenyon
)
Citizens Awareness Network President and Chief Executive Officer l
P. O. Box 83 Northeast Nuclear Energy Company
~
Shelburne Falls, MA 03170 P. O. Box 128 Waterford, CT 06385 Senior Resident Inspector Millstene Nuclear Power Station Mr. Daniel L. Curry c/o U.S. Nuclear Regulatory Project Director Commission Parsons Power Group Inc.
l P. O. Box 513 2675 Morgantown Road Niantic, CT 06357 Reading, Pennsylvania 19607 1
Mr. Allan 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 Hartford, CT 06134-1441 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
g,y -
_.g.--------._5..
..... -..=..... -
- m - f..,* '" - -M -- - -
.,,,y LIMITING SAFETY SYSTEM SETTlHGS BA!ES Steam Generator Water Level The Steam Generator Water Level Low Low trip protects the reactor from loss of heat sink in the event of a sustained steam /feedwater flow mismatch resulting from loss of normal feedwater, lhe specified Setpoint provides allowances for starting delays of the Auxiliary Feedwater System.
Low Shaft Speed - Reactor Coolant Pumos The Low Shaft Speed - Reactor Coolant Pumps trip provides core protection to prevent DNB in the event of a sudden significant decrease in reactor coolant pump speed (with resulting decrease in flow) on two reactor ecolant pumps in any two operating reactor coolant loops.
The trip setpoint ensures that a reactor trip will be generated, considering inst rument errors and response times, in sufficient time to allow the DNBR to be maintained greater than the design above limit following a four-pump inss of flw event.
Turbine Trio A Turbine trip initiates a Reactor trip. On decreasing power the Reactor trip from the Turbine trip is automatically blocled by P-9 (a power level of approximately 501r, of RATED THERMAL POWER); and on.ncreasing power, reinstated automatically by P-9.
Safety Injection Inout frem ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate Reactor trip upon any signal which initiates a Safety injection.
The ESF instrumentation channels which initiate a Safety Injection signal are
-shown in Table 3.3-3.
Reactor Trio System Interlocks The Reactor Trip System interlocks 9erform the following functions:
P-6 On increasing power, P-6 becomes activa above the Interlock Allowable Value specified on Table 2.2-1 to allow the manual block of the Source Range trip (i.e., prevents premature block of the Source Range trip during reactor startup) and deenergizes the high voltage to the deter. tors.
On decreasing power during a reactor shutdown, Source Range Level trips are automatically reactivated and high voltage restored when P 6 deactivates.
The P-6 deactivation will occur at a value below its activation value and may be calibrated to occur below the P-6 Interlock Allowable Value specified on Table 2.2-1 to prevent overlap and chatter based upon the expected bistable drift.
P-7 On increasing power P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, reactor coolant pump low shaft speed, pressurizer low pressure and pressurizer high level. Ca decreasing power, the above listed trips are automatically blocked.
Mill.siONE - UNIT 3 827 Revised by NRC Letter N
datM j
,