ML20249A788
| ML20249A788 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/16/1998 |
| From: | Andersen J NRC (Affiliation Not Assigned) |
| To: | Bowling M NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-MA1608, TAC-MA1609, TAC-MA1709, NUDOCS 9806180239 | |
| Download: ML20249A788 (10) | |
Text
.
Mr. MIrtin L. Bowling, Jr.
June 16, 1998 Rtcovtry Officer - Technic:1 Ssrvices Northstst Nuciser Ensrgy'.;ompany c/o Ms. Patricia A. Loftus Director-Regulatory Affairs P. O. Box 128 Waterford, Connecticut 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - REVISION TO TECHNICAL SPECIFICATIONS BASES (TAC NOS. MA1608, MA1609, AND MA1709)
}
Dear Mr. Bowling:
By letters dated April 17, April 23, and May 1,1998, Northeast Nuclear Energy Company (NNECO) provided the NRC with changes to Technical Specification (TS) Bases Sections 3/4.6.4,3/4.3.3.5, and 3/4.5.4, respectively. NNECO provided the TS Bases pages to the NRC for information only.
)
]
As you are aware, the TS Bases are not part of tha TSs as defined by 10 CFR 50.36. Changes to the TS Bases may voluntarily be made in accordance with the provisions of 10 CFR 50.59.
Should the proposed change involve an unreviewed safety question pursuart to 10 CFR 50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e., constitute a TS change), then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for priv NRC review and approval.
)
The TS Bases you provided cre hereby returned to you and should be inserted in the TS to m
ensure that the NRC staff and NNECO have identical TS Bases pages. The staff did not perform an evaluation of your TS Bases revisions and staff concurrence with the revisions is not implied by this letter. The staff may review the evaluations that support these TS Bases revisions during the next inspection of Millstone Unit 3's implemanation of 10 CFR 50.59.
Sincerely, Original signed by:
James W. Anderser., Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 ll
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
18eshetTile)
GHill (2)
PUBLIC WBeckner, TSB SPO-L Readir0 LBerry SPO Reading JDurr, RI l
WTraveis DScrenci, Rl PMcKee JAndersen
~ ~
ACRS DOCUMENT NAME: G:MNDERSEN%1609.WPD T.
e.n,....,4.eini.~a..
. S c.i ia.i. c - copy -ienma.ti. cam,,A rtio.u,.
r - copy.. w.,i.cnm.nti ncio.u..
u - wecopy OFFICE SPO-L PM $
SPO-L:LA ( ),6 SP@ f.Db l
l l
3 NAME JAndersen LBerry V/ih Pf4:kee V
~~
nATF 06/,-198 06/tT98 l
068tl98 06/ i9G 06/ 98 9306180239 990616 PDR ADOCK 05000423 FFICIAL RLYCORD COPY
_ _ ?_**
h
puttu g-i UNITED STATES
- f j
NUCLEAR REGULATORY COMMISSION WALailNGToN, D.C. 20565-0001
[
June 16, 1998 Mr. Martin L Bowling, Jr.
Recovery Officer - Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director-Regulatory Affairs P. O. Box 128 Waterford, Connecticut 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - REVISION TO TECHNICAL SPECIFICATIONS BASES (TAC NOS. MA1608, MA1609, AND MA1709)
Dear Mr. Bowling:
By letters dated April 17, April 23, and May 1,1998, Northeast Nuclear Energy Company (NNECO) provided the NRC with changes to Technical Specification (TS) Bases Sections 3/4.6.4,3/4.3.3.5, and 3/4.5.4, respectively. NNECO provided the TS Bases pages to the NRC for information only.
As you are aware, the TS Bases are not part of the TSs as defined by 10 CFR 50.36. Changes to the TS Bases may voluntarily be made in accordance with the provisions of 10 CFR 50.59.
Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e., constitute a TS change), then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prioi NRC review and approval.
The TS Bases you provided are hereby returned to you and should be inserted in the TS to ensure that the NRC staff and NNECO have identical TS Bases pages. The staff did not perform an evaluation of your TS Bases revisions and staff concurrence with the revisions is not implied by this latter. The staff may raview the evaluations that support these TS Bases revisions during the next inspection of Millstone Unit 3's implementation of 10 CFR 50.59.
Sincerely, I
W. Andersen, Project Manager opecial Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/end. See next page
Millstone Nuclear Power St:tisr.
Unit 3 cc:
Lillian M. Cuoco, Esquire '
Joseph R. Egan, Esquire -
Senior Nuclear Counsel Egan & Associates, P.C.
Northeast Utilities Service Company 2300 N Street, NW P. O. Box 270 Washington, DC 20037 Hartford, CT 06141-0270 Mr. F. C. Rothen Mr. Kevin T. A. ' McCarthy, Director Vice President - Work Services Monitoring and Radiation Division Northeast Utilities Service Company Department of Environmental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Emest C. Hadley, Esquire Regional Administrator, Region i 1040 B Main Street U.S. Nuclear Regulatory Commission P.O. Box 549 475 Allendale Road West Wareham, MA 02576
' King of Prussia, PA 19406 Mr. John Buckingham First Selectmen Department of Public Utility Control Town of Wateiford Electric Unit.
Hall of Records -
10 Liberty Square 200 Boston Post Road New Britain, CT 06051 Waterford, CT 06385
- Mr. James S. Robinson, Manager Mr. Wayne D. Lanning NuclearInvestments and Administration Deputy Director of Inspectiorc New England Power Company Special Projects Office 25 Research Drive 475 Allendale Road Westborough, MA 01582 King of Prussia, PA-19406-1415 Mr. John Streeter Mr. M. H. Brothers Recovery Officer - Nuclear Oversight Vice President-Millstone Unit 3 Northeast Utilities Service Company Northeast h'uclear Energy Company P. O. Box 128 P.O. Box 128 Waterford, CT 06385 Waterfonj, CT 06385 Deborah Katz, President Mr. M. R. Scully, Executive Director Citizens Awareness Network Connecticut Municipal Electric P.O. Box 83 Energy Cooperative shelbume Falls, MA 03170
]
30 Stott Avenue Norwich, CT 06360 Mr. Allan Johanson,' Assistant Director Office of Policy and Management Mr. David Amerine Policy Development and Planning l
Vice President-Human Services Divisicn.
l Northeast Utilities service Company 450 Capitol Avenue - MS# 52ERN j
P. O. Box 128 P. O. Box 341441 L
Waterford, CT 06385 Hadford, CT 061341441 l
l
Millstone Nucle r Power Station Unit 'l cc:
The Hor. arable Terry Concannon Mr. William D. Meinert Nuclear Energy Advisory Council Nuclear Engineer Room 4035 Massachusetts Municipal Wholesale Legislative Office Building Electric Company Capitcl Avenue P.O. Box 426 Hartford, CT 06106 Ludlow, MA 01056 Mr. Evan W. Wcollacott Attomey Nicholas J. Scobbo, Jr.
Co-Chair Ferriter, Scobbo, Caruso, Rodophele, PC Nuclear Energy Advisory Council 1 Beacon Street,11th Floor 128 Terry's Plain Road Boston, MA 02108 Simsbury, CT 06070 Citizens Regulatory Commission Mr. John W. Beck, President ATTN: Ms. Susan Perry Luxton Little harbor Consultants, Inc.
180 Great Neck Road Millstone -ITPOP Project Office Waterford, CT 06385 P.C Box 0630 Niantic, CT 06357-0630 Mr. B. D. Kenyon (Acting)
Chief Nuclear Officer-Millstone Northeast Nuclear Energy Company i
P.O. Box 128 Waterford, CT 06365 Mr. Daniel L. Curry Project Director l
Parsons Power Group Inc.
l 2675 Morgantown Road j
Reading, PA 19607 i
Mr. Don Schopfer Verification Team Manager Sargent & Lundy 55 E. Monroe Street Chicago,IL 60603 4
4 t' G. D. Hicks Lirntor-Unit 3 Northeast i4ucient Energy Company P.O. Box 128 Waterford, CT 06385 Senior Resident inspector
- Millstone Nuclear Power Station clo U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 I
f L
BEVISED TECHNICAL SPECIFICATIONS BASES FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423
)
Replace the following pages of the Appendix A, Technical Specifications Bases, with the attached pages. The revised pages. The revised pages contain verticallines indicating the
]
areas of change.
1 Remove insert G 3/4 3-4 B 3/4 3-4 B 3/4 5-2a B 3/4 5-2a B 3/4 6-3a B 3/4 6-3a B 3/4 6-3b 8 3/4 6-3b h
i l
1
1 l
- INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The CTERABILIsY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distri'aution of the core. The OPERABILITY of this system is demonstrated by irrad'.ating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring Fo(Z) or F% a full incore flux map is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range channel is inoperable.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the responsa of those features important to safety. This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12 " Instrumentation for Earth-quakes," April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the Remote Shutdown Instrumentation ensures that suf-ficient capability is available to permit safe shutdown of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design i
Criterion 19 of 10 CFR Part 50.
I Calibration of the Intermediate Range Neutron Amps channel from Table 4.3-6 applies to the signal that originates from the output of the isolation amplifier within the intermediate range neutron flux processor drawers in the control room and terminates at the displays within the Auxiliary Shutdown Panel.
The OPERABILITY of the Remote Shutdown Instrumentation ensures that a fire will not preclude achieving safe shutdown. The remote shutdown monitoring MILLSTONE - UNIT 3 B3/43-4 N
Depa%CY CORE COOLING SYSTEMS BASES 3/4.5.4 REFUELING WATER STORAGE TANK' The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injec-tion by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and i
boron concentration ensure that:
(1) sufficient water is available within i
containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following a large break (LB) LOCA, assuming mixing of the RWST, RCS, ECCS water, and other sources of water that may eventually reside in the sump, with all control rods assumed to be out. These assumptions are consistent with the LOCA analyses.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical j
characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOLA. This pH band minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The maximum / minimum solution temperatures for the RWST in MODES 1, 2, 3 and 4 are based on analysis assumptions.
l l
l l
1 1
MILLSTONE - UNIT 3 8 3/4 5-2a kh h E ktter htM h 16, M i osu
CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL _(fontinued) 1.
Definitions and constants CFM - cubic feet per minute RPM - revolutions per minute Blower RPM - 3550
. Blower ft'/ revolution =.028 ft' Standard CFM = gas volume converted to conditions of 68'F and 14.7 psia.
2.
Neasure and record the following information:
Containment--Average of 3LMS*P934, 935, 936, and 937 (psia)
Pout--From 3HCS*PIIA or B (psia) l Tc--Containment temperature (*F)
Pin--Measure with a new inlet gauge or calculate from Equation 3a below j
(psia) scfm measured--See Procedure / Form 3613A.3-1 AP,--From Table 2 (psi)
A--As found Slip Constant Accuracy--Instrument accuracy range from Table 1.
3.
Calculate as found slip constant (A) a.
Pin - Containment - AP, I
b.
- Accuracy 3550 maarured 14_,J_
- Tc + 460 0.028
- 0.95 Pin 528 i
A-
'I Ema
- 14.7
- 14.7 % * ' M
- Tc + 460
\\
,l Pin Pin 528 i
i l
l I
l Revised by NRC letter dated June 16, 1998 I
NILLSTONE - UNIT 3 8 3/4 6-3a i
0500
CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL (Continued) 4.
Calculate expected postaccident flow rate using A calculated in Step 3.
a.
Slip RPM
= A * (4.937)%
- 1.218 b.
Actual Inlet CFM ACFM
.028 (3550 - Slip RPM) c.
Standard CFM scfm - ACFM 0.725 d.
Postaccident scfm Minimum - scfm
- 0.95 e.
Acceptance Flow Rate Postaccident scfm minimum 2 41.52 scfm.
Table 1 Accuracy Range (Ref. 2) scfm (measured)
Accuracy Ranae 30 to < 40 9.13 scfm 40 to < 50 6.98 scfm S
50 to < 60 5.81 scfm 60 to < 90 5.17 scfm Table 2 Inlet Piping Loss (Ref.1) scfm Measured AP, (psi)
(Unad.iusted) 30
.21 40 31 50
.52 60
.73 70
.98 80 1.28
References:
1.
Calculation. 20-RPS-722GM, " Flow Acceptance Criteria for 3HCS*RBNR 1A/B Blowers 3HCS* CIA /B."
2.
Calculation PA 90-L0E-0132GE, " Hydrogen Recombiner Flow Error Analysis."
The~ acceptance flow rate is the required flow rate at the worst case containment conditions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the LOCA.
The analysis assumes the l
recombiners are started no later than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident. The 18-month surveillai.ce shall verify the gar temperature and blower flow rate concurrently.
~
MILLSTONE - UNIT 3 8 3/4 6-3b 0581