ML20217G719
| ML20217G719 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G722 | List: |
| References | |
| NUDOCS 9710140170 | |
| Download: ML20217G719 (15) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION s*
g WASHINGTON. o.o. 8044 Hoot NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY AND WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 l
MILLSTONE NUCLEAR POWER STATION. UNIT 2 l
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 208 License No OPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Northeast Nuclear Energy Com)any, et al. (the licensees dated April 10, 1997, complies wit 1 the standards and requiren)ents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i)d without endangering the health that the activities authorized by this amendment can be conducte and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, oko1$$Mk$iOo$$36 p
Accordingly, Facility Operating License No. DPR-65 is amended by changes i.
to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2 No. DPR-65 is hereby amended to read as)follows:of Facility Operating License (2)
Technical Soecifications The Technical Specifications contained in Ap)endix A, as revised through Amendment No. 208, are here)y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance to be l
l implemented within 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/k9 FM k Phillip F+ McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to Technical Specifications Date of Isauance:
Septaber 30, 1997
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ATTACHMENT TO LICENSE AMENDMENT 1i0.206 rACILITY OPERATING LICENSE NO. 028-11 OutKET NO. 50-336 r
Replace the following sages of the Operating License and Appendix A Technical Specifications, with tie attached pages.
The revised pages are identified b amendment number and contain vertical lines indicating the areas of change. y Remove 10 hit 11 11 VII-Vil 1-5 1-5 3/4 6-25 3/4 6 25 3/4 6-26 3/4 6-26 3/4 6-27 3/4 6 27 3/4 6-03 3/4 6 28 3/4 9-16 3/4 9 16 3/4-9-17 3/4 9 17 3/4 9-18 3/4 9 18 B 3/4 6-5 B 3/4 6-5 B 3/4 9-3 8 3/4 9-3
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DEFINITIONS SECTION PAGI l
Reactor Trip System Response Time................
15 Engineered Safety Feature.'tesponse Time.............
15 Physics Tests..........................
16 Unrodded Integrated Radial Peaking Factor - F, 16 Source Check 16 Radiological Effluent Monitoring and Offsite Dose CalculationManual(REMODCN) 1-6 Radioactive Waste Treatment Systems...............
16 l
Purge Purging.........................
1-6 Venting.............................
18 Member ( s) o f the Publ i c................ '.....
1-8 Site Boundary..........................
18 Unrestricted Area........................
1-8 Storage Pattern.........................
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NILLSTONE - UNIT 2 Amendment No. 7 #, JJJ. 117.
J#, J#. 208
1 11E1D LINITING COM ITION FOR OPERATION AND SURVEILLANCE REQUIRENENTS SECTION E&fd.
3/4.6 CONTAINMENT SYSTJ,81 3/4.6.1 PRIMARY CONTAINMENT.................
3/4 6 1 Containment Integrity................
3/4 6 1 l
Containment Leakage.................
3/4 6 2 Containment Air Locks 3/4 6 6 Internal Pressure 3/4 6 8 Air Temperature...................
3/4 6 9 Containment. Structural Integrity 3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4 6 12 Containment Spray Sys' tem 3/4 6-12 Containment Air Recirculation System 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6 15 Containment Ventilation System 3/4 6 19 I
3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4 6 20 Hydrogen Monitors 3/4 6 20 Electric Hydrogen Recombiners - M..........
3/4 6-21 Hydrogen Purge System................
3/4 6 23 Post Incident Recirculation Systems 3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT................
3/4 6-25 Enclosure Building Filtration System 3/4 6 25 Enclosure Building 3/4 6 28 l
t NILLSTONE - UNIT 2 VII Amendment No. 1974 177 208 one
e DEf'INITIONS AXIAL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX the power level detected by(Yr) used for normal control and indication is thelowerexcorenuclearinstrumentdetectors(L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power levels.
The AXIAL SHAPE INDEX (Y) used for the tri) and pretrip signals in the reactor protection system is the, above i
value (Y ) modif< ed by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel.
4 Ya = fy Y, = A Y, + B CORE OPERATING LIMITS REPORT 1.24 The CORE OPERATING LIM 1TS REPORT is the unit specific document that provides the core operating limits for the current operating reload cycle.
1hese cycle specific core operating limits shall be determined for each reload cycle in accordance with specification 6.g.l 7. Plant operation within these operating limits is addressed in individual specifications.
f3 CLOSURE BUILDING INTEGRITY DELETED REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its tri) setpoint at the channel sensor until electrical power is interrupted to tie CEA drive mechanism.
ENGINEERING SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation,setpoint at the channel sensor until the ESF equipment is capable of MILLSTONE + UNIT 2 1-5 Amendment No. 77. J77 177. 208 cm
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CONTAlhMDif $YSTEMS 3/4. 8.) SEC0lWARY CONTAIMENT IELq$URE_ BUILDING FILTRATION SYSTEN LIMITING CONDITION FOR OPERATION 3.6.5.1 Two se>arate and independent Enclosure Building Filtration Trains l shall be OPERABL:.
APPLICABILITY: MODES 1, 2, 3 and 4.
AGIlON:
With one Enclosure Building Filtration Train inoperable, restore the inoperable train to OPERAB.E steus within 7 days or be in COLD SHU100WN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIRENENTS 4.6.5.1 Each Enclosure Building filtration Train shall be. demonstrated l
OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiat-ing, from the control room, flow through the HEPA filter and charcoal absorber train and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal absorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the train by:
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MILLSTONE - UNIT 2 3/46-25 Amendment No. 208 0702 w..
CONTAIMENT SYSTEMS SURVEILLANCEREQUIREMENTS(Continued) 1.
VerifyinJ that the cleanup train satisfies the in place testing l acceptance criteria and uses the test procedures of Regulatory Positions C.S.a.
C.5.c and C.5.d of Regulatory Guide Revision 2, March 1978, and the train flow rate is 9000 cfm 1.52 I
i 10%.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 ' Revision 2, March 1978, meets the laboratory test m criteria of Regulatory Position C.6.a of Regulato'ry Guide 1.52, Revision 2 March 1978.*
3.
l Verifying a train flow rate of 9000 cfm i 10% during train l
operation when tested in accordance with ANSI N510 1975, After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying c.
within 31 days after removal that a laboratory analysis of a representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide'l.52 Revision 2. March 1978.*
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is s 6 inches Water Gauge while operating the train at a flow rate of 9000 cfm i 10%.
l 2.
Verifying that the train starts on an Enclosure Building Filtra-l tion Actuation Signal (EBFAS).
After each complete or partial replacement of a HEPA filter bank by I
e.
verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI H510-1975 while operating the train at a flow rate of 9000 cfm l
t 10%.
ASTM D3803-89 shall be used in place of ANSI N509-1976 as referenced in table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should be conducted at a temperature of 30'C and a relative humidity,of 95% within the tolerances specified by ASTM D3803 89.
Additionally, the charcoal sample shall have a removal efficiency of 2 95%.
MILLSTONE - UNIT 2 3/4 6-26 Amendment No. 27, 77, 177, 208 0292
CONTAlletDif SYSTEMS SURVEILLANCEREQUIREMENTS(Continued) f.
After each complete or partial replacement of a charcoal absorber bank by verifying that the charcoal absorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510 1975 while operating the train at a flow rate of 9000 cfm i 10%.
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NILLSTONE - UNIT 2 3/4 6 27 Amendment No. 208 cm
coiffAllmDff SYSTEMS ElEl0EEE_ElllDllR l
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i LINITING Cole! TION FOR OPERATION 3.6.5.2 The Enclosure Building shall be OPERABLE.
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l APPLICABILITY: MODES 1, 2, 3 and 4.
&GilQtit With the Enclosure Building inoperable restore th) Enclosure Building to OPERABLEstatuswithin24hoursorbeInCOLDSHUTMWNwithinthenext36 hours.
A SURVEILLANCE REQUIREMENTS 4.6.5.2.1 OPERABILITY of the Enclosure Building shall be demonstrated at least once per 31 days by verifying that each access opening is closed except when the access opening is being used for normal transit entry and exit.
4.6.5.2.2.
At least once per 18 months verify each Enclosure Building Filtration Train produces a negative pressure of greater than or equal to 0.25 inches W.G. in the Inclosure Building Filtration Region within 1 minute after an Enclosure Butiding Filtration Actuation Signal, i
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NILLSTONE - UNIT 2 3/4 6 28 Amendment No. 208 om
'l REFUELING QPERATIONS STORARE POOL AREA VENTILATION SYSTEN - FUEL * $&g[
LIN! TING CONDIT10ll FOR OPERATION 3.9.15 At least one Enclosure Building Filtration Train shall be OPERABLE and capable of automatically initiating operation in the auxil.
l inry exhaust mode and exhausting through HEPA filters and charcoal adsorbers on a storage pool area high radiation signal.
APPLICABILITY: WHENEVER IRRADIATED FUEL IS IN THE STORAGE POOL.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one Enclosure Building Filtration Train is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.9.15 The above required Enclosure Building Filtration Train shall l
be demonstrated OPFRABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.
from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the train operates for at least l
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on, b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the train by:
l NILLSTONE - UNIT 2 3/49-16 Amendment No. 77, 208 0293
I EEMELING OPERATIONS SURVE!LLANCE REQUIREMENTS (Continued) 1.
Verifying that the cleanup train satisfies the in place testing l
acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.5.c and C.5.d of Regulatory Guide 1.52 Revi-sion 2, March 1978, and the train flow rate is 9000 cfm i 10%.
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2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory i
Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*
3.
h.fifying a train flow rate of 9000 cfm i 10% during train operation l when 'ested in accordance with ANSI H510 1975.
c.
Aft n ever/ 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying i
within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52, Revision 2, March 1978.*
d.
At least once per 18 months by:
1.
Verifying that the pressure drop acroe.s the combined HEPA filters and charcoal adsorber banks is s 6 inches Water Gauge while operating the train at a flaw rat,e of 9000 cfm i 10%.
l 2.
Verifying that on a Spent Fuel Storage Pool Area high radiation signal, the train automatically starts (unless already operating) and directs its exhaust flew through the HEPA filters and charcoal l
adsorber banks, After each complete or partial replacement of a HEPA filter bank by e.
verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 thile operating the train at a flow rate of 9000 cfm i 10%.
l ASTM D3803-89 shall be used in place of ANSI H509-1976 as referenced in table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should be conducted at a temperature of 30'C and a relative humidity of 95%
within the tolerances specified b ASTM D3803 89.
Additionally, the charcoal sample shall h' ave a removaf efficiency of 195%.
MILLSTONE - UNIT 2 3/49-17 Amendment No. 77, 177, 208 0293
e.
KEFUELING OPERATIONS SURVEILLAN0EREQUIRENENTS(Continued) f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510 1975 while operating the train at a flow rate of 9000 cfm i 10%.
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NILLSTF"' - UNIT 2 3/4 9-18 Amendment No. 203 0293
e.
CONTAINMENT. SYSTEMS matre 3/4.6.5 SECONDARY CONTAINMENT 2/4.6.5.1 ENCLOSURE BUILDING FILTRATION SYSTEM
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l The OPERABILITY of the Enclosure Building Filtration System ensures that containment leakage occurring during LOCA conditions int 6 the annulus l
will be filtered through the HEPA filters and charcoal adsorber trains prior l
to discharge to the atmosphere.
This requirement is necessary to meet the assumptions used in the accident analyses and limit the sito boundary radia-tion doses to within the limits of 10 CFR 100 during LOCA conditions.
The laboratory testing requirement for the charcoal sample to have a removal efficiency of 4 95% is more conservative than the elemental.and organic iodine removal efficiencies of 90% and 70%, respectively, assumed in the DBA analyses for the EBFS charcoal adsorbers in the Millstone Unit 2 Final Safety Analysis Report. A removal efficiency acceptance criteria of 195%
will ensure the charcoal has the capability to perform its intended safety function throughout the length of an operating cycle.
3/4.6.5.2 ENCLOSURE BUILDING l
The OPERABILITY of the Enclosure Butiding ensures that the releases of
-l radioactive materials from the arimary containment atmosphere will be restricted to those leakage patis and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with operation of the Enclosure Building Filtration System, will limit the site boundary radiation l
doses to within the limits Of 10 CFR 100 during accident conditions One Enclosure Building Filtration System train is required to establish a negative pressure of 0.25 inches W.G. in the Enclosure Building Filtration Region within one minute after an Enclosure Building Filtration Actuation Signal is generated.
The one minute time requirement does not include the time necessary for the associated emergency diesel generator to start and power Enclosure Building Filtration System equipment.
To enable the Enclosure Building Filtration System to establish the required negative pressure in the Enclosure Building, it is necessary to ensure that all Enclosure Building access openings are closed.
For double door access openings,.only one door is required to be closed and latched, except for normal passage.
For single door access openings, that door is required to be closed and latched, except for normal passage.
A door is OPERABLE when it is capable of automatically closing and latching.
If the required door is not capable of automatically closing and latching, the door must be maintained closed and latched or personnel may be stationed at the door to ensure that the door is closed and latched after each transit through the door. Otherwiss, the access opening (door) should be declared inoperable and the appropriate technical specification action statement entered.
MILLSTONE - UNIT 2 B 3/4 6-5 Amendment No. 208 0294
i REFUELINS OPERATIR5 aAsEs I
i 3/4,t.13 STORACE POOL RADIATION MONITORig i
1 The OPERABILITY of the storage pool radiation monitors ensures that i
sufficient radiation monitoring ca radiation levels resultini from 1)pability is available to detect excessive the inadvertent lowering of the storage pool water level or 2) tae release of activity from an irradiated fuel assembly.
3/4.9.14 1 3/4.9.15 STOPM E P0OL AREA VENTILATION SYSTEM i
The limitations on the storage pool area ventilation system ensures that i
all radioactive material released from an irradiated fuel assembly will be i
filtered through the HEPA filters ar.d charcoal adsorber prior to discharge to i
the atmosphere.
The OPERA 8ILITY of this system and the resulting iodine j
removal. capacity are consistent with the assumptions of the accident analyses.
The laboratory testing requirement for the charcoal sample to have a
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removal efficiency of 195% is more conservative than the elemental and organic iodine removal efficiencies of 90% and 70%, respectively, assumed in the DBA analyses for the EBFS charcoal adsorbers in the Millstone Unit 2 Final Safety Analysis Report. A removal efficiency acceptan:e criteria of 195%
will ensure the charcoal has the capability to perform its intended safety i
function throughout the length of an operating cycle.
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3/4.9.16 SHIELDED CASK j
The limitations of this specification ensure that in an event of a cask i
tilt accident 1) the doses from ruptured fuel assemblies will be within the assumptions of the safety analyses, 2) K, will remain s.95.
3/4.9.17 MOVEMENT OF FUEL IN SPENT FUEL P0OL i
The limitations of this specification ensure that, in the event of a fuel i
assembly or a consolidated fuel storage box drop accident into a-Region 8 or C rack location completing a 4 out of-4 fuel assembly geometry, K, will remain j
s 0.95.
j 3/4.9.18 SPENT FUEL P0OL - REACTIVITY CONDITION l
The limitations described by Figures 3.9 la, 3.9 lb, and 3.9 3 ensure that, the reactivity of fuel assemblies and consolidated fuel storage boxes, introduced into the Region C spent fuel racks, are conservatively within the j
assumptions of the safety analysis.
The limitations described by Figure 3.9 4 ensure that the reactivity of
.the fuel assemblies, introducted into the Region A spent fuel racks, are conservatively within the assumptions of the safety analysis, i
MILL 5 TONE - L8IIT 2 B3/493 Amendment No. 77. JP7, 117, om 191, ill iib ;208
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