ML20214V935
| ML20214V935 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/02/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20214V938 | List: |
| References | |
| TAC 61658, TAC 65274, DPR-65-A-117 NUDOCS 8706150013 | |
| Download: ML20214V935 (26) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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.a WASHINGTON, D. C. 206S5
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 l
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.117 License No. DPR-65 q
1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment by Northeast Nuclear Energy Company, i
A.
et al. the licensee), dated May 21, 1986, as supplemented by letter l
dated May 27, 1987, complies with the standards and requirements of t
the Atomic Energy Act of 1954, as amended (the Act), and the j
Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the I
l provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by 4
this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; j
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 3
of the Comission's regulations and all applicable requirements have been satisfied.
l i
i fS'N! U ja P
i
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.117, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
F THE NUCLEAR REGUL TORY COMMISSION
/-
r
F. Stolz, Director ject Directorate I-4 vision of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: June 2,1987 I
l e
t ATTACHMENT TO LICENSE AMENDMENT NO 117 FACILITY OPERATING LICENSE N0. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are provided to maintain document completeness.
t Remove Pages Insert Pages 11 11 1x ix xiv xiv i
1-8 1-8 3/4 9-7 3/4 9-7 3/4 9-21 3/4 9-21 3/4 9-22 3/4 9-22 3/4 9-23 3/4 9-23 4
3/4 9-24 3/4 9-24 3/4 9-25 3/4 9-26 3/4 9-27 i
B 3/4 9-2 B 3/4 9-2 8 3/4 9-3 8 3/4 9-3 B 3/4 9-4 8 3/4 9-4 5-5 5-5 l'
5-6 5-6 i.
I L
)
.. ~
INDEX l
DEFINITIONS SECTION PAGE i
1.0 DEFINITIONS Defined Terms.................................................
1-1 Thermal Power.................................................
1-1 Rated Thermal Power...........................................
1-1 Operational Mode..............................................
1-1 i.
l Action............
1-1 Ope ra bl e - Ope rab i l i ty........................................
1 -1 Reportable Event..............................................
1-1 Con ta i nme n t I n teg ri ty.........................................
1 - 2 Channel Calibration...........................................
1-2 i
Channel Check.................................................
1-2 s
Channel Functional Test.......................................
1-2 Core Alteration...............................................
1-3 Shutdown Margin...............................................
1-3 I de n ti fi e d Le a k a ge............................................
1 - 3 i
Unidentified Leakage..........................................
1-3 i
l Pressure Bounda ry Leakage.....................................
1-3 l
Con trol l ed Lea k a ge............................................
1-3 l
l Az i mu t h a l Powe r T i l t..........................................
1 - 4 Do s e Eq u i val e n t I-131.........................................
1 - 4 E-Ave ra ge Di s i n tegra ti on Ene rgy...............................
1-4 Staggered Test Basis..........................................
1-4 Frequency Notation............................................
1-4 Axial Shape Index.............................................
1-5 l
MILLSTONE - UNIT 2 Amendment No, p,M.JH,111
. -m.
m
-.-. m.
w
- 7 i
1 p
1 I
i l
INDEX i
DEFINITIONS j
i SECTION PAGE h
Unrodded Planar Radial Peaking Factor - F9....................
1-5 Enclosure Building Integrity...................................
1-5 i,
)
Reactor Tri p Sys tem Res ponse Time..............................
1-5 i
i l
Engineered Safety Feature Response Time........................ 1-5
)
j Physics Tests..................................................
1-6 1
j Unrodded Integrated Radial Peaking Factor - F.................
1-6 r
i
}
Source Check...................................................
1-6 Radiological Effluent Monitoring and Offsite' Dose Calcul ati on Manual (REM 0DCM).................................
1-6 l
t Radioacti ve Was te Trea tment Sys tems............................
1-6 l
l Purge - Purging................................................
1-6 l
{
Venting........................................................1-8 t
i j
Membe r ( s ) o f t he P ub l i c........................................
1 - 8 S i t e B o u n d a ry..................................................
1 - 8
)
Unrestricted Area..............................................
1-8
]
S t o ra g e P a t t e r n................................................
1 - 8 l
f i
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1 i,
i l
1 1
MILLSTONE - UNIT 2 Amendment No.19d,Ill,117
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 B O RO N CO N C E NT RAT I O N......................................
3 / 4 9 - 1 3/4.9.2 INSTRUMENTATION..........................................
3/4 9-2 3/4.9.3 DECAY TIME...............................................
3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS.................................
3/4 9-4 3/4.9.5 COMMUNICATIONS...........................................
3/4 9-5 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING.................
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING..........
3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION................. 3/4 9-8 3/4.9.9 CONTAINMENT RADIATION MONITORING.........................
3/4 9-9 3/4.9.10 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................
3/4 9-10 3/4.9.11 WATER LEVEL - REACTOR VESSEL.............................
3/4 9-11 3/4.9.12 STORAGE POOL WATER LEVEL.................................
3/4 9-12 3/4.9.13 STORAGE POOL RADI ATION M0NITORING........................ 3/4 9-13 3/4.9.14 STORAGE POOL AREA VENTILATION SYSTEM - FUEL MOVEMENT..... 3/4 9-14 3/4.9.15 STORAGE P0OL AREA VENTILATION SYSTEM - FUEL STORAGE...... 3/4 9-16 3/4.9.16 SH I E L DE D C ASK............................................ 3/4 9-19 3/4.9.17 HOVEMENT OF FUEL OVER REGION !! RACKS....................
3/4 9-21 3/4.9.18 SPENT FUEL P00L..........................................
3/4 9-22 3/4.9.19 S P E NT FU EL P00L.......................................... 3/ 4 9-26 3/4.9.20 S P ENT FU EL P00 L.......................................... 3/ 4 9-2 7 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN MARGIN..........................................
3/4 10-1 t
3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS........................
3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY....3/410-3 l
MILLSTONE UNIT 2 IX Amendment No, p),7pf,79) TTT
4 i
~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.10.4 PHY S I C S T E ST S............................................
3/4 10-4 l
3/4.10.5 CENTER CEA MISALIGNMENT..................................
3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................
3/4 11-3 3/4.11.3 TOTAL D0SE...............................................
3/4 11-6 1
MILLST0flE - Uti!T 2 X
Amendment No JM,109
INDEX BASES PAGE SECTION 3/4.7 PLANT SYSTEMS 3/4.7.1 TU RB IN E CYCL E......................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....... B 3/4 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM.......... B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM.................................. B 3/4 7-4 3/4.7.5 FLOOD LEVEL........................................... B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............. B 3/4 7-4 3/4.7.7 SEALED SOURCE CONTAMINATION........................... B 3/4 7-5 3/4.7.8 S N U B B E RS.............................................. B 3 / 4 7-5 3/4.7.9 FIRE SUPPRESSION SYSTEMS.............................. B 3/4 7-6 l
3/4.7.10 PENETRATION FIRE BARRIERS............................. B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS................................. S 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................... B 3/4 9-1 3/4.9.3 DECAY TIME............................................ B 3/4 9-1 l
3/4.9.4 CONTAINMENT PENETRATIONS..............................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................
B 3/4 9-1 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING.............. B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLING CIRCULATION.............. B 3/4 9-2 MILLSTONE-UNIT 2 XIII Amendment No. JJ,35,69.95,104
~
~-
INDEX BASES SECTION PAGE 3/4.9.9 AND 3/4.9.10 CONTAINMENT AND RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................
B 3/4 9-2 3/4.9.11 AND 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL WATER LEVEL................................. B 3/4 9-2 3/4.9.13 STORAGE POOL RADIATION M0NITORING........................ B 3/4 9-3 3/4.9.14 AND 3/4.9.15 STORAGE P0OL AREA VENTILATION SYSTEM........ B 3/4 9-3 3/4.9.16 S HI EL DED CAS K............................................ B 3/4 9-3 3/4.9.17 MOVEMENT OF FUEL OVER REGION II RACKS.................... B 3/4 9-3 3/4.9.18 SPENT FUEL P00L.......................................... B 3/4 9-3 3/4.9.19 SPENT FUEL P00L.......................................... B 3/4 9-4 l
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S HUT DOW N MARG I N.......................................... B 3/4 10- 1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS........................ B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY..............................................
B 3/4 10-1 l3/4.10.4 PHYS I CS TESTS............................................ B 3/4 10-1 3/4.10.5 CENTER CEA MISALIGNMENT.................................. B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................ B 3/4 11-2
'i 3/4.11.3 TOTAL D0SE............................................... B 3/4 11-4 4
MILLSTONE - UNIT 2 XIV Amendment No. pp,Jpp,Jpp,117 l
i
1 i
TABLE 1.1 OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER
- TEMPERATURE ff 1.
POWER OPERATION
> 0.99
> 5%
> 300*F 2.
STARTUP 3 0.99
< 5%
3 300*F 4
3.
HOT STANDBY
< 0.99 0
3 300'F 4.
HOT SHUTDOWN
< 0.99 0
300*F> T
> 200*F avg 1
5.
COLD SHUTDOWN
< 0. 98 0
c.
200 F i
6.
REFUELING **
< 0.95 0
140'F i
- Excluding decay heat.
i i
Fuel'in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
4 i
MILLSTONE - UNIT 2 1-7 Ameho' ment No. 61. 7 2 1
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DEFINITIONS O
VENTING 1.35 VENTING is the controlled process of discharging air or das from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition. in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does i
not imply a VENTING process.
MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC'shall incl'ude all persons who are not occupa-tionally associated with the plant. This category does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the 4
plant.
The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.
h 4
SITE BOUNDARY 1.37 The SITE BOUNDARY shall be that line beyond which the land is not-owned, leased or otherwise controlled by the licensee.
UNRESTRICTED AREA 4
1.38 An UNRESTRICTED AREA shall be any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection 1
of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, connercial institutional and/or recreational purposes.
4 STORAGE PATTERN i
i 1.39 The Region II spent fuel racks contain a cell blocking device in every-4th rack location for criticality control. This 4th location will be referred to as the blocked location. A STORAGE PATTERN refers to a blocked location l
and all adjacent and diagonal Region II cell locations surrounding the blocked l
location.
3 l
MILLSTONE - UNIT 2 1-8 Amendment No. /Y)Y,ll7
~
REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1800 pounds, with the exception of the consolidated fuel storage box, shall be prohibited from travel over irradiated fuel assemblies in the storage pool.
APPLICABILITY:
DURING ALL CRANE OPERATION.
ACTION:
With the requirements of the above specification not satisfied, place load in a safe condition.
SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and/or physical stops which prevent crane travel with loads in excess of 1800 pounds over irradiated fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to initiation of irradiated
. fuel handling operations and at least once per 7 days during irradiated fuel handling operations.
MILLSTONE - UNIT 2 3/4 9-7 Amendment No.117
REFUELING OPERATIONS
.l SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be in operation *,
APPLICABILITY: MODE 6 at all reactor water levels.
ACTION:
With less than one shutdown cooling loop in operation, suspend all operations j
involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetra-tions providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE **.
APPLICABILITY: MODE 6, whenever all the following conditions are not satisfied:
a.
reactor vessel water level at or above the vessel flange; and b.
the reactor vessel pit seal installed; and c.
the combined available volume of water in the refuel pool and refueling water storage tank exceeds 370,000 gallons; and d.
(1) one LPSI pump not in shutdown cooling service and aligned to take suction from'the RWST and deliver flow to the RCS is'0PERABLE,**; or (2) one HPSI pump -aligned to take suction from the RWST and deliver flow to the RCS 'is OPERABLE.**
ACTION:
With less than the required shutdown cooling loops OPERABLE, initiate correc-tive action to return the loop (s) to OPERABLE status within one hour.
The provisions of Specification 3.0.3 are not applicable.for 3.9.8.1 and 3.9.8.2.
- The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of j
the reactor pressure vessel hot legs.
- The normal or emergency power source may be inoperable for each shutdown cooling loop.
MILLSTONE-UNIT 2 3/4 9-8 Amendment No. H, 71 i
T REFUELING OPERATIONS MOVEMENT OF FUEL OVER REGION II RACKS LIMITING CONDITION FOR OPERATION 3.9.17 Prior to movement of a fuel assembly, or a consolidated fuel storage box, over a Region II rack in the spent fuel pool, the boron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of greater than or equal to 800 ppm.
APPLICABILITY: Whenever a fuel assembly, or a consolidated fuel storage box, is moved over the Region II racks in the spent fuel pool.
't ACTION:
With the boron concentration less than 800 ppm, suspend the movement of all fuel over Region II racks.
3 SURVEILLANCE REQUIREMENTS 4.9.17 Verify that the boron concentration is greater than or equal to 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to any movement of a fuel assembly, or a consolidated fuel storage box, over a Region II rack in the spent fuel pool and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.
4 t
MILLSTONE - UNIT 2 3/4 9-21 Amendment No. JSP,117
REFUELING OPERATIONS SPENT FUEL P0OL LIMITING CONDITION FOR OPERATION 3.9.18 The Reactivity Condition of the spent fuel pool shall be such that K
is less than or equal to 0.95 at all times.
eff APPLICABILITY: Whenever fuel is in the spent fuel pool.
ACTION:
Borate until Keff *.95 is reached.
SURVEILLANCE REQUIREMENTS 4.9.18.1 Ensure that all fuel assemblies to be placed in Region II (as I
shown in Figure 3.9-2) of the spent fuel pool are within the enrichment and burn-up limits of Figure 3.9.1 by checking the assembly's design and burn-up documentation.
4.9.18.2 Ensure that the contents of each consolidated fuel storage box to be placed in Region II (as shown in Figure 3.9-2) of the spent fuel pool are within the enrichment and burn-up' limits of Figure 3.9-3 by checking the design and burn-up documentation for storage box contents.
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MILLSTONE - UNIT 2 3/4 9-22 Amendment No. 199.117
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FUEL ASSEMBLY INITIAL ENRICHMENT, WT. % U-235 FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE A5 A FUNCTION OF INiilAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 i,
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FIGURE 3.9--3 WINIMUM REQURED FUEL ASSEMBLY EXPOSURE AS A FUNCTION 0F INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 AS 1
CONSOLIDATED FUEL i
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REFUELING OPERATIONS SPENT FUEL P0OL LIMITING CONDITION FOR OPERATION 3.9.19 Each STORAGE PATTERN of the Region II spent fuel pool racks shall 4
require either that:
(1) A cell blocking device is installed in those cell locations shown in. Figure.3.9-2; or (2)
If a cell blocking device has been removed, all cells of the STORAGE PATTERN must have consolidated fuel in them, including the formerly blocked location; or-(3) Meet both (a) and (b):
J
'(a)
If a cell blocking device has been removed, all cells of the STORAGE PATTERN must have consolidated fuel in-them 4
except the fomerly blocked location.
(b) The fomerly blocked location is vacant and a consolidated fuel box or cell blocking device is imediately being.
placed into the fomerly blocked cell.
APPLICABILITY: Fuel in the Spent Fuel Pool i
ACTION:
Take imediate action to comply with either 3.9.19(1),(2),or(3).
i SURVEILLANCE REQUIREMENTS 4.9.19 Verify that 3.9.19 is satisfied at the following times.
(1) Prior to removing a cell blocking device.
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(2) Prior to removing a consolidated fuel storage box from its Region II storage location.
MILLSTONE - UNIT 2 3/4 9-26 Amendment No.117 i
REFUELING OPERATIONS SPENT FUEL POOL LIMITING CONDITION FOR OPERATION 3.9.20 Prior to consolidation of spent fuel assemblies, the candidate fuel assemblief must have decayed for at least 5 years.
APPLICABILITY:
During all consolidation operations.
ACTION:
With the requirements of the above specification not satisfied, replace candidate assembly with an appropriate substitute or suspend all consolidation activities.
SURVEILLANCE REQUIREMENTS The decay time of all candidate fuel assemblies for consolidation shall be 4.9.20 determined to be greater than or equal to five years within 7 days prior to moving the fuel assembly into the consolidation work station.
- The storage of consolidated spent fuel is limited to five (5) consolidated spent fuel storage canisters (i.e.,10 spent fuel assemblies consolidated into 5 storage canisters / locations).
MILLSTONE - UNIT 2 3/4 9-27 Amendment No. 117
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTPATION The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the sourc.e range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the radio-active decay of the short lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
The requirement for two trains of spent fuel pool cooling to be OPEPABLE for 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> after subcriticality for the most recently discharged 1/3 core ensures that high water temperature will not degrade resin in the spent fuel pool demineralizers and that the temperature and humidity above the pool are compatible with personnel comfort and safety requirements. The shutdown cooling (SDC) system is a high capacity system. One train of the SDC is sufficient to cool both the core and the spent fuel pool should a failure occur in the spent fuel pool cooling system.
The requirement for the reactor to remain in MODE 5 or 6 until the most recent 1/3 core offload has decayed 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> ensures that alternate cooling is available during this time to cool the spent fuel pool should a failure occur in one train of the spent fuel pool cooling system.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly infomed of significant changes in the facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.
MILLSTONE - UNIT 2 B 3/4 9-1 Amendment No. 72, 114
i REFUELING OPERATIONS BASES 3/4.9.6 CRANE OPERABILITY - CONTAINt1ENT BUILDING The OPERABILITY requirements of the cranes used for movement of fuel assem-blies ensures that:
- 1) each crane has sufficient load capacity to lift a fuel element, and 2) the core internals and pressure vessel are protected from exces-sive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel hand-ling accident.
Specific analysis has been performed for the drop of a consoli-dated fuel storage box on an intact fuel assembly. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at leart one shutdown cooling loop be in operation ensures that (1) sufficient coofing capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
s The requirement to have two shutdown cooling loops OPERABLE when the refuel pool is unavailable as a heat sink ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel water level at or above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is readily available for core cooling. Adequate time is thus available to initiate emergency procedures to provide core cooling in the event of a failure of the operating shutdown cooling loop.
3/4.9.9 and 3/4.9.10 CONTAINMENT RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
MILLSTONE - UNIT 2 B 3/4 9-2 Amendment No. D,7J,117
REFUELING OPERATIONS BASES 3/4.9.13 STORAGE P0OL RADIATION MONITORING The OPERABILITY of the storage pool radiation monitors ensures that sufficient radiation monitoring capability is available to detect excessive radiation levels resulting from 1) the. inadvertent lowering of the storage pool water level or 2) the release of activity from an irradiated fuel assembly.
3/4.9.14 & 3/4 9.15 STORAGE P00L AREA VENTILATION SYSTEM The limitations on the storage pool area ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
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3/4.9.16 SHIELDED CASK The limitations of this specification ensure that in the event of a D
ce:;k tilt accident 1) the doses from ruptured fuel assemblies will be
]
within the assumptions of the safety analyses, and 2) K,ff will remain i.95.
3/4.9.17 MOVEMENT OF FUEL OVER REGION II RACKS The limitations of this specification ensure that, in the event of a fuel assembly or a consolidated fuel storage box drop accident into a l
Region II rack location completing a 4-our-of-4 fuel assembly geometry.
l K,ff will rema n 1 0.95.
3/4.9.18 SPENT FUEL POOL The limitations described by Figure 3.9-1 ensure that the reactivity of fuel assemblies and consolidated fuel storage boxes, introduced into I
the Region II spent fuel racks, are conservatively within the assumptions of the safety analysis.
MILLSTONE - UNIT 2 B 3/4 9-3 Amendment No, M. A0A/,117
REFUELING OPER ATIONS BASES I
3/4.9.19 SPDir FUEL POOL The limitations of this specification ensure that the reactivity conditions of the Region 11 storage racks and spent fuel pool Keff will remain less than or equal to 0.95 The Cell Blocking Devices in the 4th location of,the Region !! storage racks are designed to prevent inadvertent placement and/or storage of fuel assemblies '
in the blocked locations. The blocked location remains empty to provide the flux trap to maintain reactivity control for fuel assembly storage in any adjacent Only loaded consolidated fuel storage boxes may be placed and/or locations.
stored in the 4th location, completing the STORAGE PATTERN, after aJ adjacent, and diagonal, locations are occupied by loaded consolidated, fuel storage boxes.
3/4.9.20 SPBir FUEL POOL The limitations of these specifications ensure that the decay heat rates and radioactive inventory of the candidate fuel assemblies for consolidation are conservatively within the assumptions of the safety analysis.
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MILLSTONE - UNIT 2 B 3/4 9-4 linendment No,117 ea ee
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,060 + 700/-0 cubic feet.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shsll be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a) The new fuel (dry) storage racks are designed and shall be main-tained with sufficient center to center distance between assemblies to ensure aK
<.95.
The maximum fuel enrichment to be stored in these racks is 3.7beightpercentofU-235.
b) Region I of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a K*[(or<ed in this region may have a maximum fuel en
.95 with the storage pool filled with unborated water. Fuel assemblies ment of 4.5 weight percent of U-235. Consolidated fuel storage boxes may also be stored in this region, c) Region II of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations to ensure a K
_.95 with the storage pool filled with unborated water.
Fuelassembli8[f<toredinthisregionmustcomplywithFiaure3.9-1toensure s
that at least 85% of the design burn-up has been sustained. The contents of consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3.
d) Region II of the spent fuel storage pool is designed to pemit storage of consolidated fuel in the 4th location of the storage rack and ensure a K
< 0.95.
Placement of consolidated fuel in the 4th location isonlypekttedifallsurroundingcellsoftheSTORAGEPATTERNare occupied by consolidated fuel.
ORAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of. the pool below elevation 22'6".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 384 storage locations in Region I and 962 storage locations in Region II for a total of.1346' storage locations.,
- This translates into 1277 storage locations to receive spent fuel and 69 storage locations to remain blocked.
MILLSTONE - UNIT 2 5-5 Amendment No. 30.58.709.117
t DESIGN FEATURES 5.7 SEISMIC CLASSIFICATION Those structures, systems and components identified as Category I Items in Section 5.1.1 of the FSAR shall be designed and maintained to the 5.7.1 original design provisions contained in Section 5.8 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.8 METEOROLOGICAL TOWER LOCATION _
The meteorological tower location shall be as shown on Figure 5.8.1 5.1-1.
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5.9 SHORELINE PROTECTION The provisions for shoreline protection described in Amendments 34, 5.9.1 15, 1976.
35 and 36 to the FSAR shall be completed by June i
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i MILLSTONE - UNIT 2 5-6 Amendment No. 9,799,j37 t
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