ML20005D839
| ML20005D839 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/14/1989 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005D837 | List: |
| References | |
| NUDOCS 9001020051 | |
| Download: ML20005D839 (25) | |
Text
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'o,'n UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION i
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PUBLIC SERVICE COMPANY.0F COLORADO DOCKET WO. 50 267 FORT.ST..VRAIN.WUCLEAR GENERATlWG STATION AMENDRENT.TO. FACILITY.0PERATlWG LICENSE Amendment No. 75 License No. DPR-34 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Company of Colorado (the licensee) dated September 14, 1989 as revised December 4, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will net be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in ac:ordance with 10 CFR Part 51 of the Comission's regulations and all epplicable requiremcuts have been satisfied.
9001020051 891214 PDR ADOCK 05000267 P
PNV 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.D.(2) of Facility Operating License No. DPR-34'is hereby anended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment !!o.75, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Attachme nt:
Changes to the Technical l
Specifications Date of Issuance:
December 14, 1989 l
l l
l
v.
ATTACHMENT TO. LICENSE ANENDMENT NO. 75 TO. FACILITY OPERATING LICEliSE NO. DPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 1
2-9 2-9 1
4.5-3 4.5-3 4.7-1 4.7-1 l
l 4.7-2 4.7-2 l
4.7-3 4.7-3 l
4.7-4 4.7-4 4.7-5 4.7-5 l
j 4.7-6 4.7-7 4.7-8 l.
l 4.7-9 l
4.7-10 4.7-11 I
i 5.7-1 5.7-1 5.7-2 5.7-2 j.
5.7-3 5.7-4 5.7-5 l
5.7-6 l
5.7-7 l
5.7-8 5.7-9 l
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Fort St. Vrain #1 Technical Specifications Amendment No. 75 Page 2-9 2.23 CALCULATED BULK CORE TEMPERATURE The CALCULATED BULK CORE TEMPERATURE shall be the calculated average temperature of the core, including graphite and fuel, but not the reflector, assuming a loss of all forced circulation of primary coolant flew, 2.24 CORE AVERAGE INLET TEMPERATURE The CORE AVERAGE INLET TEMPERATURE shall be the arithmetic average of the operating circulator inlet temperatures, adjusted for circulator power input, steam generator regenerative heat loads, and PCRV liner cooling system heat losses.
l 2.26 CORE ALTERATION (S) l CORE ALTERATION (S) shall be the movement or manipulation I
of any component within the PCRV that alters the core l
reactivity (except for insertion of control rod pairs or I
reserve shutdown material) or activities that could result I
in damage to the core components, while fuel is in the l
reactor vessel. Suspension of CORE ALTERATION (S) shall I
not preclude completion of movement of a component to a I
safe conservative position or condition.
l 2.30 SHUTDOWN MARGIN
[
SHUTDOWN MARGIN shall be the instantaneous amount of I
reactivity by which the reactor is subcritical or would be j
suberitical from its present condition assuming that all l
OPERABLE control rod pairs are fully inserted except for l
the single control rod pair of highest reactivity worth I
capable of being withdrawn, which is assumed to be fully l
withdrawn.
(
Amendment No. 75
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C' Fori' t. Vrain #1 t._
Technical Specifications Amendment No. 75
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Page 4.5-3 Specification LCO 4.5.2 - Reactor Vessel Internal Maintenance.
Limiting Conditions for Operation l
I (These requirements have been deleted.
Refer to LCO 4.7.1 for Reactor Vessel Internal Maintenance Limiting Conditions for l
Operation.)
t Amendment No. 75
4 Fort St. Vrain #1-
2 Jechnical SpGeifications
/ J
' Amendment No. 75 Page 4.7-1 1
i LIMITING CONDITIONS FOR 4.7 FUEL HANDLING AND STORAGE SYSTEMS 5)ERATION-I Objectives j
To prevent an uncontrolled release of radioactivity during irradiated fuel handling and storage by defining the minimum operable equipment and characteristics.
I SPECIFICATION LCO 4.7.1 FUEL HANDLING AND HAINTENANCE IN THE REACTOR l LIMITING CONDITION FOR OPERATION y
l The following reactor conditions shall be maintained:
l a.
The PCRV shall be depressurized to atmospheric pressure l
(< 1 psig) or slightly below, I b.
The CORE AVERAGE INLET TEMPERATURE shall be 165 degrees F or l
1ess*, and l c.
The SHUTDOWN MARGIN requirements of LCO 3.1.4 shall be met.
l APPLICABILITY:
Whenever both primary and secondary PCRV closures I
of any PCRV penetration (s) are removed.
I l*
Applicable only when the fuel handling machine or auxiliary l
transfer cask is mounted on the reactor vessel, with the cask l
isolation valve and reactor isolation valve open.
Amendment No. 75
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Technical Specifications Amendment No. 75 Page 4.7-2 l SPECIFICATION LCO 4.7.I (Continued)_
l ACTION:
l a.
With the conditions of a or b above not met, restore the l
condition (s) to within the above limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or l
terminate fuel handling and reactor vessel internal l
maintenance, retract the fuel handling mechanism or any l
other remotely operated mechanisms from the PCRV, and close j
the reactor isolation valve or opening through the PCRV as l
soon as practicable.
Before the CORE AVERAGE INLET j
TEMPERATURE reaches 400 degrees F, a control rod drive and I
orifice assembly shall be reinstalled wherever both primary l
and secondary PCRV closures are removed.
l b.
With the SHUTDOWN PARGIN requirements of LCO 3.1.4 not met, I
comply with the ACTION items of LCO 3,1.4.
l ASSOCIATED SURVEILLANCE REQUIREMENT:SR 5.7.3 l BASIS FOR SPECIFICATION LCO 4.7.1 l To prevent the outleakage of primary coolant and potential release of i
I activity during fuel handling or maintenance in the reactor vessel, l the reactor must be depressurized and maintained within the required l conditions. The CORE AVERAGE INLET TEMPERATURE is limited to 165 l degrees F to prevent short-term pressurization of the fuel handling I equipment over 5 psig (the maximum allowable working pressure of the l fuel handling equipment) as a result of accidental inleakage of water l into the vessel during fuel handling.
l The ACTION statements ensure that the reactor and Fuel Handling l Machine will be placed in the safest configuration as soon as l practicable, if a required condition cannot be maintained. The l requirement to reinstall the control rod drive and orifice assembly l before the CORE AVERAGE INLET TEMPERATURE reaches 400 degrees F is l designed to avoid damage to the reactor isolation valve seal l material.
Amendment No. 75
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Yechnical Specifications Amendment No. 75 Page 4.7-3 l SPECIFICATION LCO 4.7.2 FUEL HANDLING MACHINE 1 LIMITING CONDITION FOR OPERATION l The Fuel Handling Machine (FHM) shall be OPERABLE with:
I a.
A helium atmosphere
- in the FHM at atmospheric pressure-(< 1 l
psig) or slightly below, l b.
The fuel handling purge system connected and OPERABLE, with a i
supply of helium
- available, and the gas waste system available l
to receive purge gas, l c.
One cooling water coil operating with the outlet coolant water j
temperature 150 degrees F or less, and l
1.
An additional cooling water coil OPERABLE, or i
2.
The backup fire water connections and hose OPERABLE, i'
l d.
The reactor building overhead crane attached, unless the FHM is l
bolted to a reactor isolation valve over the reactor, a fuel i
storage well, the original fuel shipping cask loading port, or l
) e.
it e a
aa ih rf rr t or ntation and 1
placement of fuel
- elements, reflector elements, or defueling l
l elements OPERABLE.
i i
l APPLICABILITY:
During use of the FHM for reactor internal I
maintenance or any handling of IRRADIATED FUEL *.
I l*
A helium atmosphere is not required in the FHM when it is empty l
or when handling nonirradiated fuel or handling IRRADIATED FUEL
]
that has undergone fission product decay for 100 days or more, or l
when the FHM is not being used in fuel handling operations with l
the reactor core or fuel storage wells.
Amendment No. 75
, Fort St. Vrain #1 E
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Technical Specifications Amendment No. 75 Page 4.7-4 l SPECIFICATION LCO 4.7.2 (Continued) l ACTION:
l a.
With requirements a.,
or b.,
or d. above not satisfied.
I within I hot.r initiate action to retract the fuel transfer I
mechanism and close the reactor isolation valve and FHM cask i
valve.
l b.
With requirement a.
above not satisfied when the FHM cask l
valve is closed, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to reduce gas l
inflow to the 'FHM and/or increase gas outflow to the gas l
waste system, as appropriate.
I c.
With requirement c.
above not satisfied, within I hour l
initiate action to return the IRRADIATED FUEL elements l
within the FHM to the reactor core, to the fuel storage I
wells, or the fuel shipping casks, and terminate fuel l
handling with the FHM.
l d.
With requirement e above not satisfied, terminate placement l
of the fuel elements, reflector elements, or defueling l
elements within the reactor vessel with the FHM.
l ASSOCIATED SURVEILLANCE RE0VIREMENT:
SR 5.7.1 l BASIS FOR SPECIFICATION LCO 4.7.2 l The objective of this specification is to ensure the prevention of l any uncontrolled release of radioactivity during handling of I IRRADIATED FUEL or reactor internal maintenance, and to ensure the l correct installation of fuel elements into the fuel storage wells and l installation of fuel elements, reflector elements, or defueling i elements into the reactor core.
Defueling elements are described in l the Fort St.
Vrain Defueling Safety Analysis Report, GA-C19694, l submitted to the NRC, August 16, 1989 (P-89287).
l The OPERABILITY requirements for the FHM ensure that:
l a.
Failure of a primary seal at any boundary would result in I
negligible outleakage or no more than slow inleakage of air, l
since the machine is maintained at approximately atmospheric l
pressure (< 1 psig) or slightly below, Amendment No. 75
-e Fort St. Vrain #1 h
hiechnicalSpecifications Amendment No. 75 Page 4.7-5 l BASIS FOR SPECIFICATION LCO 4.7.2 (Continued) l b._ The FHM is connected to the gas waste system, and can be vented l
while in transit and/or when the cask valve is shut, giving l
assurance that no pressure buildup in or escape of fission l
products from the machine should occur, l c.
Fuel elements contained in the FHM will be maintained at surface l
tempera tures below 750 degrees F to prevent significant graphite 1
l oxidatten in the event there is any inleekage of air. An outlet l
cooling '. ster temperature of less than or equal to 150 degrees F l
from one of the two redundant cooling systems provides adequate l
cooling to maintain the fuel elements below 750 degrees F (FSAR l
Sections 9.1.1 and 14.6.3.1).
Silencing of the low-flow alarm by l
increasing the flow of cooling water ensures existence of cooling l
water flow, while the 150 degrees F limit ensures adequacy of l
flow, and I d.
A seismic event will not adversely affect t=
FHM when it is I
bolted to a reactor isolation valv's over the reactor, a fuel l
storage well, the original fuel shipping cask loading port, l
bolted to another seismically qualified location, or supported by I
the reactor building overhead crane.
l The ACTION statements ensure that the FHM will be promptly placed in l a safe configuration in the event any of the OPERABILITY requirements l can no longer be met.
For example, if a switch or alarm necessary to l verify correct seating of fuel elements or other elements becomes l inoperable, the ACTION statement prohibits continuing seating of the l elements in the core. However, it does not prohibit unloading the l FHM into a fuel storage well where exact orientation is not a safety l concern. This would permit the FHM to be unloaded for easier repair l and minimizes radiation exposure to maintenance personnel.
Amendment No. 75
J Fort St. Vrain e2 Technical $pecifications Amendment No. 75 Page 4.7 6 l SPECIFICATION LCO 4.7.3 FUEL STORAGE WELLS l LIMITING CONDITION FOR OPERATION l
I Each fuel storage well containing IRRADIATED FUEL shall have:
l a.
A helium atmosphere maintained at approximately atmospheric l
pressure (< 1 psig) or slightly below, and l b.
Both cooling water coils OPERABLE with at least one coil in l
operation, and the outlet cooling water temperature of each coil l
operating shall be 150 degrees F or less, or I c.
One cooling water coil operating with the outlet cooling water I
temperature ISO degrees F or less, and the fuel storage well l
l emergency booster fan OPERABLE and capable of moving a minimum I
total air flow of 9000 cfm through the fuel storage vaults.
l d.
No IRRADIATED FUEL located in the central column of a fuel i
i storage well.
l APPLICABILITY:
When IRRADIATED FUEL is stored in the fuel storage l
well.
l ACTION: With less than the above required conditions satisfied, I
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to re-establish the l
required conditions within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or perform one of the l
following within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
l a.
Transfer IRRADIATED FUEL to a storage well or wells for l
which the required conditions are met, or j
l b.
tstablish backup cooling to the affected fuel storage wells, l
l or I
c.
Perform an engineering evaluation to confirm that the l
hottest fuel ele. ment surface temperature will not exceed 750 l
degrees F.
l ASSOCIATED SURVEILLANCE REQUIREMENT:
SR 5.7.2 Amendment No. 75 I
Fort $t. Vrain 41 Technical Specifications i
Amendment No. 75 Page 4.7-7 l
l BASIS FOR $PECIFICATION LCO 4.7.3 i
l l The storage well cooling water system is designed with two 100'4 l capability cooling coils supplied from independent water sources l (FSAR Section 9.1.2).
l The accident conditions described in the FSAR postulate the total i
i loss of cooling water to one of the nine fuel storage wells.
If this I were to occur, adequate cooling could be achieved by an increase in
( the normal ventilation air flow to cool the well b/ convection on the l external surface.
The increase in air flow is supplied by the fuel I storage well emergency booster fan. This specification is based on j the analysis in FSAR Section 14.6.3.2 which uses the conservative I assumption that a total flow of 9000 cfm would be drawn (equally l divided) through all three vault compartments of the fuel storage l wells, thus adequately protecting the affected storage well and fuel l within it from damaging temperatures.
(There are three fuel storage l wells in each ci the '5ree fuel storage vaults).
l IRRADIATED FUEL elements are not stored in the central column of a l fuel storage well because they cannot be adequately cooled in that l location (FSAR Section 9.1.2.2.2).
l To prevent significant oxidation of the IRRADIATED FUEL, the fuel l storage wells are designed to maintain the IRRADIATED FUEL cool and l under a nominally dry atmosphere of helium. An outlet temperature of i 150 degrees or less from a single cooling coil ensures the hottest l IRRADIATED FUEL element surface temperatures will be maintained below I 750 degrees F, preventing any significant graphite oxidation in the l event of air inleakage into the storage well.
The helium storage l system provides purified helium for this service, giving sufficient l protection against a meist atmosphere.
l The ACTION statements provide for corrective actions within an l adequate titre to prevent the hottest stored fuel element surface I temperature from reaching 750 degrees F,
thus obviating any l significant oxidation in the unlikely combined events of air l inleakage and loss of normal cooling.
Amendment No. 75
(3I. Fort $t. Vrain #1
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/echnical$pecifications Amendment No. 75 Page 4.7 8
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i $PECIFICATION LCO 4.7.4 SPENT FUEL SHIPPING CA$K l LIMITING CONDITION FOR OPERATION lA spent fuel shipping cask shall not be loaded or partially loaded l with IRRADIATED FUEL having less than 100 days of fission product I decay.
l APPLICABILITY: At all times.
l ACTION:
l a.
IRRADIATED FUEL with less than 100 days of fission product l
decay shall be removed from the spent fuel shipping cask l
prior to lifting the cask.
I b.
The provisions of LCO 4.0.3 are not applicable.
l ASSOCIATED SURVEILLANCE RE001REMENT:
) BAS 15 FOR $PECIFICATION LCO 4.7.4 1 The pottntial radiological consequences of an accident whereby the j spent fuel shipping cask breaks open while being lowered to the j truck, have been analyzed in FSAR Section 14,6.3.3.
This analysis I assumes that the cask is loaded with the most radioactive IRRADIATED j FUEL elements contemplated to be shipped from the plant after 100 l days of fission product decay.
Amendment No. 75
^
Fert $t. Vrain 82 Technical Specifications Amendnent No. 75 Pagt 4.1 9 l SPECIFICATION LCO 4.7.5 INSTRUMENTATION I
i l LIMITING CONDITION FOR OPERATION I
l The reactivity of the core shall be continuously monitored by at I least two startup channel neutron flux monitors in accordance with l LCO 4.4.1 (Tables 4.4-1 and 4.4-4).
l ADPLICABILITY:
REFUELING l ACTION:
l a.
With one of the above required neutron flux monitors l
inoperable, or not operating, immediately suspend all l
operations involving CORE ALTERATIONS, any evolution l
resulting in positive reactivity changes, or schement of l
1RRADIATED FUEL in the PCRV.
l b.
With both of the above required neutron flux monitors l
inoperable or not operating:
l 1.
Immediately suspend all operations involving CORE l
ALTERATIONS, any evolution resulting in positive l
reactivity thanges, or movement of IRRADIATED FUEL, l
2.
Retract the fuel handling mechanism or any other l
remotely operated mechanism from the PCRV, l
3.
Close the reactor isolation valve or opening through l
the PCRV as soon as practicable, and l
4.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> evaluate the SHUTDOWN MARGIN per l
l ASSOCI ATED SURVEILLANCE REQUIREMENT:
SR 5.7.5 Amendment No. 75
Fort 5t. Vrain el Technical 5pecifications i
Amenement No. 75 Page 4.7-10 i
l BASIS FOR SPECIFICATION LCO 4.7.5 i The OPERABILITY of the startup channel neutron flux monitors ensures l that redundant monitoring capability is available to detect changes l in the reactivity condition of the core. This specification also I applies to reactor internal maintenance that does not involve a CORE l ALTERATION, such as a helium circulator changeout or modifications or l repair of the primary coolant purification systems.
For this l maintenance where no changes are being made to core reactivity, l activities are permitted in the event of inoperable startup channel l flux monitors, provided the other ACTION requirements are met.
l The ACTION statement ensures that activities that could affect the l reactivity condition of the core are suspended whenever neutron flux l monitoring capabilities are degraded.
i l
1 Amendment NO. 75
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i Fort St. Vrain #1 i
([)Ame:dmentNo.
(2) technical specifications 75 Page 4.7-11 l SPECIFICATION LCO 4.7.6 COMMUNICATIONS DURING CORE ALTERATIONS j
I LIMITING CONDITION FOR OPERATION l Direct two-way communications shall be maintained between operations l Control Room personnel and the Fuel Handling Machine (FHM) Control l Room personnel.
l APPLICABILITY:
During CORE ALTERATIONS conducted from the l
Refueling floor.
l ACTION: With no direct communications between the operations Control
)
l Room personnel and the FHM Control Room personnel, suspend l
all CORE ALTERATIONS.
l ASSOCIATED SURVEILLANCE REQUIREMENT:
SR 5.7.6 l BASIS FOR SPECIFICATION LCO 4.7.6 l The requirement for communications ensures that fuel handling l personnel can be promptly informed of significant changes in the l facility status or core reactivity conditions during CORE l ALTERATIONS, and operations Control Room personnel can be informed by l fuel handling personnel whenever CORE ALTERATIONS are being performed l so that core conditions can be monitored.
l The FHM Control Room and operations Control Room personnel must I coordinate control rod movements to ensure the required SHUT 00WN l KARGIN is maintained during CORE ALTERATIONS. Maintaining direct l communication also permits the operations Control Room personnel to l immediately request a stop of any movements causing excessive count l rate changes.
Amendment No. 75
2.y Fort St. Vrain #1 h
hTechnicalSpecifications Amendment No. 75
)
Page 5.7-1
)
l 5.7 FUEL HANDLING AND STORAGE SYSTEMS - SURVEILLANCE REQUIREMENTS l
Objective i
l To ensure the prevention of any uncontrolled release of j
l radioactivity during fuel handling and fuel storage by l
establishing the minimum frequency and type of surveillance on l
the equipment for the fuel handling and storage systems, i
l $PECIFICATION SR 5.7.1 FUEL HANDLING MACHINE (FHM) l i
l The FHM shall be demonstrated OPERABLE whenever LCO 4.7.2 is i
l applicable:
q l a.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that:
l l
1.
The internal pressure is within the limit of LCO 4.7.2, and l
2.
The cooling coil water outlet temperature is within the i
limit of LCO 4.7.2.
l b.
Within 31 days prior to beginning refueling operations and once l
per 12 months thereafter by:
1 1.
Functionally testing the FHM, FHM cask valve and associated I
reactor isolation valve (s), and by performing a CHANNEL TEST l
of the interlocks, limit switches, and alarms, l
2.
Functionally testing the redundant cooling water coils and l
verifying:
l a)
The flow rates are sufficient to silence the low-flow l
alarms, and I
b)
The outlet temperatures are less than 40 degrees F, l
3.
Performing a CHANNEL CAllBRATION of the cooling water l
temperature alarms, l
4.
Functionally testing the FHM cooling water leak detector by l
adding water to the drain header, 1
5.
Visually inspecting the backup fir,e water connections and l
hose to verify the hose and connector are in place and I
undamaged, and Amendment No. 75
! 7 ",.
Fort St. Vrain #1 i '.
h hTechnical $pecifications Amendment No. 75 i
Page 5.7-2 i
l l SPECIFICATION SR 5.7.1 (Continued).
l 6.
Functionally testing the fuel handling purge system, i
l including availability of a supply of helium
- and the 1
l availability of the gas waste system to receive purge gas by i
i evacuating and filling the FHM, j
l c.
Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to initial attachment to the FHM, and once l
per 31 days thereafter, demonstrate the reactor building l
overhead crane OPERABLE by:
l 1.
Performing a
visual inspection of crane components, i
l including cable and reeving, blocks and sheaves, and the l
special lifting hook for carrying the FHM when it is i
l installed and secured on the crane, and l
2.
Functionally testing the upper limit switch of the FHM l
lifting hoist under no load by slowly running the block into I
the limit switch, l
l ASSOCIATED LCO:
l l*
A helium atmosphere is not required in the FHM when it is empty l
or when handling nonirradiated fuel or handling IRRADIATED FUEL l
that has undergone fission product deca *y for 100 days or more, l
or when the FHM is not being used in fuel handling operations l
with the reactor core or fuel storage wells.
Amendment No. 75
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i F;rt St. Vrain #1 h
h Technical Specifications Amendmee'. No. 75 Page 5.7-3 1
1 l BASIS FOR SPECIFICAi!ON SR 5.7.1 l
i l The FHM provides for safe reactor fuel handling. To ensure the l reliability of the FHM during the fuel handling operations, the FHM l and the isolation valve (s) will be functionally tested pM or to fuel 1
l handling operations and once per 12 months thereafter, of extended l
l operation.
l A functional test of the fuel handling purge system and cooling water i system and an inspection of the backup fire water connections and 1
l hose will be made. These checks ensure the capability to maintain l the proper atmosphere environment within the FHM, to prevent any
]
l uncontrollable release of activity, and the capability to maintain l the surface temperature of fuel elements within the FHM below 750 l degrees F.
l The reactor building overhead crane is inaccessible for visual
)
l inspections and tests during operation with the FHM.
It must be l moved to an accessible location to perform the surveillances l identified. Many of the crar:e operations involve several days when l it is attached to the FHM and is not moved.
Inspections once per 31
)
l days are in addition to other crane preventive maintenance j
l inspections in accordance with ANSI B.30.2 requirements and they are l appropriate for assuring safe operation of the reactor building l overhead crane, i
Amendment No. 75
.. t Fort $t. Vrain #1
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Ih) Technical $pecifications o
Amendment No. 75 Page 5.7-4 i
1 SPECIFICATION SR 5.7.2 FUEL STORAGE WELLS
't l SURVEILLANCE REQUIREMENTS l The cooling water, purge, and ventilation systems for each fuel l storage well containing 1RRADIATED FUEL shall be demonstrated l OPERABLE whenever LCO 4.7.3 is applicable *:
t i
I a.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by:
l i
l 1.
Verifying that the outlet cooling water temperature of l
operating cooling coil (s) is 150 degrees F or less, with a l
flow rate of greater than 7 gpm, and either:
4 l
a)
Both cooling water coils are OPERABLE with at least one I
coil in operation, or j
b)
One cooling water coil is OPERABLE and in operation, l
and the fuel storage well emergency booster fan is j
l 2.
Verifying that the pressure within the well is at l
approximately atmospheric pressure (< 1 psig) or slightly below.
l 3.
Verifying that no IRRADIATED FUEL elements are inserted into l
the central position of fuel storage wells.
1 b.
Once per 31 days by verifying that the fuel storage well l
emergency booster fan operates upon manual initiation.
I c.
Once per 18 months by verifying the capability of the fuel l
storage well emergency booster fan to draw a minimum of 9000 cfm j
of air through the fuel storage wells.
l ASSOCIATED LCO:
l Each of these surveillances shall be first performed within 1
45 days af ter approval of this amendment or sooner.
Amendment No. 75
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Amendment No. 75 Page 5.7-5 l BASIS FOR SPECIFICATION SR 5.7.2 l Fuel elements contained in the fuel storage wells will be maintained I at surface temperatures below 750 degrees F to prevent significant l graphite oxidation in the event there is any inleakage of air. An l outlet cooling water temperature of less than 150 degrees F in l operating cooling coils provides adequate cooling to maintain the l fuel elements below 750 degrees F (FSAR Section 9.1.2).
l Verifying that the pressure within the well is at approximately l atmospheric pressure (< 1 psig) or slightly below ensures that only a l negligible outleakage or no more than slow inleakage of air would l result from a failure in a primary seal.
l This specification is based on the analysis in FSAR Section 14.6.3.2 l which uses the conservative assumption that a total flow of 9000 cfm l would be drawn (equally divided) through all three vault compartments l of the fuel storage wells, thus adequately protecting the affected l storage well and fuel within it from damaging temperatures.
l The specified tests and testing frequencies are sufficient to l demonstrate the OPERABILITY of the fuel storage well emergency l booster f an, should it be called upon for performance of its required l Safety function.
l 1RRADIATED FUEL elements are not stored in the central column of a l fuel storage well because they cannot be adequately cooled in that l location (FSAR Section 9.1.2.2.2).
l The surveillance frequencies of this specification have been i established to be generally consistent with Standard Technical l Specification frequencies for LWR Fuel Storage Pool Air Cleanup l System surveillances.
l Amendment No. 75 i
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Q)TechnicalSpecifications Amendment No. 75 Page 5.1-6 o
I SPECIFICATION SR 5.7.3 FUEL HANDLING AND MAINTENANCE IN THE REACTOR I a.
The reactor pressure and temperature conditions shall be i
determined to be within the limits of LCO 4.7.1 once per 12 l
- hours, l b.
Verification of SHUTDOWN MARGIN shall be in accordance with l
l ASSOCIATED LCO:
LCO 4.7.1 l BASIS FOR SPECIFICATION SR 5.7.3 4
l The surveillance requirement frequency g'.ves adequate assurance that I changes in reactor conditions will be detected in time to permit I corrective actions if required.
Amendment No. 75
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- Amendment No. 75 Page $.7-7 i
l SPECIFICATION SR 5.7.4 SPENT FUEL SHIPPING CASK l SURVEILLANCE REQUIREMENTS l Prior to loading the spent fuel shipping cask, the IRRADIATED FUEL l elements shall be determined to have undergone fission product decay l for 100 days or more.
l A,SSOCIATED LCO:
LCO 4.7.4 l BAS 15 FOR SPECIFICATION SR 5.7.4 l Determination prior to loading the cask that the IRRADIATED FUEL l elements have undergone at least 100 days of fission product decay l ensures that a cask loading accident is within the assumptions used l in the safety analysis.
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Amendment No. 75
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Teehnical Specifications Amend 2ent No. 75 Page $.7-8 i
1 SPECIFICATION SR 5.7.5 INSTRUMENTATION i
l Each startup channel neutron flux monitor shall be demonstrated l OPERABLE whenever LCO 4.7.5 is applicable:
l a.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by performance of a CHANNEL CHECK, l b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the initial start of CORE ALTERATIONS, l
l by performance of a CHANNEL TEST, and l c.
Once per 7 days, by performance of a CHANNEL TEST.
l ASSOCIATE 0 LCO:
LCO 4.7.5 l BASIS FOR SR 5.7.5 l The surveillance requirements ensure that the neutron flux monitors I are capable of detecting changes in reactor conditions in time to l permit corrective actions if required.
These are in addition to the l calibration requirements of SR 5.4.1.
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Amendment No. 75
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([) Amendment No. 75 Technical Specifications i,
Page 5.7-9 4
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} SPECIFICATION SR 5.7.6 COMMUNICATIONS DURING CORE ALTERATIONS l SURVEILLANCE REQUIREMENTS l Direct communications between the operations Control Room personnel l and the FHM Control Room personnel shall be demonstrated within one I hour prior to the start of and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE l ALTERATIONS.
I ASSOCIATED LCO:
LCO 4.7.6 i BASIS FOR SPECIFICATION SR 5.7.6 l The surveillance times specified give adequate assurance that l communications will be available as needed.
l Amendment No. 75
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