ML19345C768
| ML19345C768 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/10/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345C769 | List: |
| References | |
| NUDOCS 8012080322 | |
| Download: ML19345C768 (12) | |
Text
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NUCLEAR REGULATORY COMMISSION y
wasrv. rON. D. C. 20555 gv j VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-28 1.
The luclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power Corcoration (the licensee) dated November 6,1980, complies with the standards and requirements 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 (1) that the activities authorized 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 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 require-ments have been satisfied.
2.
Accordingly, the license is amended by changes to the. Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
B.
Technical Specifications
-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION e
uddfs Thomas
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 10, 1980
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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET-NO. 50-331 4
- 1.. Replace the following pages of the Appendix "A" Technical Specifica-4 tions with the enclosed pages. The revised pages are identified by i
Amendment number and contain vertical lines indicating the a~rea of-change.
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Remove Insert 183 183 185 185 185-a 185-a 186 186 l
187 187 i
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Add pages 185-b and 186-a.
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VYNPS 4.12 SUHVEILLANCE HEQUIHEMENT 3 12 LIMITING CONDITION FOR OPERATION
- Thereafter, the SHMs shall be checkfd datly moved and one ir an adjacent quadrant. For for response.
an SRM to be considered operable the following conditions shall be satisfied:
1.
The SRM shall be inserted to the normal
. operat ing level.
(Use of special movable, dunking type detectors during intitial fuel loading and major core
^
alterations in place of normal detectors is permissible as long as the detector is connected into the proper circuitry which contain the required rod blocks).
2.
The SHM shall have a minimum of 3 ces with all rods fully inserted in the core.
3 Prior to spiral unloading, the SRMs shall Prior to spiral unloading or reloading, the SHHs shall be functionally tested. Prior to l
be proven operable as stated in Sections spiral reloading, the SPMs shall be checked 3 12.B.1 and 3 12.B.2 above, however, for neutron response.
during spiral unloading the count rate may drop below 3 cps.
4.
Prior to spiral reloading, two diagonally adjacent fuel assemblies, which have previously accumulated exposure in the reactor, shall be loaded into their previous core positions next to each of
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the 4 SHMs to obtain the required 3 cps.
Until these eight bundles have been loaded, the 3 cps requirement is not necessary.
C.
Fuel Storage Pool Water Level C.
Fuel Storage Pool Water Level Whenever irradiated fuel is stored in the Whenever irradiated fuel is stored in the fuel storage pool, t'
pool water level shall fuel storage pool, the pool level shall be be maintained at a level of at least 36 feet.
recorded daily.
Amendment No. 59
.m VYNPS 3 12 LIMITING CONDITION FOR OPERATION 4.12 SURVEILLANCE REQUIREMENT 1.
The reactor mode switch.shall be locked 1.
This surveillance requirement is the same in the "Re fuel" position. The refueling as that given in Specification 4.12.A..
interlock which prevents more than one control rod from being witndrawn may be bypassed on a withdrawn control rod ~after the fuel assemblies in the cell containing (controlled by) that control rod have been removed from the reactor core. All other refueling interlockt shall be' operable.
2.
This surveillance requirement is the same 2.
SRMs shall be operable in the core as that given in Specification 4.12.B.
quadrant where fuel or control rods are being moved, and in an adjacent quadra nt. The requirements for an SRM to be considered operable are given in Specification 3 12.B.
3 If the spiral unload / reload method of core alteration is to be used, the following conditions shall be met:
The shutdown margin of the core shall a.
be verified prior to spiral unloading.
b.
The core shall be spirally unloaded with the exception of 2 diagonally adjacent fuel assemblies next to each SHM, which shall be removed last.
c.
The core shall be spirally reloaded to its original configuration in exactly the reverse of the unloading spiral with the exception of the eight fuel assemblies described in Section 3 12.B.88.
Amendment No. 59 185
6 VYNPS 3 12 LIMITING CONDITION FOR OPERATION 4.12 SURVEILI.ANCE REQUIREMENT d.
At least 50) of the ' fuel assemblies to be resloaded into the core shall D
have previously accumulated a minimum g
exposure of 1000 Mwd /T.
F.
Fuel Movement F.
Fuel Movement Fuel shall not be moved or handled in the Prior to 'any font handling or movement in' the
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reactor core for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following reactor reactor core..the licensed operator shall shutdown to cold shutdown conditions.
verify that the ' reactor has been in _the cold shutdown condition for a minimum of.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G.
Crane Operability G.
Crane Oparability 1.
The reactor building crane shall be 1.
a.
Within one month prior to spent fuel-operable when the crane is used for cask handling operations, an 2
handling of a spent fuel cask.
inspection of crane cables, sheaves, hook, yoke and cask lif ting trunnions will be made. These inspections shall meet the requirements of ANSI Standard B30.2, 1967 A crane rope shall be replaced if any of the replacement criteria given-in ANSI B30.2.0-1967 are met.
b.
No-load mechanical and electrical tests will be conducted prior to lifting the empty cask from its transport vehicle to verify proper operation of crane controls, brakes and lifting speeds. A functional test of the crane brakes will be conducted each time an empty cask is lifted clear of its transport vehicle.
Amendment No. 59 185-a
4 D**
VYNPS ow-c
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.:n 4.12 SURVEILLANCE REQUIREMENT LIMITING CONDITIONS FOR OPERATION 3 12 2.
Crane Travel 2.
Crane Travel Crane travel limiting mechanical stops Spent ' fuel casks shall be prohibited from
-shall-be installed,on the' crane trolley travel over irradiated fuel assemblies.
rails prior to cask handling operations to prohibit cask travel over irradiated fuel assemblies.
11. Spent Fuel Pool WM ar Temperature 11. Spent Fuel Pool Water Temperature Whenever irradiated fuel is in the spent fuel Whenever irradiated fuel is stored in the pool, the pool water temperature shall be spent fuel pool, the pool water temperature recorded daily. If the pool water shall be maintained below 1500F.
temperature reaches 150 F, all refueling 0
operations tending to raise the pool water temperature shall cease and measures taken immediately to reduce the pool water 0
temperature below 150 F.
i Amendment No. 59 185-b
VYNPS Ba ses :
3 12 & 4.12 REFUELING A.
During refueling operations, the reactivity potential of the core is being altered. It is necessary to require certain interlocks and restrict certain refueling procedures such that there is assurance that inadvertent criticality does not occur.
To minimize the possibility of loading fuel into a cell containing no control rod, it is required that all control rods are fully inserted when fuel is being loaded into the reactor core. This requirement assures that during refueling the refueling interlocks, as designed, will prevent inadvertent criticality. The core reactivity limitation of Specification 3 2 limits the core alterations to assure that the resulting core loading can be controlled with the reactivity control ' system and interlocks at any time during shutdown or the following operating cycle.
The addition of large amounts of reactivity to the core is preve ed by operating procedures, which are in turn backed up by refueling interlocks on rod withdrawal and movement of the refueling platform. When the mode switch is in the "Re fuel" position, interlocks prevent the refueling platform from being moved over the core if a comtrol rod is withdrawn and fuel is on a hoist.
Likewise, if the refueling platform is over the core with fuel on a hoist, control rod motion is blocked by the i
interlocks. With the mode switch in the refuel position only one control rod can be withdrawn.
B.
The SRMs are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and station startup. Requiring two operable SRMs in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that quadrant during such alterations. The requirement of 3 counts per second. provides assurance that neutron flux is being monitored. Under the special condition of complete spiral core unloading, it is expected that the count rate of the SHMs will drop below 3 cps before all.the fuel is unloaded.
Since there will be no reactivity additions, a lower number of counts will not present a hazard. When all of the fuel has been removed to the spent fuel storage pool, the SRMs will no longer be required. Requiring the SRMs to be operational prior to fuel removal assures that the SHHs are operable and can be relied on even when the count rate may
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go below 3 cps.
Prior to spiral reload, two diagonally adjacent fuel assemblies, which have previously accumulated exposure in the reactor, will be loaded into their previous core positions next to each' of the 4 SRMs to obtain the required 3 cps.
Exposed fuel continuously produces neutrons by spontaneous fission of certain plutonium isotopes, photo fission, and photo disintegration of deuterf um in the moderator.. This neutron production is normally great enough to meet the 3 cps minimum SHM requirement thereby providing a means by which SHM response may be demonstrated before the spiral reload begins.
In the event that the core is to be spirally unloaded and reloaded, requirements to verify shutdown margin l,
Amendment No. 59 186
m a
VYNPS prior to unloading the core and also to reload only to the original core configuration assure that no unanticipated flux perturbations will occur during the performance of core alterations and in particular those core alterations performed with SRM indication less than 3 cps.
During the spiral reload the fuel will be loaded in the exact reverse order that it was unloaded with the exception of the initial.eight fuel assemblies which are loaded next to the SRMs to.
provide a means of SRM response.
C.
To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established. This minimum water level of 36 reet is established because it would be a significant change from the normal level, well above a level to assure adequate cooling (just above active fuel).
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Amendment No. 59 186-a
VYNPS 3 12 & 4.12 (Continued) it is desirable to perform maintenance on two control rods and /or control rod drives at the D.
During certain periods, same time. This specification provides assurance that inadvertent criticality does not occur during such maintenance.
The maintenance is performed with the mode switch in the "Befuel" position to provide the refueling interlocks normally In order to withdraw a second control rod available during refueling operations as explained in Part A'or these Bases.
af ter withdrawal of the first rod, it is necessary to bypass the refueling int erlock on the first control rod which prevents more than one control rod from being withdrawn at the same time.
ane requirement that an adequate shutdown margin be demonstrated with the control rods remaining in service insures that inadvertent criticality cannot occur 1he shutdown margin is verified by demonstrating that the core is shut down even if the during this maintenance.
strongest control rod remaining in service is fully withdrawn. Disarming the directional control valves does not inhibit control rod scram capability.
E.
The intent of this specification is to permit the unloading of a significant portion of the reactor core for such purposes as inservice inspection requirement s, examiniation af the core support plate, etc.
This specification provides assurance that inadvertent criticality does not occur during such operation.
This operation is performed with the mode switch in the " Refuel" position to provide the refueling interlocks no naally available during refueling as explained in the Bases for Specification 312. A.
In order to withdraw more than one it is necessary to bypass the refueling inter'ock on each withdrawn control rod which prevents more than control rod, one control rod from being withdrawn at a time. The requircment that the fuel assemblies in the cell controlled by the control rod be removed from the reactor core before the interlock can be bypassed insures that withdrawal of another control rod does not result in inadvertent criticality.
Each control rod essentially provides reactivity control for the fuel assemblies in the cell associated with that control rod.
Thus, removal of an entire cell (fuel assemblies plus control rod) results in a lower reactivity potential of the core.
One method available for unloading or reloading the core is the spiral unload / reload. A spiral unloading pattern is one by which the fuel in the outermost cells (four fuel bundles surrounding a control rod) is removed first. Unloading continues by unloading the remaining outermost fuel by cell with tae exception of 2 diagonally adjacent fuel assemblies next to each SHM. These assemblies will be removed after the removal of the center cell, which is the last cell removed from the core. Spiral reloading is reverse of unloading with the exception that two diagonally adjacent bundles, which have previously accumulated exposure in-core, are placed next to each of the 4 SRMs before the actual Additionally, at least 50% of the fuel asemblies to be reloaded into the core shall have spiral reloading begins.
previously accumulated a minimum exposure of 1000 Mwd /T to insure the presence of a minimum neutron flux as described in Bases Section 3 12.B.
The intent of this specification is to assure that the reactor core has been in the cold shutdown conditon for at least F.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following power operation and prior to fuel handling or movement. The safety analysis for the postulated refueling accident assumed that the reactor had *>cen shut down for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for fission product decay prior to any fuel handling which could result in dropping of a fuel assembly.
187 Amendment No. 59
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