ML20010J242
| ML20010J242 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/26/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010J243 | List: |
| References | |
| NUDOCS 8109300016 | |
| Download: ML20010J242 (12) | |
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UNITED STATES k*
NUCLEAR REGULATORY COMMISSION
,3,I WASHINGTON, D. C. 20556
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o r-f POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FIT 2 PATRICK NUCLEAR POWER PtANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated December 6,~ '1979, complies with the standards and requirements of tne Atomic Energy Act of 1954,'as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 Comission's regulatio'ns; 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 E.
The issuance of this amendment.is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8109300016 810826~ '
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Accordingly, facility Operating License No. 'DPR-59 is amended by changes to the Technical Specifications as indicated in the attachment, and Paragraph 2.C(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specificatio'ns 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.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0',ac. K/ Ippolito, Chief Q;p-Thor Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 26, 1981 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY' OPERATING
- LICENSE NO.
' DOCKET NO.' 50-333 Revise Appendix A as follows:
Remove'Pages Inser:'Pages 227 227 230 230 230a 231 231' 232 232 234 234 235 235' 235a 235b SS 49 n
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JAFNPP 4
3.10 LIMITING CONDITIONS FOR 4'.10 SURVEILLANCE REQUIREMENTS f
OPERATION 4.10 CORE ALTERATIONS t
3.10 CORE ALTERNATIONS Applicability:
Applies to the periodic testing of those 6
Applies to fuel handling and core re-interlocks and instruments used during activity limitations.
refueling and core alterations.
Objective:
Objecti,ve To assure that core reactivity is within To verify the operability of inst'ru-the capability of the control rods and mentation and interlocks used in j
refueling and core alterations.
to prevent criticality during refueling.
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Specification:
Specificationt l
It A.
Refueling Interlocks A.
Refueling Interlocks i
l 1.
The Reactor Mode Switch shall 1.
Prior to any fuel handling, with the be locked in the Refuel head off the reactor vessel, the position during core altera-refueling interlocks shall b,
j tions and the refueling functionally tested. They shall interlocks shall be operable also be tested at weekly intervals except as specified in thereafter until no longer required Specifications 3.10.A.2, and following any repair work 3.10.D, and 3.10.E associated with the interlocks.
2.
Fuel shall not be loaded into 2.
Whenever the reactor is in the refuel mode the reactor core unless all and rod block interlocks are being bypassed control rods are fully for core unloading, u.ae licensed operator inserted except in accord-and a member of the reactor analyst department ance with Specification 3.10.A.7.
shall verify that the fuel from the, cell has been removed before the corresponding 3.
The fuel grapple hoist load control rod is withdrawn, switch shall be set at <p50 lbs.
1 Amendment No. 59 227
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3.10 (cont'd)
JAFNPP 4.10. (con' t) control rod a f t er the fuel l
assemblics in the cell
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containing (controlled Oy) j i
that control rod have been l
s 1
t removed from the reactor I
core.
All other refueling interlocks shall be operable.
7.
In the " refuel" mode, there are inter-
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locks which prevent the refueling bridge (if loaded) from moving,toward the core unless all control rods are fully inserted. These interlocks may be bypassed during spiral loading except for those control cells which contain fuel or that control cell which is being loaJed.
Interlocks for all i'
cells containing fuel, or for any cell z5 nut to be loaded, shall be operable.
4 B.
' Core Monitoring D.
Coro Monitoring During core altera~tions two SRM's Prior to making alterations to shall be operable, one in the core the core the SRM's shall be quadrant where fuel or control rods functionally tested and checked for are being moved and one in an neutron response. Thereafter, the adjacent quadrant. For an SRM to be SRM's will be checked daily for considered operable, the following response, except as specified in conditions shall b'c satisfied:
7 Specification 3.10.B.3 and 4.
1.
The SRM shall be inserted to the normal operating Icvel.
(Use of special novabic,,' ~
.,y dunking type detectors during s
init'ial fuel loading and major core alterations in place of l
normal detectors is per-missable,as long as the detector is connected into the normal SRM circuit.)
B l
59 Am..na m..
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JAl'NPP '
4.10 (cont'd)
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3.10 (cont'd) f 1
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2.
The SRM shall have a minimum of
-3 counts /sec with all rods I
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fully inserted in'the core 1-ll cxcept as noted in 3 and 4 below.
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3.
Prior to' spiral unloading, the Spil's l-shall have' an initial cot 3nt rate of
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>3 CPS.
During spiral unloading, t J.
ll count rate of the SRM's saay drop bele 3 CPS.
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4.
During spiral reload, IRf1 operability I
i will be verified by using a portable external source every 12 hourn until enough fuct is loarled to maintain 3 CPS, s
Alternatively, two fuel assemblics will '
bq loided in different culin containing'
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control blades around each SPMsto obtain.-
the requiteil 3 CP5. 'llntil these two -
i assemblic's have,been loaded in a given l
s quad rant, "i t' is not necesnary for the SitM cln that quadrant to indicate the I
t minimum count rate of 3 CPS.
The loading of fuel near the SRM's does not violate the intent of the spiral re-loading pattern.
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Amendment No.
59 230a I
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4.10 (con *,t )
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' 3.lo (con't)
C.
Spent Fuel Storage Pool Water Level C.
Spent Fuel Storage Pool Water Ie el,-
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_Whenever leradiated fuel is stored whenever irradiated fuel is ste;;d,_
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in the spent fuel storage pool, the in the spent fuel storage pedl, the pool water level shall be maintained pool 1cvel shall be recorded daily, at a minimum level of 33 ft.
Control Rod Drive and Control Rod i.
D.
D.
Control Rod ari Control Rod Drive Drive Maintenance f
l Maintenance 1.
This surveillance requirement l
is the sane as driven in l
1.
A maximum of two non-adjacent 4.10.A control rods separated by more than two control rods in any-direction, may be wLeh(raun i
-from the core for the purpose of performing control rod core /or control rod drive maintenance providing the l
following conditions are satisfied, except as specified
,f in 3.lO.D.2 below and 3.10.A.7 a bo'< e.
a.
The Reactor Mode Switch shall be locked in the e v Refuci position. The refueling Interlock which
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prevents more than one
' control rod from being withdrawn may be bypassed for one of the control rods for which maintenance is being performed. All cther refueling interlocks shall be operabic.
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b.
Specification 3.3.A.1, shall be met or the control rod directional control valves for a Amendment No. 59 231 l
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3.1\\. (con't)
- JMt3It 4.10 (con't) k
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minimum of eight control rods surrounding each drive out of service for maintenance will be disarmed electrically and sufficient margin to prevent criticality demonstrated, except as specified in 3.10.A 7.
2.
More than two control rods may 2.
Sufficient control rods shall i
be withdrawn from the reactor be withdrawn prior to,
core provi,ded performing this maintenance to demonstrate that with a margin of 0.25 percent Ak that the j
The Reactor Mode Switch, a.
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shall be locked in the core can be made subcritical at Refuel position. The any time during the maintenance refueling interlock which with the highest worth operable prevents more than one control rod fully withdrawn and ll control rod from being all other operable rods fully withdrawn may be bypassed inserted. Alternately, if a
.on a withdrawn control rod minimum of eight control rods after the fuct assemblies surrounding each contro1 rod in the cell containing out of service or maintenance (controlled by) that are to be fully inserted and control rod have been have their directional control j
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removed from the reactor valves electrically disarmed d
l core. All other refueling the 0.25 percent Ak margin i
interlocks shall be will be met with highest worth f
control rod remaining in service during the maintenance period fully withdrawn.
j Amendment No. 59 232 D
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3.10 RASES:
JAFNPP t
A, Refueling Interlocks the condition of the refueling j
equipment and control rods.
During refueling operations, the Depending on the sensed condition,'.
reactivity potential of the. core is interlocks are activated which being altered.
It is necessary to prevent movement of the refueling t.
require certain interlocks and equipment withdrawal of control rods l
restrict certain refueling (rod block).
procedures such that there is assu'rance that inadvertent Circuitry is provided which senses criticality does not occur.
the following conditions:
l To minimize the possibility of 1.
All rods inserted.
'I loading fuel into a cell containing no control rod 'it is required that 2.
Refueling platform positioned all control rods surrounded by fuel near or over the core.
assemblies'are fully inserted when fuel is being loaded in the reactor 3.
Refueling platform hoists are core.
This requirement assures that fuel-loaded (fuel grapple, I
during refueling the refueling frame mounted hoist, monorail interlocks, as designed, will mounted hoist).-
prevent inadvertent critically.
The core reactivity limitation of 4.
Fuel grapple not full up.
4 l
Specification 3.3 timits the core alterations to assure that the 5.
Scrvice platform hoist fuel-reculting core loading can be loaded.
controlled with the reactivity control systems and interlocks at 6.
One rod withdrawn.
I any time during shutdown or the following operating cycle.
When the Mode Switch is in the Refuel position, interlocks prevent Addition of large amounts of the refueling platform from being recctivity to the core is prevented moved over the core if a control rod b operating procedures, which are is withdrawn and fuel is on a hoist.
in turn backed up by refueling Likewise, if the refueling platform interlocks and circuitry which sense is over the corn with fuel on a holst, control rod motion is blocked by the interlocks. When tho' Mode i
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Amendment No.
59 23e t
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3.Yu DASES (con't) l r
Switch is in the Refuel position only one control rod can be withdrawn except as noted in l
Specifications 3.lO.A, D and E.
The refueling interlocks, in combination with core nuclear design and refueling. procedures limit the probability of an j
inadvertent criticality. The i
i nucicar characteristics of the core assure that the reacter ir subcritical even when the highest worth control rod is fully l
withdrawn. The combination of refueling interlocks for control l
rods and the refueling platform provide redundant nethods of preventing inadvertent criticality even after procedural violations.
l The interlocks on hoists provide yet another method of avoiding inadvertent criticality.
For a new core the dropping of a
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fuel assembly into the vacant fuel l
location adjacent to a withdrawn control rod does nto result in an i
excursion or a critical i
configur'ation, thus adequate margin is provided.
A spiral.mitfading pattern is one in which the fuel in the outer-most cells (four fuel bundles surrounding a control blade) is removed first.
Unloading continues by removing the remaining outermost fuel by cell so that the center cell will be f
removed last. Spiral loading is the l
reverse of unloading. Spiral loading and un-loading preclude the formation of flux traps (moderator-filled cavities surrounded j
en all sides by fuel).
It is not necessary j
to accomplish a full core offload or onload in order to utilize the spiral movement pro-cedure.. as long as the partial unloading / reloading 235
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plan complies with the description given above.
core quadrant where fuel or control 5
rods are being moved' assures i
The Spiral unloading procedure is a special case adequate monitoring of that quadrant of the method described in Specification 3.10.A.6.
during sucli alterations. The The 3piral loading pre-edure is justified by the requirement of 3 counts /sec provides l
same logic used in the Bases for Specific,ction assurance that neutron flux is being l
3.10.D.
There it is noted that any control cell monitored and insures that startup which contains 4 fuel bundles and a fully inserted is conducted only if the source f
control blade is nore reactive than the same range flux level is above the
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control cell after the fuel bundles and control minimum assumed in the control rod blade have been withdrawn. Thus, during spiral drop accident.
3 loading or unloading, the shut!')wn margin of the partially loaded core can not possibly be less Under the special condition of spiral core than the shutdown margin of the complete core unloading, it is. expected that the SRM which is required to comply with Specification 3.3.
emmt rate will drop below 3 CPS before all I
of t he - fuel is unloaded. Since there will be B.
Core Monitoring no reactivity additions, a lower number of counts will not present a hazard. When all of The SRM's are provided to monitur th'e fuel has been removed to the spent fuel the core during periods of plant storage pool, the SRM's will no longer bc l
shutdown and to guide the operator.
required.
Requiring the SRM's to be operable during refueling operations and prior to fuel removal assures that the SRM's plant startup. Requiring two are operable and can be relied on even when operable SRM's in or adjacent to a the count rate drops below 3 CPS.
4 f
During spiral loading of the core, SRM operability
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will be verified by using a portabic external source every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until enough fuel has I
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been loaded to maintain at least 3 CPS, Alternatively, two fuel assemblies will be loaded in different cells containing control blad'es around each SRM to obtain the req' aired 3 CPS.
Unitl these two assemblice have been loaded, the adjacent SRM is not required to indicate the minimum count. rate of 3 CPS.
C.
Spent Fuel Storage Pool Water Level To assure that there'is adeq'u' ate water to shield and cool the irradiated fuel assemblics stored in the pool,'a minimum pool water IcVel is established. The minimum water i'
level of 33 f t is established because it would be significant change from the normal i
Amendment No.
59 23sa
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i Icvel (37 ft-91n.),.well above a Icvel ti, assure adequate cooling (just alove active fuel).
i D.
Control Rod and Control Rod Drive j
Maintenance During certain periods, it is desirable to perform maintenance on t
two control rods and/or control rod drives at the same time.
This l
specification provides assurances that inadvertent criticality does f
not occur during such maintenance.
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Amendment No. 59 23sh
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