ML19257C898
| ML19257C898 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/04/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19257C891 | List: |
| References | |
| NUDOCS 8001310060 | |
| Download: ML19257C898 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION W ASHWGTON, D. C. 20J55
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JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION, UNIT NO.1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 33 License No. DPR-lf 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applit ation fcr amendment by Jersey Central Power & Licht Company (the licensee) dated November 16, 1979, complies with the standards and requirments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission't rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the applicatinn, the provisions of the Act, and the rules and regulations oc the Cocinission; C.
There is reasorable assurance (i) that the activities authorized by this amenoment. 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 regulaticr.s; D.
The issuance of this anendnent will not be inimical to the cocinon defense and security or to the health anc safety of the public; and E.
The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1843 023 800131 0 06C 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No.
DpR-16 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, 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
' vryE Dennis L. Zieman, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 4,1980 1843 024
ATTACHMENT TO LICENSE AMENDMENT NO. ^3 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain vertical lines indicating the areas of change.
PAGES 3.9-1 3.9-2 3.9-3 4.9-1 4.9-2 I
1843 025
3.9 REFUELING 3.9-1 Applicability:
Applies -to fuel handling operations during cfueling.
Objective:
To assure that criticality does not occur during refueling.
Specification:
A.
Fuel shall not be loaded into a reactor core cell unless the control rod in that core cell is fully inserted.
B.
During core alterations the reactor acde switch shall be locked in the RE.UEL position.
C.
The refueling interlocks shall be operable with the fuel grapple hoist loaded switch set at 148S lb. during the fuel handling operations with th'e head off the reactor vessel.
If the frame-mounted auxiliary hoist, the trolley-counted auxiliary hoist or the service platfor s hoist is to be useu for handlin:; fuel with the head off the reactor vessel the load licit switch on the heist to be used shall be set at 1400lb.
D.
During core alteratiens the source r:nge monit' r nearest o
the alteration shall be operable.
E.
Removal of one centrol rod or rod drive techanism may be performed provided that all the following specifications are satisfied.
1.
The reactor code switch is locked in the refuel position.
2.
At least two (2) source range monitor (SRM) channels shall be operable and inserted to the normal operation level.
One of the operable SRM channel detectors shall be located in the core quadrant where the control rod is being removed and one shall be located in an adjacent quadrant.
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F.
Removal of any nu:nber of control rods or rod drive ecchanisms
=ay be performed provided all the followine, specifications are satisfied:
1.
The reactor =cde switch is locked in the refuel position and all refueling interlocks are operable as required in Specification 3.9.C.
The refueling interlocks associated with the control rods being withdrawn may be bypassed as required afte-the fuel assemblies have been removed from the core cell surrounding the control rods as spe-cified in 4, below.
Amendment No. g, 43 g4}
3.9-2 At least two (2) source range monitor (SPM) channels shall be operable and inserted to the nocaal operation level. One of the 2.
operable SRM channel detectors shall be located in t located in an adjacent quadrant.
- 3. All other control rods are fully inserted with the exception of one rod which may be partially withdrawn not more than two notches to perform refueling interlock surveillance.
The four fuel assemblies are removed from the core cell surrounding each control rod or rod drive mechanism to be 4.
removed.
least 0.25% a k, plus The core is suberitical by at C settling in 5.
equivalent reactivity for the ef fect of any Bin the core, with the most react 9
inverted tubes ~ present r maining control rod withdrawn.
An evaluation will be conducted for each refuel /relcad to ensure that actual core criticality for the proposed order of 6.
defuelity ard refueling is tounded by previous analysis performed to support such defueling ard refueling activities, otherwise a new analysis shall be performed.
Tne new analysis must show that sufficient conservatism exists' for the proposed order of defueling and refueling before such operation shall be allowed to proceed.
With any of the above requirenents not met, cease core alterations or control rod removal as appropriate, and initiate action to satisfy G.
the above regairements.
BASIS:
During refueling operations, the reactivity p3tential of the core is is necessary to require certain interlocks and being altered.certain refueling procedures such that there is assurance It restrict that inadvertent criticality does not occur.
Addition of large amounts of reactivity to & core is prevented by operating procedures, which are in turn backed up by ref ueling on rod withdrawal and movement of the refueling interlocks (1) is in the " Refuel" position, hten the mode switch the refuelirg platfoca fran being moved over the platform.
interlocks prevent
- Likewise, core if a control rod is withdrawn and fuel is on a hoist.
refueling platform is over the core with fuel on a hoist With the mode switch if the control roi motion is blocked by the interlocks.
in tne refuel position only one control rod can be withdrawn (1,2).
Se one rod withdrawal interlock nay ce bypassed in order to allow multiple control rod removal for repair, modifications, or core l
1843 027 Amendment No. J4, M
3.9-3 unloadirg. We require en-s for simultanecus renoval of more than one Control rod are rore strirgent than the recuirements for removal of a single control rod, since in the latter case Specification 3.2.A assures that the core will remain subcritical.
Fuel handlirg is normally corducted with the fuel grapple hoist. The total load on this hois: r.en the interloc< is recuired consists of the weight of the fuel grapple 2M the fuel assemly. Tnis total is approximately 773 lbs. in the extended position in comparison to the load limit of 485 lbs. provisions have also been trade to allow fuel handlirg with either of the three auxiliary hoists ard still maintain 3
the refueling interlocks.
The 400 lb load trip setting on these hoists is adequate to trip the interlock when cne of the more than 600 lb. fuel buMles is beirg handled.
Se source range monitors provide neutron flux monitorire carabilities with the reactor is in the ref ueling and shutdcwn modes (3).
Specification 3.9.D assures that the neutron flux is monitored as close as possible to the location where fuel or controls are beirs moved. Specifications 3.9.E and F require the operability of at least two source range monitors when control rods are to be rer.oved.
i REFERDCES:
(1) FIEAR, Voltrae I, Secdon VII-7.2.5 (2) FIEAR, Voltrae I, Section XIII-2.2 (3) FESAR, Voltrae I, Sections VII-4.2.2 aM VII-4.3.1 mr._ -
l _
1843 028 Araendment No. Ji, M
4. 9 - 1, t
4.9 REFUELING Aoplicability: Applies to the periodic testing of those interlocks and instruments used during refueling.
Objective:
To verify the operability of instrumentation and interlocks in use during refueling.
Soecification:
A.
The refueling interlo;ks shall be tested prior to any fuel handling with the head off the reactor vessel, at weekly intervals thereafter until no longer required and following any repair work associated with the inter-locks.
B.
Prior to beginning any core alterations, the source range monitors (SRMs) shall be calibrated.
Thereafter, the SRM's will be checked daily, tested monthly and calf brated every 3 months until no longer required.
C.
Within four (4) hours prior to the start of control rod removal pursuant to Specification 3.9.E verify:
1.
That the reactor mode switch is locked in the refuel position and that the one rod out refueling interlock is operable.
2.
That cao (2) SRM channels, one in the core quadrant where the control red is being removed and one in an adjacent quadrant, are operable and inse-ted to the normal operation level.
D.
Verify within four (4) hours prior to the start of control rod removal pu suant to Specification 3.9.F and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, until replacement of all control rods or roc drive mechanisms and all control rods are fully inserted that:
1.
the reactor mode switch is locked in the refuel posi-tion and the one rod out refueling interlock is operable.
2.
Two (2) SRM channels, one in the core quadrant where
/
a control rod is being removed and one in an adjacent quadrant, are operable and fully inserted.
3.
All control rods not removed are fully inserted with the exception of one rod which may be partially withdrawn not more than two notches to perform refueling interlock surveillance.
4.
The four fuel assemblies surrounding each control rod or rod drive mechanism being removed or maintained at the same time are removed from the core cell.
AmendmentNo.'yf,43
4.9-2 E.
Verify prior to t.he start of removal of control
]
rods pursuant to Specification 3.9.F that Specification 3.9.F.5 will be met.
F.
Following replacement of a control rod or rod drive rxchanism removed in accordance with Specification 3.9.F, prior to inserting fuel in the control cell, verify that the bypassed refuel,ing interlocks associated with that rod have been restored and that the control rod is fully inserted.
Basis:
The refueling interlocks (I) are required only when fuel is being handicd and the head is off the reactor vessel.
A test of these interlocks prior to the time when they are needed is sufficient to ensure that the~ interlocks are operabic.
The testing frequency for the refueling interlocks is based upon engineering judgment and the fact that the refueling interlocks are a backup for refueling procedures.
The SRM's (2) provide neutron monitoring capability during core alterations. A calibration using external testing equipment to calibrate the signal conditioning equipment prior to use is sufficient to ensure operability.
The fre-quencies of testing, using internally generated test signals, and recalibration, if the SRM's are required for an extended period of time, are in agreeaent with other instruments of this type which are presented in Specification 4.1.
The surveillance requirements for control rod removal assure that the requirements of Specification 3.9 are met prior to' initiating control rod removal and at appropriate intervals thereafter.
L
References:
(1)
FDSAR, Volume I, Section VII-7-2.5 (2)
FDSAR, Volume I, Sections VII-4.2.2 and VII-4-5.1 1843 030 Amendment No. J8, 43