ML19210C983

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Tech Specs Change Request 78,incorporating Amend 28 to OL for All Refueling Cycles
ML19210C983
Person / Time
Site: Oyster Creek
Issue date: 11/16/1979
From:
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19210C977 List:
References
TASK-06-07.C2, TASK-16, TASK-6-7.C2, TASK-RR NUDOCS 7911200389
Download: ML19210C983 (11)
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JEPSEY CLUI'RAL PC.;ER & LIGIIT CG4PAFi CYSTLR CREEK NUCLC'in CL!JLRATIt;0 ST7 JIOli Provisionel Opercting License !;o. DPR-16 T *.. ting License Change bcqu t .. . 73 Docket I;o. 50-219 Applicent sutraits, by this Technical Spccification Chcngc Ecquest No. 78 to the Oyster Creck Nuclear Generating Station Technical Specification enanges to incorporate Amendment 23 for all Eefueling Cycles .

JEDSEY CLNTPdL IC'Eh & LIGIIT COMPANY BY}y) p ~ j 

                                             ~~ VICL' Pf' ;ICt.

STATE OF Nb JEPSLY ) 

                          )

CCONTY OF liORRIS ) Sworn and subscribed to before me this / _, day of y +,,, /. , , 1979. 

                                                 ~. h , ,              -/    ,

Notary Public PHYLLIS A. KABIS NOTARY FU!illC OF NEW JERSEY My Commission Expires Au2416,1934 

                                                                        , 1 (-

s $\\ s 7911200

UNITED STATES CF N'IRICA HUCILAR REGUIATCRY CGMISSION IN THE t'ATIER OF ) 

                                             }                  DOCKET NO. 50-219 JERSEY CD1 TRAL poi;ER & LIGHT CGIPANY )

CERTIFICATE OF SERVICE This is to certify that c copy of Technical Specification Change Ecquest No. 78 for tne Cyctcr Creek Nuclect Generating Station Techncial Specificationc, filed with the U. S. Nuclear Regulatory Comicsion on November 16, 1979, hoc this 16th day cf November , 1979 been served on the Fbyor of Lacey Township, Ocean County, New Nrsey by deposit in tne United Stater Mail, addressed as follows: The Ilonarcble Itry Iru Smith Ityor of Lacey 1bwnchip P. O. Eox t.75 Forked River, New Jersey 08731 JERSEY CEKITAL PG;ER & LIGIT CQ1PANY BY 8/ , V Vice P 

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id DATED: Noveraber 16, 1979 

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Jersey Central Power & Light Company ( r rC 3 ,)3.gh.g,E ;y ,' [r' y Jj Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 November 16, 1979 Tne llonorable Mary Lou Smith Ityor of Iccey Township P. O. Box 475 Forked River, New Jersey 08731

Dear Ityor Smith:

Enclosed herewith is one copy of Technical Specification Change Rcquest No. 78 for the Oyster Creek Nuclect Generating Station Technical Specifications. 7nis document was filed witn the U.S. Nuclear Regulatory Commission on November 16, 1979. Very truly yours, 

   ~

dhaw, Ivan R. Pinf ck, , Vice President la Enclosure 1 7/ 1 1}} Jersey Central Power & Ught Company is a Member of the General Pubic Utilities System

JERSEY CENTFAL POWTR & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET NO. 50-219) PROVISIONAL OPERATIN3 LICENSE NO. DPR-16 Applicant hereby requests the Commission to change Appendix A to the above captioned license as follows:

1. Sections to be changed:

Sections 3.9 and 4.9

2. Extent of Changes:

Tnis change is identical to Amendment 23 but deletes the requirement that it be in effect for only one cycle. The changes allow for single and multiple control rod or rod drive mechanism removal under specified controls. They also allow for loading fuel without having all of the control rods inserted. These changes will make it possible for the core to be unloaded and reloaded without using 137 blade guides to support all of the control rods in an inserted position.

3. Changes reauested:

See attached revised pages.

4. Discussion:

The effects of the proposed changes on the safe operation of the plant were reviewed in the attached safety evaluation. From the evaluation, it can be concluded that the changes will not adversely affect the public health and safety. The changes will provide benefits in the operation of the plant by allowing the core t::, be unloaded and reloaded without using one blade guide for each control rod (137) and by allowing multiple control rod drive maintenance activities. This has been demonstrated under Amendment 23 which was used for cycle 6/7 offload / reload. 4 g- 11, 

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3.9-1 

     *
  • 3.9 ' REFUELING Applicability: Applies to fuel handling operntions during refueling.

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 mode switch shall be locked in the REFUEL position. C. The refueling interlocks shall be operable with the fuel grapple hoist loaded switch set at 1485 lb. during the fuel handling operations with th'e head off the reactor vessel. If the frame-mounted auxiliary hoist, the trolley-mounted auxiliary hoist or the service platform hoist is to be used for handling fuel with the head off the reactor vessel the load limit switch on the hoist to be used shall be set at 1400lb. D. During core alterations the source range monitor nearest the alteration shall be operable. E. Removal of one control rod or rod drive mechanism may be performed provided that all the following specifications are satisfied.

1. The reactor mode 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 channci detectors shall be located in the core quadrant where the control rod is being removed and one shall be located in an adjacent quadrant.

F. Removal of any number of control rods or rod drive mechanisms may be performed provided that all the following specifica-tions are satisfied:

1. The reactor mode 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 after the fuel assemblics have been removed from the core cell surrounding the control rods as spe-cified in 4, below.

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                                                                                    .      ! s s

Amendment No. 23

3.9-2

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 chall be located in the core quadrant where a control rod is being removed and one shall be 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.
4. The four fuel assemblies are removed from the core cell surrounding each control rod or rod drive mechanism to be removed.
5. The core is subcritical by at least 0.25% a k, plus equivalent reactivity for the effect of any B4 C settling in inverted tubes present in the core, with the most reactive remaining control rod withdrawn.
6. An evaluation will be conducted for each refuel / reload to ensure that actual core criticality for the proposed order of defueling and refueling is bounded by previous analysis performed to support such defueling and refueling activities, otherwise a new analysis shall be performed.

We new analysis must show that sufficient conservatism exists for the proposed order of defueling and refueling before such operation shall be allowed to proceed. G. With any of the above requirements not met, cease core alterations or control rod removal as appropriate, and initiate action to satisfy the above requirements. BASIS: During refueling operations, the reactivity potential of the core is bcing altered. It is necessary to require certain interlocks and restrict certain refueling procedures such that there is assurance that inadvertent criticality does not occur. Addition of large amounts of reactivity to the core is prevented by operating procedures, which are in turn backed up by refueling interlocks (1) on rod withdrawal and movement of the refueling platform. When the mode switch is in the " Refuel" position, interlocks prevent the refueling platform from being moved over the core if a control 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 interlocks. With the mode switch in the refuel position only one control rod can be withdrawn (1,2). 

      %e one rod withdrawal interlock may be bypassed in order to allow multiple control rod removal for repair, modifications, or core
                                                                <1(*     ))6

3.9-3 unloading. The requirements for simultaneous removal of more than one Control rod are more stringent than the requirements for removal of a single control rod, since in the latter case Specification 3.2.A assures that the core will remain subcritical. Fuel handling is normally conducted with the fuel grapple hoist. The total load en this hoist when the interlock is required consists of the weight of the fuel grapple and the fuel assembly. This total is approximately 773 lbs. in the extended position in comparison to the load limit of 485 lbs. Provisions have also been made to allow fuel handling with either of the three auxiliary hoists and still maintain the refueling interlocks. The 400 lb load trip setting on these hoists is adequate to trip the interlock when one of the more than 600 lb. fuel bundles is being handled. The source range monitors provide neutron flux monitoring capabilities with the reactor is in the refueling and shutdown 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 being moved. Specifications 3.9.E and F require the operability of at least two source range monitors when control rods are to be removed.

REFERENCES:

(1) FDSAR, Volume I, Section VII-7.2.5 (2) FDSAR, Volume I, Section XIII-2.2 (3) FDSAR, Volume I, Sections VII-4.2.2 and VII-4.3.1 

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4.9-1 4.9 REFUELING . Applicability: 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. , Specification: A. The refueling interlocks 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 calibrated e.very 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 two (2) SRM channels, one in the core quadrant f where the control red is being removed and one in an i adjacent quadrant, are operable and inserted to the normal operation level.

D. Verify within four (4) hours prior to the start of control rod removal pursuant to Specification 3.9.F and at least once per 24 hours thereafter, until replacement of all control rods or rod 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 wb -

a control rod is being removed and one in an adj . _. t 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.
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                                                                        .            4 7/ '   119' Amendment No. 23

4.9 ,- . E. Verify prior to the 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 r.:cchanism 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 II) are required only when fuel is being handled 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 SR!i'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 SRii's are required for an extended period of time, are in agreement 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. ' I l l i

References:

FDSAR, Volume I, Section VII-7-2.5 (1)  ! (2) FDSAR, Volume I, Sections VII-4.2.2 and VII-4-5.1 4 .7 /. 5 11 SI L .. 

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Amendment No. 23}}

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