ML20082N622

Rev 1 to Tech Spec Change Request 201 to License DPR-16, Revising Tech Specs to Accomodate Implementation of 21-month Operating Cycle w/3-month Outage

ML20082N622
Person / Time
Site:	Oyster Creek
Issue date:	08/29/1991
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20082N619	List: ML20082N615 ML20082N622
References
NUDOCS 9109100004
Download: ML20082N622 (6)

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GPU NUCLEAR CORPORATION '

OYSTER CREEK NUCLEAR GENERATING STATION t

Operating License  :

No. DPR-16  :

1 Technical Specification  !

Change Recuest No. 201, Rev. I  !

Doc (et No. 50-219 l.

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Applicant-submits, by this Technical Specification Change Request No. 201, Rev. I to the Oyster Creek Nuclear Generating' Station Technical Specifications, a proposed change to page 4.2-1. i r / -

By J. J. f arfon "

esident and Director V'eP) ster Creek ,

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SwornandSubscribedtobeforemethisQ9*k day of , 1991.

WE benyPeaseHeser / l My Commiselon tgises /d 93 t t

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91o9100004 910829 L DR ADOCK0500g9 E

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the matter ) Docket No. 50-219 GPU Nuclear Corporation )

CERTIFICATE OF SERVICE l This is to certify that a copy of Technical Specification Chan,e Request No. 201, Rev. I for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on August 29 , 1991, has this day of Auaust 29 , 1991, been served on the Major of Lacey Township, Ocean County, flew Jersey by deposit in the United States mail, addressed as follows:

The Honorable Debra Madensky I.ayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 1 /

By J. J. I;arft orf Vi e P' e:I dent and Director Oy ter Cl ok l

. 4 0YSTER CREEK NUCLEAR GENERATING STATION OPERATING LICENSE NO. DPR-16 i DOCKET NO. 50-219 .

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 201, Rev. 1 l l

t Applicant hereby requests the Commission to change Appendix A to the above {

captioned license as below, and pursuant to 10 CFR 50.91, an analysis l concerning the determination of no significant hazards considerations is also presented:  ;

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1. Section to be Chanaed l Technical Specification Sections 4.2. A, and 4.2.C.1.  !

2. Extent of Chanoo  :

Technical Specification Sections 4.2.A. and 4.2.C.1 are revised to -

delete restriction that the refueling outage interval is not to exceed 20 conths. -

3. Chanaes Reuves_ tad The requested change: are shown on attached Technical Specifications  ;

page 4.2-1.  ;

4. Purpose l

Technical Specification Section 4.2.A currently requires a control rud >

withdrawal test to demon trate that the core can be made subcritical with a margin of 0.25% A k, at any time in the subsequent cycle. This .

test is specified to be performed following a refueling outage when  !

core alterations were performed, with a clarification that this  !

criteria is not to exceed 20 months.  :

Technical Specifications Section 4.2.C.1 currently requires scram time testing of all operable control rods with reactor pressure above 800  !

psig. This test is specified to be performed after each major refueling outage and prior to resuming power operation, with a clarification that this interval is not to exceed 20 months.  ;

As stated in the current Technical Specification Section 3.2-and 4.2 Bases, the purpose of Technical Specification Section 4.2.A is to verify adequate shutdown margin for reactivity control for the subsequent operating cycle. This test is performed following a j refueling outage with the core in the cold, xenon free condition, which ensures that the criterion is satisfied for the entire subsequent fuel -

cycle. The purpose of Technical Specification Section 4.2.C.1 is to . i verify acceptable control rod scram insertion times for the subsequent >

operating cycles after refueling prior to resuming operations. Review '

of seven (7)_ control rod scram insertion time tests from 1982 to present indicates test acceptance criteria has been consistently satisfied.

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1 4.2 REACTIVITY CONTROL l Anglicability: Applies to the surveillance requircments for reactivity control.  !

Qbiective: To verify the capability for controlling reactivity.

SoecificatioJ1 .

1 A. Following a reactor refueling when core alterations were performed, sufficient control rods shall be withdrawn to den.onstrate with a margin '

of 0.25% o k that the core can be made subcritical at any time in the '

subsequent fuel cycle with t ie strongest operable control rod fully  ;

withdrawn and all other operable rods fully inserted. ,

B. The control rod drive housing support system shall be inspected after reassembly. '

C. 1. After each major refueling outage and 3rior to resuming power l ;

caeration, an operable control rods sla11 be scram time tested from ,

11e fully withdrawn position with reactor pressure above 800 psig.

2. Following each reactor scram from rated pressure, the mean 90%  !

insertion tim shall be determined for eight selected rods. If the [

mean 90% insertion time of the selected control rod drives does not ,

fall within the range of 2.4 to 3.1 seconds or the measured scram  !

time of any one drive for 90% insertion does not fall within the range of 1.9 to 3.6 seconds, an evaluation shall be made to provide reasonable assurance that proper control rod drive performance is maintained.

3. Following any outage not initiated by a reactor scram, eight rods shall be scram tested with reactor pressure above 800 psig provided these have not been measured in six months. The same criteria of 4.2.C(2) shall apply.

D. Each partially or fully withdrawn control rod shall be exercised at least once each week. This test shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event of power operation is continuing with two or more inoperable control rods or in the event power operation is continuing with one fully or partially withdrawn rod which cannot be moved and for which control rod drive mechanism damage has not been ruled out. The surveillance need not be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the number of inoperable rods has been reduced to less than two and if it has been demonstrated that control rod drive mechanism collect housing failure is not the cause of an immovable control rod.

E. Surveillance of the standby liquid control system shall be as follows:

1. Pump operability 0nce/ month

2. Boron concentration 0nce/ month determination Corrected: 12/24/84 0YSTER CREEK 4.2-1 Amendment No.: 13, 75, 144 l

.be J These results confirm that control rod scram insertion time does not

- n v . r. , significantly degrade with operating cycle length. Additionally,

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Technical Specification Section 4.2.D requires that each partially or

• N fully withdrawn control rnd be exercised at least once each week. This surveillance serves as a periodic check agatast deterioration of the

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'gs. control rod system and provides additional assurance of control rod operability.

C Yhe 20 month surveillance interval restriction for these tests is not

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d NM.) relevant since the purpose of these tests is to verify acceptable 4f reactivity contro; parameters, following refueling activities for the st.bsequent operating cycle. Therefore, the proposed change to delete this restriction has no effect on tne requirements for reactivity

,fe;,;+ c' for the subsequent operating cycle. This change does not tivolve any change to the actual surveillance requirements, ner does it

involve any change to the limits and restrictiore on plant operations. The reliability of systems and components relied upon

o prevent or mitigste the consequences of accidents previoutly avaluated is not 6 graded, Assurance of cdequate reactivity centrol for the subsequent operating cycle is maintained. This _

change does not involve anv change to system or muipr.nnt configuration. Therefore, th's chang does ,at increase the probability of occurrence or the :enser:ecces of an Occident previously evaluated.

2. Operation of the facility in accordance with the propt ri amendment would not create the possibility of a new or .ti.fferent kind of accident from any accident previously evaluated. The proposed amendment removes the 20 month interval restriction on survillance perhrmed following refueling activities which verify acceptable reactivity control for t'ne subsequent operating cycle.

This change does not invola any change to the actual surveillance requirements, nor does it '.n w;ve any change to the limits and restrictions on plant operation. This change does act involve r ~

change to system or equipment configuration. Assurance of adequate reactivity control for the subsequent operating cycle is a maintained.

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3. Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety. The proposed amendment removes the 20 month interval restriction on surveillance performed following refueling i

activities which verify acceptable reactivity control for the subsequent operating cycle. This change does not involve any change to +he actual survei.!ance requirements, nor does it involve an, .hange to the limits and restrict 4.aqs on plant

, operation. The reliability of syst ems a,$d components is not degraded. Assurance of adequate ra activity control for the

subsequent operating cycle is maintained. Therefore, it is concluded that operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety.

The proposed deletion of the 20 month interval restriction is not relevant to the purpose of the Technical Specification surveillance. Implementation of the proposed amendment will maintain the required level of assurance of adequate reactivity control for subsequent operating cycle. Thus, operation of the facility in accordance with the proposed amendment involves no

< significant hazards considerations.

6.0 IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon issuance.

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