ML20072L470

TS Change Request 220 to License DPR-16,updating & Clarifying SRs for Control Rod Exercising & Standby Liquid Control Pump Operability Testing to Be Consistent W/Generic Ltr 93-05

ML20072L470
Person / Time
Site:	Oyster Creek
Issue date:	08/19/1994
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20072L463	List: ML20072L459 ML20072L470 ML20072L474
References
GL-93-05, GL-93-5, NUDOCS 9408310310
Download: ML20072L470 (5)

Text

_. - - _. _ .-

l l

GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION Facility Operating Licerise No. DPR-16 Technical Specification Change Request No. 220 Docket No. 50-219

)

Applicant submits, by this Technical Specification Change Request.No. 220'to i the Oyster Creek Nuclear Generating Station Operating License, proposed changes to pages 4.2.-1 and 4.2-3.

i

- ~ l By kpfC,J.J.Bartob N Vice President and Director Oyster Creek 4

Sworn and Subscribed to before me this / f day of 1994.

otary Public of NJ -

JUDITH M. CROWE Notary Public of NewW MyCommission Expires //@f / 4I a 9

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the matter of ) Docket No. 50-219  ;

GPU Nuclear Corporation )

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 220 for Oyster Creek Nuclear Generating Station Operating License, filed with the U.S. Nuclear Regulatory Commission on August 19, 1994, has this day of August 19, 1994, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Theodore J. Hutler Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By J. JT Ta'rton N '

Vice President and Director Dyster Creek

I Page 1 of 3 OYSTER CREEK MUCLEAR GENERATING STATION FACILITY OPERATING LICENSE NO. DPR-16 l DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 220 GL 93 Tech Spec Improvements Applicant hereby requests the Commission to change Appendix A to the above i captioned license as indicated below, and pursuant to 10 CFR 50.92, an analysis concerning the determination of no significant hazards considerations is also .

presented. l 1.0 SECTION TO BE CHANGED Section 4.2.D 4.2.E.1, and 4.2 bases.

2.0 EXTENT OF CHANGE Update and clarify Technical Specification 4.2.0, 4.2.E.1 and 4.2 bases to ,

be consistent with Generic Letter 93-05, line-item Technical Specifications Improvements to reduce surveillance requirements for testing during Power Operation.  ;

This TSCh would change the requirement to exercise all control rods daily in the event of continued operation with one immovable or two or more inoperable control rods. Control rods would only be required to be exercised within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the condition of one immovable or two inoperable control rods and then be exercised weekly thereafter.

Also this TSCR would change the requirement of performing the standby liquid control system pump operability surveillance on a monthly frequency to quarterly.

3.0 CHANGES REQUESTED  :

The requested changes are shown on attached Technical Specification pages 4.2-1 and 4.2-3. ,

i 4.0 DISCUSSION GL 93-05 enclosure 1, provides guidance for preparing a license amendment request to change the Technical Specifications (TS) to reduce testing during power operation. These line-item TS improvements are based on the recommendations of a U.S. Nuclear Regulatory Commission (NRC) study that included a comprehensive examination of surveillance requirements and is reported in NUREG-1366, " Improvements to Technical Specifications Surveillance Requirements" December 1992.

Page 2 of 3 4.0 DISCUSSION - (Cont'd)

The NRC staff encourages licensees who plan to adopt these line-item TS improvements to propose TS changes that are consistent with GL 93-05 guidance. Also, licensees should not propose changes to extend any surveillance interval if the recommendations of NUREG-1366 are not compatible with plant operating experience.

The proposed revision to the Control Rod Drive (CRD) exercise requirement is compatible with plant operating experience and GL 93-05 guidance. Only one instance of required daily testing in the last seven years was identified. This exercise testing occurred during three consecutive days while two control rods were declared inoperable for maintenance activities. No other control rods were identified as being inoperable during this exercise testing. Existing TS 4.2.0 replaced "at least once per" with "within" that is identical to GL 93-05 guidance. Also a typo on the word " collet" was identified and corrected.

The existing TS 4.2 Bases was also changed to update and clarify the requirement to exercise the control rods so as to provide consistency with the proposed surveillance frequency.

The proposed revision to the Standby Liquid Control (SLC) pump operability requirement is compatible with plant operating experience and GL 93-05 guidance. No instances of either pump failing its surveillance testing criteria in the last five years was identified. Existing TS 4.2.E.1 replaced " month" with "3 months" that is consistent with GL 93-05 guidance.

5.0 DETERMINATION We have determined that the proposed technical specification changes include no significant hazards consideration as discussed below.

1. Although the surveillance requirements are lessened by these proposed changes, the changes are consistent with those found acceptable by the NRC in GL 93-05. The proposed changes have been determined to be compatible with our plant operating experience.

Based on these considerations, it is concluded that the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. The proposed changes do not involve physical changes to the plant or changes in plant operating configuration. The changes only involve frequency of testing required to be performed. The changes are consistent with those found acceptable by the NRC in GL 93-05. )

Thus, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

l 1

Page 3 of 3 1

3. Although the surveillance requirements are lessened by these l proposed changes, the changes are consistent with those found acceptable by the NRC in GL 93-05. The proposed changes have been determined to be compatible with our plant operating experience.

Based on these considerations, it is concluded that the changes do not involve a significant reduction in a margin of safety.

6.0 IMPLEMENTATION We request that the amendment authorizing this change become effective 60 days after issuance.

1