ML20205B273

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 158,revising Section 3.3.D.1.c to Limit Unidentified Leakage for RCS to Max Leak Rate Increase of 2 Gpm within Any 24 H Period While Operating at steady-state

ML20205B273
Person / Time
Site:	Oyster Creek
Issue date:	03/17/1987
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20205B250	List: ML20205B245 ML20205B273 ML20205B276
References
NUDOCS 8703270579
Download: ML20205B273 (4)

Text

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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION l Provisional Operating l License No. DPR-16 Technical Specification Change Reauest No. 151 Docket No. 50-219 Applicant submits, by this Technical Specification Change Reauest No.' 158

to the Oyster Creek Nuclear Generating Station Technical Specifications, a

! change to page 3.3-2.

By - 'J l Petfr u. riedler Vice President and Director Oyster Creek j Sworn and Subscribed to before me this /M day of 4Ad4 1987.

k- d'A A Notary Public of NJ Ex pia an 6/s/9i 1

B703270579 870317 PDR ADOCK 05000219 p PDR

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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 Reauest No. 158 for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Connission on March 17, 1987 , has this day of March 17, 1987 , been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By - -

N Pete G . 7 Edler' Vice President and Director Oyster Creek 16929

OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET N0. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST h0. 158 Applicant hereby requests the Commission to change Appendix A to the above captioned license as below, and pursuant to 10CFR50.91, an analysis concerning the determination of no significant hazards considerations is also presented:

1. Section to be Changed Section 3.3

2. Extent of Change Revise Section 3.3.D.l.c to limit the unidentified leakage for the reactor coolant system to a maximum leak rate increase of 2 gpm within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while operating at steady state power.

3. Changes Requested The requested change is shown on attached Technical Specification page 3.3-2.

4. Discussion By a letter dated September 5, 1986, the NRC requested GPU Nuclear (GPUN), the licensee for the Oyster Creek Nuclear Generating Station (OCNGS) to justify its Technical Specification (TS) requirements (TS3.3D.l.c) for unidentified leakage against the requirements of Generic Letter (GL) 84-11, attachment 1, item B. Briefly, OCNGS TS3.3D.l.c states that reactor coolant system leakage shall be limited to a 2 gpm increase in unidentified leakage rate within any 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period while operating at steady state power. GL 84-11 states that a maximum increase in unidentified leakage of 2 gpm within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while operating would be sufficiently restrictive to ensure timely investigation of potential through-wall cracks in austenitic stainless steel piping.

GPUN agrees that the OCNGS TS3.3D.1.c for the unidentified leakage is not as restrictive as the requirements of GL 84-11 and is proposing this amendment to revise the time interval from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Since this proposed amendment increases the time interval for the same flow rate (2 gpm), this change places a more restrictive requirement on the maximum allowable rate of increase for the unidentified reactor coolant system leakage.

This proposed change would increase the margin of safety through more restrictive limiting conditions of operation for the unidentified reactor coolant system leakage.

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Likewise, the more restrictive limiting conditions of operation would provide for the timely detection of potential cracks, and would decrease the probability of a design basis loss-of-coolant accident.

5. Determination Based upon the hereinbefore discussion, we have evaluated that this change request involves no significant hazards considerations. In sumary, we have determined that the proposed amendment would not:

a. Involve a significant increase in the probability or consequences of an accident previously evaluated; This proposed change would place more restrictive limiting conditions of operation for the unidentified reactor coolant system leakage which provides for the timely detection of potential through-wall cracks in austenitic stainless steel piping. By this timely detection the probability of a design basis loss-of-coolant accident would decrease. This proposed change would not have any effect on the consequences of the design bases accidents previously evaluated,

b. Create the probability of a new or different kind of accident from any accident previously evaluated; This proposed change only places more restrictive limiting conditions of operation for the unidentified reactor coolant system leakage, so this proposed change does not create the probability of a new or different kind of accident.

c. Involve a significant reduction in a margin of safety; This proposed change would increase the margin of safety by the initiation of timely actions for the detection of potential through-wall cracks in austenitic stainless steel piping, and thereby reduces the probability of a design basis loss-of-coolant accident.

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