ML20205B276

Proposed Tech Specs 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 Power

ML20205B276
Person / Time
Site:	Oyster Creek
Issue date:	03/17/1987
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20205B250	List: ML20205B245 ML20205B273 ML20205B276
References
NUDOCS 8703270581
Download: ML20205B276 (3)

Text

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D. Reactor Coolant System Leakage

1. Reactor coolant system leakage shall be limited to:

a. 5 gpm unidentified leakage

b. 25 gpm total (identified and unidentified)

c. 2 gpm increase in unidentified leakage rate 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

2. With the reactor coolant system leakage greater than the limits in 3.3.0.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. With any reactor coolant leakage greater than the limit in 3.3.D.l.c above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in the shutdown, condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. For determination of unidentified leakage, the primary containment sump flow monitoring system shall be operable except as specified below:

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a. With the primary containment sump flow integrator inoperable:

1. Restore it to operable status within 7 days.

2. Calculate the unidentified leakage rate utilizing an acceptable alternate means as specified in plant procedures,

b. If Specification 3.3.D.4a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

5. For determination of identified leakage, the primary containment eauipment drain tank monitoring system shall be operable except as specified below:

a. With the primary containment eauipment drain tank monitoring system inoperable:

1. Restore it to operable status within 7 days.

2. Calculate the identified leakage rate utilizing an acceptable alternate means as specified in plant procedures,

b. If Specification 3.3.0.5.a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

0YSTER CREEK 3.3-2 8703270581 870317 PDR ADOCK 05000219 p PDR 16920

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QPU Nuclear Ngg f 100 Interpace Parkway Parsippany. New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:

March 17, 1987 The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, New Jersey 08731

Dear Mayor Connors:

Enclosed herewith is one copy of Technical Specification Change Request i

No. 158 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on March 17, 1987 .

Very truly yours,

, h, 3

. Fiedler f Vice President and Director Oyster Creek PBF/DJ/pa(16929)

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l 16929 GPU Nuclear is a part of the General Pubhc Utilities System

OPU Nuclear NUCIMF 100 Interpace Parkway Parsippany New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:

March 17, 1987 Mr. David M. Scott, Acting Chief Bureau of Nuclear Engineering Department of Environmental Protection CN411 Trenton, New Jersey 08625

Subject:

Oyster Creek Nuclear Generating Station Provisional Operating License No. OPR-16 Technical Specification Change Request No. 158 Pursuant to 10CFR50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Commission on March 17, 1987 .

l Very truly yours, GAL.

Puter 8. Fiedler Vice President and Director Oyster Creek PBF/DJ/pa(16929 )

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16929 GPU Nuclear is a part of the General Public Utilities System

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