ML20071K865

Forwards Amend Applications 141 & 125 to Licenses NPF-10 & NPF-15,respectively,revising TS 3.9.8.1 & 3.9.8.2 & Bases Re Shutdown Cooling & Coolant Circulation

ML20071K865
Person / Time
Site:	San Onofre
Issue date:	07/28/1994
From:	Rosenblum R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20071K869	List: ML20071K865 ML20071K877 ML20071K897
References
NUDOCS 9408020060
Download: ML20071K865 (2)

Text

r-L Southem Califomia Edison Company 23 PARME R ST RE ET IRVIN E, CA LIFORNI A 92718

"***".1..".,"*'" July 28, 1994 O I'o V. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Amendment Application Nos. 141 and 125 Change to Technical Specification 3.9.8.1 " Shutdown Cooling and Coolant Circulation -- High Water Level," Technical Specification  ;

3.9.8.2, " Shutdown Cooling and Coolant Circulation -- Low Water Level," and the Refueling Operations, Bases: 3/4.9.8, " Shutdown Cooling and Coolant Circulation" San Onofre Nuclear Generating Station Units 2 and 3 Enclosed are Amendment Application Numbers 141 and 125 to facility Operating Licenses NPF-10 and NPF-15, respectively, for the San Onofre Nuclear Generating Station Units 2 and 3. These amendment applications consist of Enclosure 1, Proposed Ch nge Number 402 (PCN-402), and are requests to revise Technical Specification (TS) 3.9.8.1 TS 3.9.8.2, and their Bases. Also ,

provided is Enclosure 2, the proposed changes for the Technical Specification Improvement Program (PCN-299) Technical Specifications.

The purpose of TS 3.9.8.1 and TS 3.9.8.2 is to ensure that: 1) sufficient cooling is available to remove decay heat from the Reactor Coolant System, 2) water in the reactor vessel is maintained below 140*F, and 3) sufficient i coolant circulation is maintained in the reactor core to minimize boron ,

stratification leading to a boron dilution incident.

While not affecting the purpose of the TSs PCN 402 requests changes which will facilitate testing of hw Pressure Safety Injection System components and will permit additional flexibility in scheduling maintenance on Ge shutdown cooling system. These changes will provide time savings during votages without compromising plant safety and, as such, are identified as a Cost Beneficial Licensing Action (CBLA).

The specific requests made by PCN-402 are as follows:

1) reduce the water level where two trains of shutdown cooling (SDC)  !

are required from 23 feet to 20 feet above the reactor pressure vessel flange,

2) increase the time a required train of the SDC system may be removed from service from up to I hour per 8-hour period to up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour periM,

3) allow the SDC system to be removed from service to allow testing of

- Low Pressure Safety Injection system components, U.,:.000*i 940so2006o 94o72s 0(;

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r[,5 Document Control Desk 4) allow for running 1 train of shutdown cooling with additional requirements when the water level is less than 20 feet but greater than 12 feet above the reactor pressure vessel flange,

5) add an action to be taken when operating 1 train of SDC with less than 20 feet of water above the reactor. pressure vessel flange when the specified requirements are not met,

6) delete the obsolete reference to the implementation of DCP 2-6863 and MMP 3-6863, and

7) delete an obsolete footnote allowing removal of both trains of SDC with the water _less than 23 feet above the reactor vessel flange from the Unit : TSs.

Parts of this request for a TS change were made possible due to the recent design change which allows us to cross tie the SDC system with the containment spray system. The NRC approved the cross tie design change by License Amendments 106 and 95 for Units 2 and 3, respectively. Now that this capability exists, cost savings due to reduced outage times are possible. The proposed changes will allow the required maintenance and testing to be scheduled and performed in a cost effective way saving Southern California Edison (Edison), et al., approximately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (approximately $800,000) of l critical path time in the Cycle 8 refueling outage for each Unit. A similar savings is anticipated for future outages.

This amendment application is identified as a CBLA. Therefore, priority review and approval of this amendment application is requested. Edison requests approval by December 31, 1994, to support the San Onofre Unit 2 refueling outage which is anticipated to begin in January of 1995. Edison would like to schedule a meeting to discuss this PCN with the NRC in late August or early September, so that any questions can be addressed and resolved expeditiously.

If you need additional information on this Technical Specification change request, please let me know.

Sincerely, l m u. L Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 H. Kocol, California Department of Health Services l

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