ML20086K500
| ML20086K500 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 07/17/1995 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20086K501 | List: |
| References | |
| NUDOCS 9507200172 | |
| Download: ML20086K500 (2) | |
Text
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ZG Southem Califomia Edison Company P. O. 80x 128 SAN CLEM ENTE, CALIFORNIA 92674 0128 RICHARD M. ROSEN8 LUM TELEpMONE July 17, 1995 m......
m u.mo U. S. Nuclear Regulatory Commission g
Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Proposed Technical Specification Change NPF-10/15-434 San Onofre Nuclear Generating Station Units 2 and 3
Reference:
December 30, 1992, letter from Harold B. Ray (Southern California Edison (Edison)) to USNRC Document Control Desk;
Subject:
Docket Nos. 50-361 and 50-362, Amendment Application Nos. 129 and 113; Change to Technical Specifications 3/4.3.2 and 3/4.3.3; San Onofre Nuclear Generating Station Units 2 and 3 Enclosed are e /ndment Application Numbers 139 and 123 to Facility Operating Licenses W and NPF-15 for San Onofre Nuclear Generating Station Units 2 and 3, respo..valy.
The Amendment Applications consist of Proposed Technical Specification Change Number NPF-10/15-434 (PCN-434).
PCN-434 is provided as to this letter.
The proposed change is to revise surveillance requirements associated with Technical Specification 3/4.3.1, " Reactor Protective Instrumentation," and Technical Specification 3/4.3.2, " Engineered Safety Feature Actuation System Instrumentation." The surveillance interval is to be increased to 120 days for performance of channel functional tests for certain Reactor Protective System (RPS) and Engineered Safety Feature Actuation System (ESFAS)
Instrumentation. The proposed change also revises Bases 3/4.3.1, " Reactor Protective and Engineered Safety Features Actuation System Instrumentation,"
to reflect the new interval.
The current quarterly surveillance interval for functional units of both the RPS and ESFAS is based on an analysis presented in Combustion Engineering Owners Group Topical Report CEN-327-A including Supplement 1.
Based on CEN-327-A, Southern California Edison (Edison) asked Combustion Engineering to provide a document specifically for San Onofre Units 2 and 3 which would extend RPS and ESFAS Channel Functional Testing (CFT) intervals from 3'l-day sequential testing and 90-day sequential testing to 120-day staggered testing.
In addition, to fully realize the benefits of this further RPS/ESFAS CFT interval extension, Edison commissioned Pickard, Lowe and Garrick, Inc. to perform a plant specific nuclear instrumentation system unavailability study to support extension of the Nuclear Instrumentation excore detectors monthly i
verifications to 120 days. Edison reviewed the Plant Protective System trip j
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setpoints to determine those that might be impacted by the increased surveillance interval and evaluated each of those setpoints to determine if changes were required. A detailed discussion of each of the above evaluations and their results is provided in the enclosure.
Increasing the channel functional test surveillance interval for these RPS and ESFAS instrumentation channels has four principle benefits: 1) RPS and ESFAS system unavailability will be decreased, 2) the potential for inadvertent ESFAS actuation and reactor trip will be decreased, 3) burdens on plant personnel involved in performing channel functional tests will be reduced significantly, and 4) there will be a significant cost savings.
This amendment request is expected to result in a total present worth savings of over $1,000,000 for the two units over the lifetime of the plant.
Because of this significant savings this submittal is being submitted as a Cost Beneficial Licensing Action (CBLA). to this letter provides a cost benefit analysis which demonstrates this savings.
The reference (PCN-405) also requested changes to portions of Technical Specifications 3/4.3.1 and 3/4.3.2. The proposed changes from this amendment request (PCN-434), including affected pages from the reference (PCN-405), are provided as Enclosure 6.
If you have any questions regarding this amendment application, please contact me.
~
Sincerely, hY Enclosures cc:
L. J. Callan, Regional Administrator, NRC Region IV A. B. Beach, Director, Division of Reactor Projects, 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 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 H. Kocol, California Department of Health Services
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