ML20104B154
| ML20104B154 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/09/1992 |
| From: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20104B156 | List: |
| References | |
| NUDOCS 9209150012 | |
| Download: ML20104B154 (4) | |
Text
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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-362 h end=ent Application No. 102 Changes to Technical Specifications 3/4.4.8.1, 3.4.8.3.1, and 3.4.8.3.2 San Onofre Nuclear Generating Station Unit 3
References:
1)
May 3, 1991 letter from F. R. aandy (SCE) to Document Control Desk (NRC),
Subject:
Docket No. 50-362, Surveillance Capsule Test Report, San Onofre Nuclear Generating Station, Unit 3 2)
December 20, 1991 letter from Harold B. Ray (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Amendment Application Nos.113 and 97, Changes to Technical Specifications 3/4.4.8.3.1, 3/4.1.2.3 and 3/4.5.3, San Onofre Nuclear Generating Station, Units 2 and 3 f
3)
September 9, 1992 letter from R. M. Rosenblum (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Reference Temperatures for Pressurized Thermal i
Shock, Reactor Vessel Beltline Materials, San Onofre Nuclear Generating Station, Units 2 and 3 Provided in Encloture 1 is Amendment Application No. 102 to Facility Operating This amendment applic3 tion consists of Proposed Change Number (PCN))359. Lice PCN-359 is a request to revise Technical Specification (TSs) 3/4.4.8.1,
' Pressure / Temperature Limits," 3.4.8.3.1 " Overpressure Protection Systems-RCS Temperature 5302*F," and 3.4.8.3.2, "Overpr?ssure Protection Systems-RCS Temperature >302'F."
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PDR ADOCK 05000362 jt P
y Document Control Desk
- Reference 1 transmitted the test and analysis results of the Unit 3 reactor sen el surveillance capsule specimen which was removed in May 1990 after 4.33 Effective full Power Years of operation.
By Peference 1, the NRC was advised that the existing Unit 2 Pressure-Temperature (P-T) limits were being implemented at Unit 3 until the new Unit 3 P-T limits were ap) roved by the NRC. The new Unit 3 P-T limits identified in this proposed c1ange were calculated based upon the test and analysis results of the Unit 3 surveillance capsule and updated material properties identified in our July 6,1992 response to Generic letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR 50.54 (f)." The new Unit 3 P-T limits are significantly more restrictive than what is currently being used at Unit 3.
Therefore, by October 10, 1992, the P-T limits in this proposed change will be administratively implemented at Unit 3 until the NRC approves this license amendment request.
The proposed change res!ses 1) the Reactor Coolant System (RCS) P-T limit curves based on the test results of the Unit 3 surveillance capspie analysis, and 2) the Low Temperature Overpressure Protection (LTOP* system enable j
temperature based on the methodology for determining Li TP enable temperaturer recommended by NUREG-0800 Branch Technical Position RSB 5-2, Revision 1, "0verpressurization Protecticn of Pressurized Water Reactors While Operating at low Temperatures."
The proposed change also adds new P-T limit curves (Figures 3.4-6 and 3.4-7) for Remote Shutdown cooldown operation.
These two new curves account for the difference in Total Loop Uncertainties (TLUs) for pressure between Remote Shutdown instruments and the Control Room shutdown instruments.
The TLUs for temperature for both the Remote Shutdown instruments and the Control Room shutdown instruments are identical.
The proposed P-T limits and the LTOP enable temperatures shall be effective until 8 effective full power years (EFPY) of operation.
By Reference 2 changes to other portions of TS 3.4.8.3.1 were proposed (see for the TS 3.4.8.3.1 pages affected by both Reference 2 (PCN-358) and this PCN-359]. This license amendment request fulfills the commitment in Reference 2 to revise the existing Unit 3 LTOP enable temperatures. A proposed license amendment will be submitted by October 30, 1992, to request a revision to the Unit 2 LTOP enable temperatures to satisfy the Unit 2 commitment in Reference 2.
As required by 10 CFR 50.61. " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock," paragraph (b)(1), by Reference 3 we are submitting the current and projected va' lues of Reference Temperatures for Pressurized Thermal Shock (RTns).
Document Control Desk
- If you have any questions regarding this TS change request, please let me know.
Very truly yours.
Enclosures cc:
J. D. Martin, Regional Administrator, NRC Region V C. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2, and 3 H. B. Fields. NRR Project Manager, San Onofre Units 2 and 3 R. H. Hickman, California Department of Health Services P
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P ENCLOSURE 1-PROPOSED CHANGE NPF-15-359 UNIT 3
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