ML20073T072
| ML20073T072 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/06/1994 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20073T077 | List: |
| References | |
| NUDOCS 9407080151 | |
| Download: ML20073T072 (4) | |
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Southem Califomia Edison Company 23 PAwmE R STREET RsCHAND M. RCSteestuM S t L t ***o"8 July 6, 1994 ..c,........ m.. ..o V. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 -Gentlemen:
Subject:
Docket No. 50-362 Supplement 2 to Amendment Application No. 102 Reactor Coolant System Pressure / Temperature Limits 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:
(See Enclosure 1) Provided as Enclosure 2 is Supplement 2 to Amendment Application No.102 to Facility Operating License NPF-15 for the San Onofre Nuclear Generating Station, Unit 3. Supplement 2 revises Proposed Change Number PCN)-359 (Reference 1). PCN-359 revises Technical Specifications (TSs)(3/4.4.8.1, " Pressure / Temperature Limits," 3.4.8.3.1, "Overpressuro Protection Systems-RCS Temperature s302*F," and 3.4.8.3.2, " Overpressure Protection Systems-RCS Temperature >302'F." Supplement 2 to Amendment Application No. 102 is being submitted because 1) theexistingUnit3 Pressure / Temperature (PT)limitsandLowTemperature Overpressure Protection (LTOP) enable temperatures will expire at 8 Effective Full Power Years (EFPY) in November 1994 and 2) the PT limits and LTOP enable temperatures included in the license amendment request submitted by Reference 1 also expire at 8 EFPY. Supplement 2 revises the PT limits and LTOP enable temperatures to be effective until 20 EFPY. As in Re:~erence 1, The new Unit 3 PT limits in this proposed change were calculated based upon 1) the predicted fluence values from the Unit 3 surveillance capsule (Reference 2) removed after 4.33 EFPY, 2) updated Unit 3 material properties in response to C ric Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR Sv.. f) " (References 3, 4, and 5), and
- 3) methodologies previously reviewed and approved by the NRC.
The only difference is that the 8 EFPY curves previously submitted in Reference 1 were based on an overly conservative initial RTg for the limiting plate material. The 20 EFPY curves in this proposed change were developed using an initial RT which was determined in accordance with the 1986 edition of ASME Section m 111 Code,SectionNB-2331(a)(3)andconsistentwithSectionC.1.1of 9407080151 94o706 -{'
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Document Control Desk Regulatory Guide 1.99, Revision 2. The new LTOP enable temperatures were based on the methodology recommended in Branch Technical Position RSB 5-2, Revision 1, "0verpressurization Protection of Pressurized Water Reactors While Operating at low Temperatures." By Reference 6 (PCN-354), Southern California Edison (Ste.; proposed changes to other portions of TS Index Page XIX, ISs 4.4.8.1.2, and the associated Bases to TS 3/4.4.8. Because these TSs are also affected by thi
- -oposed license amendment (PrN-335), TS pages which incorporate changes from PCN-354 and PCN-359 are provided for your information as Enclosure 5.
The proposed changes are identified by their respective PCN numbers. SCE informed the NRC in Reference 1 that administrative PT limits which were more restrictive than the PT 1*9its proposed in Reference 1 were implemented at Unit 3. SCE will continue this conservative approach and use the same administrative limits until the NRC approves this license amendment request. This is acceptable since the PT limits in this proposed change were also found to be less restrictive than the existing administrative limits in all areas that the plant normally operates or would be expectt.d to operate. If you have any questions regarding this TS change request, please let me know. Sincerely, lQagicWl,.,e /l: ~) l GlG.]. [- Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Ffeld Office, 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. Koc.ol, California Department of tiealth Services
REFERENCES 1. April 30, 1993, letter from Harold B. Ray (SCE) to Document Control Desk (NRC),
Subject:
Docket No. 50-362, Supplement :s Amendment Ap)lication No. 102, Reactor Coolant System Pressure / Temperature Limits, C1anges 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 2. May 3, 1991, letter from F. R. Nandy (SCE) to Document Control Desk (NRC),
Subject:
Docket No. 50-362, Surveillance Capsule Test Report, San Onofre Nuclear Generating Station, Unit ? 3. July 6, 1992, letter from R. M. Rosenblum (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Generic Letter 92-01, Revision " Reactor Vessel Structural Integrity,10 CFR 50.54(f)," San Onofre Nuclear Generating Station Units 2 and 3 4. January 29, 1993, let er from Walter C. Marsh (SCE) to Document Control Desk (NRC),
Subject:
Dot.ket Nos. 50-361 and 50-362, Supplemental Response to Generic Letter 92-01, Revision 1 " Reactor Vessel Structural Integrity, 10 CFR 50.54(f)," San Onofre Nuclear Generating Station, Units 2 and 3 5. June 22, 1994, letter from Walter C. Marsh (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Revision to Supplemental Response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR 50.54(f)," San Onofre Nuclear Generating Station, Units 2 and 3 6. September 3,1992, letter from Harold B. Ray (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Proposed Technical Specification Change No. NPF-10/15-354, San Onofre Nuclear Generating Station, Units 2 and 3 l i
4 ENCLOSURE 2 i SUPPLEMENT 2 TO PROPOSED CHANGE NPF-15-359 UNIT 3 ., _.}}