ML20036A034
| ML20036A034 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/30/1993 |
| From: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20036A035 | List: |
| References | |
| NUDOCS 9305070276 | |
| Download: ML20036A034 (4) | |
Text
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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
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Gentlemen:
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Subject:
Docket No. 50-362 1
Supplement to Amendment Application No.l102 ; imits j
Reactor. Coolant. System Pressure / Temperature L Changes to Technical' Specifications 3/4.4.8.1, l
3.4.8.3.1', and 3.4.8.3.2 i
San Onofre Nuclear Generating Station i
Unit 3 i;j
References:
(See Enclosure =1) l
.Provided as Enclosure 2 is a supplement to Proposed Change Number (PCN)-359/'
Amendment Application No.102 to Facility Operating License NPF-15 for the San.
Onofre Nuclear Generating Station (SONGS), Unit 3.. This supplement supersedes-1 in.its entirety our submittal of Reference 5.
This supplement ~ revises Technical ' Specifications. (TSs) 3/4.4.8.1, " Pressure / Temperature' Limits'" ~
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~3.4.8.3.1, " Overpressure Protection Systems-RCS Temperature 5302*F," and-3.4.8.3.2,: " Overpressure' Protection Systems-RCS Tem)erature >302*F." -
i Editorial corrections are also being made to make tie Unit 3.TSs consistent with'the Unit 2 TSs.
Reference 1 transmitted the_. test and analysis results of the Unit 31 reactor r
vessel surveillance ~ capsule specimen which was-removed in May.1990. after 4.33 i
Effective: Full' Power Years (EFPY).of operation. -The~new Unit 3' Pressure.
< Temperaturet (P-T) limits identified in this proposed change were calculated
' based upon the test and analysis results of th' Unit.3-surveillance capsule, e
- and updated material properties identified in References 6 and 7.
q By Reference 8 Southern California Edison.(SCE) informed:the NRC that -
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~ dministrative P-T limits which.are:more.-restrictive than the P-T limits from 1
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- the existing' calculations oferecord have been: implemented at San Onofre Units.
!2 and'3 while the calculations of record:were being reevaluated. :Theiresults 1
of our reevaluation concluded that the new Unit 3 P-T limits:in this proposed _
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l Document Control Desk change are less restrictive than the administrative P-T limits currently in effect at Unit 3.
SCE will continue to implement the existing Unit 3 administrative P-T limits until the NRC approves this license amendment request.
The proposed change revises existing P-T limit curves (Figures 3.4-2, 3.4-4, and 3.4-5), deletes Figure 3.4-3, and adds new curves (Figures 3.4-6 and 3.4-Figure 3.4-3 is deleted because there are now only two heatu 7).
restrictions, i.e., 50*F/HR with the Reactor Coolar.t System (RCS)p ratecold leg temperature less than or equal to 159 F, or the maximum permitted heatup rate of 60 F/HR with the RCS cold leg temperature greater than 159'F.
Figures 3.4-6 and 3.4-7 account for the difference in the Total Loop Uncertainties (TLUs) for pressure between the shutdown instruments on the Remote Shutdown Panels and the shutdown instruments in the Control Room. The TLUs for temperature i
for both the Remote Shutdown instruments and the Control Room shutdown instruments are equal.
The proposed change also revises the Shutdown Cooling System (SDCS) enable temperature for RCS Low Temperature Overpressure Protection (LTOP) in TSs 3.4.8.3.1, 3.4.8.3.2, and Table 3.4-3, " Low Temperature Overpressure Protection Range." The enable temperature for the SDCS Relief Valve is based on the methodology recommended by NUREG-0800, Branch Technical Position RSB 5-2, Revision 1, "0verpressurization Protection of Pressurized Water Reactors While Operating at Low Temperatures." This license amendment request fulfills the commitment in Reference 2 to revise the existing Unit 3 LTOP enable temperatures.
The proposed P-T limits and LTOP enable temperatures shall be effective until 8 EFPY of plant operation.
l By Reference 2 (PCN-358) and Reference 3 (PCN-354), changes were proposed to other portions of TS Index Page XIX, TSs 4.4.8.1.2, 3.4.8.3.1, and the associated Bases to TS 3/4.4.8.
Because these TSs are also affected by this proposed license amendment (PCN-359), TS pages which incorporate changes from PCNs 358, 354, and this revision to PCN-359 are provided for your information as Enclosure 3.
The proposed changes are identified by their respective PCN numbers in the margin.
By Reference 4, SCE submitted the Units 2 and 3 current values (current as of September 11,1992) and projected values of reference temperatures for pressurized thermal shock (RTns) required by 10 CFR 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock."
l Reference 4 fulfills the 10 CFR 50.61 requirements for San Onofre Unit 3.
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Document Control Desk If you have any questions regarding this TS change request, please let me know.
i Sincerely, E
I Enclosures cc:
J. B. Martin, Regional Administrator, NRC Region V C. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2, and 3 M. B. Fields, NRR Project Manager, San Onofre Units 2 and 3 H. Kocol, California Department of Health Services-a b
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REFERENCES 1.
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 j
2.
December 20, 1991 letter from Harold B. Ray (SCE) to Document Control Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, l
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 i
Nuclear Generating Station, Units 2 and 3 3.
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 r
4.
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 Shock, Reactor Vessel Beltline Materials, San Onofre Nuclear Generating Station, Units 2 and 3 5.
September 9,1992 letter from Harold B. Ray (SCE) to Document Control Desk (NRC),
Subject:
Docket No. 50-362, Amendment 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 6.
July 6,1992 letter from R. M. Rosenblum (SCE) to Document Control L
Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR 50.54(f)," San Onofre Nuclear Generating Station, Units'2 and 3 i
I 7.
January 29, 1993 letter from Walter C. Marsh (SCE) to Document Control Desk (NRC),
Subject:
Docket 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 8.
December 2, 1992 letter from Walter C. Marsh (SCE) to Document Control Desk (NRC),
Subject:
Docket Hos. 50-361 and 50-362, Proposed License Amendments to Update the Pressure-Temperature Limits and Low Temperature Overpressure Protection Enable Temperatures,. San Onofre Nuclear Generating Station, Units 2-and 3 i
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