ML20202F126
| ML20202F126 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/01/1997 |
| From: | Rainsberry J SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-361-97-11, 50-362-97-11, NUDOCS 9712090021 | |
| Download: ML20202F126 (6) | |
Text
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50df Hf RN CALHORNR H
EDISON LC"thn, An IPISO418T1X%tTIOy Al
- Congwn December 1, 1997 U.S. Nuclear Regulatory Commission l
Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Revision of Table 1 of the Safety Evaluation Report for Amendments 127 and 116 for Units 2 and 3 respectively San Onofre Nuclear Generating Station Units 2 and 3
Reference:
1)
NRC Inspection Report 50-361/97-11;50-362/97-11, San Onofre Nuclear Generating Station Units 2 and 3 2)
Telecon notes between Mr. Brian Woods, SCE, and Mr. T. R. Tjader, NRC Review Coordinator of Technical SpecificationBranch,9/10/95 An NRC inspection was conducted June 2-13, 1997 at San Onofre Nuclear Generating Station, Units 2 and 3.
This inspection included the licensee's implementation of Improved Technical Specifications for both units.
During the inspection, the NRC inspectors identified several items that had not been relocated to the documents listed in Table 1 of the Safety Evaluation Report for Amendments 127_and 11.6 to the Units 2 and 3 respectively.
Edison committed to provide an update to Table 1, " Summary of Relocated SONGS Technical Specifications," of the Safety Evaluation Report to reflect the actual points of relocation for all elements of the Technical Specifications. includes a revised lable 1, " Summary of Relocated SONGS Technical Specifications."
Differences between the information in Table 1 and the actual points of relocation were discussed with the NRC Review Coordinator of the Improved Technical Specifications prior to implementation of the new Technical Specifications. The NRC concluded in this discussion that the decision regarding where the administrative requirements are relocated is up to the Licensee except for Sections " Review and Audit" and " Record Retention."
These two items are to be relocated to the Quality Assurance Topical Report a) because the 10 CFR 50.54 review is more appropriate than the 10 CFR 50.59 g}r process, and b) this would permit continued NRC oversight of these programs.
San Onofre Nuclear Generating Station P. O Ilox 128
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Document Control Desk If you would like additional information regarding the Enclosure, please let me know.
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Enclosure cc:
E. W. Merschoff, 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 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3
- e Table 1 Summary of Relocated SONGS Technical Specifications Relocation Relocation Existing TS Title Document Contral 2.2 3 LSSS (Instrumentation)
LCS 2.0.100 S50.59 4.0.5 Inservice Inspection and Testing TS 5.5.2.10 S50.55a Programs LCS 5.0.103.2.5 S50.59 LCS 5.0.103.2.6 3/4.1.3.2 Position Indicator Channels--
SR 3.1.5.2 550.59 operating LCS 3.1.106 3/4.1.3.3 Position Indicator Channels--
SR 3.1.5.4 S50.59 i
Shutdown LCS 3.1.106 l
3.1,1.3 Moderator Temperature Coefficient, LCS 3.1.100 S50.59 Cycle Specific Parameter (COLR) 3.1.3.6 Regulating CEA Insertion Limits, LCS 3.1.102 S50.59 Cycle Specific Parameter (COLR) 3.1.3.7 Part Length CEA Insertion Limits, LCS 3.1.103 S50.59 Cycle Specific Parameter (COLR) 3/4.2.1 Linear Heat Rate, Cycle Specific LCS 3.2.100 S50.59 Parameter (COLR) 3/4.2.1 DNBR Cycle Specific Parameter LCS 3.2.101 S50.59 (COLR) 3.2.7 Axial Shape Index, Cycle Specific LCS 3.2.102 S50.59 Parameiar (COLR) 3/4.3.1 Loss of Load Trip LCS 2.0.100 S50.59 3/4.3.1 Steam Generator High Level Trip LCS 2.0.100 550.59 3/4.3.2(10)
Toxic Gas Isolation Signal LCS 3.3.101 550.59 3/4.3.3.1 Radiation Monitoring LCS 3.3.102 550.59 Instrumentation 3 /4. 3. 3. 2 Incore Detectors LCS 3.3.103 550.59 3/4.3.3.3 Seismic Instrumentation LCS 3.3.104 550.59 3/4.3.3.4 Meteorological Instrumentation LCS 3.3.105 S50.59 3/4.3.3.7 Fire Detection Instrumentation LCS 3.3.106 S50.59 3/4.3.3.9 Explosive Ga3 Monitoring LCS 3.3.107 S50.59 Instrumentation ___
Relocation Relocation Existing TS Title Document Control 3/4.3.3.10 Vibration and Loose-Parts LCS 3.3.108 S50.59 Monitoring System 3/4.3.4 Turbine Overspeed Protection LCS 3.3.109 550.59 Tables 3.3-2 Besponse Tine Tests LCS 3.3.100 550.59 l
& 3.3.5 TABLES 3.3.100-1, 3.3.100-2 3/4.4.6 Chemistry LCS 3.4.101 S50.59 3.4.9 Structural Integrity U FSAR 5. 4.1. 4.1, 550.59 &
5.2.4.2.2 550.55(a)
TS 5.5.2.5 LCS 5.0.103.2.5 3/4.4.10 Reactor Coolant Gas Vent System LCS 3.4.102 550.59 j
3/4.5.1 Safety Injection Tank SRs LCS 3.5.100 550.59 4.5.1.c & 4.5.1.e 3/4.5.2 & 3 ECCS Subsystems Reporting LCS 5.0.104.2.a 550.59 Requirement Table 3.6-1 Containment Isolation Valves LCS 3.6.101 S50.5'.
TABLE 3.6.101-1 3/4.7.2 Steam Generator Pressure /
LCS 3.7.109 550.59 &
Tu.npe ra tu re Limitations 550.55(a) 3/4.7.6 Snubbers LCS 3.7.108 S50.59 &
S50. 55 (a) 3/4.7.7 Sealed Source contamination LCS 3.7.107 S50.59 &
10CFR2 0 3/4.7.8 Fire Suppression System (Title ti/A N/A only) 3/4.7.8.1 Fire Suppression Water System LCS 3.7.105 550.59 3/4.7.8.2 Spray and/cr Sprinkler Systems LCS 3.7.103 S50.59 3/4.7.8.3 Fire Hose Stations LCS 3.7.102 550.59 3/4.7.9 Fire Rated Assemblies LCS 3.7.104 550.59 3/4.8.4.1 Conta'.nment Penetration LCS 3.8.100 S50.59 Conductor Overcurrent Protective Devices 3/4.8.4.2 Motor Operated Valves Thermal LCS 3.8.101 S50.59 Overload Protective Devices
.2-
er Relocation Relocation Exi..'.ing TS Title Document Control 3/4.9.1 Boron Concentration, Cycle LCS 3.9.100 650.59 Specific Parameter 3/4.9.3 Decay Time LCS 3.9.101 S50.59 3/4.9.5 Communication LCS 3.9.102 S50.59 l
3/4.9.6 Refueling Machine LCS 3.9.103 550.59 a
3/4.9.7 Fuel Handling Machine--Spent CS 3.9.104 S50.59 Fuel Fool Building 5.1.3 Site Boundary for Gaseous UFS AR Fig. 2.1-5 550.59 Effluents ODCM Fig. 2-2 5.1.4 Site Boundary for Liquid ODCM Fig. 1-2 550.59 Effluents 5.2.1 Containment Configuration UFSAR 3.8,1,1 5
59 5.2.2 Design Pressure and Temperature UFSAR 6.2 S50.59 TABLE 6.2-3 5.4.'
Reactor Coolant System Design UFSAR 5.1 550.59 Pressure and Temperature TABLE 5.1-2 UFSAR 5.2
.i.4.2 Reactor Coolant System Volume UFSAR 5.1 550.59 TABLE 5.1-2 5.5.1 Meteorological Tower Location UFSAR 2. 3. 3 550.59 5.7.1 Component Cyclic or Transient UFSAR 3.7.3.2 S50.59 Limit TABLE 3.9-1*
TS 5.5.2.4 Figures Fuel Storage Patterns for Region LCS 4.0.100 S50.59
- .6-3 &
II Racks FIG. 4.0.100-1 5.6-4 FIG. 4.0.100-2 6.2.2.d Sko Present During Core LCS 5.0.100.1.3 S50.59 Alterations TABLE 5.0.100-1 S50.54 6.2.2.e Fire Brigade LCS 5.0.100.1.4 550.59
[
6.4 Training LCS 5.0.101.1 550.59 LCS 5.0.101.2 6.5 Review and Audits QA Topical Report 550.54(a)
SCE-1-A, sect.
17.2.20 6.6 Peportable Occurrence Action DCLETED (10 CFR N/A 50.72 & 73)
- Tablu 3.9-1 will be updated in Revision 13 of the UFSAR scheduled for submittal prior to January 21, 1998 __.
r.'s l
.*e Relocation Existing TS Title Relocation Document Conttrl 6.6.1.d Security Plan Implementation LCS 5.0.103.1.1.a 550.54(p) 6.8.1.e Emergency Plan LCS 5.0.103.1.1.b 950. 54 (q)
Implementation 6.8.2 Review and Approval Process LCS 5.0.103.1.2 550.54(a) 6.8.3 Temporary Change Process LCS 5.0.103.1.3 550.54(a) 6.8.4.b In Plant Radiation LCS 5.0.103.2.3 S50.59 Monitoring 6.8.4.f Radiological Environmental ODCM 5.0 Part 50 Monitoring Program TS 5.5.2.1 App. I LCS 5.0.103.2.4 6.9.2 ECCS Actuation Special LCS 5.0.104.2.a S50.59 Report S50.72 S50.73 6.10 Record Retention QA Topical Report
$50.59 SCE-1-A, sect.
17.2.20.5 6.10.2.h Inservice Inspection Program QA Topical Report
$50.59 Requirements SCE-1-A, sect.
$50,55(a) 17.2.20.5.2.h
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LCS 5.0.103.2.5 I
6.11 Radiation Protection Program LCS 5.0.103.2.1 550.59 &
10CFR20 6.13 Process Control Program QA Topical Report
$50.59 &
SCE-1-A, sect.
550. 54 (a) 17.2.20.3.1.I, QA Topical Report SCE-1-A, sect.
17.2.20.5.2.n 6.2.1 offsite Organization UFSAR SEC. 13.1 S50.59 &
UFSAR FIG. 13.1-1 S50.54 QA Topical Report SCE-1-A, sect. 17.2.1 Figure 6.2-2 Unit Organization UFS AR S EC. 13.1.2.2.2 550.59 &
UFSAR FIG. 13.1-2 550.54 Table 6.2-1 Minimum Shift Crew LCS TABLE 5.0.100-1 550.59 &
Composition 950.54 Figure 6.2-3 control Room Area LCS 5.0.100.1.3 550 59 LCS FIG. 5.0.100-1 "
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