ML20045F681
| ML20045F681 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/02/1993 |
| From: | Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9307080233 | |
| Download: ML20045F681 (14) | |
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Southem Califomia Edison Company 23 PARKER STREET
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tRVINE, CALIFORNIA O2718 July 2, 1993 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
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Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Eighth Edition of the Integrated Implementation Schedule (IIS)
San Onofre Nuclear Generating Station Units 2 and 3
Reference:
Letter from W. C. Marsh (SCE) to Document Control Desk (NRC),
dated January 4,1993; Seventh Edition of the Integrated Implementation Schedule (IIS).
Enclosures 1 through 3 provide the semi-annual update of the Eighth Edition of the Integrated Implementation Schedule (IIS) for the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3.
Enclosures 1 and 2 list, by outage, the Schedule A, B, and C projects for SONGS 2 and 3, respectively.
- lists the ongoing evaluations for major issues for SONGS 2 and 3.
A comparison to the Seventh Edition of the IIS (referenced) reveals that the following changes have occurred to the Cycle 7 and Cycle 8 schedules:
ACTION UNIT CYCLE SCHEDULE MODIFICATION Completed 2
7 C
Replace Seismic Instrumentation (DCP 6792)
Completed 2
7 C
Fire Protection Panel Mods (DCP 6861)
Completed 2
7 C
UREA Formaldehyde System Removal (DCP 6728)
Deleted 2/3 7
B FFCPD HUT Modifications (DCP 6773)
Sched 2/3 7
C to B CR 63 electrical panel modifications Change (DCP6605.08)
Sched 2/3 7
C to B Install DG Turbo Pre Lube NRC IE Notice Change 85-32 (DCP 6754) i Added 2/3 7
B Equipment Hatch Backup Power in accordance i
with NUMARC 91-06 Added/
2/3 7
B Inverter Rocm Temperature Alarms in Completed accordance,with PRA sent to NRC (DCP 6831) g
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The Steam Generator Overfill Protection System (SG0PS) has been deleted as
.i noted in the seventh edition of the IIS letter, dated January 4,1993, and i
letter from R. M. Rosenblum, SCE to NRC dated March 30, 1993.
The Full Flow Condensate Polishing Demineralizer (FFCPD) Regenerative Waste HUT DCP was cancelled since the scope of the work identified will be accomplished without capital modifications.
DCP 6605.08, CR 63 electrical panel modification, has been moved from Schedule C to Schedule B.
The modification is considered a part of the evaluation for a major NRC initiated issue not required by regulation, license condition or order. This is part of the Human Engineering upgrades determined necessary by the CRDR evaluations as part of NUREG 0700.
DCP 6754, installation of the Diesel Generator Turbo Prelube, has been moved from Schedule C to Schedule B.
This upgrade will improve the EDG reliability factors per NRC IE notice 85-32.
Approximately 50% of resources for the Unit 2 and the Unit 3 Cycle 7 refueling outages will be allocated to regulatory projects.
i The Westinghouse Analytical Ranking Program (WARP) was not used to rank the relative safety significance of each Schedule A and 8 modification because their implementation schedules have been established in separate correspondence.
If you have any questions on the Eighth Edition of the San Onofre Units 2 and 3 IIS, please let me know.
Very truly yours, 0
Walter C. Mar h j
Manager of Nuclear Regulatory Affairs Enclosures i
i cc:
B. H. Faulkenberry, Regional Administrator, NRC Region V C. W. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2&3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 j
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SONGS 2 CYCLE 7 INTEGRATED IMPLEMENTATION SCHEDULE-UNIT 2 CYCLE 7 SCHEDULE A - NRC RULE OR ORDER l
MODIFICATION REFERENCE LETTER / COMMENTS Station Blackout Modification 10CFR50.63 (DCP 6711)
UNIT 2 CYCLE 7 SCHEDULE B - REGULATORY COMMITMENT l
MODIFICATION REFERENCE LETTER / COMMENTS Control Room (CR) annunciator NUREG 0700 (DCP 6609.00) rearrangement modification CR 63 Annunciator modifications NUREG 0700 (DCP 6609.02)
CR 63 electrical panel modifications NUREG 0700 (DCP 6605.08)
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Control Room human factors SCE letter to NRC dated June 18, modifications 1990 (DCP 6605.06)
CR 61 Panel Modifications (DCP 6605.09) Cycle 7 plus 120 2
days Component Cooling Water (CCW) seismic From SSFI and SCE letter to NRC t
make up addition dated July 30, 1990 (DCP 6742.07)
Modify plant protection system (PPS)
LER 2-90-014, 3-89-007 (DCP 6827) test switches Modify overspeed protection on steam LER 2-90-012, 2-92-007 (DCP 6869) driven auxiliary feedwater pumps Spill prevention control and H. Newton (SCE) letter to A. Coe countermeasures modification (Cal Regional Water Quality Board) dated November 14, 1991; The current issued SPCC plan or agreed upon equivalent engineering practices will be completed by the end of the year (DCP 6878) 1 2CR 61 panel modifications will continue during both Unit 2 and 3 Lycle 7 outages and will be completed during the first 120 days of Unit 3 Cycle 7 operation.
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Delete cycling MSIS relay; Provide LER 3-90-002-01 (DCP 6826) partial ESF actuation annunciator Steam driven auxiliary feedwater pump LER 2-91-014 (DCP 6869) steam supply check valve modifications Load Center Transformer Replacements LER 2-92-008 (DCP 6974)
(SR portion will be completed in C7, with non-safety related work continued
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in Cycles 8 and 9)
Add T-hot and T-cold indicators to NUREG 0800 (DCP 6939)
Remote Shutdown Panel I
Inverter Room Temperature Alarm PRA to NRC (DCP 6831.01), completed Equipment Hatch Backup Power NUMARC 91-06 Install DG Turbo Pre Lube NRC IE Notice 85-32 (DCP 6754)
UNIT 2 CYCLE 7 SCHEDULE C - PLANT BETTERMENT MODIFICATION REFERENCE LETTER / COMMENTS i
Ladders and platforms On going program (DCP 6735.01)
Cross connect shutdown cooling (DCP 6863.00) and containment spray systems 4
Install removable digital polar (DCP 6855) crane controls Low pressure safety injection (DCP6858) pump seal upgrades Add external test points to plant (DCP6828) protection system (PPS) panel Snubber reduction On going program (DCP 6683.03)
Replace the low pressure turbine (DCP6868) bellcws with stainless steel bellows t
Turbine building sump radiation Non outage related modification monitor low flow alarms (DCP6191) i Safety Injection system pipe vent (DCP6697) relocation I
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Post accident sampling system (PASS)
(DCP6751) skid enhancements Pressurizer Vent (DCP6863.01)
Install cooler n respiratory / breathing (DCP6842) air system Remove MICDS inside/outside Containment (DCP 6808.01) l Modify PMS and COLSS back up,:omputer (DCP 6716) system Install oxygen monitor in the FFCPD Lab (MMP 6891)
Replace Flow Probe in the Plant (MMP6835)
Vent Stack radiation monitor Modify 90 minute emergency Control (DCP6888)
-Room lighting battery backup v
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SONGS 2 CYCLE 8 INTEGRATED IMPLEMENTATION SCHEDULE UNIT 2 CYCLE 8 SCHEDULE A - NRC RULE OR ORDER THERE ARE NO SCHEDULE A ITEMS IDENTIFIED AT THIS TIME.
UNIT 2 CYCLE 8 SCHEDULE B - REGULATORY COMMITMENT 1
MODIFICATION REFERENCE LETTER / COMMENTS Provide annunciator alarms for open LER 3-90 rA > and SCE to NRC letter containment emergency sump isolation dated February 2,1991 valves and closed ECCS and CS pump y
mini flow valves r
UNIT 2 CYCLE 8 SCHEDULE C - PLANT BETTERMENT MODIFICATION REFERENCE LETTER /CONMENTS Install removable refueling machine (DCP6864) controls Add permanent breathing air and (DCP6809) communication stations to steam generator platform Replace refueling cavity seals (DCP6857)
Redesign blowdown drain system (DCP 6752)
Replace NMC radiation monitors (DCP6876,6926)
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Replace circ water 4T data logger (DCP6963)
Replace loose parts and vibration (DCP6851) monitoring system Replace sodium and chloride analyzers (DCP6884)
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Replace conductivity instrumentation (DCP6885)
Replace pH instrumentation (DCP6886)
Turbine Governor Valve Modifications (DCP6914) i 4
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i SONGS 3 CYCLE 7 INTEGRATED IMPLEMENTATION SCHEDULE UNIT 3 CYCLE 7 SCHEDULE A - NRC RULE OR ORDEP f
MODIFICATION REFERENCE LETTER / COMMENTS
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r Station Blackout Modification 10CFR50.63 (DCP 6711)
UNIT 3 CYCLE 7 SCHEDULE B - REGULATORY COMMITMENT MODIFICATION REFERENCE LETTER / COMMENTS Control Room annunciator NUREG 0700 (DCP 6609.00) rearrangement nodification
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CR 63 Annunciator Modifications NUREG 0700 (DCP 6609.02)
CR 63 electrical Panel modifications NUREG 0700 (DCP 6605.08)
(To be completed durin Unit 2 Cycle 7 outage)g i
Control Room human factors modifications SCE letter to NRC dated June 18, 1990 (DCP 6605.06)
CR 61 Panel Modifications (DCP 6605.09) Cycle 7 plus 120 days' Component Cooling Water (CCW) seismic From SSFI and SCE letter to NRC make up addition dated July 30, 1990 (DCP 6742.07)
Modify plant protection system (PPS)
LER 2-90-014, 3-89-007 (DCP 6827) test switches Modify overspeed protection on steam LER 2-90-012, 2-92-007 (DCP 6869) driven auxiliary feedwater pumps Spill prevention control and H. Newton (SCE) letter to A. Coe countermeasures modification (Cal RWQB) dated November 14, 1991; The current issued SPCC plan or o
agreed upon equivalent engineering practices will be completed by the end of the year (DCP 6878)
Delete cycling MSIS relay; Provide LER 3-90-002-01 (DCP 6826) partial ESF actuation annunciator Steam driven auxiliary _feedwater pump LER 2-91-014 (DCP 6869) steam supply check valve modifications j
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'CR 61 panel modifications will continue during both Unit 2 and 3 cycle 7 outages and will l
be completed during the first 120 days of Unit 3 Cycle 7 operation.
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i Add T-hot and T-cold indicators to NUREG 0800 (DCP 6939)
Remote Shutdown Panel i
Load Center Transformer Replacements LER 2-92-008 (DCP 6974) i (SR portion will be completed in C7, with NSR work continued in Cycles 8 and 9)
Inverter Room Temperature Alarm PRA to NRC (DCP 6831.01), completed l
Equipment Hatch Backup Power NUMARC 91-06 Install DG Turbo Pre Lube NRC IE Notice 85-32 (DCP 6754)
UNIT 3 CYCLE 7 SCHEDULE C - PLANT BETTERMENT i
MODIFICATION REFERENCE LETTER / COMMENTS i
Ladders and platforms On-going program; Non-outage related modification (DCP 6735.01) i Cross connect shutdown cooling and (DCP 6863.00) containment spray systems Install removable digital polar crane (DCP 6855) controls I
Low pressure safety injection pump (DCP 6858) seal upgrades Add external test points to plant (DCP6828) protection system (PPS) panel j
Snubber reduction On-going program (DCP 6683.03)
Turuur building sump radiation Non outage related modification monitor lowflow alarms (DCP6191)
Replace low pressure turbine bellows (DCP6868) with stainless steel bellows i
Pressurizer Vent Modification (DCP6863.01) i i
i Replace fire and security computers Non outage related modification (DCP l
7018)
Remove MICDS inside/outside Containment (DCP6808.01)
Temporary Facility Modification Non outage related modification l
incorporations (DCP 6748) i 4
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system Install oxygen monitor in the FFCPD lab (MMP6891) i Replace Flow Probe in the Plant (MMP 6835)
Vent Stack radiation monitor i
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SONGS 3 CYCLE 8 INTEGRATED IMPLEMENTATION SCHEDULE UNIT 3 CYCLE 8 SCHEDULE A - NRC RULE OR ORDER THERE ARE NO SCHEDULE A ITEMS IDENTIFIED AT THIS TIME.
UNIT 3 CYCLE 8 SCHEDULE B - REGULATORY COMMITMENT MODIFICATION REFERENCE LETTER / COMMENTS Provide annunciator alarms for open LER 3-90-010 and SCE to NRC letter containment emergency sump isolation dated February 2, 1991 (DCP 6609) l valves and closed ECCS and CS pump i
mini flow valves UNIT 3 CYCLE 8 SCHEDULE C - PLANT BETTERMENT MODIFICATION REFERENCE LETTER / COMMENTS Install removable refueling machine (OCP6864) controls Add permanent breathing air and (DCP6809) communication stations to steam generator platf' ;;
Replace refueling cavity seals (DCP6857)
Redesign blowdown drain system (DCP6752)
Replace NMC radiation monitors (DCP6876,6926)
Replace circ water 4T data logger (DCP6963)
Upgrade loose parts and vibration (DCP6851) monitoring system Replace sodium and chloride analyzers (DCP6884)
Replace conductivity instrumentation (DCP6885)
'l Replace pH instrumentation (DCP6886)
Turbine Governor Valve Modifications (DCP6914)
Replace TGIS (DCP 6933) 4
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ONGOING EVALUATIONS OF MAJOR ISSUES (SONGS 2 and 3)
GL 88-20, SUP 4 Individual Plant Examination of External Events (IPEEE), to
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be completed by 6/01/95.
GL 89-04 Guidance on developing acceptable Inservice Testing Programs, to be implemented by completion of Unit 3 Cycle 8 refueling.
GL 89-10 The initial Safety-Related Motor-0perated Valve Testing and Surveillance will be completed for Units 2 and 3 by the end i
of their respective Cycle 8 refueling outages. Periodic i
verifications of MOV operability will follow.
GL 91-15 In response to Generic Letter 91-15, " Operating Experience i
Feedback Report, Solenoid Operated Valve Problems At U.S.
Reactors," SCE has completed a review of Industry's and San Onofre-specific operating experience with the use of solenoid operated valves. This review also included revisiting NRC Bulletins, Information Notices, and recommending potential corrective actions. SCE is currently assessing the implementation of review findings.
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