IR 05000206/1992035

Meeting Repts 50-206/92-35,50-361/92-35 & 50-362/92-35 on 921203.Major Areas Discussed:Status of Unit 1 Permanent Shutdown Planning

ML13329A218
Person / Time
Site:	San Onofre
Issue date:	12/31/1992
From:	Wong H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML13329A217	List: IR 05000206/1992035 ML13329A216
References
50-206-92-35-MM, 50-361-92-35, 50-362-92-35, NUDOCS 9301200228
Download: ML13329A218 (36)

Text

U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report No /92-35, 50-361/92-35, and 50-362/92-35 Docket No, 50-361, 50-362 License No DPR-13, NPF-10, NPF-15 Licensee:

Southern California Edison Company Irvine Operations Center 23 Parker Street Drive Irvine, California 92718 Facility Name:

San Onofre Units 1, 2, and 3 Meeting at:

Region V Office Walnut Creek, California Report Prepared By: T. B. Sundsmo, Project Inspector Approved By:

___9_

H. Wong, Chief Date Signed Reactor ProjectsSection II Summary A meeting was held on December 3, 1992, to discuss the status of Unit I permanent shutdown planning. A copy of the slides used during the licensee's presentation is enclose PDR ADOCK 05000206 P

PDR

DETAILS 1. Meeting Attendees Southern California Edison Company (SCE)

W. Marsh, Assistant Manager, Nuclear Regulatory Affairs R. Waldo, Operations Manager G. Hammond, Supervisor, Onsite Nuclear Licensing D. Opitz, Unit 1 Outage Manager C. Anderson, Emergency Planning Supervisor R. Ashe-Everest, Nuclear Fuels Group Supervisor A. Tally, Supervisor of Health Physics Nuclear Requlatory Commission S. Richards, Deputy Director, Division of Reactor Safety and Projects R. Samworth, Senior Project Manager, NRR H. Wong, Chief, Reactor ProjectsSection II T. Sundsmo, Reactor Projects Inspector T. Meadows, Senior Licensing Examiner F. Wenslawski, Deputy Director, Division of Radiation Safety and Safeguards R. Pate, Chief, Safeguards, Emergency Preparedness and Non-Power Reactor Branch J. Reese, Chief, Facilities Radiological Protection Branch A. McQueen, Emergency Preparedness Analyst G. Good, Emergency Preparedness Analyst 1. Norderhaug, Physical Security Specialist Others R. Lacy, Manager, Nuclear Department, San Diego Gas and Electric 2. Details The meeting convened at 1:00 p.m. Mr. Richards opened the meeting by thanking SCE management for coming to Region V

'to present the details involved with the permanent shutdown of Unit 1. Mr. Hammond introduced the SCE presentatio The following topics were presented by members of the SCE staff:

A. Mr. R. Ashe-Everest presented the discussion regarding the transshipment of fuel from the Unit 1 Spent Fuel Pool (SFP) to Units 2/3. Slides of the previous transshipment of fuel showed the methods used to transport the fue For the upcoming transshipment, each shipment will involve seven fuel assemblies transported dry inside a cask. Because the fuel will have decayed sufficiently before transport, no cask cooling will be neede III2 B. Mr. D. Opitz presented post-shutdown plant configuration, modifications, implementation schedule, and salvage topics. Some of the key discussion items included:

-

Systems needed to support the plant would be classified as

"required operable" instead of safety-related. Other systems would be abandoned for salvage. No equipment lay-up plans have been made. System boundaries have been approved, and annotated on plant drawing The maximum estimated temperature of the SFP six months after core off-load is 180 degrees F; it would take about 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> to reach this temperature upon a loss of all SFP coolin The Auxiliary Feedwater (AFW) Storage Tank will be the source of make-up water to the SFP. Water level in the tank will be maintained so that the required capacity of make-up can be achieved passively by gravity drainin The SFP will not require any boron in its water to maintain the required level of subcriticality. Although the SFP is currently filled with borated water, there are no plans to maintain a specific boron leve Systems that would be required operable were discussed. Of note, the Emergency Diesel Generators would be maintained until the maximum estimated SFP temperature upon loss of cooling had decreased to 150 degrees C. Administrative controls and plant staffing topics were presented by Mr. R. Waldo. Discussion items included:

-

Post Shutdown Administrative Controls had been approved by NR These requirements were derived from operating TS that were modified to delete requirements not applicable to a defueled reactor, to maintain requirements applicable to all modes of operation, and to add requirements that were needed to support a stable defueled conditio Plant staffing of Unit 1 will be reduced in a controlled manner over the next few years. Units 2/3 may be impacted because many of the Unit 1 staff, who tend to be more senior, will be reassigned to Units 2/3; no lay-offs of permanent employees were anticipated. Potential effects on site staff morale were discusse Other topics discussed included the long term integrity of the cooling water intake structure, SFP level monitoring systems/alarms, and the Certified Fuel Handler progra D. Mr. C. Anderson described how the SONGS Emergency Preparedness Plan (EP) would continue to be implemented at Unit 1. Because the SONGS

• II3 EP Plan is a site-wide procedure, the permanent shutdown of Unit 1 does not require significant plan revision. When the core is defueled, the potential for any significant release is greatly reduced. However, many EP events, such as fires, security, and contaminated injuries would still be possible. The highest anticipated classification level of such events would be an Aler Current plans were to maintain the Unit 1 Control Room notification systems (yellow and red phones) and siren panels operabl E. The transition of Health Physics during the Permanent shutdown was presented by Mr. A. Tally. After the reactor is defueled, access to some areas will be controlled by locking the areas. Radiation area access will still be controlled by Radiation Work Permit. An automated dosimeter program using alarming dosimeters will be implemented. The current survey program will be maintained, but the frequency of surveys will be adjusted (decreased) based on plant conditions. Since the HP technicians work on all three units, there should be no significant staffing problem F. Mr. W. Marsh presented the licensing actions, plans and schedules that were applicable to the Unit 1 permanent shutdown. Key events included:

-

NRC approved the Possession Only License for Unit Submittals of Permanently Defueled TS, and the Certified Fuel Handler Program were scheduled for December 15, 199 The Preliminary Decommissioning Plan had received management approval at SCE, and had been submitted to the NR. Closing Remarks The Region V staff remarked that the information presented had provided very good insight into the upcoming events associated with the permanent shutdown of Unit 1. Mr. Wong emphasized the need for good communications between NRC and SCE when requirements were identified that did not apply to a permanently defueled plant. Mr. Richards endorsed this comment, and added that NRC expected all regulatory requirements would be met and supported early discussion of requirements which were impractical in the plant's current shutdown mode. SCE personnel acknowledged these comment The meeting adjourned at 4:30 ENCLOSURE 2 NRC MEETING AGENDA Plans for Transshipment (Bob Ashe-Everest) Post Shutdown Plant Configuration, Modifications, Implementation Schedule, Salvage (Dave Opitz) Administrative Controls Letter Provisions and Unit Staff Transition Plan (Ray Waldo)

- Licensing Actions - Plans & Schedules (Walt Marsh) Emergency Plan Changes (Cyrus Anderson) Post Shutdown Radiation Control (Al Tally)

UNIT 1 FINAL SHUTDOWN PROJECT DECEMBER 3, 1992 NRC Region V Briefing

PROJECT SCOPING ITEMS

"

Shutdown P & IDs O

Breakers Books o

Thermal Equilibrium and Heat up Calculations o

No Boron Requirements for the Spent Fuel Pit o

Effluent Calculations for LOP or Dropped Fuel Assembly o

Final Configuration Control Plan o

Maintenance Program Changes

GENERAL COMMENTS

"

Normal Technical Specifications prior to Offload

"

Administrative Control Letter once Defueled o

POL Once Defueled o

Cost Effective Schedule, limited Overtime

"

Defueled o

All systems no longer required are removed from service

No Plant Lay up o

Containment Systems Drained and De-energized o

Secondary Plant Drained and De-energized o

All boric acid systems removed from service o

AFWST to be used as Seismic Makeup for the SFP after offload

"

Radwaste Systems to remain in service o

Increase in redundancy during shutdown since systems are not being removed from service o

Effluent Considerations

CONTAINMENT SYSTEMS Drained and De-energized o

All flamable items (oil, chemicals) removed o

Cathodic Protection on the Sphere o

Containment locked and vented to stack (slight negative pressure)

o Reactor Head not completely reassembled (ALARA)

o Fire Protection will still be viable through CRS

"

Storage Racks and Lift Rig Storage

Normal Decontamination Efforts o

Pressurizer Safety Valve removed o

No extra effort to drain low spots in systems o

RCS Crud Burst consistent with normal plant shutdown

SYSTEMS TO BE ELIMINATED o

CONTAINMENT SYSTEMS o Letdown 0 Sumps o Containment Isolation o Control Rod Drive 0 Containment Ventilation o Containment Water level Indication o Fuel handling o H2 Monitoring o Nuclear Instrumentation System o Pressurizer o Reactor Coolant Pump Seal Water o Reactor Coolant System o Residual Heat Removal o Reactor Protection System o Sphere Enclosure o Teleflex o Subcooling Margin Monitor o Seismic Monitoring

o BORIC ACID SYSTEMS o Boric Acid System o Chemical Recirculation System o Volume and Control System o

SECONDARY PLANT o Main Steam o Feedwater o Flash evaporators o Feedwater sampling o Feedwater Heaters o Feedwater System o Chemical Feed System o Hydrazine Addition o

CONDENSATE / CONDENSER 0 Condensate Air Removal o Condensate o Condensate Sampling o Condenser Vents and Drains

a TU-RBINE GENERATOR o Generator o Generator Gas o Generator Seal Oil o Turbine o Turbine Lube Oil o Turbine Control Oil o Turbine Plant Sample Coolers o High Pressure Turbine o Low Pressure Turbine o

NON SAFETY RELATED COOLING o Circulating Water System o Turbine Plant Cooling Water o

ACCIDENT MITIGATION / MONITORING SYSTEMS o Dedicated Shutdown Diesel o Safety Injection o Emergency Lighting o Post Accident Sampling o

GASEOUS RADWASTE

PLANT SYSTEMS TO BE MAINTAINED o

DECAY HEAT REMOVAL o Intake o Salt Water Cooling o Component Cooling Water o Spent Fuel Pool Cooling

RADWASTE/ SPENT FUEL POOL CHEMISTRY CONTROL o Liquid Radioactive Waste Collection o Liquid Radioactive Waste Processing o Radwaste Drains o

SPENT FUEL PIT MAKEUP o Primary Make-up o Reservoir o Auxiliary Feedwater Storage Tank

UNIT 1 FINAL SHUTDOWN CONFIGURATION SERVICE WATER CCW RESERVOIR SURGE TAw.

PMU PPS PRIMARY C>

MAKEUP TANK CCW HX NOTE THIS CONFIGURATION SELECTED APPLIES DURING CORE HFIRE FIRE PPS OFFLOAD UNTIL DECAY SYSTEMS HEAT RMOVAL IS NOT

--

E7'REQUIRED

.

SWC PPS CIRC WATERS INTAKE F

X DPS AUX FDWTR SFP PPSSTORAGE CIRC WATER SFP1 PTANK ouTvA SPENT FUEL POOL AUX

BUILDING DMYN EXCHGR HUT HUT HUT SUMPS YARD LEGEND REHEATER aSPCON INE SODU M

SFP MAKEUP HOLUPK RADWASTE

.

PUMPS

o AC POWER SUPPLY o

Diesel Generators o

Main, Aux A, Aux B, Aux C transformers o

Electrical Systems o 220 KV o 12 K o 4K 0 480 V o DC 0 MCC's o Vital Buses o Utility Bus

UNIT I FINAL SHUTDOWN CONFIGURATION SWTCHYARD NOTE: THIS CONFlGURAT10N SATCHYARD APPUES DURING CORE OFFLOAD UNTIL DECAY HEAT REMOVAL IS NOT AUX TcM

-.,M"XMAI REQUIRED AXM WWC (D-MOD MAIN AUX "A4 AUX 08B';

XFMR XFMR BUS 1A BUS 18 4KV BUS 1C 4KV BUS 2C MvY SST SST A&

fviv\\ SST SSTtAA DG f

1. 1

1. 3

1. 2

1. 4DO2 4 80VYW 480V 480VwM'

(/2 480V BUS #1 BUS #3 BUS #2 BUS #4 FIRE PP FIRE PP SWC PP SWC Pp CCW P CCW PP MCC CCW PpPP MCC CHGR CHGR

'

2 MCC CHGR CHGR

1. IA

- A IH+-

4C, DC BUS #1 SFP Pp DC BUS #2 I

I I

IM 12KV LEGEND VB VB VB VB VB Us NORTH/SOUTH XFMR iTRAIN 1 fl #2 #3 f3A #4 SPARE -o-CONSTRUCTION WW-f TRAIN 2 SFP PP LOAD CENTERS SD08E (NSR)

o SUPPORT SYSTEMS REQUIRED 0 Yard Sumps and Drains o Fire Protection o Cranes o Met Tower o Gaseous N2 and Liquid Nitrogen o Snubbers (13 left)

o Instrument Air System o Lighting o Perimeter Lighting o Misc Ventilation - CREATS functional o Radiation Monitors o Service and Domestic Water o Security o Secondary Sumps and Drains o Telephones o Sirens and Siren Control Panel o

POSSIBLE SALVAGE o HP Turbine

PAGE 1 2-N~ov-92 UNIT 1 -

FINAL SHUTDOWN PROJECT CONFIGURATION CHANGES REQUIRED FOR SHUTDOWN CRANGE SYSTEM REOUIRED MECHANICAL 1. 005 REMOE 16 C0 H BOTTLES 2. GNI REMOVE 2 H. 1.5 \\2 BOTTLES 3. PZR REMOVE SAFETY ON MO PER PROCEDURE 4. CVS BLOCK OPEN VALVES CV-IO.CV-116 S. ISA USINO AIR RECEIVERSNVITH AUX AIR COMPRESSOR 6. CRS BLOCK OPENC-9:

FE PROTEC7IO\\

7. RMS MONITOR UGRADES S. DSD REMOVE BANX & ESGINE !AYlzRY 9. S:S REMOVE UPS BATTErY 10. AFW USE FOR SF? MA.UP 11. SWC REMOVE BATTERY FOR GASENGINE 1 REMOVE BOSTSLS ELECTRICAL 1. VBl-S-1109V UFT9LEADS(OR PULL FUSES) EZ-2-lICV LIFT 3 LEADS (OR PULL FSS)

3. VE3-S--ISV LIFT I LEAD (OR PULL FUSES)

4. VB4-S-140V LIFT 12LEADS(OR PULL FUSES)

S. V114-R-150O LIFT 7 LEADS (OR PULL FUSES)

FCN-OCONPIG

UNIT 1 FINAL SHUTDOWN MAJOR MILESTONES BEGIN COASTDOWN 11/18/92 OPEN BREAKERS 11/30/92 BEGIN TRANSSHIPMENT DRY RUNS 01/11/93 BEGIN TRANSSHIPMENT 01/22/93 COMPLETE TRANSSHIPMENT 02/12/93 COMPLETE FUEL TRANSFER EQ CHECKOUT 02/19/93 MODE 8 02/22/93 REFUELING CAVITY FLOODED 02/25/93 BEGIN CORE ALTERATIONS 03/01/93 CORE OFFLOADED 03/10/93 CONTAINMENT CLOSURE 05/15/93 SECURE CIRCULATING WATER PUMPS 06/29/93 SFP THERMAL EQUILIBRIUM OF 1500F 03/20/95 0W MA

• a SONGS 1 OPERATION FOR FINAL SHUTDOWN

EXISTING TECHNICAL SPECIFICATIONS APPLY UNTIL DEFUELED

ADMINISTRATIVE CONTROLS LETTER APPLIES AFTER DEFUELING

"AT ALL TIMES" LCO

-

Fire Suppression Water System

MODE 6 LCO

-

One Emergency Diesel Generator without Autostart

SONGS 1 OPERATION FOR FINAL SHUTDOWN (Continued)

MODIFIED MODE 6 LCOs

-

.Fuel Loading and Refueling Limits (SFP Boration Not Required)

-

Vital Buses Energized by MCCs (Not Inverters)

-

Reactor Residual Heat Removal (Not Required)

ADMINISTRATIVE CONTROLS

'-

Spent Fuel Pool Temperature

-

One Train of Cooling

-

Spent Fuel Pool Makeup (AFWST)

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

Unit 1 Operations Transition Plan November 18, 1992 Date 11/1/92 1/4/93 4/1/93 9/1/93 3/1/94 Shift Superintendents/CFH

5

4

Control Room Supervisors/CFH

5

4

Control Operators/SCO

5

4

Asst. Control Operators

5

0

Plant Equip. Operators/NCEO

10

4

Nuclear Operations Ass RO/SRO Staff

2

0

Staff

12

9

TOTAL

48

29

TOTAL DISPLACED

34

53

OPERATOR QUALIFICATION PROGRAM Certified Fuel Handler Provides the supervision and oversight previously provided by SRO Current SROs will be grandfathered as CFHs We are developing a program to qualify new CFH *

It will cover:

Operating, abnormal and emergency procedures

Administrative controls

Accident analyses

Fuel handling equipment design and operation

Technical specifications

Emergency plan

Supervisory skills

Industry events

NON-CERTIFIED EQUIPMENT OPERATOR Provides the workers previously designated as Assistant Control Operators and Plant Equipment Operator Currently qualified ACOs and PEOs will be grandfathered as NCEO N We are developing a program to qualify newACFHs. It will

.

cover:

General training

Science and engineering fundamentals

Plant systems

Operating, abnormal, and emergency plan procedures

Administrative controls

Fundamental operating practices and standards

CHANGES TO SONGS EMERGENCY PREPAREDNESS PROGRAM THE EMERGENCY PLAN IS A SITE-WIDE DOCUMENT SIGNIFICANTLY REDUCED POTENTIAL FOR RADIOLOGICAL RELEASE NO DECREASE IN EMERGENCY RESPONSE CAPABILITY COMPARISON TO YANKEE AND RANCHO SECO 0 RECOGNITION/CLASSIFICATION OF UNIT 1 EVENTS SHIFT STAFFING CHANGES CHANGES TO EPIPs CHANGES TO FACILITIES & EQUIPMENT TRAINING PERSONNEL ON THESE CHANGES 10. NO AFFECT ON RELATIONSHIPS WITH LOCAL AGENCIES 11. CHANGES TO THE EMERGENCY PLAN WILL BE REVIEWED AND COORDINATED THROUGH NRR

SONGS 1 HEALTH PHYSICS TRANSITION PLAN

• ACCESS CONTROL:

CONTROL WILL NOT CHANGE UNTIL AFTER THE FUEL IS OFFLOADED AND THE UNIT IS PLACED IN SAFSTO * LOCKED AREAS:

WHEN THE UNIT IS DEFUELED AND PLACED IN SAFSTOR SECURITY WILL DEVITALIZE THE AREAS. SOME OF THE AREAS WITH RADIOLOGICAL CONCERNS WILL BE LOCKED AS THE MECHANISM FOR ACCESS CONTRO * RADIATION EXPOSURE PERMIT AREAS:

THE CONTROLLING MECHANISM FOR ENTRY TO RADIOLOGICAL AREAS WILL BE THE RADIATION EXPOSURE PERMI DURING SAFSTOR THE REP WILL BE PREPARED AND ISSUED FROM UNIT 2/3 PLANNING OFFIC WORKERS WILL NEED TO INITIATE THEIR WORK ACTIVITY FROM UNITS 2/ SONGS 1 HEALTH PHYSICS TRANSITION PLAN

• AUTOMATED DOSIMETRY CONTROL:

PRIOR TO SAFSTOR WORKERS WILL HAVE THE ABILITY TO SIGN IN ON AN REP AND SELF LOG INTO THE DOSIMETRY STATIO THEY WILL PICK UP AN ALARMING DOSIMETER WHICH IS KEYED INTO THE REP PROCES * WHOLE BODY PERSONNEL MONITORING:

AS THE WORKERS EXIT THE AREA THEY WILL BE REQUIRED TO GO THROUGH THE WHOLE BODY PERSONNEL MONITOR OR PERFORM A WHOLE BODY FRIS * SURVEY PROGRAM:

A SURVEY PROGRAM WILL BE MAINTAINED. SURVEYS WILL BE PERFORMED ON A ROUTINE BASIS TO DETERMINE RADIOLOGICAL CONDITIONS IN WORK AREA LOCATIONS, WILL REMAIN APPROXIMATELY AS PRESENTLY DON FREQUENCIES, WILL BE BASED UPON THE PROBABILITY OF CHANGING RADIOLOGICAL CONDITIONS AND THE FREQUENCY WITH WHICH THE AREA WILL BE VISITE SONGS 1 HEALTH PHYSICS TRANSITION PLAN

• JOB COVERAGE:

WORK WILL BE SUPPORTED AS IT IS IN THE EXISTING PROGRA * STAFFING:

PRESENT STAFFING WILL CONTINUE UNTIL THE START OF TRANSSHIPMENT. WE WILL THEN INCREASE OUR STAFFING TO MEET THE NEEDS OF THE PROJEC AFTER MAY 1993, STAFFING WILL BE DETERMINED BY THE NUMBER OF CUSTOMERS AND THE SCOPE OF WOR * WORK MANAGEMENT:

PRESENT SCHEDULING IS THROUGH THE UNIT 1 SCHEDULING GROUP. DURING THE SHUTDOWN PROCESS THIS WILL BE TRANSFERRED TO OUTAGE MANAGEMEN *

0*

SONGS 1 HEALTH PHYSICS TRANSITION PLAN PLANNING AND SCHEDULING DURING SAFSTOR:

WORK AFTER SAFSTOR WILL BE SCHEDULED FROM UNITS 2/ ANY HP SUPPORT WILL NEED TO BE SCHEDULED AS A PART OF THIS PROCESS AND THE TECHNICIANS WILL BE ASSIGNED FROM THE UNIT 2/3 RESOURCE Edison Objectives

• Safely Comply With Regulations

• Minimize Post-Shutdown Costs

• Licensing Actions

• Obtain POL

• Advise NRC Of Intended Administrative Controls

• Request Exemptions From 10 CFR 50

• Permanently Defueled Technical Specifications

Fuel Handler Certification

• Submit Preliminary Decommissioning Plan

• Licensing Actions (Continued)

• Resolution of Other Commitments

• Modification of Emergency Plan

• Modification of Security Plan

• Submit Proposed Decommissioning Plan

CHANGES TO SONGS EMERGENCY PREPAREDNESS PROGRAM 1. THE EMERGENCY PLAN IS A SITE-WIDE DOCUMENT SIGNIFICANTLY REDUCED POTENTIAL FOR RADIOLOGICAL RELEASE NO DECREASE IN EMERGENCY RESPONSE CAPABILITY COMPARISON TO YANKEE AND RANCHO SECO RECOGNITION/CLASSIFICATION OF UNIT 1 EVENTS SHIFT STAFFING CHANGES CHANGES TO EPIPs CHANGES TO FACILITIES & EQUIPMENT TRAINING PERSONNEL ON THESE CHANGES 10. NO AFFECT ON RELATIONSHIPS WITH LOCAL AGENCIES

.

11. CHANGES TO THE EMERGENCY PLAN WILL BE REVIEWED AND COORDINATED THROUGH NRR

Edison Objectives

• Safely Comply With Regulations

• Minimize Post-Shutdown Costs

Licensing Actions

• Obtain POL

• Advise NRC Of Intended Administrative Controls

• Request Exemptions From 10 CFR 50

• Permanently Defueled Technical Specifications

Fuel Handler Certification

• Submit Preliminary Decommissioning Plan

• Licensing Actions (Continued)

• Resolution of Other Commitments

• Modification of Emergency Plan

• Modification of Security Plan

• Submit Proposed Decommissioning Plan