ML13333C019

Summary of 840308 Meeting W/Utils in Bethesda,Md Re Licensee Revised Proposal for Integrated Living Schedule Submitted by .List of Attendees & Agenda Encl

ML13333C019
Person / Time
Site:	San Onofre
Issue date:	03/20/1984
From:	Mckenna E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
LSO5-84-03-030, LSO5-84-3-30, TAC-54376, NUDOCS 8403220001
Download: ML13333C019 (37)

Text

05 UNITED STATES A

NUCLEAR REGULATORY COMMISSION 0

WASHINGTON, D. C. 20555 March 20, 1984 Docket No. 50-206 LS05-84-03-030 LICENSEE:

SOUTHERN CALIFORNIA EDISON COMPANY FACILITY:

San Onofre Nuclear Generating Station, Unit No. 1

SUMMARY

OF MARCH 8, 1984 MEETING On March 8, 1984, representatives of Southern California Edison Company (the licensee) and members of the NRC staff met in Bethesda, Maryland.

The.purpose of the meeting was to discuss the licensee's revised proposal for an integrated living schedule as submitted by letter dated February 27, 1984. is a list of attendees at the meeting. is a set of handouts used during the meeting.

'The licensee presented their revised proposal for an integrated living schedule (ILS) which establishes implementation dates for all well-defined backfit projects. With these projects, the schedule spans three refueling outages.

Also provided are schedules for evaluation for several projects, such as the long-term seismic program and TMI Supplement 1 issues.

In these cases, the evaluation will determine the intended scope of required back fitting which will then be incorporated into the ILS for implementation.

With regard to the SEP Topics, the licensee will continue to work with the NRC staff to define the scope of any required plant modifications through the SEP Integrated Assessment process. These modifications will then be ranked by the ILS methodology to determine implementation schedules.

In a few areas, such as fire protection and equipment environmental quali fication, deadlines have been established by regulation and the licensee's expected schedule may not be compatible with these dates. The licensee will submit exemption requests for these issues.

6403220001 840320 PDR ADOCK 05000206 PDR

2 -

March 20, 1984 The licensee also summarized the actions they will need to complete for plant restart. They include submittal of the ILS license condition, exemption requests and several proposed changes to the technical specifications as well as resolution of issues related to the seismic reevaluation.

Original signed by Eileen McKenna, Project Manager Operating Reactors Branch #5 Division of Licensing

Enclosures:

1. List of Attendees

2. Handouts from meeting cc w/enclosure See next page DISTRIBUTION Docket NRC PDR' Local PDR ORB #5 Reading DCrutchfield EMcKenna OELD JNGrace EJordan ACRS (10)

NSIC CC list NRC Participants DL &

DL:

5 DL!Fk"1 DARB #5 EMcKenna:jc

%bCrutchfield 3 /19 /84

/V/84

Mr. Kenneth P. Baskin cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montogmery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:

Joseph 0. Ward, Chief Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U.S. Environmental Protection Agency Region IX Office ATTN:

Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 John B. Martin, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596

NRC/SCE MEETING San Onofre Unit No. 1 Integrated Assessment Living Schedule March 8, 1984 NAME AFFILIATION Gerald Hammond SCE Russell Krieger SCE Jack Rainsberry SCE Michael Short SCE Thomas Philips San Diego Gas & Electric C. Grimes NRC F. Miraglia NRC J. Hannon*

NRC D. Crutchfield*

NRC E. McKenna NRC

• Part-time Attendance Enclosure I

AGENDA REVISED INTEGRATED LIVING SCHEDULE SAN ONOFRE UNIT 1 REVIEW OF ORIGINAL SCHEDULE PURPOSE BASIS FOR SCOPE ESTIMATES PRIORITY LENGTH NRC RESPONSE REGULATORY REQUIREMENTS LENGTH ASSUMPTIONS REVISED SCHEDULE CRITERIA FOR INCLUSION OF PROJECTS CONSIDERATION OF PROJECTS WITH REGULATORY DEADLINES BASIS FOR SCOPE ESTIMATES SCHEDULING INCLUSION OF FUTURE PROJECTS SEP TMI LONG TERM SEISMIC OTHERS

ORIGINAL SCHEDULE SCOPE DEVELOPED TO ESTABLISH IMPLEMENTATION DATES FOR ALL POTENTIAL SONGS 1 BACKFITS INCLUDED ALL POTENTIAL BACKFITS PROJECTS WITH SPECIFIC SCOPES AND PREVIOUS SCHEDULES PROJECTS UNDER NEGOTIATION SEP TMI SEISMIC REEVALUATION PLANT BETTERMENT PROJECTS

ORIGINAL SCHEDULE COST ESTIMATES COSTS BASED ON CONSERVATIVE ASSUMPTIONS CURRENT DETERMINISTIC CRITERIA FOR ALL PROJECTS ESTIMATES BASED ON INFORMATION AS OF MID-1983 PRIORITY AND SCHEDULING WESTINGHOUSE ANALYTIC RANKING PROCESS NORMAL SCHEDULING TECHNIQUES

ORIGINAL SCHEDULE

SUMMARY

73 PROJECTS 15 CYCLES FOR INSTALLATION 2010 COMPLETION DATE NO PROJECTS DELAYED BY SCHEDULING CONSTRAINTS

NRC RESPONSE SCHEDULE NOT ACCEPTABLE SIGNIFICANT DELAYS IN IMPLEMENTING MODIFICATIONS PRESCRIBED BY REGULATIONS ADEQUATE JUSTIFICATION FOR SUCH LONG DELAYS IS NOT PROVIDED ASSUMPTION OF CURRENT CRITERIA TOO CONSERVATIVE REITERATE POSITION THAT ILS IS DESIRABLE

REVISED SCHEDULE SCOPE DEVELOPED TO ESTABLISH IMPLEMENTATION DATES FOR ALL WELL DEFINED SONGS 1 BACKFITS PROJECTS WITH REGULATORY DUE DATES TO BE IMPLEMENTED ACCORDING TO REGULATION OR HAVE SPECIFIC EXEMPTIONS PROJECTS WITH SPECIFIC SCOPES AND PREVIOUS SCHEDULES "EVALUATIONS" TO BE PERFORMED FOR PROJECTS UNDER NEGOTIATION PLANT BETTERMENT PROJECTS UNCHANGED

REVISED COST ESTIMATES REVISED SCOPES BASED ON SONGS 1 SPECIFIC CONCERNS ESTIMATES BASED ON INFORMATION AVAILABLE AT START OF FIRST QUARTER 1984

RFVISED SCHEDULF 26 TASKS 3 CYCLES FOR IMPLEMENTATION 1990 COMPLETION DATE PROJECTS WITH REGULATORY DUE DATES TO FILE SEPARATELY FOR EXEMPTIONS

INCLUSION OF FUTURE PROJECTS PROJECTS AS YET UNDEFINED TO HAVE IMPLEMENTATION SCHEDULES ESTABLISHED IN ACCORDANCE WITH ILS METHODOLOGY AS SCOPES.ARE AGREED WITH NRC EXAMPLES:

SEP TMI LONG TERM SEISMIC OTHER

CONCLUSION MEETS SCE NEEDS FOR STABILITY AND PREDICTABILITY MEETS NEEDS FOR RESPONSIVE IMPLEMENTATION OF PLANT SAFETY ENHANCEMENTS GEH:1116F

ENCLOSURE 1 SONGS 1 INTEGRATED LIVING SCHEDULE REGULATORY ITEMS BY REFUELING OUTAGE CYCLE 9 Title Efcomatic Actuator Replacement Electrical Drawing Verification Project Wide Range Gas Monitor Plate-Out: Evaluation Regulated Instrument Buses Safety Grade Upgrade of AFWS Equipment Regulatory Guide 1.97:

Evaluation Control Room Design Review:

Evaluation Replacement of SV99 Actuation Circuit Automatic Trip of Reactor Coolant Pumps:

Evaluation CVCS Valves MOV-LCV-1100B, C, D Waste Gas Decay Tank Monitoring Instrumentation Condensate Storage Tank Flooding Potential:

Evaluation Safety Parameter Display System:

Evaluation Inadequate Core Cooling: Evaluation Radiological Effluent Technical Specification Modifications Post Accident Sampling 02 and Cl Monitoring Improvements to Operational Radiation Monitoring System Resolve Long-Term Seismic Issues and Modification Schedule

SONGS 1 INTEGRATED LIVING SCHEDULE REGULATORY ITEMS BY REFUELING OUTAGE CYCLE 10 Title Third Train Auxiliary Feedwater Safety Injection System Modifications Replace GE Cable to RHR Pumps NIS Rockbestos Cable Replacement

SONGS 1 INTEGRATED LIVING SCHEDULE REGULATORY ITEMS BY REFUELING OUTAGE CYCLE 11 Title Health Physics Facility Upgrade, Including Facilities for Men and Women Reactor Coolant Pump Lift Rigs Steel Decking Under Turbine Deck North Extension Solidified Resin Storage Facility GEH:0886F

ENCLOSURE 2 OUTAGE SCHEDULE Cycle Begin Outage Return to Service January 1, 1985 9

April 1, 1986 July 1, 1986 10 January 1, 1988 April 1, 1988 11 October 1, 1989 January 1, 1990 GEH:0886F

Project Categories

1. Project continues to be under evaluation as part of the Systematic Evaluation Program. Evaluation is currently continuing.

2. Project is included in the seismic reevaluation program. Projects necessary to achieve hot standby to be completed prior to restart, long term resolution evaluation is included in ILS.

3. Project included in original schedule assumes major backfit effort. Current schedule reflects performance of an evaluation, the results of which may or may not indicate the need for further backfit.

4. Fire Protection Project has deadline as prescribed in Exemption letter dated March 23, 1983 based on the addition of a dedicated safe shutdown system.

5. Project currently under evaluation to determine necessity of implementation.

6. Project has deadline prescribed by Commission Regulation. Exemption request will be submitted separately to determine schedule.

7. Project has now been included in the return to service program.

SONGS 1 INTEGRATED LIVING SCHEDULE REGULATORY ITEMS BY REFUELING OUTAGE Revised Deletion Cycle of Priority Project Category*

Implementation Comments CYCLE 9 PROJECTS 1

SEP III-5.A Pipe Break Inside 1

Containment -

Leak Detection 2

Seismic Upgrade of Main Steam 2

and Feedwater Piping 3

Seismic Upgrade of Component 2

Cooling and SWC CYCLE 10 PROJECTS 3a Completion of Seismic Upgrade 2

of Component Cooling and SWC 4

SEP VII-3, XV-2, TMI, App. R 10 Lead times do Third Train Auxiliary Feedwater not allow Cycle 9 5

Seismic Evaluation of Electrical 2

Cabinets/Equipment 6

Seismic Upgrade of Residual 2

Heat Removal System 7

Efcomatic Actuator Replacement 8

SEP IX-3, Auxiliary Saltwater 1

Cooling Pump Upgrade (Partial) 9 Electrical Drawing Verification 9

Project CYCLE 11 PROJECTS 10 Wide Range Gas Monitor Plate-Out 3

9 Modification 11 SEP III-5.B, Pipe Break Outside 1

Containment-Leak Detection 12 Regulated Instrument Buses 9

• Categories explained on first page.

-2 Revised Deletion Cycle of Priority ProJect Category*

Implementation Comments 13 SEP 11-3.A & II-3.B, Hydrologic 1

Description and Flooding Potential High Groundwater 14 Seismic Upgrade of RWST 2

15 SEP IV-2, Reactivity Control 1

System Single Failure Protection 16 SEP IX-5, Ventilation System 1

Upgrades 17 SEP VII-l.A, Isolation of Reactor 1

Protection Systems 18 SEP V-11.B, RHR Interlock 1

Requirements 19 SEP V-11.A, Requirements for 1

Isolation of High and Low Pressure Systems CYCLE 12 PROJECTS 19a Completion of SEP V-II.A, 1

Requirements for Isolation of High and Low Pressure System 20 Safety Injection System 10 Lead times do Modifications not allow Cycle 9 21 SEP III-5.A, Pipe Break Inside 1

Containment -

Pipe Whip Restraints, Barriers, etc.

CYCLE 13 PROJECTS 21a Completion of SEP III-5.A, Pipe 1

Break Inside Containment -

Pipe Whip Restraints, Barriers, etc.

22 Safety Grade Upgrade of AFWS 9

Equipment 23 Health Physics Facility Upgrade, 11 Scheduling Including Facilities for Men constraints and Women do not allow earlier cycles.

-3 Revised Deletion Cycle of Priority ProJect Category*

Implementation Comments 24 Seismic Evaluation of Vent 2

Stack 25 SEP III-4.A Upgrade Plant 1

Structures and Equipment for Tornado Missiles CYCLE 14 PROJECTS 25a Completion of SEP III-4.A 1

Upgrade Plant Structures and Equipment for Tornado Missiles 26 Seismic Upgrade of Accident 2

Mitigation Systems CYCLE 15 PROJECTS 26a Completion of Seismic Upgrade 2

of Accident Mitigation Systems 27 SEP II.l.C (Also TMI and Seismic 1

Upgrade) Control Room HVAC Replacement/Upgrade 28 SEP 111-2 Upgrade Plant Structures 1 for Wind and Tornado Loads 29 SEP VI-7.C.2, Failure Mode 1

Analysis ECCS CYCLE 16 PROJECTS 29a Completion of SEP VI-7.C.2, 1

Failure Mode Analysis ECCS 30 Reactor Coolant Pump Lift Rigs 11 Scheduling constraints do not allow earlier cycles.

31 SEP VI-7.B, ESF Switchover from 1

Injection to Recirculation 32 Fire Protection Appendix R 4

Safe Shutdown -

Phase 1

-4 Revised Deletion Cycle of Priority Project Category*

Implementation Comments CYCLE 17 PROJECTS 32a Fire Protection Appendix R 4

Safe Shutdown -

Phase 2 CYCLE 18 PROJECTS 33 SEP VI-7.C.2, Redundant Valve 1

in Recirculation Path to Loop B Hot Leg (Partial Single Failure Analysis) 34 Regulatory Guide 1.97 3

9 Evaluation can be done in earlier cycle.

35 Replace GE Cable to RHR Pumps 10 Project to be more effectively implemented with EQ Project.

36 Steel Decking Under Turbine Deck 11 North Extension 37 SEP VI-7.C.2, Upgrade Redundant 1

N2 Supply to FCV 1115 DEF (Partial Single Failure) 38 Upgrade Temporary Volume Control 5

Tank Level Instrumentation 39 Seismic Upgrade of Electrical 2

Raceways CYCLE 19 PROJECTS 39a Completion of Seismic Upgrade 2

of Electrical Raceways 40 SEP III-5.B, Pipe Break Outside 1

Containment -

Pipe Whip Restraints, Barriers, etc.

41 Control Room Design Review -

3 9

Evaluation Phase 1 can be done in earlier cycle.

-5 Revised Deletion Cycle of Priority Prolect Category*

Implementation Comments CYCLE 20 PROJECTS 41a Control Room Design Review -

3 9

Evaluation Phase 2 can be done in earlier cycle.

42 SEP VIII-3.B, DC Power System 1

Bus Voltage Monitoring and Annunciation 43 SEP III-7.B Design Codes, Criteria 1 and Load Combinations Containment LOCA & Seismic Analysis 44 SEP VIII-4, Electrical Penetration 1 of Containment 45 Environmental Qualification -

6 Phase 1 CYCLE 21 PROJECTS 45a Environmental Qualification -

6 Phase 2 46 Valve Seat Upgrade/Replacement 7

CV 525 & 527 47 Replacement of SV99 Actuation 9

Scope is Circuit small and is Regional concern.

48 SEP.VI-4, Containment Isolation 1

Electrical (Partial)

Provide CIAS for Inside RCSS Valves and Eliminate Override on Outside Valves 49 SEP VI-4, Containment Isolation 1

Systems 50 Automatic Trip of Reactor Coolant 3

9 Evaluation Pumps can be done in earlier cycle.

-6 Revised Deletion Cycle of Priority Project Category*

Implementation Comments CYCLE 22 PROJECTS 51 CVCS Valves MOV-LCV-1100B, C, D 9

Scope is small and is Regional concern.

52 12 kV Construction Power System 7

Improvements 53 SEP VI-4, Containment Isolation 1

Electrical (Partial)

Diesel Generator Radiator Fans Loading 54 SEP VIII-l.A, Potential Equipment 1

Failures Associated with Degraded Grid Voltage 55 Waste Gas Decay Tank Monitoring 9

Scope is Instrumentation small and is Regional concern.

56 NIS Rockbestos Cable Replacement 10 Project to be more effectively implemented with EQ Project.

57 Condensate Storage Tank Flooding 3

9 Evaluation Potential can be done in earlier cycle.

58 SEP IX-3, Station Service and 1

Cooling Water Systems (Partial) 59 SEP VI-4 Containment Isolation 1

Electrical (Partial)

Re-Letter "Block SIS" Annunciator Window 60 Seismic Upgrade of South Turbine 2

Extension 61 SEP III-1, Classification of 1

Structures, Systems, and Components

-7 Revised Deletion Cycle of Priority Project Category*

Implementation Comments 62 Safety Parameter Display System 3

9 Evaluation can be done in earlier cycle.

63 Inadequate Core Cooling - Phase 1 3 9

Evaluation can be done in earlier cycle.

CYCLE 23 PROJECTS 63a Inadequate Core Cooling -

Phase 2 3 9

Evaluation can be done in earlier cycle.

64 SEP XV-1, Increase in Feedwater 1

Flow 65 SEP VII-3, Systems Required for 1

Safe Shutdown (Redundant Component Cooling Level Instrumentation) 66 Radiological Effluent Technical 9

Scope is Specification Modifications small 67 Post Accident Sampling 02 and 9

To be more Cl Monitoring effectively implemented with completion of PASS.

68 Improvements to Operational 9

Project has Radiation Monitoring System major regional concern.

69 SEP II-3.A, II-3.B and III-3.A.

1 Ventilation Building and Fuel Storage Building Rooftop Drainage 70 Solidified Resin Storage Facility 11

-8 Revised Deletion Cycle of Priority ProJect Category*

Implementation Comments 71 SEP V-10.A, Residual Heat Removal 1

Heat Exchanger Tube Failures 72 SEP V-5, Reactor Coolant Pressure 1

Boundary Leakage Detection 73 SEP III-8.A, Loose Parts 1

Monitoring System GEH:0314F

PROPOSED DEDICATED SHUTDOWN SYSTEM COMPLIANCE WITH 10 CFR 50.48(c) and III.G OF APPENDIX R TO 10 CFR 50 SAN ONOFRE UNIT 1 INTRODUCTION By letter dated November 18, 1982 the NRC accepted our plans for an Alternate Shut down System for compliance with the Safe Shutdown requirements of Appendix R to 10 CFR 50, which were submitted on June 30, 1982 in accordance with 10 CFR 50.48(c).

By letter dated March 23, 1983 the NRC granted in part, a schedular exemption to 10 CFR 50.48(c) as requested in our letters of June 30, 1982 and August 3, 1982.

The NRC decision specifically granted the following exemption with respect to schedular implementation of modifications and additions to San Onofre Unit 1 to meet the requirements of Section III.G of Appendix R to 10 CFR Part 50:

1.

The effective date of the Fire Protection Rule used for computing the implementation of the fire protection features specified in 10 CFR 50.48(c)(3) is replaced by October 31, 1983.

2. The date of NRC approval used for computing the imple mentation of the fire protection features specified in 10 CFR 50.48(c)(4) is replaced by October 31, 1983.

Based on this exemption decision, the Alternate Shutdown System modifications identi fied in our June 30, 1982 submittal must be completed prior to startup from the current outage in accordance with 10 CFR 50.48(c)(4).

The Alternate Shutdown System was prepared in anticipation of extensive modifications which would be required by the SEP Integrated Assessment.

To this date, no large set of modifications has been identified by SEP. It is therefore desired to provide a shutdown system which only resolves the issues of Section III.G of Appendix R. This will provide a system which will facilitate compliance with NRC schedules and require ments and can be incorporated into the San Onofre Unit 1 Integrated Living Schedule.

DEDICATED SHUTDOWN SYSTEM A Dedicated Shutdown System (DSS) is being developed which will comply with the requirements of Section III.G.3 of Appendix R. The DSS will provide a dedicated power supply using a non-safety related diesel generator and associated electrical equipment. In addition, the systems required to achieve and maintain cold shutdown will be limited by the use of the steam generators in a single phase mode of heat transfer when steam can no longer be generated. Indication and control will be localized at the auxiliary control panel which will be powered by the dedicated diesel.

Operator action will be relied upon as appropriate to perform required system control actions.

-2 The associated circuit problem will be greatly reduced by using dedicated power supplies only. *The normal sources of electrical power will be completely de energized using a procedure similar to the one now in effect per the interim safe shutdown procedure. Where required, limited re-routing may be necessary.

An additional impact on the existing Fire Protection Program at San Onofre Unit 1 will be the addition and redefinition of fire areas for the DSS implementation in accordance with the requirements of Section III.G of Appendix R and the generic guidance which has been issued by the NRC subsequent to the effective date for 10 CFR 50.48. These changes will most likely require a complete revision of the Fire Hazards Analysis for San Onofre Unit 1.

ENVIRONMENTAL QUALIFICATION EXEMPTION REQUEST

1. Determine which equipment will be qualifiable Establish schedule for qualification I

Provide JCO's for qualification beyond startup Utilize JCO's as basis for exemption

2. Items which are not qualifiable Provide JCO's (if not replaced prior to operation)

Obtain replacement equipment Establish a replacement schedule Obtain exemption from deadline Utilize JCO's as basis for exemption

.JCO's Extent of Qualification (Possible Failure Modes)

Affect on System Backup/Redundant Equipment/System (Overall Safety Function is Performed)

Affect of Equipment Failure

POST ACCIDENT SAMPLING SYSTEM (PASS)

SAN ONOFRE UNIT 1 I.

INTRODUCTION The San Onofre Unit 1 PASS is a Combustion Engineering (CE) skid mounted unit. It is installed in an underground pit with two chambers, for shielding purposes. The first chamber, accessible only when the shielded cover is opened, contains the PASS skid, piping from the containment, electrical and control penetrations, a HVAC system for environmental control, and a sump.

The second is the operator's control area with the control boards and it's own HVAC system and also is shielded from the first chamber. The second chamber is accessible by an entry stairwell.

It is approximately 400 feet from the control room and is within the radiation control area.

II. CONSTRUCTION TO DATE Action Date Purchase Order issued to CE.

June, 1980 Construction of PASS Pit Initiated.

January, 1981 Final Construction to Receive PASS August, 1981 Skid into PASS Pit.

CE PASS Skid Delivery to Site September, 1981 CE PASS Skid into Pit.

January, 1982 CE/SCE Punch List initiated to track July, 1982 numerous startup problems.

Many Unit 1 parts utilized by San Onofre September, 1982 Units 2 and 3 for startup of similar through CE PASS units.

January, 1983 Minimum Effort and Improvements, Including May, 1983 Presevation.

through Present

-2 III. START-UP REQUIREMENTS Action Time Required Procure Replacements for Parts Utilized 3 month lead time for San Onofre Units 2 and 3.

Reinstall Components and Perform Remaining 4 months PASS Skid Upgrades.

Perform Start-Up Testing (after 4 months -

real installation of parts and completion time assuming of upgrades).

no system failures 9 months, actual time based upon experience at San Onofre Units 2 and 3 Training & Operational Procedures 6 months Checkout.

Total Time to Complete Above Itemized 22 months Actions and Declare PASS Operational

REQUIREMENTS FOR RETURN TO SERVICE

1. Fire Protection modifications as specified in Supplement 1 to Fire Protection SER dated February 4, 1981 with the exception of Safe Shutdown.

2. TMI modifications as specified in confirmatory order dated March 14, 1983 with the exception of PASS.

3. Seismic Upgrade of Safe Shutdown Systems as described in Restart Plan.

4. Submit proposal for Dedicated Safe Shutdown System.

5. Submit Request for deferral of PASS.

6. Provide an exemption to EQ March 31, 1985 deadline.

7. Submit proposed change to Fire Protection Tech Spec for new modifications and superceding P.C. No. 92.

8. Respond to NRC questions on Operating History and Reliability of Transamerica Delaval Diesel Generators.

9. Implement Post-Trip Review Program and Procedure.

10.

Provide NRC with information concerninq Post-Trip Review Program and Procedure.

11.

Submit Revised Proposed Change which includes Auxiliary Saltwater Cool ing Pumps and Screen Wash Pumps as backup.

12.

Provide information regarding operability of Containment Vent Valve Actuators.

13. Provide a revision to Proposed Change No. 124 which will incorporate Appendix J Leakage Testing Requirements for the Personnel Air Locks.

14. Respond to NRC comments on P. C. No. 128.

REQUIREMENTS FOR RETURN TO SERVICE (continued)

PAGE 2

15.

Submit revised Tech Spec on OMS.

16. Submit ILS license condition.

17.

Radiological Effluent Tech Specs.

18.

Provide NRC with PC on Heatup and Cooldown curves.

19. Proposed Change on Organization.

20. Reanalyze qualification of Charging Pumps to include increased temperature.

21.

Submit license condition requiring:

a. Shutdown within SEFPM for Steam Generator Inspection

b. Submit inspection plan 45 days prior to startup.

22. Technical Specification on Plant Staff Overtime.

23.

Post-TMI Technical Specifications.

24. Submit Proposed Change to Technical Specifications on AFWS.

PROPOSED CHANGES UNDER NRC REVIEW March 7, 1984 Proposed Change Submitted to No.

NRC SUBJECT 76 10/20/78 Revises T.S. 4.4 on Surveillance requirements for the Station Battery System. Superseded by P.C. #126.

83 09/12/79 Incorporates radiological T.S.

per 10 CFR 50 Appendix I.

(12/17/81) 92 04/04/80 Adds T.S. to cover new Fire Protection Systems. To be super seded by P.C. #136.

115 03/30/83 Liquid & Gaseous Effluent Releases.

Only if P.C.#83 is not approved.

120 07/20/83 Appendix A, Boron Dilution Require ments.

124 09/09/83 Containment Isolation Testing.

126 11/30/83 DC Battery Surveillance Require ment.

128 12/05/83 Decay Heat Removal Capability 129 12/05/83 Deletion of Non-Radiological Regulatory Requirements.

PROPOSED CHANGES BEING DRAFTED 119 Appendix A, Nuclear Power Plant Staff Working Hours.

125 Post TMI Technical Specification 127 AFW Technical Specifications.

130 sent to station 3/5/84 Organizational Change.

134 License Condition on ILS.

135 Aux. Saltwater Cooling Pump.

136 Fire Protection.

SEISMIC ISSUES WHICH MUST BE RESOLVED PRIOR TO IMPLEMENTING RTS PLAN

1. Methodology and criteria for evaluating pipe reaction loads on structural members.

2. Methodology and criteria for evaluating structural member connections.

3. Requirements to support 25% reduction in containment response spectra.

4. Criteria for small bore piping walkdowns.

SEISMIC ISSUES WHICH MUST BE RESOLVED WITH NRC PRIOR TO RTS

1. Piping evaluations

2.

Pipe reaction loads on structures

3.

Electrical raceways

4. Masonry walls

5. Vent stack

6. In situ backfill soil conditions

7. Vertical ground motion

8. Pipe support bending calculation

9. Review of EG&G piping calculations