IR 05000322/1988010
| ML20205T721 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/02/1988 |
| From: | Blough A, Crescenzo F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205T713 | List: |
| References | |
| 50-322-88-10-MM, NUDOCS 8811140365 | |
| Download: ML20205T721 (160) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION Region I Meeting No.:
50-322/88-10 Docket No.:
50-322
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License No.:
NPF-36 Licensee:
Long Island Lighting Company Post Office Box 618 Shoreham Nuclear Power Station Wading River, New York 11737 Facility Name:
Shoreham Nuclear Power Station Meeting At:
USNRC, Region I, King of Prussia, Pennsylvania Meeting Conducted: October 17, 1988 Prepared By:
M
//-1~8P d4 Frank Cresetrnzo, Senior Resident Inspector Date Approved By:
/ /- 2-PP X~ Randy 6 Tough, Chief Date Reactor Projects Section No. 3B Meeting Summary:
A management meeting was held a NRC Region I on October 17, 1988, to discuss the readiness of the Shoreham facility and staff for power operations above 5%
power.
The meeting lasted three nours.
A consultant to Suffolk County monitored the meeting.
GS11140365 881102 PDR ADOCK 05000322 O
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OETAILS 1.0, Purpose The management meeting was held at the request of Region I to. discuss the licensee's readiness for power operations above 5% power. The information
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will be used by Region I staff in planning and allocating inspection resources to Shoreham.
2.0 Meeting Summary The reeeting was opened with brief comments by NRC Region I Administrator, Mr. William T. Russell. Mr. R. Youngdahl, opened the Long Island Lighting
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Company's (tILCo) presentation by highlighting the readiness of his staff to complete the necessary actions required for issuance of a full power license. Presentations were then made by LILCo managers to address the i
readiness of each of the t..ajor functional organizations at the facility.
A copy of the presentation materials is enclosed as Attachment I.
Overall, the licensee's presentation suggested the facility ai a staff at Shoreham are near ready for power operations above 5%. No major obstacles to readiness were icentified by the licensee.
Staffing and morale were presented as adequate and it was suggested these areas would improve upon issuance of a full power license.
The programs for Operations, Operations Support, Engineering, Training, and Quality Assurance are established and adequately staffed.
The facility is near ready for critical operations and only minor work items remaia, outstanding.
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The licensee is also coordinating a self assessment of its readiness status. Each of the major onsite programs will be self-assessed, and the Quality Assurance Department will conduct a comprehensive self assessment encompassing all major areas of plant readiness.
Tha licensee hopes to conclude the assessment and issue its report by mid-November.
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Meeting Summan Mr. Russell closed the meeting by acknowledging the licensee's presenta-tion, and by suggesting the licensee keep the Regiunal staff informed as to facility readiness for NRC inspection activities, Me, Russell stated that NRC readiness assessment inspection activities would not commence until at ter the licensee completed its self cssessment. The licensee was encouraged to focus its self assessment on personnel performance factors as well as program adequacy.
Attachments:
1.
Meeting Attendees 2.
Licensee presentation Materials
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ATTACHMENT I, Meeting Attendees U S. Nucleae Regulatory Commission W. Russell, Regional Administrator W. Kane, Director, Olvision of Reactor Projects (LRP)
S. Collins, Deputy Olrector, ORP W. Johnston, Deputy Director, Division Reactor Safety (ORS)
J. Wiggins, Chief, Reactor Projects Branch No. 3, DRP M. Shanbaty, Chief, Facilities Radiation Protection Section, Division of I.adiation Safety and Safeguards (DRSS)
A. Randy Blough, Chief, Reactor Projects Section No. 3B, ORP J, Gutierrez, Regional Counsel F. Crescenzo, Senior Resident Inspector, Shoreham S. Brown, Project Manager, Office of Nuclear Reactor Regulation L. Doerflein, Project Engineer, ORP
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S. Horwitz, Public Affairs, RI N. Conicell:, Operations Engineer, DRS
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Long_I,sjand_ Lighting Company R. Youngdahl, President, long Island Lighting Company J leonard, Jr., Vice President - Office of Nuclear Operations S. Skorupski, Jr., Assistant Vice President - Office of Nuclear Operations W. Steiger, Plant Manager J. Smith, Director - Office of Training E. Youngling, Manager, Nuclear Engineering Department J. Notaro, Manager, Nuclear Quality Assurance Department C. Davetio, Manager, Nuclear Operations Support Department Other Attendees S. Sholly, MHB Technical Associates, Consultant to Suffolk County S. Benkelman, Newsday, Reporter
P. Gutis, New York Times, Reporter
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.i Readiness Meeting
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Octoaer 17, -988
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i u Table of Contents Iab 1.
Organizational Readiness
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SNPS Plant Readiness 3.
Engineering & Tech Support Readiness 4.
NOSD Readiness
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OA Readiness
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l Nuclear Operations Organization it.C. Youngdahl President
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J.D. Le onard, J r.
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Nuclear Operatione l
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S.S. Skorupaki Q
A'est VP J.A. Notato J.L. Smith Nuc. Ops.
Direotor Manager Tr alning NQAD C.A. Dave.;0 W.E. Steige r, Jr, E,J. Youngling Manager Manager Manager NOSD SNPS NED I
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Direct Access
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As Needed
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i Shoreham l
Nuclear Power
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October 1988
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SHOREHAM NUCLEAR POWER STATION PLANT READINESS
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- Operations and Startup Testing a Maintenance
- Radiological Controls
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- Surveillance Activities
- Outage and Modification
- Self Assessment I
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001 88
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OPERATIONS AND STARTUP TESTING i
- Operators Code of Professionalism
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- Operations Staffing i
- Operator Ti s!alog a EOPs Upgrnded to Rev. 4 GWR-CPGs
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- Test Cor.dition Heatup l
- STP Lessons Learned Review
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- STP Transients Performed on SNPS Simulator l
- Performance Monitoring Program Revised l
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SNPS-2 OCT 88
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l OPERATIONS STAFF Read. By Tech Soec Current Staff WE (1)
SRO (1)
WS (SRO) (1)
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RO (2)
NSO (RO) (1)
NASO (RO) (2)
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EO (2)
Radwaste Operator (1)
Ol Equipment Operator (5)
STA (1)
STA (1)
OPS Shift Advisor
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Five Of The Six Crews Have An Equipment Operator Who Possess And Maintains An Active RO License.
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Established 2 Day Watch Engineers
O SNPS-3 OCT 88
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O OPERATOR TRAINING
- On-Shif t Training Programs Accredited by INPO Licensed Operator Equipment Operator
Radwaste Operator Shif t Technical Advisor 1987 and 1988 NRC License Examinations identified No Generic Weaknesses O
8 SRO ticenses eranted 7 RO Licenses Granted
. December 1988 License Candidates
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- Field Operator Training Emphasized Startup Equipment
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Lubrication Control
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EOP Field Work O
SNPS-4 OCT 88 L
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OPERATOR TRAINING READINESS FOR S/U
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Shoreham Crew Simulator H'
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BEFORE 88 INPr) GOAL 88 REQUAL LEAD CREW 88 SNPS#4a
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Q ;lr EMERGENCY OPERATING PROCEDURES i
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Shoreham EOP's Currently Conform to
l BWR-EPG Revision 4 EOP Upgrade Completed May 1988
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SNPS Is the Second BWR in Region 1 To Be At Revision 4 NRR Has Authorized Use of Revision 4 EOPs i
O Shoreham procedures eeneration Package
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Originally Submitted March,1987 NRC Reo,ut, Ic" Additional Information (RAI)
April,1988 SNPS Response to RAI Submitted July,1988 l
l NRR Review Pending
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TEST CONDITION HEATUP
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July 3,1985 5% Low Power License Received
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July 9,1985 SRV Functional Test Performed l
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I July 11,1985 150 PSIG Plateau Reached.
System Expansion DW Entry.
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i August 7,1985 Rated Pressure Plateau. System l
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l Expansion Testing. HPCI O
T* * " " S **'* r '*v ' ' T* * " " S -
Chemical And Radiochemical
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Testing. Radiation Measurement
October 4,1985 RCIC Vessel injection At Rated
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Pressure.
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October 6,1985 Initial Turbine Generator Roll l
To Rated Speed.
October 8,1985 End of Heatup Testing.
Begin Source Replacement
Outage
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SNPS-Ba OCT 88
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O TEST CONDITION HEATUP (Continued)
l August 3,1986 Startup For 5% Retest Program.
August 21,1986 RCIC Tuning At Rated Pressure August 23,1986 HPCI Tuning At Rated Pressure August 24,1986 RCIC Vessel Injection And Stability Demonstration At i
l 150 PSIG.
August 25,1986 Main Turbine Roll And O
excitation checks.
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l August 26,1986 Main Turbine Generator
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Synchronization To The Grid l
And 24 Hour Run.
t August 27,1986 RCIC Cold Quickstart t
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August 28,1986 HPCI Quickstart And Stability Demonstration At 150 PSIG l
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August 31,1986 Reactor Shutdown And Cooldown
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O SNPS-6b OCT 88
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TEST CONDITION HEATUP (Continued)
May 22,1987 Reactor Startup.
May 26,1987 ADS Valve 18-Month Surveillance.
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May 31,1987 RCIC Functional And Stability
Demonstration From Remote
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Shutdown Panel, i
June 4,1987 Generator Synchronized For 8-Hour Run.
June 5,1987 HPCI Endurance Run.
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June 6,1987 Reactor Shutdown And Cooldown
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l!O SNPS-6c OCT 88 l
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STP LESSONS LEARNED REVIEW
- PATP Test Reduction And Optimization Program Reviewed General Electric Startup Test
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Reduction Program And Selected Specific Activities That Would Reduce Unnecessary Challenges To Safety Systems.
Individual Test Changes Were Approved By General Electric Via FDDR's And Modifications
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i To The General Electric Startup Test Specification.
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O hanges ROC Reviewed Reviewed STP's Against Other BWR Startup a
Reports For Lessons Learned:
Clinton Nine Mile Fermi Perry Reviewed STP's Against Other BWR STP's:
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Hope Creek Limerick O
SNPS-7a OCT 88
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STP LESSONS LEARNED REVIEW (Continued)
Neutron Flux Stability Recirculation System Bistable Flow a
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SNPS-7b OCT 88
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O STP LESSONS LEARNED REVIEW (Continued)
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- Changes Made To Address And Enhance STP's L
In The Following Areas:
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Deleted Rod Pattern Exchange Startup Test j
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Control Room From Greater Than 20% to Between
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10 And 25% Of Rated Power Deleted Maximum Power Search For MSIV Fast O
closure Surveiiiance e
Allowed Re' actor Water Cleanup NPSH To Be
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Evaluated Using Preop Data l
Widened TC-4 Natural Circulation Testing Window To Between 75% And 100% Power Rod Lines
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Corrected Level Criteria For Recirculation Flow Controi System To Be Commensurate With
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Prior Deletion Of Auto Load Following Testing j
t Refined Acceptance Criteria For EOC-RPT i
Coastdown f
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SNPS-7c OCT 88 O
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Control Room Operators, Reactor' Engineering
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STP 22 Pressure Regulator
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l STP 24 Main Turbine Valve Surve!Ilance STP 25 MSIV's j
STP 27 Turbine Trip And Load Reject i
STP 28 Shutdown From Outside Control Room
S1 P 29 Recirc Flow Control System
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lO STP 30 Recirculation System l
STP 31 Loss Of Offsite Power l
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- Changes Made To Address And Enhance The i
Following Areas j
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Human Factors
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Team Work And Communications
Data Retrieval And Required Analysis
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i Administrative Duties (Crew Briefings, ETC)
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Dovetails To Normal, Abnormal, Emergency Procedures l
Dovetails To Special Startup Tech Specs l
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!O SNPS-8 OCT 88 l
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O MAINTENANCE
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- Maintenance Program Self Assessment
- Work Planning & Scheduling Reorganization
- MWR Prograni improvements
- Foreman Rotation Program
- Maintenance Training Programs Accredited
- Security Computer Reliability Upgrade
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- Lubrication Program Review
- Upgrade of RMS Surveillance Procedures
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- Purchase of Spare Computers to Facilitate Maintenance, Training & Testing
- Hypochlorination System Performance Upgrade
- Replaced 'B' Station Battery - End of Life 12 Years Old O
Snes-a oCT 88
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MWR PROGRAM IMPROVEMENTS j
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- Revised MWR priority system to address outage j
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- Conduct field walkdowns of proposed MWRs
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- Increased Job pre-planning Breakdown of work activities to the task level
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Provide estimate of RWP hours i
Verify materiel status
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. increased field supervisory time for foreman
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- Improved MWR, PM and Surveillance scheduling
l Weekly work plan l
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Plan of the day for work activities
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Daily work status updated by field foreman
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- Report monthly MWR trends to management and
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field supervision
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O SNPS-10 OCT 88 i
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O LUBRICATION PROGRAM
- Program review started in response to comments from region administrator's tour of SNPS and IEN 88-12 'Overgreasing of Electric Motors"
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Research all motors servicing rotating equipment for greasing requirements through field inspection and review of vendor requirements O
correct deficiencies which exist in froid Review all PM SAWS for correct lubrication practices Ensure lube codes clearly define proper method of greasing Revise program to improve control of lubrication activities O
SN PS-11 OCT 88
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- Solit injection System to Provide Separate Injection for RBSW/TBSW
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a Replaced Sample Pump to Enhance System Reliability l
- Reworked Inlet Piping to Sarr.ple Pump to Enhance Maintainability
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- Added Supoorts to RBSW/TBSW Injection
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Systems to Eliminate Vibration Induced O
Piping Failures i
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- Added High Chlorine Concentration Trip i
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to Ensure Compliance with SPDES Permit
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O SNPS-12 OCT 88 i
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O RADIATION MONITORING SYSTEM SURVEILLANCE PROCEDURES M/O REFUEL
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Funct Cal & Runct
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D11-P NL-13 Liquid Radwaste Mon Disch.
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D11-P N L-19 Drywell Filter Train Exhaust P
W D11*P N L-21 Low Range Station Vent post P
W Accident
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D11'P N L-22 Low Range RBSVS Post Accident p
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D11-P NL-23 A/B RHR A/B Discharge Rad Monitor p
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l D11 PNL-25A/B Control Room Vent Intake itad p
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C/D Rad Monitor l
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sitioa v ai ex8 u ia e e
e Monitor
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i D11 PNL-61 Containment Drywell Atmosphere P
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D11-P NL-7 9 Salt Water Drain Tank Discharge P
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D11 PNL-128 HI Range Station Vent Post p
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D11 PNL-134 High Range RBSYS Post Accident p
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j D21 RE-85A/B Primary Containment High Range yfg pfw Area
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D21-PNL-85A/B Indication & Alarm Panel N/A W
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Legend P= Performed in Field We Written - ROC Approved
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l D11-PNL-24 RBCLOW Sys W
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D11-PNL-29 Reactor Bldg Vent Exhaust W
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D11-PNL-45 Radwaste Steam Generator W
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)O j D11-PNL-52 Hot Water Heating System W
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Heat Exchanger
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D11-PNL-53 Steam Seal Evaporator W
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D11-PNL-54 TBCLCW W
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! D11-PNL-55 Radwaste Bldg Vent Exhaust W
D11-PNL-57 Turbine Bldg Vent Exhaust W
l D11-PNL-77 Radwaste Tank Vent Exhaust W
D11-PNL-81 Radwaste Sample Room W
D11-PNL-127 PASF Vent P
I I D21-RTS-46 Analog Interface GAMC P
i SNPS-13a OCT 88 O
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RADIOLOGICAL CONTROLS
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- Radwaste Program Self Assessment
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- Radwaste Process improvments i
- Water Management Program Established
- PASF Ready For Above 6% Operation
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- Radiochemistry Laboratory Certified By NYS l
l Department Of Health For Environmental Lab j
Program i
Split Sample Program - Excellent Results
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BWORG Chemistry Guldlines Adopted l
a Computerized Chemistry Data Management i
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- New Health Physics Procedures Prepared
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- ALARA Training Expanded
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- Purchased and installed New Health Physics
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O RADIOLOGICAL CONTROLS (Continued)
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- Received National Voluntary Laboratory Accreditation Program (NVLAP) Certification in All Eight Categories For Inhouse Dosimetry
Processing ( 10 CFR 20)
- Health Physics And Radiochemistry Technician Training Programs Accredited l
- Health Physics Personnel Assignraents At i
Operating Nuclear Power Station (7 Technicians,4 Supervisors) To Maintain P""*'"**d'"'"
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sNes-14b oCT 88
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O RADWASTE PROGR.AM SELF ASSESSMENT
i Reorganized Radwaste Section
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Evaluated HIC Handling for ALARA Consideration
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Improved Evaporator Level Measurements l
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Evaluated Compactor Operation
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I i O SN PS-15 OCT 88
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RADWASTE PROCESS IMPROVEMENTS
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Revised Operating Philosophy Based Upon
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j Decision Matrix Analysis I
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Evaluated Procedure Workability At Full Power
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i Established Monitoring And Mitigation Controls
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For Oil Intrusion into Sumps
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l lO SNPS-16 OCT 88
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Monitor Sources Of input To Detect
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lO SNPS-17 OCT 88
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O POST-ACCIDENT SAMPLE FACILITY OPERABILITY Procedures in Place Emergency Operation, Routine (Testing)
i Operation,
Instrument Calibration And Maintenance i
PASF Preventive Maintenance Program i
j Twice Per Week
- Check pH/ Boron Analyzer j Q Weekly
- Check ION Chromatograph
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l Monthly
- Conductivity Functional
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- Equipment inventory L
- Vent Tanks l
- Radiation Monitor Source i
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Check
- Check Panels, Lamps, i
i Standards, Etc.
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- IC Maintenance
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- Operate Facility (Liquid /
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SNPS-18a OCT 88
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--
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- -
- - - - - - - - - - - - - _ _ - -
- - _ - - - - - - - - - - - - _ - - - _ - _
,
i O POST-ACCIDENT SAMPLE FACILITY OPERABILITY
PASF Preventive Maintenance Prcaram (Con't)
l
,
I 3 Months
- O-Ring Check, Leakage 6 Months
- Coolant Gas / Isotopic Sample
- Valve Lineup i
- Test Matrix 10, ph/ Boron
'
- Oxygen Analyzer Calibration /
!
Maintenance
!
Yearly
. Replace pH/ Boron Electrodes l
.O
'
'
.
18 Months
- Conductivity Monitor Calibration i
- Radiation Monitor Calibration
!
PM Activities Average 100 Manhours Per Month
!
l l
Results Over Last Year i
- Demonstrated Ability To Sample And Analyze
!
!
- No Long-Term Instrument Malfunctions l
i i
i i O sNPS,eh ocr 88
-
!
[
-
_
- _
I
_
SPLIT SAMPLE QUALITY CONTROL
,
l j
- Inter-Laboratory Analyses
'
NUS - Annual
,
NWT NENCA - Quarterly NWT QCHEM - Quarterly
,
i AN ALYTIC (Radioactivity) - Semi-Annual i
ELAP (NYS DOH) - Annual EPA - Annual
i OC Division - Quarterly
J
- Inter-Laboratory Results
- O R*d'o*ot'v'tY ^"*'YS ** - '
- ^Sr**m*"t
)
Samples include: 1-131 Cliarcoal, Xe/Kr Gas,
Gamma Isotopic Particulate Filter, Gamma Isotopic Liquid (Reactor Coolant), Tritium,
'
-
l Gross Beta, Gross Alpha
!
I Water Chemistry Analyses - 97% Agreement
'
Samples include: Chloride, Fluoride, Sulphate, j
'sphate, Silica, Boron, Total Organic Carbon, ils (Cr, Cu, Fe, Na, Zn)
I
.
fQ SNPS-19 OCT 88
-
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i
CHEMISTRY DATA MANAGEMENT PROGRAM
Main Frame Computer Program 80% Developed
Elements Of System Routine Analysis Data Sheets Mirrored On Terminal Keyed To System, Sample Date & Time Browsed By Any User Password Control For Add, Review, Revise, Delete
Output Available O
cata Summaries (All System Parameters Over Specified Time)
Data Statistic Special Reports (Hours Above Limits / Goals, INPO Performance Indicators, Fuel Warranty Reports)
Trend Plots For Any Parameter On File includes 30 Specified isotopes Daily Plant Chemistry Summary (Proposed)
Benefits Wide Distribution Of Data Real Time improved Trending More Parameters Trended O
SNPS-20 OCT 88
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O i
ALARA TRAINING
i i
Formal Program (Classroom)
<
ALARA For Radiation Workers ALARA For First Line Super \\lsors l
ALARA For Design Engineer ALARA For Management
-
Special 'Ha, ids-On" Training i
e
,
!
Approximately 4 Days in Duration
,
'
,
One Day Classroom
!
.O Rwe, MwR, ach pianning, Est. uan-Rem,
'
Radiological Controls
'
.
3 Day Mockup ' Hands-On" I
'
i l
Scenario Developed (Disass Pump, Replace Gaskets, Etc)
j i
included Performace Of A Job With
'
!
Simulated Radiological Conditions l
Use Of PC's, Containments, Etc.
j Health Physics Personnel Interact As
'
H.P. Coverage Video Tape With Crhiques
O SNPS-21 OCT G8 i
!
.
- __ - _ _
-
_ -
- -..
-. L
-
- - - - - - -
,
C SURVEILLANCE ACTIVITIES l
All 002 And 001 Surveillances That Can Be Performed in Our Present Operational Condition Are Completed
.
Major Surveillance Activity Period Completed
9/30/88 388 Surveillance Procedures For 8797 Manhours O
No Surveillance Scrams Or ESF Actuations Directly Attributable to Personnel Errors No Surveillances Due Requiring A Plant Outage
Until 1/6/89 l
l 0-SNPS-22 OCT 88
-
.
-
O TECHNICAL CORRESPONDENCE
,
CILAR Program Priority 1 Same Major Equipment As SNPS Priority 2 Generic Or Similar To SNPS Priority 3 May Apply To SNPS O
-
Priority 4 Information Only items
,
O SNPS-23a OCT 88
_ - _ _ - _ _ _ _ - - - - _ - _ _ _ _ - - - _
-
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10CFR50.73 RELATED
L.ENRF.ND 3/1/88 To 7/31/87 8/1/87 TO 9/30/88 ag. '
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a MONTHS
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READINESS SELF ASSESSMENT c
i
. Establish Plant Self Assessment Team Team Leader Assistant Plant Manager
Team Composition Managers, Section Heads
-
Supervisors, Foremen and Physical Workers From All SNPS Areas; Peer Evaluators from other Utilities Scope Assess Readiness Of Physical Plant And Of Personnel For O
100% Full Power Operation
'
Duration Two Weeks October 10 Thru 21 Focus Activities With Greatest Impact On Safety How Direct Observations, Personnel interviews, Document Reviews s
Manhours Estimate 1500 l
O sses-24 ocT 88
.
O
'
READINESS SELF ASSESSMENT Types Of Activities To Evaluate Assess Personnel Readine.ss To Operate
Assess Radiation Protection Practices
,
Assess Physical Plant Readiness (EG;
=
Line Ups, Scaffolds, Labelling, Gas Bottle Storage, Mechanical Jumpers)
Inspect Plant Equipment inspect Plant Material Condition O
& Housekeeping Audit & Reverify Logs (LL&J, MWR, Temp Mod, Etc.)
Review And Analyze MWR Backlog (Any Incomplete Work)
Modification Closecuts
,
incomplete Maintenance Activities Review All Open NRC IEN, IEB & Generic Letters
Review All Open ISEG Recommendations
(Incis SOER, SEER, O&MR's)
Review Past NRC Inspection Reports For
Open items Or Concerns And Check Follow Up
i O SNeS-2s OCT 88
'
'
.
---
- - - -
--
__
.
-
-.
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Nuclear i
Engineering Department
,
!
October 1988
,
i
'
u
-.-
--..
..--
.
-
-
- -
-.
.
O Engineering and Technical Support l
SNPS Engineering and Technical Support
Disciplines Day-To-Day Support Functions
Plant Support Activities
O Engineering Assurance Activities a
t Design Transfer
'
.
l Engineering Activities
,
!
Operational Roadiness Evaluation
l O
NED#2
_
_
_... - _ - _ _, -
... _ _ _ _, _ _ _ _ _ _ _ _ _ _ _.
_
.
..
w a
C)
Shoreham Engineering And Technical Support Disciplines
- Mechanical
- Electrical
- Instrument & Control
- Civil / Structural
- Engineering Mechanics
- Materials Engineering O
'* ^ " ' Y * ' *
- Health Physics Engineering
- Thermal Hydraulic Analysis
- Equipment Qualification
!
- Project Management
'
l
- Reliability Engineering
- Fire Protection Engineering
- Radiological Analysis O
NED#3
_
___
O Day-To-Day Support Functions Engineering Support Team On-Call 24 Hours
A Day, Seven Days A Week
.
Project Engineering Provides Focal Point For All Engineering Support Requests Actively Participate in:
-
Weekly Department Managers Meeting Plant Management Meetings
-
.
>
O Plan-Of-The Day Meetings
-
,
Nuclear Review Board (NRB)
-
Modification Review Committee (MRC)
-
Site Safety Committee
-
Corporate ALARA Review Committee
-
Nuclear Training Review Committee
-
l l
l Procurement Committee
-
Applicable Quallty Assurance Audits
-
Entrance And Exit Meetings O
NED#4
.
-
- - -
,, _ - -. -., - - - - -,. -, _. - _ -
,.,.., _. - - _ - _.., - _ _. - _. - _. _ _ _ _,.
-___.,,--_c.,
-..--.,,. - - ___--, -. -- ---_ _ - - -
_-
O Pl ant Support Activities 1987 - 1988 Design Output Packages
(DOPs)
Engineering Change 1,644
'
Requests Safety Evaluations 15 8
NRC Bulletins, Circulars 122
O
& Notices L,lLCO Deficiency Reports 708
(LDRs)
Vendor Technical Bulletins
'
ALARA Reviews
- Spare And Replacement 1019 Part Technical Reviews
.
O NED#5
__
_ _...... _
.
_.. __,__.
_ _ _ _ _ _ _ _ _ _ _ _ _.. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,
_ _., _ _ _.., _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
')
'
Engineering Assurance Activities Design Transfer Independent Readiness
.
Assessments 62 Assessments Engineering Activity Surveillances
.
in 1987
- 1988:
On-Going Verbatim Compliance Checks in
.
Areas Of:
1987-1988 Safety Evaluations
-
-
Calculations
-
LDR Dispositions
O NED#6 i
l
_
_
O Design Transfer
Purpose is To Transfer Design Responsiblity
'
From The Architect Engineer (Stone & Webster)
To LILCO
,
Formal Transfer Process Consists Of
Design Transfer Document
-
identification / Packaging Development Of SNPS Engineering
-
Technology Manual O
Training Sessions On Design Criteria
-
Self Assessment Of Readiness Of
-
Design Group
!
Independent Evaluation By LlLCO EA
-
!
Department Manager Approval
-
>
Overall Transfer is 90% Complete
Stone & Webster Continues To Review LILCO
'
Work During This Period
- O NED#7
._
_
.
_, _ _ _ _ _ _ _... _
..
_ _ _ _ _... _.. _ _ _ _.., _.. _, _ _ _. _. _ _. _ _ _. _ _. _ _ _ _
_ _ _ _
,
O>
Engineered Safety Feature (ESF)
Actuations 1987 SALP Report identified Concern Regarding
=
ESF Actuations Engineering Modifications issued e
Administrative Tracking System Developed
.
For LER Engineering Actions Most Recent Major Surveillance Activities
Q Were Performed With No Design Related ESF Actuations O
NED#8
-
u
,
O
~
Colt Emergency Diesel Generator Tie-In Major Field Work With The Exception Of The
Final Electrical Tle-In Complete July 1988 Remaining Work To Be Completed During The
First Refueling Outage Two Of The Three Colt Diesel Generators Can
-
Supply Power Through A Temporary Line To The
'
69KV Switchyard i
i l
l l
O NED#9
__
__
_ _
_
-
-
O Thermal Stratification Of F ow In Piping Systems An IE Notice Identified A Thermal
Stratification Problem in Reactor Feedwater Piping During Recovery Following A Reactor Scram At WPPSS LILCO Determined That SNPS Was Susceptible
!
To A Similar Problem
,
O State-Of-The-Art Computer Code Was
=
Used To Quantify The Amount Of l
Stratification And Was Benchmarked Against i
WPPSS Data Modifications Required To Feedwater Piping l
Supports Are Complete
I O
NeD,,o
--
__
-
_ _ _
- -
O Check Valve Inspections
,
Concern initiated By INPO Significant a
Operation Experience Report (SOER)
'
169 Valves Evaluated Using EPRI
Guidelines O
Inspection Program invoiving 1ss vaives
-
Has Been Developed Initial Inspection Has Been Performed On
18 Valves in The Program
.
l
,
F O
NED#11
.
,
("~1 Control Room Detailed Design Review Plan Submitted December 1986 And Approved
=
By NRC Staff Detailed Control Room Design Review
.
Performed in 1987
Outstanding Human Engineering Deficiencies
.
(HEDs) Are Being Evaluated For Implementation
i
!
l
!
i
) Q NED#12
_.
_
_
- _ _ _
__- _
,
,-
___ ___ __
,
F O
Probabilistic Ris< Assessment (PRA)
'
100% Power PRA - 1983
Low Power PRA (5% Using Moblie Diesel
Generators) - 1984 Source Term Comparative Study With
ESEERCO - 1985 O
iDCoR independent Piant Evaiuation (IPE) -
January 1987 25% Power PRA - April 1987
l l
Updated 100% Power PRA - March 1988
!
'
.
Equivalent Radius For Severe Accidents
i Less Than One Mile. Based On NUREG-0396
!
Methodology i
O NED#13
-
- _._
--____ - _ _. - -
_
. _ _ _, - - - -
.
_ _ _ _ _ O
_
_
Supplemental Containment System (SCS)
Filtered Vent
Utilizes Swedish Gravel Bed Filter Design Conceptual Design And Engineering Design
Specifications Complete Designation Of QA Category II Agreed To
By NRC Staff O
Equivalent Radius Due To A Severe Accident e
Using SCS is Less Than 0.3 Mlle Land Contamination Due To Severe Accidents
is 10 Times Less With The SCS Q
NED#14
.
.
_
_ _ _
(~)
Station Blackout (SBO)
"
.
Work Has Commenced in Response To the
- SBO Rule issued June 1988 Preliminary Results Indicate The Plant
Will Be in A Four-Hour Coping Duration
'
Category O
Evaluating The 93MW Of Standby Power
(Excluding Licensed Diesel Generators)
'
Available On-Site For Use As An Alternate AC (AAC) Power Source in Addressing The SBO i
i Rule
'
'
,
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Operational Readiness Evaluation Perform internal Assessment Of Readiness For
Full Power Operation
'.
Team - Nuclear Analysis Division Manager
(Team Leader)
Nuclear Fuel Division Manager Engineering Assurance Section Personnel
,
Engineering Control And Training Section Head
'
O M n ger S&W Site Engineering Office Assessment Based On Review Of
Support Of Plant Operations
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Interface With Plant Operations i
Personnel
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Operating Experience Review Disposition And Feedback Design Change Control l
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I I
O NED#16 l
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Nuclear
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Operations Support Department
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O Nuclear Operations Support Department introduction Emergency Preparedness
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Security
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Nuclear Contracts & Materials
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Licensing
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Operational Readiness Assessment
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October 1988
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SNPS I
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Status:
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October 1988
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O O
O Table of Contents
- Local Emergency Response Organization (LERO)
i
. SNPS Emergency Response Organization (ERO)
- Outstanding Questions Oct 1988 #2
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O LERO Important Developments i
= Three day, full participation exercise - June 1988 No Deficiencies
' Reasonable Assurance" Finding by FEMA
=
"Realism Rule" upheld in Federal Court
=
)
= ASLB Decision: EBS, School Bus Driver Role Conflict, Hospital Evac Times, and Realism issues decided for LILCO y
.
Sept 1988 #3 i
Il
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O SNPS l
LERO Readiness Approx 3200 fully trained LERO members
=
I Average 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> / person training each year l
=
nineteen drills in last twelve months:
=
J 4 three-day drills 15 one-day drills 600 training sessions in last year
=
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recruited and trained 550 new bus drivers
=
for total of 1120 drivers new radio system demonstrated in exercise
=
Sept 1988 #4a
.
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SNPS
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Emergency Response Organization
- Three successful exercises: 1986, 87, 88
- Since July 1987:
5 three-day dr"s
,
l 13 one-day drills l
6 control room-only drills j
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- Three trained shifts - 894 trained people l
- 148 new people trained in 1.
st year Sept 1988 #4
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- Six full scale soundings in 1988
- May 23 - 95.5%
- Exercise Day - 29.2%
- June 10 - 96.6%
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- August 10 - 95.5%
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. September 14 - 97.7%
- October 13,1988 - 97.7%
- Sr. Level Task Force Evaluating further improvements Sept 1988 #5
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O O
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Outstanding Questions Bellmore Zoning
Plume and Ingestion Brochures
REP-10 FEMA siren test and survey
Distribute tone alert radios
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Oct 1988 #8
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O SNPS I
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Status:
Nuclear Security
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October 1988
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O Security E-Field Performance
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= Replaced original system
- System refinements throughout 1987
= Environmental alarms decreased by 36%
= Monthly average no. of E-Field Alarms decreased by 22%
= Further refinements presently being tested
= Further modifications approved this month for 2 troublesome E-Fields l
[
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Sec #2
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NRC - Logable Events I
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I National - 4th Otr Log 1987
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- Average Number of Events Per Log 124
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- Largest Number of Events in a Log-485
- Smallest Number of Events in a Log
- Total Number of Events 8,039
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- Number of Logs Received--
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-150 Categories as non-event reports-Three licensees failed to report I
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O Security NRC - Logable Events LILCO
- Number of Events 4th Otr 1987
1st Otr 1988
2nd Otr 1988
3rd Otr 1988
- Reduction in 2nd and 3rd qtr.1988 due to:
- Security computer software changes
- Increased station awareness of LDV requirements Sec #4
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Security Compensatory Hours Reduction due to:
aincreased LILCO Supervision and Control of Guard Force Activities
=E-Field Modifications
= Security Computer Software Revisions
= Assignment of Class "B" Mechanic to Lock
& Key Control
.
Sec #6 L
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Security Existing Security Computer System
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l Purchased Second Data General Computer i
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Advantages:
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l Preventive Maintenance
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Off-line Software j
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Development Off-line Training
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Sec #7
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Security l
Existing Security Computer System I
installed 13 Revisions to Security Computer Program Since 1/86:
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System is more user friendly l
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Eliminated software problems causing crashes j
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Handle additional cardkeys l
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area access i
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Security Existing Security Computer System l
j Software Revision Installed 4/26/88 Eliminated Major Cause of Crashes:
l
- Computer Crashes (Unplanned)
i i
Jan 1,1987
- April 26,1988 6.4 crashes / month l
April 27, 1988 - Sept 30, 1988 0.4 crashes / month
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- Two crashes since April 26, 1988 One was a computer hardware problem One was of unknown origin
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Sec #9 i
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Security System Upgrade l
New Facilities Preparation
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New Facilities
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New Alarm Stations Computer Room Simulator Room i
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t Factory Acceptance Tesitag ongoing
i Delivery scheduled for early 1989 l
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Sec #10
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SNPS
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Status:
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Nuclear Contracts and Material Control J
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1 October 1988
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O O
O SNPS Shelf Life Program Background Weaknesses found by audits and evaluations:
-1986 INPO Evaluation-1987 Quality Systems Audit-NRC 1987 Inspection cmc 2
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SNPS Shelf Life Program Intent:
To assure that all parts and materials utilized at SNPS are evaluated for shelf-life applicability and processed in accordance with appropriate guidelines and procedures
.
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cmc 3
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SNPS Shelf Life Program
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Shelf Life Program
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. Safety Related Material l
5400 line items evaluated and entered l
into program - complete December 1987 l
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= Non-Safety Related Material 7800 line items evaluated and entered into program - comolete July 1988 t
. TOTAL:
13,200 line items l
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SNPS Shelf Life Program conclusions
- Program is effective - Close out of Audit 08-87-03
- Program meets the intent of assuring proper i
identification and handling of shelflife material
.
cmc 6 I
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SNPS i
Chemical Control Program Background:
Original Program Had Weakness in identifying And
Controlling Chemicals :a The Plant i
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Program initiated August 1987
.
O cmc 7
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Chemical Control Program t
Intent:
.
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fluids which are permitted for in-plant use.
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SNPS
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Chemical Control Program
- Find and label chemicals already in the plant j
- Adjust procurement requirements
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- Label all new chemicals upon receipt l
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- Conduct follow up checks
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I generate lists of all chemicals on-site
evaluate compounds and use
identify use restrictions on each
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establish label program
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SNPS Chemical Control Prog am
. Highlights
- Over 3,000 Chemicals are in the Program
- Implementation Completed April 1988
- Program is Reviewed Constantly I
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NRC INSPECTION ITEMS OPENED / CLOSED
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SALP PERIOD 7/87 TO 9/88
LEGEND 7d OPENED TOTALS 7__
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140 NOV JAN MAR MAY JUL SEP DEC-r_B APR JUN AUG OCT
1987-1983
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I&E NOTICES REVIEWED FOR APPLICABILITY
'*
LEGEND 126--
IN PROCESS i12-.
100%
REVIEWED 99%
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1983 1984 1985 1986 1987 1988 YEAR
O'
Licensing SCAR ltems Numbo-Cateaorv 1 Items to be Performed During PATP
.
Category 2 Items That Can Not be Completed Until
Af ter Commercial Operation per Our Commitment O
Cetecory a IREF Commitments
Cate_g.orv 4 2 REF Commitments
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NOSD Operational Readiness Assessment
I
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i Euroose i
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i
= To Systematically Assess the Status of Commitments, Programs and Management Controls; and to Verify that l
Those Required for a Full Power License are Complete.
NOSD
_ - _ _
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_ _ _
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O O
O NOSD Operational Readiness Assessment Organization of Ass.essment Team
. Lead by NOSD Department Manager
. Coordinated by Assistant Department Manager
.
One Outside Censultant One Other NOSD Manager
.
NOSD
.
__
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.
ODerationa! Readiness Assessment
!
!
T Program
- All Divisions Participating Lead
by Division Manager l
Written Guidelines l
e
Each Division will Provide Outline
of items to be Reviewed a
- Document Review Results Reviewed by Assessment Team
-
!
.
Identify & Implement Actions
NOSD
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Shoreham Nuclear Power Station Trainina Status Accreditation Status
Office Of Training Personnel
Training Highiights
Office Of Training Readiness Self Assessment
O
,
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O OT #1
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O Accreditation Status
,
!
EO, RO, SRO, STA, RC, HP Programs
Accredited April 1988
.
i I&C, EM, MM, TS&M Programs Accredited
September 1988
Member of National Academy For Nuclear
Training - September 1988
'
O
'
All Programs implemented
+
Program Content Equivalent To Second
Round Accreditation i
l O
OT #2
.
O Office Of Trainina Personnel Total Office Of Training Compiement
.
LiLCO
Consultants
_B Total
Instructor Complement
Avg.12 Years Work Related Experience
-
Avg. 5 Years Training Related Experience
-
O Totai of 47 instructors (a Consuitants)
-
Technical, instructional Skills Development
-
,
'
And in Plant Time Required l
Rotational Assignments
6 First Line Supervisors
-
!
l l
High Achievers, Career Develop!nent,
-
Comniunications Enhanced
Rotational Assignments To Continue
-
O OT #3
O Trainina Hiahliahts J. W. Dye, Jr. Training Center a
Apprentice Thru Journeyman Approach
-
Intensive Skills Training (General and
-
Specialized)
Provides ' Grow Your Own" Capability
-
Radiochemistry And Health Physics Pilot
-
O Enhanced Engineer And Manger Training
,
Technical Staff And Manager Program
-
'
SRO Certification
-
Systems / Simulator Training For Nuclear
-
Engineering ALARA Training For Managers And Des!gn
!
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Engineers O
or #4
.-
-
.-
.
-__
__
i
Trainina Hiahliahts (Continued)
NRC Licensed Operators 32 Lic h, sed Operators Since November
-
1985 Total Of 59 Licenses
-
Hours Simulator Training In 1988
-
Plant Management Participation in Crew
-
Performance Evaluations O
Corilnuing Training e
Full Participation
-
Includes Industry And Plant Experience,
-
Skills, Refresher, infrequently Performed
)
And Complex Activities, Station Management
Special Needs Rotating Incumbonts Thru Base Programs
'
-
(Minimal Waiver)
5 Weeks Average Training Per Year
-
O OT #5
,
_ _... _ _ _, _ _ _ _ _.... _ _ _.. _ _ _ _ _ _ _.
_. _ _ _ _ _ _ _ _ _. _
O Trainina Hiahliahts
'
(Continued)
Simuiator
-
Ready For Training:
August 1987
-
Plant Modifications From 11/84 (Data Freeze) To Present 80% impiemented
-
Diverse Simulator Applications (Licensed Operators, STA, TS&M, Engineers, QA, EOP Validation, STP Transients)
O
-
Certification Procedures in Place To Control Modifications, Configuration, Falidation And Certification Application Submitted By 2nd Quarter 1990 O
OT *e
_
l O
Office Of Training Readiness Self Assessment
Establish Self Assessment Team Team Leader:
Director Team Composition:
Office Of Training Manager And Supervisors Scope:
Assess Readiness Of Office Of Training To Support Power Operation O
Duration:
October 17 Through 28
Types Of Activities To Evaluate
-
Review Training Material Tracking System
-
Review Training Needs identified From Plant
,
Readiness Self Assessment Review Development Of 1989 Training Plan
-
Review Staffing Plans
-
O OT #7
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Additional Information o
\\_
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U OT #8
- - - -
O~
J. W. Dye, Jr. Trainina Center 110,000 Square Feet a
Classrooms (33)
Conference Rooms (2)
Auditorium
.
Laboratories (4)
.
Skill Shops (11)
O Piant Specific Simulator e
Library
Media Production Center
Quiet Study Area
,
O OT #9
_
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f
....
.
.
_ -
.
Operator Trainina
,
Equipment Operator a
16 Weeks Of Classroom Training
-
'
Fundamentals
Yard And Control Building Systems
.
Turbine Building Systems
.
Reactor Building Systems
Radwaste Building Systems a
-
24 Weeks Of In-Plant OJT
-
Selected Topics From initial Training O
e
Reactor Operator
!
32 Weeks Of Classroom Training
-
Nuclear Fundamentais
Systems And Procedures
.
12 Weeks Of Simulator Training
-
1 Week Research Reactor
-
l 13 Weeks On-Shif t OJT i
-
2 Weeks Observation Training
-
4 Weeks License Review
-
O OT #10
_
O ooerator Trainina (Continued)
RO/SRO Upgrade
5 Weeks Of Classroom Training Procedures /
-
,
Technical Specifications Advanced Transient And Accident Analysis 2 Weeks Simulator Training
-
1 Week Supervisory Skills Training
-
13 Weeks Of On-Shif t OJT
-
O 4 Weeks License Review
-
1988 Licensed Operator Requalification Program
Plant Management Participation in Weekly
-
Simulator Scenario Evaluations Crew Evaluation Utilizes Equipment Operator
-
And STA O
OT #11
__
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. _ - _ _ _ _ _
.
.-
_ _ _. _
--
.
.
_
_
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Operator Trainina (Continued)
Program Content
-
Emergency Operating Procedures
Start Up Test Procedures
Case Studies
LERS/ Station Modifications
Plant Systems (e.g. HVAC)
Independent Annual Exam
-
Shif t Technical Advisor
.
O 2s week Program
-
System And Procedures Training
.
Accident Analysis Training
Mitigating Core Damage Training
Simulator Training
Station Nuclear Engineer Training
Program includes Instructor Guided Self-
-
Study
..
7 Quallfled STA's
-
2 STA Candidates To Complete Qualification
-
In November 1988 Participate in Crew Simulator Training
-
O oT #,2
.
__
Oa Simulator Specifications
Singer / Link Built
-
Two Gould Series 32,8780 Computers
-
266 Malfunctions
-
200 Remote Plant Functions
-
150 Trip Overrides
-
1/O Overrides For All Switches, Meters,
-
Lights And Recorders Remote Shutdown Panel
-
Offgas Panel
-
INPO Evaluation Conducted October 1987.
- Recommendations Implemented O
Or #13
.
.,, _ - _ - _ _..
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O Technicians Radiochemistry Technicians
24 Week Initial Training Program
-
.
Radiochemistry Fundamentals
BWR Systems
Appiled Fundamentais - Classroom /
Lab OJT/ Qualification In Three Functional
-
Areas Health Physics Technicians
22 Week initial Training Program
-
Health Physics Fundamentals
BWR Systems
Applied Fundamentals - Classroom /
Lab OJT/ Qualification in Five Functional
-
Areas O
OT #14
.
O Technicians (Continued)
Instrumentation And Control / Computer
Technician Training Comprehensive Training Program
-
14 Week Core Program
88 Weeks Of Equipment / System
Specific Training In-House Specialized Training
(E.G. Neutron Monitoring System, O
Printed Circuit Board Repair, Electro Hydraulic Control System, Reactor Manual Control System, Etc.)
Extensive Use Of Laboratories
-
Electronics And Process Labs
Individual Test Instruments And Power /
Air Supplies Actual Plant Equipment For Calibration
And Repair l
l O
OT,,s im
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-
Electrical & Mechanical Maintenance
>
,
Apprentice Training
Total 800 Hours Of Initial Training
-
,
General Maintenance (Handtools,
Layout, Setup)
Electrical Maintenance (Theory,
Safety, Circuit Construction)
Mechanical Maintenance (Theory, a
Power Tools, Machining, Simple M
hines, Pump And Valve O
inspection / Repair)
Total 16 Hours Of Specialized Training
-
Rigging a
Mechanical Fasteners
For'Kilf t Operations
O OT,,e
O Electrical & Mechanical Maintenance j
(Continued)
Journeyman Training
-
Total Of Approx. 700 Hours Of Initial Training
- Pipefitting
Crane Operations
Advanced Pump Repair
Alignment Skills
Fabrication Of Parts / Tools l
(Machining)
l O
Advanced Welding Skills (SMAW &
GTAW-Pipe)
Electrical Equipment Repair (Motors a
& Controls, Switchgear)
Specialized Advanced Skills Training
-
Total 504 Hours Of Training In Select Skills And Unique Equipment
Test Procedures Refusiing Activities
Reactor Recirculation Pump Seal Rebuild
Control Rod Drive Mechanism Rebuild / Repair
.
Polar Crane Operations
Hydraulic Control Unit Rebuild / Repair
Explosive Valve Repair
O OT #17
_
-
,
Enaineers And Manaaers
'
Technical Staff And Manager Training Program
.
-
Initial Training i
.
Seventeen Week Training Program
99 SNPS Personnel Enrolled
100% implementation Of Initial Program By November 1988
'
.
Duration Exceeds Industry Average Nuclear Engineering Simulator Training
O Four Week Program Classroom And Simulator j
-
,
- Increase Familiarity Of Plant Operations
Awareness Of Plant Modification impact f
On Operation QA/QC Systems Training
-
Increase Systems Knowledge Of Engineers /
Inspectors
-
Improved Awareness For Survelilances
-
Better Understanding For Preparation /
Conduct Of Audits O
OT #18
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Eight Week Program Fully implemented
-
Engineers / Inspectors Have Completed Program
-
SRO Certification Program
,
Eighteen Week Course
-
'
Reactor Theory
Systems
Simulator
'
n-Shift Experience
. O e
L
Mitigating Core Damage / Emergency Operating
!
Procedures Comprehensive Final Exam Jointly Administered i
-
By Plant And Training
- Walk Through - Plant
- Written Exam - Training
Simulator Exam - Training / Plant Eight Graduates i
-
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O OT *19
_
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Enaineers And Manaaers (Continued)
,
ALARA Training
I
.
Two Distinct Programs For Engineers And
-
Managers Four Hour Managers Program
-
.
Corporate Commitment To ALARA
Regulations
Cost Benefit Analysis
Staff Training O
.
Sixteen Hour Design Engineer Program
-
LILCO ALARA Program
'
Plant Layout And Access Controi
ALARA Reviews Of Design Modifications
Shielding, Routing, Crud Control,
,
Equipment Design
,
!
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Nuclear
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l October 1988
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,
introduction
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i Program / Management Overview
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Performance Based Self-Assessment a
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NQA Trend Analysis
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Organizational Alignment
Program Application
Program implementation
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Proaram/Manaaement Overview
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- Direct Executive Management involvement QA Program Policy Statement
-
Direct Presidential Access
-
Formal Reports
-
Nuclear Review Board Participation
-
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.
G QA#3
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O Nuclear Quality Assurance Department Program /Manaaement Overview i
.
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Organizational Alignment
- Direct Report to VP-Nuclear Operations
-
Quality Assurance / Quality Control
- Safety Engineering and Reliability
- Training OA#4
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LO Nuclear Quality Assurance Department Re iabil tv Project Reoorts
'
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j Thirty-five reliability project reports issued since 1985 l
Reliability project reports are recommended by l
the reliability section based on industry and
,
i Shoreham operating experience and are
-,
i prioritized by the plant manager.
l
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Reliability project reports have been completed f
e i
for safety and non-safety related systems and for
critical plant components.
!
-
Fourteen safety reiated evaiuations compieted O
t i
-
Nineteen non-safety related evaluations
!
completed
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-
One component evaluation completed for station electrical inverters
'
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-
S2ation anil model completed in 1988
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Nuclear Quality Assurance Department Comoleled Reliability Project Reoorts 1. Turbine Building Closed Loop Cooling Water System
2.
Service Water System l
3.
Hypochlorination System
4.
Condensate and Feedwater Systems 5.
Reactor Building Standby Ventilation System and Control Room Air Conditions Chilled Water System
.
6.
Traveling Screens and Screen Wash Pump
7. Low Pressure Coolant injection Mode of the Residual Heat Removal System 8.
Main Steam Isolation Valve and Steam Leakage Control System
9.
Reactor Water Clean-up System i
10. Control Rod Drive System l
11. Instrument Air System
,
,,.
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l 10. Gtandby Liquid Control System 14. Main Chilled Water System i
-
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(O Nuclear Quality Assurance Department Comole':eA Re iabili"v Project Reoorts
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15. Safety Rollei 4.as 16. Radwaste E 'wetat~> 91d Rebollers
,
17. Offgas Systen:
18. High Conductivity Hadwaste 19. Heat Tracing System
,
20. Reactor Building Standby Ventilation System O
21. Vacuum Priming System 22. High Pressure Coolant injection System 23. Low Conductivity Radwaste System 24. Reactor Building Normal Ventilation System 25. Reactor Core isolation Cooling System 26. Reactor Protection System
..
27. Core Spray System 28. Inverters 29. Reactor Building Closed Loop Cooling Water
.
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Como eted Reliability Project Reoorts (con't)
30. Shoreham Station Unit Model
31. Recirculation System 32. Sealing Water System
' 33. Generator Excitation System
'
34. Residual Heat Removal System 35. Shoreham Siren System
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RELIABILITY PROJECT REPORT R ECOM M EN DATIO NS
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1985 1986 1987 1988 1985 '188 YEAR
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Nuclear Quality Assurance Department Operatina Experience Review
.
.
.
442 INPO SOER Recommendations Reviewed i,
554 INPO SERs Reviewed 243 INPO O&MRs Reviewed 153 Shoreham LERs Reviewed 435 lSEG Projects Reports issued These reviews have resulted in 343 ISEG
,
rerconvinendations offered for evaluation of
various areas.
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1982 1984 1986 1988 l
1983 1985 1987 ALL YEARS l
YEAR
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-
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---
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Nuclear Quality Assurance Department
'
1988 Trainina & Expenditure
'
.
1.
Technical Training 11. QA/NDE/Other Ill. Out-of-town Assignments
.
.
.
-
,
QA#4i
.
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Nuclear Quality Assurance Department Proaram/Manaaement Overview l
- Program Application
-
Safety Related/ Safety Significant
-
Non-Safety Related
-
-
Quality Hotline
.
O QA#5
. _ _
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Nuclear Quality Assurance Department
-
.
b on-Safe':y Re a':ed Systems and Proarams SYSTEMS Feedwater Control Condensate Domineralizers
Neutron Monitoring Radwaste Of fgas
Process Computer Condensate Storage and a
Reactor Water Clean-up Transfer
Radwaste System Sampilng System
o Fuel Pool Cooling / Clean-Up Turbine Bldg Close Loop
Process Radiation Monitoring Cooling Wtr
Area Radiation Monitoring Compressed Air
Fire Protection Solid Radwaste
Main and Auxillary Steam Meteorollocal Monitoring
.
Condensate and Feedwater
- Station Transformers
Turbine 4160V Norm /Emer Pwr Sys
a
- Turbine Control (EHC)
- 480V Norm /Emer Pwr Sys
- Seal and RW Steam
+ 120V AC Instr Pwr
'
Turbine Lube Oli
- Heat Tracing
- Molsture Sep. Rsheater
- Main Power Transformer Dralns
'
- Extraction Steam inerting
- Generator
- RB Normal Vent
- Stator Cooling
- RW Bido Ventilation
. Hypochlorination
- Seismic Monitoring PROGRAMS
- Fire Protection
- Radwaste Processing and Shlpping
',
- Security
- REMP i
- Corrective Action Programs (Incident Reports, M&TE Problem Reports, HP incident Reports, Security incident Reports)
- Chemical Control
- Housekeeping and Industrial Safety
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CUMULATIVE HOTLINE ITEMS 1988
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Program lmplementation
- Strong Department Manager Commitment
- Active Vertical / Horizontal Interface
- Rotational Assignment of Personnel
.
OA#6
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O Nuclear Quality Assurance Department Performance Based Self-Assessment
- Audit / Surveillance / inspection
- Performance Based Techniques
- Technical Expert Utilization
.
.
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OA#7
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O Nuclear Quality Assurance Department Audit Proaram Nuclear Ooerations Sucoort Emergency Preparedness
Security
Licensing
Purchasing / Material Control
Office of Trainina Training and Qualification e
Computerized T&Q System
Simulator a
Quality AssuranC_t NRB
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Quality Systems e
Quality Control
ISEG e
Relia'ollity
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Operations
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EOPs Rev. 4 (simulator)
Reactor Engineering
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Corrective Action
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Maintenance
I&C O
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Fire Protection
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Radiological Controls Radiochemistry
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Radwaste/PCP
HP/ALARA Nuclear Enaineering l
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O Nuclear Quality Assurance Department Major Insoec': ion l': ems NRC Compliance Bulletin 87-02 35,000 Fasteners Guyon Supplied Fittings 343 Fittings EO Electrical inspections 2359 Splices GE Circuit Cards 1551 Cards GE Supplied Switchgear Panels 4200 Terminations Raceway / Conduit Spring Nut 8105 Spring Nuts O
Rework / Inspection of RHR 30 Pipe Supports /
System 52 Pipe Welds Sirens 89 Continuous Concrete Block Walls 112 Walls NRC Bulletin 88-05 236 Flanges Nonconforming Flange Material
.
Total Manhours Approx.14,000 O
oA*7e
- - - - - -
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O O
O Nuclear Quality Assurance Department Performance Based Self-Assessment
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OA#8
-
.
- _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _
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Nuclear Quality Assurance Department
.
Performance Based Self-Assessment
- Performance Based Techniques
- Personnel Interviews
- Active Field Observations
- Program / System / Attribute Challenges
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- System Walkdowns
- Independent Analysis /
.
Verification
.
..
.
OA#9 i
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Nuclear Quality Assurance Department Performance Based Techniauas Examoles
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l REMP Data To Engineering To Independently Check
e NED Calculations a
Spike TLD'e
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Spilt / Spiked Radiochemistry Samples e
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Lube Oil Wear / Corrosion Product Analysis
=
Fuel Oil Analysis For Microbe Contamination
Portal Monitor Tests J
e
)O Security Checks
l
! :'
= coleman Mantelin Trash
I System Walkdowns e
Independent Vibration Analysis Of Mechanloal Equipment
l Material (Chemloal/Physleal) Testing e
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Spilt / Spiked Fitness For Duty Program Samples e
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EOP Simulator Evaluation i
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Trend Analysis
identified Trend
'
Corrective Maintenance MWRs and LDR a
Related Equipment Deficiencies Undispositioned and Open LDRs
Procurement / Vendor Concerns I
Control of Licensee Designated Vehicles in the
Protected Area Noncompliance with Procedure
improper MWR Review and implementation e
,
OA#10
.. - - _...
-
. _ _ - _ _ _ _ _ _ _. - - _.. -.. - _ _.. _ _
- _.
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!1
Nuclear Quality Assurance Department Trend Analysis
'
Management Attention identified Trend Results
,
- Corrective Maintenance
-
Increase in MWRs Due MWRs and LDR Related to in Plant Activities
,
Equipment Deficiencies
-
LDRs improved by 47%
.
i
l
- Undispositioned and
- Open LDRs are Trending Open LDRs Down & Will Continue to l
be Closely Monitored
'
)
-
64% Decrease in
'
Outstanding
'
Undispositioned LDRs
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- Procurement / Vendor
- Improvements Noted in Concerns Hardware, Sof tware
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Concerns Continue
- Control of Licensee
- 50% Reductions in
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Designated Vehicles in incidents in 1988 When
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the Protected Area Compared to the Same Period in 1987 i
- Noncompliance With
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68% Reduction
Procedure
- Improper MWR Review
- 60%
Reduction and Implementation i
O QA#11
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Nucir - Quality Assurance Department I
f. :.;c donal Readiness Assessmen':
Purooc;r
+ Independent Asse'ssment of Plant and Personnel Readiness for Power Operation Oraanization
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. Lead by Nuclear Quality Assurance Manager
- Coordination by Safety Engineering and Reliability
. Assisted by All Nuclear Quality Assurance Department Personnel e Support By Offsite Technical Experts Scoce
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- Operations
- Maintenance
- Radiological Controls a Configuration Control
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- Licensing s Training / Staffing
- Plant Support
. NOAD Self-Assessment
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Schedula
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a Completion by November 4,1988
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QA#12 t
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O Nuclear Quality Assurance Department Readiness Ascessment Of Operations l
Review Of Audit Findings For impact
On Startup
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Continue To Observe Off Shift Activity
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Review Oi Plans And Schedule For Startup a
Testing Outstanding Procedure Change Notice Review
And Identification Of important Changes Required O
Limiting Conditions For Operations (LCO)
Review, Assure Outstanding Tech Spec items Are Identified Surveillance Of Equipment Status, Review Of
LL&J, SECP Log, Main Control Room Logs, Temporary Modifications Log To Assure These Programs Adequately Describe Plant Equipment
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O QA#12a
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Nuclear Quality Assurance Department Readiness Assessment Of Maintenance Review Of Outstanding priority 1 MWRs To
Assure Restraints To Operation Are identified Review Of Priority 1 PM/ SAWS Activities To
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Assure Equipment is Ready For Operation
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Review Of Audit Findings /LDR's For impact On
Startup Determine The Fire Protection Program And
O Fire Stops And Seals Program Are Properly Addressed Determine That Required MOV EQ Inspections
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Are Competed Battery Maintenance And Surveillance
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Review Welding Program To Assure Adequate Quallfled Personnel Are Available
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Observe Station Housekeeping For impact On
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Plant Equipment
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Nuclear Quality Assurance Department Readiness Assessment Of Radiological Controls Evaluate Quallfloations And Training Of
Health Physios, Radiochemistry And Radwaste Personnel Review Of Audit Findings /LDR's For impact e
On Startup Surveillance Of RMS Setpoints
Evaluate Operational And Physical Readiness
Of Radiochemistry Laboratory To Support Operations Review Status Of Water Chemistry Program
O Observe And Evaluate Sampling Techniques
Evaluate ALARA Program implementation
Against Operational Requirments Review Health Physios Program And Equipment
Capabilities To Support Power Operations Observe Health Physics Personnel Performing
Surveys, Swipes, And Personnel Monitoring Review Of PASF Operability
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Rooi Cause Analysis Of Effluent Monitoring e
Trends And Corrective Action Status Review Radwaste/PCP implementation To
Assure Compliance O
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Nuclear Quality Assurance Department Readiness Assessment Of Confiauration Control Review Of Audit Findings /LDR's For impact e
On Startup
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Surveillance Of Control Room Drawings To
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Verify Accuracy Review Of Engineering Requests (EEAR) For
Proper Priority
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Review Of Unprioritized EEARs And Outstanding
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DOPs For impact On Startup Surveillance Of Station Modifications To e
Maintain As-Built Configuration l
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Nuclear Quality Assurance Department Readiness Assessment Of Licensina Review Of Audit Findings For impact On e
Startup Support Outstanding LER Corrective Actions To Be
Completed Prior To Startup Open NRC Inspection items To Be Completed
Prior To Startup
!O Surveiiiance Of Commitment Tracking System
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Review Of Other NOSD Commitment Tracking a
System items For impact On Startup
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.O OA#12e
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Nuclear Quality Assurance Department Readiness Assessmen': Of Trainina/Staffina
Evaluation Of Organization's Capabilities To
Assure That Tech Spec Requirements Are Met Surveillance Of Operating Crew Qualifications
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And Identification Of Training Required in The Next 90 Days Review Of Open T&O Audit Findings For impact
,0 On Startup Review Of Startup Test Organization l
Surveillance Of Training And Qualifications
Activities
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Determine Required Resources For Startup and
Operation Are Identified And Available
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.(O Nuclear Quality Assurance Department Readiness Assessment of Plan': Suocort j
- Surveillance of Security LDV Against Corrective l
Action Request Requirements
identification of any Procurement items Which May e
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Affect Plant Startup
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Determination that Adequete Engineering Support
Exists and that Engineering has Cleared any Restraints to Startup Review of Outstanding ISEG Recommendations to
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be completed Prior to Startup Progress of HFA Relay inspections in Response
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to GE SIL Surveillance of Site Flood Protection to Ensure
Proper Installation Assessment of Block Wall inspections for impact
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on Startup Identification of Outstanding LDRs to be Closed
Prior to Startup Review Spare Parts inventory for impact on Startup
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Surveillance of Warehouse Activities, including
Shelf Life, Chemical Control, Housekeeping,
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- Q Hol Tags, and Segregation of Material
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(O Nuclear Quality Assurance Department Self Assessment
Nuclear Review Board Overview
Review Recent Quality Control and Quality
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Systems Self Assessments and Follow-Up
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Evaluate Nuclear Quality Assurance Department Programs
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Trend Analysis
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LDR
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CAR O
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Audit
Surveillance
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Inspection
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Operational Experience Reviews
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Procurement Programs
Evaluate Personnel Readiness
Experience
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Training and Qualifications
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Organization, Structure, Manpower
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Observation, Work Sampling iC QA#12h
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