ML20154E904

Forwards Summary of 880810 Meeting W/Util at Region II Ofc Re Plant Performance & Improvement Programs.List of Attendees & Handout Also Encl

ML20154E904
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	09/06/1988
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H DUKE POWER CO.
References
NUDOCS 8809190180
Download: ML20154E904 (32)

Text

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C SEp 06 d Docket Nos. 50-369, 50-370 50-413, 50-414 License Nos. NPF-9, NPF-17 NPF-35, NPF-52 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

SUBJECT:

MEETING

SUMMARY

- CATAWBA - DOCKET NOS. 50-413 AND 414; AND, MCGUIRE - DOCKET NOS. 50-369 AND 50-370 This letter refers to the meetinC conducted at your request in the NRC Region !! office on August 10, 1988.

This was a management meeting to discuss your plant performance and improvement programs. A list of attendees, a brief suntiary and a copy of your handout are enclosed.

It is our opinion that this meeting was beneficial, and provided for a better understanding of overall plant performance and your plans for the future at Catawba and McGuire, in accordance with Section 2.790 of de NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions concerning this matter, we will be pleased to discuss them.

Sincerely, dU Q,uc>,

W L

Luis A. Reyes, Director Division of Reactor Projects

Enclosures:

@*^ I' s-E ^" b 1.

Meeting Summary 2.

Meeting Attendees -

3.

Duke Power Company Handout - McGuira Nuclear Station 4

Duke Power Company Handout - Cetawba Nuclear Station cc w/encis:

(See page 2) h 91901 m 800 06 hp ADOCK O5000369 I I i

PNu 3 L-Y >

0 48 Duke Power Company 2

cc w/encis:

T. B. Owen, Station Manager, Catawba T. L. McConnell, Station Manager, McGuire bec w/encls:

NRC Resident Inspectors DRS, Technical Assistant D. Hood, NRR K. Jabbour, NRR Document Control Desk State of South Carolina R!l RII Ri!

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/1./88 j/ g/88

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ENCLOSURE 1 MEETING

SUMMARY

Licensee: Duke Power Company Facilities: Catawba and McGuire Docket Nos.:

50-413, 50-414, 50-369 and 50-370 A management meeting was held in the NRC Region 11 office on August 10, 1988, to discuss recent events, overall plant performance and improvement programs.

J. Nelson Grace discussed the NRC desire to know how Duke perceived their overall performance at Catawba and McGuire and what their future plans are to enhance performance.

H. B. Tucker discussed how they intended to be open in their discussion of their self evaluation and that the plant managers would do the briefing for their respective site.

T. L. McConnell addressed the McGuire site's strengths and their concerns and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness,

security, engineer-ing/ technical support, and operator training and safety assessment /qualitj t

verification, T. B. Owen addressed the Catawba site's concerns, the counterpoints of the concerns and their strengths and initiatives in the arcas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness, security, engineerir.9/ technical support and safety assessment / quality veiif, cation.

The NRC staff acknowledged the extensive resources and capabilities of Duke and that they have recognized many areas for improvement and that they are implementing corrective actions and developing program enhancements.

The NRC expects their licensees to promptly evaluate and correct problems and we appreciated your frank discussion of your programs to accomplish these ends.

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ENCLOSURE 2 MEETING ATTENDEES W. T. Orders, Nuclear Regulatory Commission (NRC), Senior Resident, McGuire P. K. VanDoorn, NRC, Senior Resident Inspector, Catawba M. S. Lesser, NRC, Resident Inspector, Catawba T. A. Peebles, NRC, Section Chief V. L. Brownlee, Branch Chief, DRP, RI!

C. W. Hehl, Deputy Director Division cf Reactor Projects J. Nelson Grace, Regional Administrator G. C. Lainas, NRC/NRR, DRP E. W. Merschoff, Director, Division of Reactor Safety D. B. Matthews, Director. PDII-3, NRR D. Hood, Project Manager, PDII-3, NRR K. N. Jabbour, Catawba Project Manager, NRR J.P.Stohr, Director,DivisionofReactorSafetyandSafeguards(DRSS)

F. Jape, Technical Support Staf, DRS T. Owen, Catawba, Station Manager, Duke Power Coinpany (DPC)

H. B. Tucker, Vice president Nuclear Production, DPC T. McConnell, McGuire, Station Mar.ager, DPC

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UNITED STATES

[p2 Clo,#'o,*

NUCLEAR REGULATORY COMMISSION a' *

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R EGl*N 11 o

101 MARIETTA STREET N.W.

ATL ANTA. GEORGI A 30323 t,;*s.s,/

SEP 00 8)a8 Docket Nos. 50-369, 50-370 50-413, 50-414 License Nos. NPF-9, NPF-17 NPF-35, NPF-52 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

SUBJECT:

MEFTING

SUMMARY

< CATAWBA - DOCKET NOS. 50-413 AND 414; AND, MCOUIRE - DOCKET NOS. 50-369 AND 50-370 This letter refers to the meeting conducted at your request in the NRC Region !! Office on August 10, 1988.

This was a management meeting to discuss your plant performance and improvement programs.

A list of attendees, a brief summary and a copy of your handout are enclosed.

it is our opinion that this meeting was beneficial, and piovided for a better understanding of overall plant performance and your plans for the future at Catawba and McGuire.

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10. Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the MC Public Document Room.

Should ycu have any questions concerning this matter, we will be pleased to discuss them.

Sincerely,

/

SG Luis A. Reyes, Director Division of Reactor Projects

Enclosures:

1.

Meeting Sumary 2.

Meeting Attendees -

3.

Duke Power Company Handout - McGuire Nuclear Station 4

Duke Power Company Handout - Catawba Nuclear Station cc w/encis:

(See page 2)

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Duke Power Company 2

SEP v 9..

cc w/encls:

T. B. Owen, Station Manager, Catawba T. L. McConnell, Station Manager, McGuire

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ENCLOSURE 1 MEETING

SUMMARY

Licensee: Duke Power Company Facilities:

Catawba and McGuire Docket Nos.:

50-413, 50-414, 50-369 and 50-370 A management meeting was held in the NRC Region !! office on August 10, 1988, to discuss recent events, overall plant performance and improvement programs.

J. Nelson Grace discussed the NRC desire to know how Duke perceived their overall performance at Catawba and McGuire and what their future plans are to enhance performance.

H. B. Tucker discussed how they intended to be open in their discussion of their self evaluation and that the plant managers would do the briefing for their respective site.

T. L. McConnell addressed the McGuire site's strengths and their concerns and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness,

security, engineer-ing/ technical support, and operator training and safety assessment / quality verification.

T. B. Owen addressed the Catawba site's concerns, the counterpoints of the concerns and their strengths and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, m rgency preperedness, security, engineering / technical support and safety assessment / quality verification.

The NRC staff acknowledged the extensive resources and capabilities of Duke and that they have recognized many areas for improvement and that they are implementing corrective actions and developing program enhancements.

The NRC expects their licensees to promptly evaluate and correct problems and we appreciated your frank discussion of your programs to accomplish these ends.

ENCLOSURE 2 MEETING ATTENDEES l

W. T. Orders, Nuclear Regulatory Commission (NRC), Senior Resident, McGuire P. K. VanDoorn, NRC, Senior Resident Inspector, Catawba M. S. Lesser, NRC, Resident Inspector, Catawba T. A. Peebles, NRC, Section Chief V. L. Brownlee, Branch Chief DRP, RII l

C. W. Hehl Deputy Director Division of Reactor Projects J. Nelson Grace, Regional Aduinistrator G. C. Lainas, NRC/NRR, DRP E. W. Merschoff, Director, Division of Reactor Safety D. B. Matthews, Director, PDII-3, NRR D. Hood, Project Manager, PDII-3, NRR K. N. Jabbour, Catawba Project Manager, NRR J. P. Stohr, Director, Division of Reactor Safety and Safeguards (DRSS)

F. Jape. Technical Support Staf, DRS T. Owen, Catawba, Station Manager Duke Power Company (DPC)

H. B. Tucker, Vice president Nuclear Production, DPC 1

T. McConnell, McGuire, Station Manager, DPC i

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ENCLOSURE 3 DUKE POWER COMPANY HANDOUT MCGUIRE NUCLEAR STATION 1

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,a McGUlRE NUCLEAR STATION 1.

PLANT OPERATIONS STRENGTHS:

Longer runs and improved capacity factors Use of SRO in integrated Scheduling to minimize operability conflicts improved daily operating schedules e

Daily management plant status meetir.2s Decreased number of violations from 9 Level 4 in previous SALP period to 1 Level 3 and 1 Level 4 in most recent SALP period No operator error induced reactor trips in 3 years implemented tagging / labeling program for equipment and e

components - noticeable absence of wrong unit / wrong train events in 1988 Improved housekeeping / cleanliness in all areas Control room upgrade in progress - will improve working conJitions and standardize control room indications Control of materials / loose objects in containment l

Use of plant deficiency tags to identify deficiencies and follow up actions Developed McGuire Management Council Developing international interface (Russia / Cuba / France)

FIRE PROTECTION:

Reliability enhancements to fire protection procedures Ongol:tg review / upgrade of fire protection equipment pts i

l Improved organization / training of plant fire brigade

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Thorough, technical Duka Power QA fire protection audits have been performed and Identified items for improvement that have been completed CONCERNS /lNITIATIVES:

x Operations / Maintenance work control practices and plant status knowledge needs improvement Project /2 schedule improvement allows every work activity to be updated daily.

It produces individual crew schedules to allow better planning and prioritization of work.

This provides a more accurate status of work completion and ensures controlled entry into various T. S. modes.

Plant management emphasis on improving root cause analysis of all plant events should improve our performance here.

We are pressing accountability for this analysis to lower levels in the organizational and to less significant events.

X Unplanned reactor trips and associated ESF actuations are trending upward.

Two-thirds of all recent reactor trips are caused by equipment failures.

When a piece of equipment falls when tested, it is trended and analyzed under the new Test Failure Analysis Program.

This program includes an equipment history review and a root cause analysis.

System Experts are begl~nning to analyze equipment failures not associated with test failures, in addition a PM-2 program for predictive maintenance is being i

utilized more extensively now.

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Increased number of violations due to procedural non-compliance Violations are occurring due to inadequate procedures and a lack of strict adherence to procedures.

Measures which have been taken which should improve our performance here:

(A)

Clarified Independent Verification procedure and covered it in requal training.

(B)

Clarified Tagout/ Removal and Restoration procedure and covered it in requal training.

(C)

All sections are pursuing procedure upgrade programs.

(D)

Line/ staff communications were held with station personnel to emphasize procedural adherence / procedural adequacy.

(E)

Superintendents stress procedural adherence through section head meetings to maintain a heightened awareness.

(F)

A station newsletter article, "Procedures are not Suggestions or Guidelines" by the Station Manage. was recently issued to employees (Refer to Attachment A).

(G)

G.O.

Licensing Group reviewed all incidents dealing with personnel error for trends, it was recommended that supervisors need to follow up on personnel errors to determine contributing factors or extenuating circumstances, if any, for the error.

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Emphasis on better root cause analysis should help resolve thin (Refer to Attachment B).

(H)

The Operating Excerience Management and Analysis (OEMA) function in our General Office was recently requested to review incidents from the past two years dealing with procedural adherence to determine any underlying causes for deviation.

It was determined that corrective actions for past incidents may have been too confined to a specific work group and that administrative deficiencies associated with procedural adherence should be better identified in the investigations.

The report is currently under review (Refer to Attachment C).

(1)

McGuire Operations personnel recently participated in the development of an Operations' "Commitment to Excellence" which is a professional code of conduct (Refer to ).

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RADIOLOGICAL CONTROLS STRENGTHS Catch / containment leak control program has reduced leaks and contamination Improved outage support due to improved job pre-planning and more efficient use of technicians Reduction in personnel contaminations Eliminated contract HP techs for routine work Dosimetry system accredited by the National Voluntary Accreditation Program 4

l Reduction in number of NRC violations from 8 in previous SALP period to 1 in most recent SALP period 94% free access to the Auxiliary Sullding CONCERNS / INITIATIVES X

Radwaste volume generated exceeds national average i

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A trash segregating and sorting system was implemented i

in December to reduce the volume of compacted clean trash.

i Radwaste volume reduction working group studied this concern, made recommendations to management and several j

improvements have been or are being implemented.

Upgraded shredder / compactor equipment has been purchased which will further reduce radwaste volumes.

Cumulative dose exposure exceeds national average i

There has been a reduction in cumulative dose for non-outage work.

However, the major source of exposure was work associated with refueling and maintenance i

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outages.

A4 loop Westinghouse / ice condenser plant has more maintenance requirements than those used to calculate the national average.

Efforts to increase S/G life and remove the RTO bypass system have resulted in high doses.

All radiation exposure jobs were assigned to groups in the station for detailed ALARA planning, resulting in much more detailed ALARA plans.

The initial results look good.

A major management initiative has been taken to transfer more dose accountability to craft worker and supervision and away from HP.

Increased level of management involvement and membership on ALARA committee.

l The accountabli of ALARA planning responsibilities between HP and Maintenance Planning is being clarified.

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ll1. MAINTENANCE /SURVElLLANCE STRENGTHS:

Increasing the use of system experts Valve quality group performs quality inspections on valve repairs to improve quality of work and level of experience in the field A self assessment of maintenance program against INPO criteria has identified items for improvement that are being completed on a priority basis.

New vibration monitoring equipment has been purchased to expand our capacity to monitor vibration spectrum on rotating equipment Oil analysis program has been expanded to include many other pieces of equipment and allow for earlier detection 1

of component wear / failure Developing technology to test actuators on pneumatic valves leading industry /NRC efforts to define a viable process.

Implemented test failure analysis / root cause program Improved daily operating schedules KC HX on line AP monitoring for enhanced operability l

monitoring CONCERNS / INITIATIVES:

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increased number of violations due to procedural non-compliance from 8 in previous SALP period to 11 in current period initiatives taken under the Plant Operations category were station wide and apply to this concern as well. _

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EMERGENCY PREPAREDNESS STRENGTHS:

Corrected siren activation problem with Mecklenburg County NRC unannounced inspection in March with no findings No violations during SALP period Successful annual exercises (only 2 IFI's)

Developed new procedure for event classification to make more "user-friendly" CONCERNS / INITIATIVES:

e Current TSC facility is deficient j

Pursuing design / construction of new TSC facility to meet regulatory guidance criteria.

Current schedule for completion is 1990.

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SECURITY STRENGTHS:

A dedicated lAE crew (CMD) to maintain security systems Upgrade of security barrier sizes and design Replacement of outdated explosion detectors and electric locks CONCERNS / INITIATIVES X

Replacement / repair of CCTV cameras (A)

CCTV cameras and monitors are belng replaced with state-of-art equipment.

(B)

A temporary modification was implemented to correct 4

the "wali effect".

This was necessary due to the length of time required to design and upgrade the final modification which will be completed in mid-1989.

x Need to reduce the number of lost security badges and tailgating incidents.

Site management from all groups is working together to establish a statement of value of adherence to these requirements with a consistent corrective discipline policy throughout the company including vendors.

Daily updates are provided on the closed circuit TV system concerning numbers of security problems for tmployee awareness.

The General Employee Training video has been revised to stress the importance of security badge control.

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l Data on events and groups involved is compiled, trended and provided to management for corrective action.

Neckstraps have been provided for more positive attachment of security badges.

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VI.

ENGINEERING / TECHNICAL SUPPORT STRENGTHS:

Placement of a Design Engineering office on site has l

resulted in (A) onsite problems resolution during installation of modifications i

(8) onsite interpretation of design requirements / documents i

(C)

Increased involvement in long term rotential operability problems (i.e., NS HXs)

(D)

Earlier DE involvement in station problems (i.e.,

resolution of errosion problems in S/G blowdown tank)

(E)

More immediate design inspections for operating f

problems or modifications (i.e., damaged KC flex hose)

(F)

Increased DE involvement and timeliness of operability reviews i

Topform program has increased quality of documentation and f

e design reviews I

Topform program has increased the required interface with

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the station to assure a clearer understanding of station problems j

Decreased unnecessary modification paperwork by an improved root cause analysis of problems I

RefueIing I

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Very successful during last SALP period at planning l

refuelings and meeting outage schedules l

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Operator Trainina New site specific simulator with state-of-art technology

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Increased simulator training time from 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (1987) to I

40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (1988) and then to 50-60 hours (1989)

Added designated simulator familiarization for i

non-licensed operators during requal training Implemented Training and Qualification guides and requal case studies On-shift SRO's are now rotated through training instructor slots (4 total) a Recent INPO re-accreditation only identified two concerns, lowest to date on eleven visits

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CONCERNS /lNITIATIVES:

x Temporary modification program has had no design review in i

the past.

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3 Methods to increase DE involvement in temporary l

modification program to provide a more thorough review of adherence to design basis and safety concerns are l

being investigated and will be implemented.

X Rate of incidents and violations during refueling outages 1

is too high.

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Corrective actions yet to be identified.

Outage critique and folicw-ups will help resolve this concern.

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Vll. SAFETY ASSESSMENT / QUALITY VERIFICATION STRENGTHS:

SITA audit on 0/G Auxiliary System Annual SITA audits on selected systems Thorough follow-up on known or potential safety concerns and industry events.

Examples:

(A)

Passive civil features design study (B)

Fisher valve evaluation (C)

Missing Missile Shield Bolts (D)

Bulletin on Surry's containment sump suction line cleanliness INITIATIVE:

We are placing more emphasis and efforts in improving communications with all NRC personnel, it is our desire to be very open and responsive to all NRC concerns and provide timely and accurate information.

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ENCLOSURE 4 DUKE POWER COMPANY HANDOUT CATAWBA NUCLEAR STATION

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1.

PLANT OPERATIONS Concerns 1.

Non-Conservative Approach to Tech Specs April 1987 Violation on Calibration of Power Range -

(Performance Group)

(J. K. L. Q)

Pressurizer Safety Valve Position Indication -

(Individual Supervisor)

(J. P. L)

Auxiliary Feedwater Flow Control Valves - Positioning Above 10% Power - (G.O. Licensing)

(L. Q. K)

Channel Checks On Offscale Gauges - (Operations)

(L.R)

Containment Integrity - ASME vs. Tech Spec Requirements -

(G.O. Licensing)

(L. J. Q. K. S. T)

ECCS Pump Venting - Question of Interpretation -

(Industry Initiative To Remove This Spec Further Review By Ops & Station Manager.)

Counterpoints Several Tech Spec Changes Are In Tc Correct Non-Conservative Or Incorrect Data.

(Licensee Identified) E.G., Airlock Testing Pressure Have Numerous Existing Interpretations And Are Working To Improve The Manual To Assist In Tech Spec Compliance.

l Catawba Is A Good Example Of A Non-Standard Plant Under Standard Tech Specs.

2.

Back To Back Safety Iniections Unit 1 1-23-88 / Unit 2 2-9-E8 Personnel Error -

Failure To Follow Procedures (M. N. 0) 3.

Recent Unit 2 Reactor Trips Six Unit 2 Trips In Late May-June, 1988 Counterpoint: Only : Of The o Involved Personnel Error Or i

Managenent Deficiency.

The other 4 Were Equipment Problems or Undetermined.

10 Trips on Unit 2 In This SALP:

5 Autenatic & 5 Manual 9 of The 10 Trips Involved Feedwater Transients 1 Of The 10 Trips Involved Personnel Error l

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Plant Operations (Continued)

Strengths and Initiatives a.

Long Unit 1 Run (144 Continuous Days) And > 90 % Capacity Factor At Start of Tube Leak Outage.

b.

NC Leakage Has Caused No Shutdowns In This SALP - Total Leakage Is Consistently < 1 GPM This Cycle - Each Unit.

c.

ESF's Reduced:

33 In This SALP Versus 47 In 8/86-7/87 Period.

d.

Total Trips Heduced:

11 In This SALP Versus 15 In 8/86-7/87 Period.

e.

Staff Developed A Professional Code of Conduct f.

Unit 2 Steam Generator Level Modification in 1989 Refueling - Should Improve Situation On Teodwater Transients, g.

Daily Management Plant Status Meeting h.

Plant Labeling Program To Complete 6/89 1.

Improved Plant Housekeeping - Particulary Unit 2 J.

Involvement of Compliance in Operability Decisions k.

Compliance Group Restructuring To Provide One or More SRO's In The Group 1.

Pro Active Tech Spec Review / Training Using Senior Management Person.

Ops Instructors SRO's Management Ops Audit m.

Training By Section Heads To Supervisors And Crews Conducted In Operations. Performance.

Instrumentation And Electrical Construction Dept. On Procedure Use. IV. Personnel Error's, n.

Station Manager Emphasizing The Need for Procedural Adherence And Understanding In Station Wide Letter.

This Included IV.

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Station Management Emphasizing The Importance Of Supervisory Involvement In The Plant With His Crew.

e Plant Operations (Continued)

Strengths and initiativen p.

Ops Supt. Or Station hgr. To Review All Compensatory Action Plans Before Iraplementation, q.

Wider Review Of Proposed Tech Spec Interpretations r.

Review Of OEP's With Training Services Management s.

System Expert Review Of Tech Spec Interpretations t.

Strengthening Of The G.O. As A Focal Point For NRC Communicction u.

Prioritizing Tech Spec Change Submittals Through G.O.

Licensing To NRC I

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RADIOLOGICAL CONTROLS l

concerns Inadequate Frisking - 9/87 And 11/87 NRC Inspections Response /Followupt Specific Training Provided To All t

Personnel On The Problem And Single Point RCA Access Point l

Established - Monitored By HF Hand And Foot Monitors i

Whole Body Monitors l>

HP Conducts Periodic Visual Surveillance l

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Management Surveillance - Continuing l

Program l

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Catawba Exposure Versus Industry Average l

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352 Person R M Per Unit Versus 3/1 Person Rem / Unit j

i National Average

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j Strennth/ Initiatives

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Gansaa Spectroscopy Equipment Standardized j

System Expert Established For MF's t

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Trending of Information Tor Management I

HP Self Appraisals 1

Solid Waste Reduction - 255 Cubic Meters is The Stations 1988 Goal. To Date. 39 Cubic Meters Have Been Generated.

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MAINTENANCE / SURVEILLANCE Concerns:

Clam Incident (Programmatic)

S/G Loose Parts - Reportability Timeliness Maintenance Rule Making / Maintenance Improvement Strengths / Initiatives c

Established Maintenance Engineering Services Group / Staffing a.

(Technical Support Program)

E.itablished System Expert Program And Have Used It For D/G Problem, trd Clam Incident.

P Ai.. Goals For Reducing Work Request Backlog And PM/CM Rat

_tatus"

~100 W.R.'s > 2 Years Old

~200 W.R.'s > 1 Year Old 48.2% of Outstanding W.R.'s Are < 3 Mo. Old Goala:

0 W.R.'s > 3 Month Old l

< 300 Total Non-Outage Outstanding Work 1

(By 12-31-88) 2 Recent Improvements In Violations Associated With Failuro To 1-Retest 1 Violation - 1985 1 Violation - 1986 3 Violation - 1987 1 Violation - 1988 Planning Organization - Traiaing, Single Pir ming Group Concept.

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EMERGENCY PREPAREDNESS

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Streneths/ Initiatives, No Violations In This SALP As Compared To 2 In Previous SALP Training Inprovements - Field Team Direction When In A Plume Uso Of Critical Parameters Monthly Drills / Exercises - Since Mid 1987

- Allows Use Of Alternates

- Improves Response Skills

- Heightens Interest / Involvement Mado ihe TSC A "Dedicated" Facility On 8-20-87

- Allows Quicker Activation TSC Now Automatically Activated i t Alert And Site Assembly Conducted

- Cosmetic Improvements - Position Badges, Area Signs Enclosed Radio Area For HP

- Packup Radio To NC/SC Hoved The OSC To A Larger Facility on 6-21-88

- Located Near The Single Point Access To RCA

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- Facility Is Dedicated

- Addresses past NRC Concerns Emergency Vans

- Now are Marked As such

- Are Under The Station Emergency Preparedness Coordinators Control

- Have Assigned Parking Near The Administration Building

- Emergency Kits On-Board At All Times

- $30,000 Upgrade In Air Monitors EAL Review

- 3 Stations Reviewing For Consistency In Classifying Eients 4

- Review Will Include other Utilities EALs Additional Staffing

- 1 Additional Member Added To The Station Emergency Preparedness Staff In July, 1987.

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SECURIT'l Concerns Lack Of Controls Over Safeguards Information Operations / Security Interface In Establishing SSF Degraded Mode Tailgating Strengths / Initiatives A Design Study Of The PAP Has Improved Badge Control Enhancements To The Vital Barrier Are Being Made Thru The NSM Process.

HVAC Mods Are Incorporating Barriers In The Ductwork (5/8" Rebar).

CCTV Upgrade In 1989 $300.000.

Reconfiguration Of The Fence Line. More Cameras And New Orientation.

Tactical Response Upgraded. Combat Training And Force In Force Issues To Be Addressed.

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6 ENGINEERING / TECHNICAL SUPPORT Strengths And Initiatives Desian Engineerina Onsite Design Engineering Hns On-Site Office Established April, 1988.

Use of TopForm During The Modification Program This Interface Is Being used For Involvement In Daily Operations Operator Training Onsite Simulator Operational January, 1988 Will Increase Operators Simulator Times 20 Hours / Year 1987 50 Hours / Year 1988 On Shift SRO's Periodically Rotated Into One Of Four Training Insttvetor Slots NRC Exam Pass' Rate 9-86 And 9-87 100% Pass-Rate (26/26)

Initial Hot License 20/21 Passed Total Rate To Date 46/37 EP's Revised To Include Human Factors And Have Been Verified / Validated On The Simulator.

Procedures Revised / Implemented 8-1-88.

Refuelina Activities A S Year Outage Plan Established January 1988 Use of The Reactor Building Coordinator "P oject II" Computer Program Allows Rapid Development Of Ai, Outage Work Schedule. This Worked Well For The Present Unit 1 Tube Leak outage.

Outage Logic Chart Improvements r

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SAFETY ASSESSMENT / QUALITY VERIFICATION Concerns j

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Qualification Of The QA Staff 2.

Quality Of Submittals Strengths / Initiatives Station Performance Indicator Program Analysis Of ESF Events And Personnel Errors Followup On Bullentins, Generic Letters, f, : c.

- Fi her Valves

- West Jersey Materials Passive Civil Features Design Study Reduction In Outstanding NRC Commitments (129 8-1-88 Ver.=us 195 8-1-87.)