IR 05000244/1989015
| ML17250B089 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/05/1989 |
| From: | Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17250B088 | List: |
| References | |
| 50-244-89-15, NUDOCS 8912190155 | |
| Download: ML17250B089 (84) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-244/89-15 License No.
DPR'-18 Licensee:
Rochester Gas and Electric Corporation 49 East Avenue Rochester, New York Facility:
Location:
R.
E. Ginna Nuclear Power Plant a
Ontario, New York Inspection Conducted:
October 11 - November 6, 1989 Inspector:
Approved by:
N.
S. Perry, Acting Senior Resident Inspector, Ginna E.
C.
McCabe, Chief, Reactor Projects Section 3B
~xl s/
Date
~Summar Areas Ins ected:
Routine resident inspection of plant operations, radiological controls, maintenance, sur'veillance, security, periodic and special reports, written reports of nonroutine events, and quality program improvement, There were 59 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br /> of inspection, including 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of backshift inspection.
Results:
Overall, the plant operated safely.
Plant events were dealt with effectively.
Two Human Performance Evaluation System reports were thorough (section 3.a)
and review of instrument calibration frequency was appropriate ( section 3.c).
Review of the operability of radiation monitors R-12A, 14A, 15A remains unresolved pending completion of the licensee's justification (section 3.b).
There continues to be a weakness in establishing proper of system align-ments and in independent verification of these alignments (section 3.a).
85'l2i9015s 8pgZog PDR ADOCK 0.00024<
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TABLE OF CONTENTS PAGE 1.
Persons Contacted..
2.
Summary of Operations 3.
Functional or Program Areas Inspected (71707, 62703, 71726 4.
Written Reports of Nonroutine Events (90712).
, 90713)...
6 5.
Quality Program Improvement Management Meetings (71707)..............
6.
Exit Interview (30703).
..........
...............,.............
'
DETAILS 1.
Persons Contacted The following people were among those contacted:
S.
Adams, Technical Manager
- T. Alexander, guality Control Engineer
- C. Edgar,'cting Maintenance Manager
. D. Fi lkins, Manager of HP 8 Chemistry A. Jones, Corrective Action Coordinator M.,Lilley, Nuclear Assurance Manager-
"R. Marchionda, Director of Outage Planning T.'arlow, Superintendent, Support Services R. Mecredy, General Manager, Nuclear Production
"J. St. Martin, Corrective Action Coordinator
"T.'Schuler, Operations Manager L. Sm'.th, Operations Supervisor
'"R. Smith, Senior Vice President, Production and Engineering
- S. Spector, Superintendent, Ginna Station
- J. Wicay, Superintendent, Ginna Production
,*R. Wood, Supervisor, Nuclear Security
"D'enotes persons present at exit meeting on November 7, 1989.
Summar of Plant 0 erations The plant remained at approximately full power during the entire inspec-tion period.
On October 20, 1989, a containment ventilation isolation signal was re-ceived from containment radiation monitors R10A, 11, 12.
Operators veri-fied the. isolation and, after determining that the isolation was not war-ranted, restored all systems to their normal alignment.
At,the time of the isolation signal, a health physics technician was taking a local sample at R-12.
Due to a communication error, the technician thought R-12 was out of service and a local sample was required.
The licensee con-cluded that taking the local sample caused an oscillation in the normal flow to R-12, resulting in a spike and a containment isolation signal.
To prevent recurrence, health physics technicians will verify the status of radiation monitors prior to sampling.
Another containment ventilation isolation occurred on October 23, 1989.
Prior to this isolation signal, radiation-monitor R-12 was cycling.
Ap-parently, it spiked high, causing the isolation signal.
Troubleshooting revealed a bad power supply which was temporarily replaced with a spare while a qualified power supply was ordered.
For the remainder of the in-spection period, R-12 was operating for indication only and required samples were taken dail '
In both cases, the inspector concluded that actions taken were appropriate and coprective actions were adequate.
3.
Functional or Pro ram Areas Ins ected a
~
Plant 0 erations (71707)
Portions of the licensee's management control systems were evaluated to ensure safe operation.
Control room staffing was adequately main-'ained and access to the control room was properly controlled.
Opera-tors adhered to approved procedures and understood the reasons for lighted annunciat'ors.
Control room log books were reviewed to obtain information concerning trends and activities, and recorder traces were 'observed for abnormalities.
Shift turnovers were found adequate to ensure necessary information was addressed.
The inspector veri-fied that selected engineering safety'feature valves and breakers
- were correctly aligned, and that portions of the containment isola-tion lineup were correct.
All accessible areas of the plant were toured; plant conditions and activities in progress were observed with no inadequacies identified.
.The inspector verified that plant technical specifications were complied with and selected safety-related tagouts were proper.
No inadequacies were ide'ntified.
On October 10, 1989, operators inadvertently spilled approximately 700 gallons of boric acid solution in the boric acid storage tank room..
Earlier, the boric acid filter had been isolated and flushed.
The procedure remained open, awaiting maintenance on the filter.
At this point, the chemistry department requested that the boric acid storage tanks be recirculated for sampling.
A control room operator, aware that the system alignment was abnormal, verified a path for recirculation flow to avoid deadheading the pump, then started both transfer pumps.
Several minutes later the main control board alarm for low boric acid storage tank level was received.
Operators im-mediately stopped both transfer pumps and sent an operator to 'inves-tigate the alarm.
The boric acid storage tank room had been sprayed by a hose that was used during flushing and was attached to the open filter drain line.
The pressure from the transfer pumps was suffi-cient to eject the hose from the floor drain.
Operators had not seen the open flow path through the filter when they verified that a path was =available for recirculation.
Operations personnel verified that the storage -tank level always remained above the technical specifi-cation limit.
As corrective action, the procedure for isolating and flushing the boric acid filter was changed to prevent leaving the flow path through the filter drain open after flushing.
Addition-ally, this event and its implications were discussed at a shift super-visor meeting.
A Human Performance Evaluation System (HPES) report by the licensee concluded that a second check of system lineup should be performed and that interdepartmental communications need to be strengthened for better planning.
The licensee is evaluating further actions based on these recommendation A local radiation emergency was declared on October 19, 1989 due to water spilling on the floor from the spent fuel pit skimmer filter pump vent valv'e.
The valve was promptly closed and the area was roped off and cleaned up; no abnormal exposures were produced.
The system was being restored after maintenance.
Before restoration was complete, the operator turned the shift over to his relief, explain-ing what he had done thus far.
With the lineup partially restored, the system started backfilling from the spent fuel pool.
The vent valve was open and, when the piping was full, water overflowed through the vent onto the floor.
The event was discussed with opera-tors to prevent recurrence.
Other corrective actions are being evaluated based on another HPES report.
The safety of the spent fuel pool cooling function was not affected since the piping does'not ex-tend further into the pool.
In both instances, the inspector concluded that there was minimal safety significance and-that the HPES study was thorough and ade-quately assessed each event.
However, the examples described above indicate that there continues to be a weakness in establishing proper system alignments and in independent verification of system align-ments, as described previously in NRC Inspection Reports 50-244/88-08 and 50-244/89-18.
These items will be followed further incident to open violations 88-08-02 and 89-18-03.
Radiolo ical Controls (71707)
The resident inspector periodically verified that radiation work per-mits were implemented properly, that dosimetry was correctly worn in controlled areas and dosimeter readings were accurately recorded, that access control at entrances to high radiation areas was ade-quate, that personnel used contamination monitors as required when exiting controlled areas, and that postings and labeling were in com-pliance with regulations and procedures.
On October 15, 1989, a health physics technician identified an appar-ent discrepancy with the calibration constant used in the calibration procedure for noble gas effluent radiation monitors R-12A (contain-ment purge),
14A (plant vent),
and 15A (air ejector).
These instru-ments monitor radiation after an accident condition and are required to be operable by technical specifications.
Subsequent to the end of the inspection period, the licensee determined that the radiation monitors were operable at all times.
This item remains unresolved pending review of the licensee's determination (UNR 50-244/89-15-01).
A containment entry was made on November 1,
1989 by the licensee and the inspector.
The licensee performed several maintenance and sur-veillance activities.
Prior to the entry, the health physics depart-ment held a planning meeting.
The inspector concluded that the meeting
had a positive effect on informing personnel of all activities to take place and that better coordination, especially for monitoring exposures, resulted.
No inadequacies were identified.
c.
Maintenance (62703)
The inspector observed portions of various safety-related maintenance activities to verify that redundant components were operable, acti-vities did not violate limiting conditions for operation, required administrative approvals and tagouts were used, approved procedures were used or the activity was within the "skills of the trade,"
appropriate radiological controls were implemented, ignition/fire prevention controls were properly implemented, and equipment was properly tested prior to returning it to service.
Portions of the following maintenance activities were observed:
Calibration Procedure (CP)-212, "Calibrations and/or Maintenance of RMS Channel R-12 (Containment Gas)," revision 10, effective July 13, 1989, observed October 17, 1989.
"Calibration and/or Maintenance of the "B" Aux Feed-water Bypass Loop and/or AOV-4481," revision 0, effective April 27, 1989, observed October 31, 1989.
Maintenance Procedure (M)-40, "Surveillance and Maintenance of Hydraulic Snubbers,"
revision 30, effective September 29, 1989, observed November 1,
1989.
Maintenance Work Request (MWR)-89-9139, check AOV-951 (pressuri-zer steam space sample valve) for leakage, observed November 1,
1989.
No inadequacies were identified.
The inspector noted that an apparently high number of gauges were found out of calibration during periodic calibration checks.
In one case, the instrument reading was in the nonconservative direction, but the redundant gauge was reading properly.
A concern was raised regarding the frequency of calibration checks on these instruments.
The licensee's sytem is set up to evaluate calibration frequency if the instrument is found out of calibration by greater than twice the specified allowable range, or if the instrument is found out of cali-bration by greater than the specified amount twice in a row.
The inspector verified the appropriate instrumentation was being reviewed for calibration frequency and had no further conern c
7 d.
Surveillance (61726)
The inspector observed portions of surveillances to verify that test instrumentation was properly cal.ibrated, approved procedures were.
used, work was performed by qualified personnel, limiting condition's for operation were met, and systems were. correctly restored following testing.
Portions of the following surveillance activities were ob-served:
Periodic Test (PT)-16, "Auxiliary Feedwater System," revision 60, effective October 10, 1989, observed October 30, 1989.
PT-2.7,, "Service Mater System," revision 47, effective October 10, 1989, observed November ll, 1989.
e.
No inadequacies were identified.
~Securit (71707)
During-this inspection period, the resident inspector verified that x-ray machines and metal and explosive detectors were operational, protected area and vital area barriers were well maintained, access control during security turnover was adequate, personnel were pro-perly badged for unescorted or escorted access and compensatory measures were implemented when necessary.
On October. 21, 1989, 'he plant experienced the loss of one of the high mast lights; these lights provide plant exterior area illumina-tion.
The licensee took immediate corrective action including the use of temporary, portable lighting which remained in place until the light was repaired and placed back in service.
The inspector con-cluded that the actions taken were adequate.
No inadequacies were identified.
f.
Periodic and S ecial. Re orts (90713)
Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9. 1.
and 6.9.3 were reviewed.
This review included the following considerations:
reports contained information required by the NRC, test results and/or supporting in-formation were consistent with design predictions and performance specifications, and reported information was valid.
The following report was reviewed:
Monthly Operating Report for September 1989.
No unacceptable conditions were identifie ;
Written Re orts of Nonroutine Events (90712)
Written reports submitted to the NRC were reviewed to determine whether details were clearly reported, causes were properly identified, and cor-rective actions were appropriate.
The inspector also determined whether assessment of potential safety consequences had been properly evaluated, generic implications were indicated, events warranted onsite follow-up, reporting requirements of 10 CFR 50.73 were applicable, and requirements of 10 CFR 73 had been properly met.
The following LER was reviewed (date indicated is event date):
89-011, September 20, 1989, Spurious. Actuation of Containment Venti-lation Isolation.
The following 10 CFR 21 report was reviewed (date indicated is notifica-tion date):
Defects in Foxboro Spec 200 termination modules, October 25, 1989.
The Foxboro Company notified RG&E of a potential shorting problem associated with a metallic label potentially located within.060 inch of the spade lugs.
RG&E determined that all field installed modules had the standard
.060 inch clearance.
Seven stock spare modules were identified with clearances less than
.060 inch; these modules have been corrected as recommended by Foxboro.
Additionally, guality Con-trol inspectors were informed to inspect for this condition in the future prior to acceptance.
5.
No unacceptable conditions were identified.
ual>t Pro ram Im rovement Mana ement Meetin (71707)
In response to concerns identified in the SALP report issued August 10, 1989, the licensee met with NRC Region I management to discuss the current status of the quality assurance programs at R.
E. Ginna Nuclear Power Plant.
The licensee outlined recent organizational changes, described 1989 accomplishments and ongoing activities, and stated their objectives for 1990, including staffing plans.
The meeting was a positive exchange of information; further program improvements and activities will be re-viewed in future inspection reports as part of the normal inspection pro-cess.
A copy of the handouts from the meeting is attached.
h 6.
Exit Interview (30703)
The inspector met with senior plant management periodically and at the end of the inspection period to discuss inspection scope and findings.
Based on NRC Region I review of this report and discussion held with lic-ensee representatives, it was determined this report does not contain in-formation subject to 10 CFR 2.790 restriction ATTACHE = TO INSPECTION REPORT 50-244/89-15 LICENSEE HANDOUTS FOR QUALITY PROGRAM IMPROVEMENT MEETING
NUCLEAR MISSION STATEMENT
,Our mission is to create and sustain outstanding performance in all aspects. of operation, including safety, reliability and economy, in order to maximize the value of Ginna Station to customers, employees and shareholders.
.We believe that to be an outstanding performer.
We must protect the health and safety of the community and our employees by setting safe operation as our highest priority.
We must provide a vital, challenging and safe environment for our people; one that
'provides opportunity and encourages and rewards high quality perforrnanc'e and creativity.
We must be a good neighbor, maintaining the support and good willof the public.
We must be efficient, well-managed, disciplined, arid maintain high standards of performance.
We must be bold and innovative in the management of resources and technology, achieving a profitable, competitive and technically superior operation to give the greatest value to our customers, employees and shareholders.
5/31/89
Nuclear Strat ic Plan Based on our Self-Assessment of Need; provides direction we believe necessary to:
0, Resolve long standing industry issues at Ginna Convey Management commitment to exce3.lence in our nuclear one ations
Develop ~act'o plans, m'lestones and resources to implement improvement Communicate strategy and goals to Key Nuclear line manage s and employees Completed late 1988,
'ssued Nay 1989, reviewed by Z¹O June 1989 Has achieved a positive at itude toward mprovement October 23, 1989
.
RQaE CORPORATE TO NUCLEAR QUALITY IÃPROVKNBiT o
IMPLEMENTATION OF STRATEGIC PLAN
- A SXGNIFICANT COMMITMENT TO IMPROVED GXNNA PERFORMANCE o
PROGRAMS INXTIATED INCLUDE:
- CONFIGURATION MANAGEMENT
-.Q LIST
- MAINTENANCE PROCEDURE UPGRADE
- ADMINISTRATIVEPROCEDURE UPGRADE
- PLANT BETTERMENT
- 50. 59 REVIEW PROCESS
- COMMITMENT TRACKING
-
PROCUREMENT UPGRADE
- RELIABILITYCENTERED MAINTENANCE o
XNCREASED 0 5 M AND CAPITAL EXPENDXTURE LEVEL o
INCREASED MANPOMER COMMXTMENT TO SUPPORT GINNA
. GINNA VS. INDUSTRY PERCENTILES 3.5 2.5 2.0 75/TLE 50%TLE 75XTCE 25XTVE 1.0
'83-85
'86-88 I
'89-91f Tl BEE YEAR PLBOf)S
Nuclear Staff Complement Plan October 1989 July 1991 Current Authorized Cha"che New*
Compl~~
(Approved
~06~89 permanent Employees Contractors Combined Total 460 150 610 135
595
690 Phase Additions (Nov.
1989 - July 1990)
30 640 Phase
Additions (Aug.
1990 - July 1991)
595
690
- Full Xmplementation Contingent upon PSC approval of rate recpxest filed July 1989 and due to take effect August 1990
ualit Pro ram Mana ement and Or anization Presentation at NRC meeting in Region I offices October 24, 1989 to review RG&E plans for improving the Ginna quality program.
RG&EK025 Qual. Perf.
Dept.
10/24/89
TABLE 1.
Qualit Performance Department hanaqement Organization (August
1989)
hill McCov Dept Manager Qualitv Perfor ance Charlie Anderson Manager uality Assurance Mike Iilley Manaaer uclear Assurance John Smith Manaqer aterial Enara.
&
nspect.
Services Jim. Bodine Senior Quality Performance Analvst
2.
Qualit Performance Department Em ee Orc)anization (October
1989)
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Areas of Em hasis for the A/ C Functions of the ualit Performance De artment
~
Positive a
roach:
Encourage what is good.
Build pride and sense'f accomplishment in quality activities of the Ginna organization.
~
Z,ook for ma'or im rovements:
Many small problems are symptomatic of larger problems.
S ot industr issues/trends:
Must get ahead of issues.
Review out-of-date commitments:
Some commitments may be obsolescent,,
in light of improvements in other areas since original commitment was made.
Cultivate ood workin relationshi s:
Work for a harmonious relationship with all interfacing groups, through mutual respect, good planning, good communications, et I Pro rammatic Areas of Em hasis for ualit Pro ram Im rovement Adopt a broader. vision of "quality", to extend beyond traditional scope to include many "management" issues, so that activities can progress smoothly and correctly the first time.
2.
Establish 'a QA surveillance 'program, with performance based monitoring across the spectrum of Ginna activities.
3.
Place increased emphasis on observation in conventional audits.
4.
Increase use of technical specialists in support'f audits and QA surveillances.
5.
Revamp the scheduling of monitoring/assessment activities to recognize emerging issues, prior performance, and activities crossing many organizational lines.
Retain flexibilityto perform special assessments as the needs arise.
6.
Develop -better reports for management, so that management can recognize what is important and what can/should be addressed with management action, Improve the effectiveness of the QA/QC Subcommittee to the NSARB, with less attention to individual items of small
'ignificance and more attention to "big picture" issues.
8.
Through training and attention in assignment of work, be sure that QA/QC personnel develop capabilities to perform a broad. scope of work to assure high job interest and career development for a strong'rganization in the years ahea Accom lishments/On oin Activities f
1.
Consultant completed QA/QC staffing assessment (Feb).
2.
Evaluations of QA/QC organizational arrangements performed by former department manager and QA/QC group (Mar, May).
3.
Achieved reorganization with two new managers and establishment of QC Inspection Foreman and Senior Quality Performance Analyst positions (July).
4.
Developed improved agendas, analyses, and presentations for two QA/QC Subcommittee meetings (July, Sept).
5.
6.
Completed special assessment of forced outage management with the plant's director-of outage planning (Sept).
Assigned a new Senior QA Engineer matrix responsibilities to the NSARB and to the Superintendent Support Services for maintenance management programs projects (Oct).
8.
Completed draft QA Surveillance Program procedures and, performed one pilot QA'surveillance with consultant assistance.
Developed a Quality Performance 1990 operat'ing plan and a
first draft Quality Effectiveness action plan for the Ginna
'trategic Plan (Oct).
9.
Obtained management approval to increase QA/QC staffing (Oct).
Leadershi Res onsibilit Assi nments for 1990 Ob'ectives Concernin A/ C Pro ram No.
Ob'ective Sub'ect Responsible Leader 1.
Establish QA surveillance program and increased performance based monitoring in audits.
Anderson 2.
Improve value of quality performance reports.
Bodine 3.
Improve QA/QC Subcommittee meetings.
McCoy 4.
Increase technical expertise for audits
McCoy QA surveillance.
5.
Develop QA/QC sections commitment tracking system.
Bodine 6.
Develop AFCAR tracking system.
Improve NSARB activity effectiveness.
8.
Develop QA surveillance and audit scheduling process.
9. 'et best people to fillQA/QC positions.
Bodine Schaaf Anderson Anderson Lilley Bodine 10.
Industry visits and committee parti-cipation for improved quality program.
Improve working relationship for QA/QC program.
McCoy McCoy 12.
13.
Recognize quality achievements.
Facilitate self-assessments with line organizations.
McCoy McCoy 15.
Facilitate procurement quality improvements.
14.
Department wide training schedule.
Bodine Easterbrook 16.
Facilitate quality improvements in modification engineering/construction/
turnover/training process Lilley
I
A/ C Sections Staffin Plan Excluded are the approximate 30 employees in the Materials Engineering and Inspection Services section of the Quality Performance Department.
Present Additions'
Projected Additionsrojected (10/89)
(11/89-7/90)
(7/90)
(8/90-12/90)
(1/91)
RG&E Employees
Contractors'~'
(2
3
41
'TOTAL
7
10
'Contractors filling permanent functional positions.
'~'Contingent upon savings from contractor rollovers to RG&E employee status (division wide) offsetting cost of additional new hires.
(Projected rollovers total 60 with 5 non-nuclear included, permitting 30 additional permanent positions for Ginna.)
Contingent upon PSC approval of full.rate request filed in July 1989 and due to take effect in August 1990.
RG&EK025 Qual. Perf.
Dept.
10/24/89
'I QUALITY ORGANIZATION EFFECTIVETY ENHANCEMENT SELF ASSESSMENT GOALS HOW TO BE MORE EFFECTIVELY UTILIZED AS A MANAGEMENT TOOL HOW CAN THE QUALITY ORGANIZATION SUPPORT AN OBJECTIVE OF THE SR VICE PRESIDENT FOR ACHIEVING CWORK OBJECTIVES THE FIRST TIME
THE CHANGING ROLE WITH REGARD TO
,.PLANNING (DOCUMENTATION REVIEW)
VERIFICATION THROUGH (TRADITIONAL INSPECTION, SURVEILLANCE AUDIT)
- "
ASSESSMENT (TO ASSESS EFFECTIVENESS OF ACTIVITIES)
REPORTING TO MANAGEMENT PROGRAM SUPPORT
IMPROVEMENT EMPHASIS
PRE TRANSITION PERIOD (PRIOR TO 1989)
VERIFICATION (TRADITIONAL)
A.
QC INSPECTION AND SURVEILLANCE SELECTIVELY APPLIED TO JOBS BASED ON INSPECTOR AVAILABILITY,PREVIOUS PROBLEMS ENCOUNTERED.
FOCUS MAS COMPLIANCE AND ACHIEVED LARGELY THROUGH SURVEILLANCE OF THE ENTIRE ACTIVITY.
EFFECTIVENESS DEPENDENT ON THE XNSPECTORS TRAINING AND EXPERIENCE.
B.
AUDITS FOCUS - TECHNICAL SPECIFXCATZON AND ACTIVITIES ASSOCIATED NITH "Q" COMPONENTS.
e.
VERIFICATION.BASED APPROXIMATELY 3 1/2 MAN YEAR EFFORT SCHEDULED SURVEILLANCE 1/2 MAN YEAR PERFORMED BY QC TECHS AND FOCUSED ON ACTIVITIES OF SUPPORT GROUPS ASSESSMENT (TO ASSESS EFFECTIVENESS OF ACTIVITIES)
MINIMAL REPORTING TO MANAGEMENT A.
ROUTXNE CORRECTIVE ACTION STATUS REPORTS AND RELATED TRENDS B.
GROUPS PERFORMANCE AND ACTIVITY ASSESSMENTS LIMITED TO REVIEW OF COMPLIANCE FOCUSED AUDIT REPORTS
TRANSITION PERIOD (BEGINNING 1989)
VERIFICATION A.
-QC INSPECTION AND SURVEIZLANCE QC SURVEIZLANCE PROCEDURES BEXNG ESTABZXSHED TO STANDARDIZE INSPECTOR EMPHASIS FOR VARIOUS JOBS BE AUDITS MINOR SHIFT TO INCLUDE MONXTORING OF REALTXME ACTIVITIES AND UTILIZATIONOF MORE TECHNICAL EXPERTISE IN THE SPECIALTY AREA C.
-
SCHEDULED SURVEIZZANCE BEING REPZACED BY QA SURVEIZLANCE PROGRAM
-
ASSESSNENT ASSESSNENT FUNCTIONS QA SURVEILLANCE
~ Performance-based Flex schedule
~ 1-2 wk include planning 6 report.
QA AUDITS
~ Performance-based Fixed. schedule
~
1 month ea. (1/3)
1/2 month ea.
(2/3)
SPECIAL ASSESSMENTS
~ Augment Surveillance fi Audits
~ Effectiveness reviews
~ Results prompt
~ Resources-Best Qualified cra4199
QA SURVEILLANCE (PERFORMANCE"BASED)
FEATURES (1)
FOCUS WILL BE ON ACTIVITIES ASSOCIATED WITH GINNA SAFETY-RELATED AND SAFETY SIGNIFICANT SYSTEMS (2)
FOCUS WIZZ INCLUDE ORGANIZATIONS WHICH SUPPORT GZNNA STATION (3)
FOCUS WILL INCLUDE MONITORING WEEKEND AS WELL AS.BACK SHIFTS (4)
PATTERNED AFTER SUSQUEHANNA & TMI PROGRAMS PROVIDE TIMELY FEEDBACK TO FIRSTLINE SUPERVISORS REGARDING EFFECTIVENESS OF REVAMPED PROGRAMS,
'RELATED TRAINING, ETC.
STATUS (1)
PILOT PROGRAM HAS,COMMENCED (2)
RESOURCES BEING RECRUITED (3)
TRAINING BEING SCHEDULED (4)
LINE ORGANIZATIONS ARE BEING INDOCTRINATED
AUDITS (PERFORMANCE"BASED)
FEATURES (1)
AUDIT SCHEDULES ARE BEING ADJUSTED TO BETTER COINCIDE WITH ACTIVITIES BEING CONDUCTED
, EXAMPLES INCLUDE:
OUTAGE AUDIT
RADWASTE SHIPPING'URVEILLANCE TESTING (2)
DEDICATED GROUP BEING ESTABLXSHED SO THAT SUPERVISORY CONTROL AND TRAINING CAN BE OPTIMIZED.
{3)
COORDINATION LINK WITH QA SURVEXLLANCE GROUP BEING ESTABLISHED TO BETTER OPTIMIZE SCHEDULING AND RESOURCE UTZLZZATZON (4)
TO COMPLEMENT VERIFICATION AUDITS AND BE PERFORMED CONCURRENTLY (5)
TO INCREASE UTILIZATIONOF UTILITY/TECHNICALEXPERTISE WHEN AVAILABLEAND INDEPENDENT (6)
SCHEDULES WHICH UTILZ2E 'FEWER AND MORE COMPREHENSIVE AUDITS ARE BEING ESTABLISHED (7).
INCREASED EMPHASXS ON VERTXCAL SZICE AUDITS IN 1990
STATUS (1}
AUDITORS HAVE RECEIVED INITIAL PERFORMANCE. BASED TRAINING FROM BARTECH (2)
PEER REVIEWS OF AUDIT REPORTS ARE PERIODICALLY,CONDUCTED (3)
AUGMENTED TRAINING BEING SCHEDULED
SPECXAZ ASSESSMENT BEING ESTABZISHED FEATURES (1)
(2)
(3)
(4)
(5)
COMPREHENSIVE BUT LESS STRUCTURED ASSESSMENTS OF'ONDITIONS OR ACTIVITIES REQUESTED BY MANAGEMENT LED BY OR CONDUCTED BY ANY EXPERIENCED.AND AVAILABZEQA PERSONNEL DURATION MAY VARY FROM ONE TO SEVERAL MANWEEKS UTILIZE TECHNICAL EXPERTISE WHEN APPROPRIATE REPORTED RESULTS INCZUDE STRENGTHS, WEAKNESSES AND RELATED RECOMMENDATIONS STATUS (1989 ASSESSMENTS)
(1)
EMPLOYEE ATTITUDE ASSESSMENT COMPLETED XN JUNE (2)
RADIATION PROTECTION CORRECTIVE ACTION EFFECTIVENESS COMPLETED IN SEPTEMBER (3)
CONTRACTOR QUAZITY PROGRAM EFFECTIVENESS COMPLETED IN MAY (4)
NSARB EFFECTIVENESS IN PROGRESS (5)
PROCUREMENT CONTROL SCHEDULED FOR NOVEMBER (6)
AUGUST FORCED OUTAGE ASSESSMENT SEPTEMBER (7)
OFFSXTE POWER MAXNTENANCE PRACTICES XN PROGRESS
A AUDIT OF ELECTRIC SUBSTATXONS MAINTENANCE ACTIVITIES (REFT
'.
EVENT 489-82 AND NRC VXOLATXON 89-18-07)
QUALITY ASSURANCE PERFORMED AUDIT "NUMBER 89-47:BS TO ASSESS:
ESD maintenance work control activities ESD control of procedures and practices ESD training of personnel performing the work AUDIT RESULTS INDICATE:
ESD has issued work practice MP-43.0 to all ESD work practices manual holders.
It requires the job foremen to document as found and as left position information for sliding links on the Maintenance Inspection and Test forms issued with the ESD work order.
Each electrician and service vehicle has a copy of the work practices manual and the ESD work procedures.
Therefore, a
copy of the practices and procedures should be available at each work site.
Work Outlines are prepared for complex jobs and contain more detail for performing the maintenance than the vendor manual.
The MP-43.0 work practice for documenting as found as left sliding link position has not been used yet as no work requiring sliding link movement has been performed since its issuance.
ESD has determined that part of the cause of event g 89-82 was a lack of coordination between ESD and the Ginna Station Outage coordination personnel.
They have resolved this by contacting the outage personnel and including them in the planning process for work performed at Ginna Station and Station 13A.
ACTIVITIES TO BE OBSERVED BY QUALXTY PERFORMANCE PERSONNEL INCLUDE:
Bushing replacement scheduled to be performed November 13, 1989.
ESD Department meeting on November 10, 1989 at which work practice MP-43.0 will be discussed with the electricians.
Effectiveness of Ginna Station interface with ESD.
SUNNY:
The controls currently in place at ESD are sufficient to preclude recurrence of event f89-82.
Their implementation will be investigated in November, 198 'REPORTING TO MANAGEMENT
FEATURES (1)
. TO MONITOR NEW MEASURES OF PERFORMANCE (2)
REPORTS
'MORE USER FRIENDLY (3)
IMPROVED IDENTIFZCATION AND ANALYSIS OF TRENDS
STATUS (1)
OBJECTIVES HAVE BEEN ESTABLISHED AND WILL BE IMPLEMENTED IN 1990 UNDER THE DIRECTION OF SR ANAZYST,-
QUALITY PERFORMANCE era~201
EMPHASIS SHIFT PRE-TRANSITION TRANSITION FUTURE 1.
Audits Style Quantity Compliance
performance-based
33 (40-80 hrs per)
Compliance
perf.-based
12 (40-80 hrs per)
5 (300+ hrs per)
Compliance
perf.-based
same same 3.
QA Surveillance Style Performed by Scheduling Focus Quantity Effectiveness (scheduled surv.)
Compliance 100 QC Techs Fixed Ginna-only QA.Support
&
Security
& H.P.
8-10/yr.
minimal Compliance
Perf.-based
QA Engineers/
specialist flexible Ginna
& Support Organizations QA, Safety and Management Controls Approaching
per QTR 1990 improving
85 same same same same timely plus focused
& useful era~198
MANPOWER 1.
Planning (Documentation Review)
PRE TRANSITION 1 offsite several parttime onsite (1 equiv.)
TRANSITION (MID-91)
1 + offsite-3 onsite 2.
3.
4.
5.
7.
8.
9.
Procurement Planning Supplier Auditors QC Inspection/Surveillance Inspectors Audits Surveillance Program Support Reporting to Management Special Assessment 1 equiv.
3 parttime 7 (parttime)
1/4 man year 1/2 man year 1/4 man year
10 4 + parttime'Supervisor 1 + 1/2 1 man year 2/3 man year Subtotal
14-34 era~198
A Interface Activities Modifications:
o Review modification Design Criteria, Specifications and procurement documents for inclusion. of appropriate codes and standards and for inclusion of appropriate item acceptance requirements (Inspection, Test, NDE and related documentation).
o Participate on Modification Follow Groups to review activities and.
recommend areas which should be the subject of additional surveillance, inspections or performance assessment.
Evaluate and assure quality of constructor work through:
review of, administrative and inspection procedures, audits; and surveillance of procedure implementation through overchecks of work in progress.
o Review of completed modification documentation packages prior to turnover for records storag Maintenance/0 erations o
Review MWOTR's, Maintenance procedures and procurement changes and work packages for appropriate quality classification and appropriate item acceptance requirements.
o Review operating procedures and procedure changes and other implementing procedures of other groups.
o Surveillance and/or inspections performed on in-process activities
Procurement I
o Review of procurement packages for completeness, procedural compliance and inclusion of appropriate codes, standards, and item acceptance requirements (inspection, test, NDE, traceability, a'nd related documentation)
o.
Performance of receipt inspection activities, including completion of item acceptance plan and. document review.
o
.
Control of on-site materials through appropriate tagging and
"holds".
o
.
Participation in supplier surveillance or audit activities as necessar ~
General ualit Related Activities o
Disposition or review disposition and process non-conformance reports, IDRs, and QCRs.
o Develop component related QC inspection and surveillance procedures.
o Perform inspection and surveillance in response to witness and hold points and as required to focus on problem areas.
o Review activities, reports, and industry experience for concerns or trends adverse to quality.
o Review of documents submitted for pre-PORC review and
,attendance as members of the PORC for evaluation of safety related issue l
~
ualit Issues Nuclear Assurance o
Broaden view of "Quality" o
Attention to detail o
Relationship/Interface with "non-QC" groups o.
Role in planning/maintenance activities o
Focus on industry experience o
Assessment of weak areas for management awareness
ualit Lessons Learned o
Extent and type of involvement in modification follow group changing to improve oversight of the control of design changes.
o Performance based surveillance of modification process activities and improve ability to assess the effectiveness of modification controls.
o Continue to, emphasize requirement that procedures are to be followed as written and approved procedure changes utilized as only method of'eviation.
o Improve methods of monitoring the scheduling of periodic tests.
Develop requirements and procedures as necessary to ensure appropriate oversight of offsite power equipment maintenanc t gr ~
EKCHESTER GAS and ELECTRIC CORPORATION Inter-Office Correspondence October 17, 1989 Subject: Modification Follow Group Responsibilities To:
Nuclear Assurance Group In order to provide adequate control of modifications, the following defines the minimum expectations for Nuclear Assurance relative to Modification Follow Groups.
Nuclear Assurance is to be represented on all Modification Follow Groups.
N.A. representative shall review activities and recommend areas which should be the sub)ect of additional surveillance, inspections or performance assessment.
Training shall be specifically verified as reflecting the latest revision of the Design Criteria and output documents.
Procedures shall-be verified to be based on, or revised to reflect, the final approved output documentation and shall be complete and in sufficient detail to address all required activities.
The modification Follow Group will be expected to function throughout the entire modification process and will provide a.
comprehensive review of the Modification prior to PORC turnover.
Michael P. Lille Manager, Nuclear ssurance xc: T. L. Harding mpl.002 MPL/pal
P f
MANAGZ262iT INVOLVZ269FV IN QUALITY ZMPROVEMBFZ QUALITY STRATEGY DEVELOPMENT GPC DEVELOPED STRATEGY-GROUP INCLUDES PLANT MANAGEMENT AND ENGINEERING MANAGEMENT NEW PROGRAM SUCCESS ZNVOLVEMENT OF LINE'ANAGEMENT ZN QA SURVEILLANCE PROGRAM AND IN PERFORMANCE ZNDICATOR DEVELOPMENT INTEGRATION OF QUALITY ORGANIZATION WORK PACKAGE PLANNING TECHNICAL TRAINZNG PROCEDURE REVIEW WORK IMPLEMENTATION JOINT INVOLVEMENT ZN ASSESSMENTS AND RESOLUTIONS ROOT CAUSE ANALYSIS-CORRECTIVE ACTION REPORTS~
HPES, AND FORCED OUTAGE CRITIQUE SELF EVALUATZON OF LONG TERM EFFECTIVENESS OF CORRECTIVE ACTZON SELF VERIFICATZON PROGRAMS DEVELOPED-MAINTENANCE AND OPERATIONS
h.e t (.