IR 05000483/1988015
| ML20205A746 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/22/1988 |
| From: | Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20205A733 | List: |
| References | |
| 50-483-88-15, NUDOCS 8810260085 | |
| Download: ML20205A746 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No.
50-483/88015(DRP)
Docket No. 50-483 License No. NPF-30 Licensee: Union Electric Compai:y Post Office Box 149 - Mail Code 400 St. Louis, M0 63166 Facility Name:
Callaway Plant, Unit 1 Inspection at: Callaway Site, Steedman, H0 Inspection Conducted: July 31 through August 31, 1988 Inspectors:
B. H. Little C. H. Brown kl YlhY Approved By:
R. W. DeFayetds, Chief, 7M Reactor Projects Section 3A Date Inspection Sunmary Inspection from July 31 through Aucast 31,1988_(CejortNo. 50-483/83015(DRP)).
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Areas Inspected: A routine unannour.ced safety tiispection of1Tcensee event reports, plant operatfor.s, radiological controls, maintenar,ce/ surveillance, amergency preparedness, security, engineering and technical support, and
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safety assessment / quality verification was performed.
Results: The licensee's per;onnel perfonnance in operetions, radiological controls, maintenance /curveillance 1.nd security, in general, indicated a satisfactory level of tralbing and supervicion. Enginecring and other plant
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organizations appe.ar to have good working relationships. Gae violation was
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identified ir the area of recurity (failure to follow access control
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procedures). Additionally, another violation was identified (failure to meet technical specif fration requirements); however, in accordance with 10 CFR 2 Appendix C Section V.A; no Notice of Violation was issued (paragraph 2.b.)
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for this second violation.
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8810260085 880923 DR ADOCK 05000483
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DETAILS
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1.
Persons Contacted i
D. F. 'Schnell, Senior Vice President, Nuclear
- G. L. Randolph, General Manager, Nuclear Operations
- J. D. Blosser, Manager, Callaway Plant
- C. D. Naslund, Manager, Operations Support
- A. P. Neubalfen, Manager, Quality Assurance J. R. Peevy, Assistant Manager, Technical Services W. R. Campbell, Manager, Nuclear Engineering M. E. Taylor Superintendent, Operations D. E. Young, Superintendent, Maintenance
- W. R. Robinson, Assistant Manager, Operations and Maintenance R. R. Roselius, Superintendent, Health Physics T. P. Sharkey, Supervising Engineer, Site Licensing G. J. Czeschin, Superintendent, Planning and Scheduling W. H. Sheppard, Superintendent, Outages
- G. R. Pendegraff, Superintendent, Security L. H. Kanuckel, Supervisor, Quality Assurance Program J. V. Laux, Superintendent, Technical Support, Quality Assurance G. A. Hughes, Supervisor, Independent Safety Engineer Group J. C. Gearhart, Superintendent, Operations Support, Quality Assurance
- J. J. Cassmeyer, Quality Assurance Engineer
- Denotes those present at one or more exit interviews.
In addition, a number of equipment operators, reactor operators, senior reactor operators, and other members of the quality control, operations, nintanance, health physics, and engineering staffs were contacted.
2.
Inspection of Licensee Event Repcrts (92700)
Through direct observatior.s, discussions with licensee personnel, and a review of records, the following licensee event reports were reviewed to detennine that reportability requirements were fulfilled, that immediate corrective action was accomplished, and that corrective action te prevent recurrence was accomplished in accordance with Technical Specifications (T/Ss). The LERs listed below cre considered closed, i..
(Closed) LER 88-007-00:
Reactor trip on low steam generator level due to throttle pressure limiter circuit failure and subsequent unplanned feedwater isolation.
On May 2,1988, while at approximately 99 percent reactor power, all four turbine control valves closed.
The. loss of steam demand caused the steam generator water levels to shrink resulting in an automatic reactor protection system (RPS) reactor trip on low steam generator water level. The RPS actuation initiated a feedwater isolation signal (FWIS) and an auxiliary feedwater actuation signal as designed.
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The licensed operators recovered from the reactor trip in accordance with plant procedures.
Recovery action included closing the reactor trip breakers and resetting the FWIS. Reactor Startup was delayed to permit additional evaluation of root cause of the event.
In response to the delay the licensed operator opened the reactor trip breakers which reinitiated the FWIS.
The licensee's evaluation determined that the probable cause of the turbine control valve closure was due to the Throttle Pressure Limiter (TPL) circuit failure.
The licensee's corrective action included implementing a temporary modification which bypassed the TPL circuit.
Progressive disciplining was initiated with the licensed operator involved in the unplanned FWIS incident. The incident was discussed with shift supervisors and included in the operator's requalification "lessons learned" training.
The inspectors consider that the Itcensee's corrective action to prevent recurrence is appropriate. This item is considered closed.
b.
(Closed) LER 88-008-00:
Sampling was not performed for an inoperable radiation monitor due to a circuit board failure that prevented detection of the condition.
Background: During a routine daily surveillance, with the plant operating at 100 percent power, the radwaste building vent noble gas monitor was found to be inoperable. The failure was caused by a random access memory integrated circuit failure on the microprocessor circuit board.
By design, this type failure does not alarm in the control room. The monitor's memory showed that the unit had failed approximately 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> before detection. The technical specification section 3.3.3.10 section 40 required 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples during this 19 hour2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> period.
This violation meets the tests of 10 CFR 2, Appendix C, Soctior V.A; consequently, no Notice of Violation will be issued, and +.his matter is considered closed.
(483/88015-01(DRP))
3.
Plant Operations (71707) (71710)
a.
Oy. rational Safety Verification Inspections were routinely perfomed to ensure that the licensee conducts activities at the facility safely and in conformance with regulatory requirements. The inspections focused on the implementa-tion and overall effectiveness of the licensee's control of operat-ing activities, and on the performance of licensed and non-licensed operators and shift technical advisors.
The inspections included direct observation of activities, tours of the facility, interviews
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and discussions with licensee personnel, independent verification of
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safety system status and limiting conditions of operation (LCO), and reviews of facility procedures, records, and reports. The following items were considered during these inspections:
Adequacy of plant staffing and supervision.
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Control room professionalism, including procedure adherence,
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operator attentiveness, and response to alarms, events, and
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off-normal conditions.
Operability of selected safety-related systems, includin5
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attendant alaims, instrumentation, and controls.
Maintenance of quality records and reports.
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The inspectors observed that control room supervisors, shift technical advisors, and operators were attentive to plant conditions, performed frequent panel walkdowns and were responsive to off-normal alarms and conditions. The plant has operated at essentially 100 percent power throughout the inspection pericd.
b.
Off-shift Inspection of Control Rooms The inspectors performed routine inspections of the control room during off-shift and weekend perious; these included inspections
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Letween the hours of 10:00 p.m. and 5:00 a.m.
The inspections were conducted to assess overall crew performance and, specifically, control room operator attentivaness during night shifts.
The inspectors determined that both licensed and non-licensed operators were attentive to their duties, and that the administrative controls relating to the conduct of operation were being adhered to.
c.
ESF System Walkdow2 The operability of selecteJ engineered safety features was confirmed by the inspectors during walkdowns of the accessible portions of several systems. The following items were included:
verification that procedures match the plant drawings, that equipment, instrutancatien, valve and electrical breaker line-up status is in agrem3nt with procedure checkiists, and verification that locks, teqs, jumpers, etc. arc properly attached and identifiable.
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J following system was walked down during this inspection period:
"A" Emergency Diesel Generator
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d.
Plant Material Conditions / Housekeeping The inspectors performed routine plant tours to assess material conditions within the plant, ongoing quality activities and plantwide housekeeping.
The inspectors also accompanied the licensee's management on monthly plant tours.
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The painting of various areas of the plant is continuing. The emergency diesel generator rooms are in the final stages of completion.
Plant tours showed the material condition and housekeeping to be well maintained. No equipment problems were noted that had not been placed in the work request file.
No violations or deviations were identified.
4.
_ Radiological Controls (71709)
The licensee's radiological controls and practices were routinely
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observed by the inspectors during plant tours and during the inspection of selected work activities. The inspection included direct observations
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of heslth physics (HP) activities relating to radiological surveys and monitoring, maintenance of radiological control signs and barriers, contam! nation, and radioactive waste controls. The inspection also included a routine review of the licensee's radiological and water chemistry control records and reports.
The inspectors found the controls to be effective. The controls and practices are generally supported and followed by all plant personnel.
The "hot particle" controls were in place for maintenance on the fuel trani.fer mechanism.
No violations or deviations were identified.
5.
Maintenance / Surveillance (62703) (61726)
t Selected portions of the plant surveillance, test and maintenance activities on safety-related systems and components were observed or reviewed to ascertain that the activities were perfonned in accordance with appreved procedures, reculatory guides, industry codes and standards, and the Technical Specifications.
The following items were
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considered during these inspections:
the limiting conditions for operation were met while components or systems were removed from service;
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approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibration was perforrned prior to returning the components or systems to service; parts and materials that were used were properly certified; and appropriate firo prevention, radiological, and housekeeping conditions were naintained, a.
Maintenance
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The reviewed maintenance activities included:
Work Request No.
Activity WR 108697 KFC01A Pressure regulating valve rework.
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WR 108695 KFC01A Inspect solenoid valvo.
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WR 116963 Repair / replace power supply MF-PAE01B.
WR 108698 KFC01B Rework pressure regulating valve.
WR 108696 KFC01B Inspect SV12 solenoid.
"A" Main feedwater pump lube oil reservoir level indicator repair.
WR A418681A CMP 87-1004 Modification to annunciator panel alarms.
b.
Surveillance The reviewed surveillances included:
Procedure No.
Activity ITL-EN-00P10 Loop pressure; containment spray pump "B" discharge pressure.
OSP-SE-00004 Nuclear instrument system power range heat balance.
ISF-AB-0P544 Functional - pressure steam generator "D" pressure.
OSP-ZZ-00001 Control room shift and daily log reading and channel checks.
The maintenance and surveillance functions were found to be properly performed and well controlled. The control room was kept informed of job status and problems that could effect plant operations.
Fire protection and prevention measures were noted to be in place as required. The surveillance and maintenanca cf the fire fighting equipment and the fire detection equipraent was found to be up-to-date.
No violations or deviations were identified.
6.
Emergency Preparedr.oss (8230).)
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An inspection of emergency preparedness activities was cerformed to assess the licensee's implementation of the emergency plan and implement-
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ing procedures. The inspection included monthly observation of emergency
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facilities and equipment, interviews with Itcensee staff, and a review of selected emergency implementing procedures.
The emergency facilities were satisfactorily maintained. During a spot check, the equipment was found to be functional.
Emergency procedures in the control room are being satisfactorily maintained.
No violations or deviations were identified.
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Security (71881)
The licensee's security activities were observed by the inspectors during routine facility tours and during the inspectors' site arrivals and departures. Observations included the security personnel's performance associated with access control, security checks, and surveillance ac-tivities; and focused on the adequacy of security staffing, the security response (compensatory measures), and the security staff's attentiveness and thoroughness.
One violation of security access control procedures was identified by NRC regional based inspectors. The details are included in an attachment to this report, and are considered safeguards information.
(483/88015-02(DRSS))
One violation and no deviations were identified.
8.
Engineering and Technical Support (37701)
An inspection of engineering and technical support activities was performed to assess the adequacy of support functions associated with operations, maintenance / modifications, surveillance and testing activities. Tae inspection focused on routine engineering involvement in plant operations and response to plant problems.
The inspection included direct observation of engineering support activities and discussions with engineering, operations, quality control and maintenance personnel.
The engineering and technical support being provided to operations continues to be timely. The support provided to implement a timely completion of Bulletin Number 88-05 was considered to be professional.
No violations or deviations were identified.
9.
Safety Assessment / Quality Verification (35701)
An inspection of the licensee's quality prograas was performed to assess the inplementation and effectiveness of programs associated with managt-ment control, verification, and oversight activities. The intpectors considered areas indicative of everall management invchement in quality matters, self improvement programs, respense to regulatory and industry initiativas, the freauency of irinagement plant tours and control room observations, and management personnel's attendance at technical and planning / scheduling nieetings.
The inspectors attended On-site Review Committee meetings and incident / event critiques and reviewed related documents, focusing on the licensee's root cause determinations and corrective actions. The inspection also included a review of quality records and selected quality assurance audit and surveillance activities.
Performance in this area included the following major item:
NRC Bulletin 88-05 and Supplement 1, Nonconforming Materials
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Background NRC Bulletin 88-05 and 88-05, Supplement 1, notified utilities of nonconforming materials (flanges and fittings) and requested certain actions and reports by the licensee.
On August 3, 1988 the NRC issued Supplement 2 to Bulletin 88-05. This supplement suspended further record search, field testing and justification for continuing operation (JCO)
requirements. The inspectors reviewed the licensee's response and findings in this matter.
Licensee's Response The licensee provided resources and personnel to develop and isplement programs and procedures to accomplish the following:
Procurement record search - to identify suspect nonconforming
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material by heat number.
Procurement package review - to determine quantity and location of
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suspect components.
Testing of suspect components.
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Evaluation / documentation of test results.
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Licensee's Findings / Action
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The licensee completed the identification and location of safety related material. The document search identified a total of 343 individual components (flanges) installed in safety related systems. One hundred and twenty flanges were determined to be inaccessible and a JC0
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evaluation was applied. The remaining 223 flanges were determined to be accessible for field testing.
Field hardness testing (Equotip) comenced on July 11, 1988. Test results showed 139 flanges met the acceptance criteria for hardaess (Brinnell Hardness Values 137 to 187).
Eighty-four flanges tested
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outside c' the acceptable rtnge. At the time Supplement 2 was issued, field testing had beer, completed on all but five "accessible" flanges.
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The licensee decided to continus the testing and the evaluation of test results of all accessible flanges.
This program was completed on i
August 5
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The inspectors cicsely monitored the licensee's overall response in this matter.
The inspectors attended status briefings, observed field testing activities and reviewed test results and JC0 evaluations.
The inspection l
showed that the program was comprehensive and implemented in a timely fashion.
The licensee estimates that response to this area of concern l
involvt.d approximately 20 man-months effort.
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i Tracking and follow-up inspection will be under NRC Bulletin 88-05 and
Supplements thereto.
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t No violations or deviations were identified.
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10. Violations for Which a "Notice of Violation" Will Not be Issued The NRC uses the Notice of Violation as a standard method for formalizing the existence of a violation of a legally binding requirement. However,
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because the NRC wants to encourage and support licensee initiatives for
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self-identification and correction of problems, the NRC will not
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generally issue a Notice of Violation for a violation that meets the tests of 10 CFR 2, Appendix C, Section V. A.
These tests are:
(1) the violation was identified by the licensee; (2) the violation would be categorized as Severity Level IV or V; (3) the violation was reported to the NRC, if required; (4) the violation will be corrected, including measures to prevent recurrence, within a reasonable time period; and (5)
it was not a violation that could reasonably be expected to have been prevented by the licensee's corrective action for a previous violation, t
Violations of regulatory requirements identified during the inspection for which a Notice of Violation will not be issued are discussed in Paragraph 2.b.
11.
Exit Meeting (30703)
The inspectors met with licensee representatives (denoted under Persons Contacted) at intervals during the inspection period. The inspectors summarized the scope and findings of the inspection.
The licensee representatives acknowledged the findings as reported herein. The inspectors also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the
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inspectors during the inspection.
The licensee did not identify any such documents / processes as proprietary.
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