IR 05000483/1990005
| ML20034A723 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/12/1990 |
| From: | Hague R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20034A646 | List: |
| References | |
| 50-483-90-05, 50-483-90-5, NUDOCS 9004240187 | |
| Download: ML20034A723 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION III
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Report No. 50-483/90005(DRP)
Docket No. 50-483 License No. NPF-30 -
Licensee: Union Electric Company Post Office Box 149 - Mail Code 400 St. Louis,.MO 63166 Facility Name: Callaway Plant, Unit'l Inspection at: Callaway Site, Steedman, MO Inspection Conducted:
February 1 through March 31, 1990 Inspectors:
B. H Little C. H.
i Approved By: R a
ague, Chief d-
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eat or Pr jects Section 3C Dat'e
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Inspection Summary j
Inspection from February 1 through March 31, 1990 (Report No. 50-483/90005(DRP))
Areas Inspected: A routine unannounced safety inspection of-plant operations, maintenance and surveillance, and previous findings was performed.
Results: The operating crew continued to be alert and used acceptable communications during evolutions involving plant activities (Paragraph 2).
The maintenance and surveillance personnel adhered-to the plant work controi
procedures and performed the work in a professional manner. The material a
condition of the plant continued to be maintained at a high level (Paragraph 3).
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9004240187 900413
PDR ADOCK 05000483
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DETAILS
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1.
Persons Contacted D. F. Schnell, Senior Vice President, Nuclear
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- G. L. Randolph, General Manager, Nuclear Operations
- J. D. Blosser, Manager, Callaway Plant
C. D. Naslund, Manager, Operations Support
- J. V. Laux, Manager, Quality Assurance
- J. R. Peevy, Assistant Manager, Technical Services
- W. R. Campbell, Manager, Nuclear Engineering M. E. Taylor, Assistant Manager, Work-Control D. E. Young, Superintendent, Operations-
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W. R. Robinson, Assistant Manager, Operations and Maintenance R. R. Roselius, Superintendent, Health Physics
- T. P. Sharkey, Supervising Engineer,. Site Licensing G. J. Czeschin, Superintender,t, Planning and Scheduling r
W. H. Sheppard, Superintendent, Maintenance
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G. R. Pendegraff, Superintendent, Security L. H. Kanuckel, Supervisor, Quality Assurance Program
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- G. A. Hughes, Supervisor, Independent Safety Engineer Group
- J. C. Gearhart, Superintendent, Operations-Support, Quality Assurance
- T. A. Robertson, Quality Assurance Engineer C. S. Petzel, Quality Assurance Engineer J. A. McGraw, Superintendent, Design Control
- 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 ~,
r maintenance, health physics, and engineering staffs were contacted.
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2.
Plant Operations (71707)
a.
Operational Safety Verification Inspections were routinely performed'to ensure that the licensee conducts activities at the facility-safely and in conformance with regulatory requirements.
The inspections focused on the implementation and_overall effectiveness of the licensee's-control of operating activities, and on the performance of licensed and non-licensed operators and shift _ technical advisors.
The inspections-t
. included direct observation of activities, tours of the facility, interviews and discussions with licensee personnel, independent verification of 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:
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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 off-normal conditions.
Operability of selected safety-related systems,- including
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attendant alarms, instrumentation, and controls.
Maintenance of quality records.and reports.
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Inspector observations during plant walkdowns indicated that the licensee's programs relating to plant material conditions and housekeeping are being effectively carried out. Deficiencies observed were appropriately tagged.
Shift activities and associated communications showed attentiveness and a continuing commitment to-disciplined communication.
At the conclusion of-this inspection period, the Callaway plant was operating at 100 percent-power.
This-extends the days of continuous power operation to approximately--205.
Several short duration power reductions occurred due to equipment i
problems. Two of the power reductions were due to_ main'feedwater pump (MFP) problems.
In one case a MFP tripped at 100 percent-power. Operator attentiveness and training facilitated _ maintaining the plant within the operating envelope without a reactor trip.
b.
Off-shift Inspection of Control Room
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The inspectors performed routine inspections of the control room
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during off shift and weekend periods.
The inspections were conducted to assess overall crew performance and, specifically, control room operator attentiveness during night shifts.
i The inspectors observed -the operating crew's performance during i
routine fire brigade training drills conducted during-off-shift periods. The fire brigade teams were-adequately staffed, ' responded promptly, and demonstrated a good drill attitude.
During one fire -
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drill (March 1, 1990), control room operators sounded the fire alarm
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and activated the pagers, but failed to make the Gaitronics and
radio announcement'of the drill.
This resulted in some delay and need for additional phone calls to the control room. An operator aid has been developed to assure complete communication.
announcements are made for actual or drill conditions, i
i The inspectors determined that both licensed and non-licensed l
operators were attentive to their duties, and that the
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administrative controls relating to the conduct of operation were
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l being adhered to.
All activities were conducted in a safe and adequate. manner.
3.
Maintenance / Surveillance (62703) (61726)
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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 performed in accordance
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with approved procedures, regulatory guides, industry codes and standards, and the Technical Specifications. The following items were considered during these inspections:
the limiting conditions for operation were met while components or systems were removed from service; 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 performed prior to returning.
the components or systems to service; parts and. materials that were used were properly certified; and appropriate-f. ire prevention, radiological, and housekeeping conditions were maintained.
The observed ongoing maintenance and surveillance activities were found'to be properly authorized.and were being performed using approved procedures. The activities were noted to be scheduled and required.
isolations and tagging were found to be correctly carried out. The
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limiting conditions for operation were adhered to during the performance.
of these activities. -In general, the workmanship was found to be satisf actory, and housekeeping was adequately maintained at the job site.
Planning and scheduling maintained a relatively smooth flow of work for.
the available manpower and plant conditions.
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a.
Maintenance
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The reviewed maintenance activities included:
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Work Request Number Activity
Various Preventative maintenance on "A" diesel'
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generator, air start system, calibration of.
instrumentation, and inspection of DG-ESW
limitorque valves.
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Various Preventative maintenance o'n "A" essential i
service water and "A" ultimate heat' sink cooling tower.
W127449 Wall thickness measurement of essential.
service water backwash piping.
W130512 Pump out "A" diesel generator fuel oil tank.
for fuel oil replacement.
1 CMP-90-1017 Modification of Halon control panels for engineered safety features switchgear rooms so that a trip of one train of the Halon protection
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does not trip both trains of Class 1E air.
.h conditioners for these rooms'.
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b.
Surveillance The reviewed surveillances included:
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Procedure No.
Activity-ISL-SG-00A58 Loop - vibration; seismic, response spectrum recording. system.
ISF-GN-OP937-Functional pressure; containment pressure protection.
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ISF-SB-00A32 Functional annual; solid. state protection system. train "B" functional test.
ITL-BG-OF375 Loop - flow; -letdown-chiller heat exchanger bypass flow.
ITL-EN-00L15 Loop - level; spray addition tank. level.
ISF-GG-00R28 Functional - nuclear; fuel building
ventilation radiation detector.
J ITL-EN-00L19 Loop - level; spray addition tank level.
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OSP-SB-C0001 Reactor trip breaker P-4 verification.
OSP-SB-00001 Reactor trip breaker - trip actuating '
device operational test.
OSP-SB-00002 Reactor trip breaker - trip actuating device, 18 month operational test.
_ Control room shift and-daily' log readings
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and channel checks.
ODP-ZZ-00008 Night. order / standing. order log.
l OSP-SF-00002 Control rod. movement test.
On February 2,1990, while at 100 percent reactor power,' a rod control (RC) urgent failure alarm occurred dur.ing rod control motion' testing.
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As a result of the failure the plant entered Technical Specification
(T/S) 3.1.3.1 Action b (hot standby within-six hours). The licensee
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determined that the failure was indicative of an electrical problem j
in the RC system and that the rods were trippable.
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The licensee requested a temporary waiver of compliance of T/S 3.1.3.1
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Action b with an allowed outage time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to provide additional l
time to correct the problem and preclude a plant shutdown.
The requested
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temporary waiver of compliance was granted by NRR.
i Subsequent trouble shooting identified one defective circuit card in the-i electronic counter circuit. The defective card was replaced and the.RC
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system tested satisfactorily.
T/S 3.1.3.1 Action b was exited on i
February 3, 1990. The licensee considered the failure as isolated since this was the first failure of the circuit since 1987 following the
cabinet cooling modification.
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The inspector observed the licensee's response to the event from the control room.
The operating crew took appropriate action, adhering to procedures and T/S requirements, and making initial preparations for
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plant shutdown.
The operating crew received prompt support from management, engineering and I&C staff.
This led to the early assessment
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of the problem and provided prompt technical basis for obtaining the compliance waiver.
This event is reported in Licensee Event Report (LER) Number 483/90002.
All activities were conducted in an adequate and safe manner.
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Follow-up on Previous Inspection Findings (92700)
(Closed) Unresolved Item 483/89004-01(DRP) Backup water supplies to the auxiliary feedwater (AFW) pump operability requirements.
This matter related to the operability. requirements of the AFW system as specified in the Limiting Conditions for Operation (LCO), Technical Specification (T/S) 3.7.1.2, specifically associated with the words " associated flow paths and "an operable steam supply system". This matter also relates
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to conflicting surveillance requirements of T/S 4.7.1'.2.1 (a.4) and
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(b.1).
Surveillance a.4 requires verification that each automatic valve in the flow path is in the fully open position, where as surveillance b.1-implies that some automatic valves are closed eg; actuates to its full j
open position.
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In response to this matter, the licensee performed safety evaluations
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and submitted amendment applications to revise T/S 3.4.7.1.2.
Amendment application (ULNRC-2109 dated November '14, 1989) proposed clarification to Surveillance Requirements 4.7.1.2.a (4) and 4.7.1.2.b (1) by~:
identifying automatic valve positions to be verified to demonstrate i
operability. Amendment application (ULNRC-2167 dated March 6,1990)
proposed additional conditions to the LCO and additional requirements
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to the Action Statements.
The inspector reviewed the above amendment applications and the associated safety evaluations and determined that the licensee has
taken appropriate action in this matter, and this item is considered
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closed.
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Exit Meeting (30703)
The inspectors met with licensee representatives (denoted under. Persons f
Contacted) at intervals during the inspection period. The inspectors
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summarized the scope and findir.gs of the inspection. The licensee j
representatives acknowledged the findings as reported herein. The
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inspectors also discussed the likely informational content of the t
inspection report with regard to documents or processes reviewed by the inspectors during the inspection. The licensee did not identify any.such i
documents / processes as proprietary.
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