IR 05000155/1989019
| ML19354E398 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/10/1990 |
| From: | Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19354E397 | List: |
| References | |
| 50-155-89-19, NUDOCS 9001310134 | |
| Download: ML19354E398 (8) | |
Text
.
.
.
-
.
U. S. NUCLEAR REGULATORY COMMISSION
-
REGION III
Report No. 50-155/89019(DRP)
Docket No. 50-155 License No. OPR-6 Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Big Rock Point Nuclear Plant Inspection At:
Charlevoix, Michigan Inspection Conducted:
November 29 through December 31, 1989
'
'
Inspectors:
E.A. Plettner
.
-
.
.
.
N.R. Willif sen
,
(
v
[/
Approved Byr) ^R. W De yette, hief.
I / N/90 Reactor Projects Section 2B Date
'
Inspection Summary Inspection on November 29 through December 31, 1989 (Report No. 50-155-89019(ORP))
Areas Inspected:
The inspection was routine, unannounced, and conducted by the senior resident inspector and the resident inspector.
The functional areas inspected consisted of the following:
management meetings; evaluation of licensee quality assurance program implementation; evaluation of licensee self-assessment capability; surveillance activities; maintenance activities on various caiponents; operationel safety verification which included the off gas isolation system; and a temporary instruction dealing with fitness-for-duty training.
Results:
The licensee has responded in a timely manner to issues and concerns presented to it by the NRC.
The management meeting between the licensee and Region III was informative with both groups benefitting from the discussions.
The quality assurance and self-assessment programs continue to improve.
The surveillance, maintenance, and operational safety programs appeared to be performed in a manner to ensure public health and safety.
Fitness-For-Duty training was conducted as prescribed in 10 CFR Part 26.
No significant safety items were identified in this report.
9001310134 900110
"
{DR ADOCK 05000155 PDC y
l
!
I
L.
i
.
.
-
.
.
DETAILS 1.
Persons Contacted
+*T. E1 ward, Plant Manager
- R. Krchmar, Acting Quality Assurance Superintendent
+*H. Hoffman, Maintenance Superintendent
- W. Trubilowicz, Operations Supervisor
+*G. Withrow, Plant Engineering Superintendent
+*R. Alexander Technical Engineer
- E. Zienert, Director Human Resources
- P. Donnelly, Nuclear Assurance Administrator
+*J. Beer, Chemistry / Health Physics Superintendent
- D. Lacroix, Nuclear Training Administrator
+ G. Petitjean, Special Project Engineering Supervisor
+ D. Moeggenberg, Mechanical / Civil Engineering Supervisor
+ J. Toskey, Senior Engineer
+ J. Fremeau, Director of Nuclear Safety
+ M. VanAlst, Property Protection Supervisor
+ D. Hoffman, Vice president Nuclear Operations
+ J. Eddy, Plant Licensing Engineer
+ K. Berry, Director Nuclear Licensing
+ D. Hughes, Director Quality Assurance Support Nuclear Regulatory Commission
+ R. Pulsifer, Project Manager, NRR
+ W. Forney, Deputy Director, Division of Reactor Projects
+ R. DeFayette, Section Chief, Division of Reactor Projects, Branch 2B The inspectors also contacted other licensee personnel in the Operations, Maintenance, Engineering, Radiation Protection, and Technical Departments.
- Denotes those present at the exit interview on January 4,1990.
+ Denotes those present at the Management meeting held on December 5, 1989.
2.
Management (30703)
A management meeting was held on December 5, to discuss the 1989 refuel /
maintenance outage.
Included in the discussion were the performance of field maintenance services, inspection results of the Reactor Depressurization System valves, Integrated Living Schedule items completed, radiation protection activities, Integrated Leak Rate Test results, procedure upgrades, Final Hazards Summary Report update, planned Safety System Functional Inspection, and planned Security upgrades.
3.
Evaluation of Licensee Quality Assurance Program Implementation (35502)
_.
This inspection was performed to evaluate the effectiveness of the licensee's implementation of its quality assurance program and to determine-if, based on this evaluation, a follow-up regional inspection is warranted.
.
.
l
,
,
O e
.
.
a.
Onsite QA/QC Group and the Offsite Nuclear Assurance Group The onsite QA/QC group and the offsite Nuclear Assurance group were active in ensuring the implementation of quality assurance.
The function of the onsite QA group was to perform surveillance inspections.
Management oversight ensures that the person performing the QA inspection has the expertise to overview the work.
The NRC inspector noted no changes in the licensee personnel performing the inspections from the previous inspection in this area conducted in 1988.
The qualifications of the licensee inspectors continue to improve through training.
The offsite nuclear assurance group was determined by review of audits to have an independent view of the plant and had performed effective reviews of the plant.
The inspector's review of the licensee's tracking :ystem indicated that items were accurately recorded, tracked, and closed out.
An inspector concern was that most audits are programmed audits performed on a scheduled basis for all areas of the plant and were not selected audits based on problem areas.
b.
Root Cause Analysis The Big Rock Point Corrective Action Review Board (CARB) started using a trial root cause analysis worksheet and evaluation system during reviews of deviation reports (DRs) and event reports (ERs) in 1988.
The licensee has committed to formally implement a root cause analysis procedure program by April 1990.
Additional areas require inspections before a determination can be made to determine if c follow-up regional inspection is needed.
The results of those inspection findings will be documented in a subsequent inspection report.
No violations or deviations were identified in this area.
4.
Evaluation of Licensee Self-Assessment Capability (40500)
The objective of this inspection was to evaluate the effectiveness of the licensee's self-assessment programs.
The inspection focused on determining whether the licensee's self-assessment programs contributed to the
-
prevention of problems by monitoring and evaluating plant performance, providing assessments and findings, and communicating and following up on corrective action recommendations.
-
The Big Rock Point Plant has five groups that focus on the licensee's self-assessment programs.
Two of these groups are required by Technical Specifications (TS), the Plant Review Committee and the Nuclear Safety Services Department.
The three other plant review groups are:
the i
l
!
.
,
a
.
.'
.
,
Operating Experience Review Group, the Corrective Action Review Board, and
the Technical Review Committee.
Except for the Technical Review Committee an evaluation of the above groups was performed and documented in a previous Inspection Report No. 50-155/89018(DRP).
'
Technical Review Committee
.
The senior resident inspector attended the Technical Review Committee
!
meeting conducted on December 14.
The Committee consisted of individuals
!
having multi-disciplinary training or skills.
Issues discussed during the=
meeting were the following:
Fuel transfer cask low water level alarm i
CV 4000 Feedwater Regulator Valve Replacement i
Individual Plant Evaluations The committee discussions, inspector review of materials used in the f
presentations, and the review of meeting minutes indicates that licensee
actions had been adequate in addressing plant concerns.
- No violations or deviations were identified in this area.
'
5.
Monthly Surveillance Observation (61726)
Station surveillance activities listed below were observed to verify that the activities were conducted in accordance with the Technical Specifications and surveillance procedures.
The applicable procedures were reviewed for adequacy, test and process instrumentation was verified
'
to be in their current cycle of calibration, personnel performing the tests appeared to be qualified, and test data was reviewed for accuracy and completeness.
The NRC inspectors ascertained that any deficiencies identified were reviewed and resolved.
The NRC inspectors observed the licensee's performance of the following surveillance tests on the indicated dates:
November 29:
T7-28, " Emergency Diesel Generator Auto Test Start,"
Revision 8, October 24, 1988.
December 3:
T7-03, " Control Rod Coupling Integrity Test at Power,"
Revision 16, October 20, 1989.
December 4:
T180-01A, " Containment Ventilation Valves Leak Rate Test,"
Revision 38, May 31, 1989'
December 6:
T30-31, "RDS Cabinet Test (Sensor Cabinet D/ Actuation Cabinet 4)," Revision 30, August 29, 1989.
December 6:
T30-26, " Electric and Diesel Fire Pump, L2 Module Test,"
Ifevision 17, February 2, 1989.
!
!
-
.
.
.
-
.
December 6:
T7-33, " Weekly Check of ASD System Equipment," Revision 1, February 1,1989.
December 7:
T7-28, " Emergency Diesel Generator Auto Test Start,"
Revision 8, October 24, 1989.
A technician from the Corporate Laboratory obtained vibration data for offsite computer analysis and trending.
December 26:
T7-24, " Battery Pilot Cell Readings," Revision 11, May 17, 19B9.
December 28:
T7-28, " Emergency Diesel Generator Auto Test Start,"
Revision 9, December 8, 1989.
Vibration readings were taken during the surveillance to trend machine performance.
December 28:
T30-14, " Core Spray Heat Exchanger Leak Test," Revision 17, October 9, 1989.
On December 6, the senior resident inspector and project manager observed the performance of surveillance activities on the RDS Cabinet Test (Sensor Cabinet D/ Actuation Cabinet 4).
During the test operations personnel encountered a problem.
Testing was halted, equipment was declared inoperable, and the appropriate Limiting Condition for Operation (LCO),
was entered.
Discussions were conducted between operations personnel and maintenance personnel to resolve the issue.
Appropriate corrective measures were implemented involving the replacement of two modules.
Repairs were completed, the equipment was satisfactorily tested, returned to service, and the LC0 was exited.
No violations or deviations were identified in this area.
I 6.
Monthly Maintenance Observation (62703)
Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry
'
codes or standards and in conformance with Technical Specifications.
.
The following items were considered during this revi w:
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 calibrations were performed prior to returning components or. systems to service; quality control records were maintained; activities were accomplished by qualified personnel-parts and materials used were certified; and radiological and fire l
prevention controls were implemented.
'
Work requests were reviewed to determine status of outstanding jobs and to assure that priority was assigned to safety'related equipment maintenance which may affect system performance.
i-1
.
o
.
.
The NRC inspectors observed the licensee's performance of the following maintenance work orders on the indicated dates:
November 29:
No. 89-EPS-0264, dated October 20, 1989, for repairing the local panel alarm for low lubrication oil pressure on the Emergency Diesel Generator.
December 1:
No. 89-RDS-0165, dated November 29, 1989, for replacing the pilot valve on Reactor Depressurization System Train "B".
December 4:
No. 89-C15-0024, dated December 4,1989, for repairing a small air leak around the shaft of containment ventilation isolation valve CV-4094.
December 5:
No. 89-VAS-0237, dated December 5, 1989, for repairing a steam leak in the west air-heater for containment ventilation air.
December 6:
No. 89-PRO-0205, dated December 6, 1989, for repairing the electronic door alarm on the Alternate Shutdown Building entrance.
December 6:
No. 89-RDS-0166, dated December 12 1989, " Sensor Cab FP/L B/5 Trip" in conjunction with Procedure IRDS-7, " Bistable Module Replacement RDS Sensor Cab," Revision 7, October 3, 1988.
December 29:
No. 89-ASD-0047, dated December 20, 1989, for performing monthly battery maintenance on the Alternate Shutdown System battery, in conjunction with Procedure T30-20, " Monthly Stationary Battery Voltage _and Specific Gravity Readings," Revision 23 December 20, 1989.
No violations or deviations were identified in this area.
7.
Operational Safety Verification (71707)
The NRC inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators during the inspection period.
Instrumentation and recorder traces were examined for abnormalities and discussed with the control room operators, as was the status of control room annunciators.
Reviews were conducted to confirm that the required leak rate calculations were performed and were within Technical Specification limits.
It was observed that the Plant Manager,
-
the Production and Performance Superintendent, and the Operations Supervisor were well informed on the overall status of the plant making visits to the control room and touring the plant.
Supervisors were well informed on the overall status of the plant and they made frequent visits.-
to the control room and regularly toured the plant.
System walkdowns were performed to verify the operability of the Off-Gas Isolation system.
Tours of the containment sphere and turbine building were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
Radiation protection controls were inspected, including Radiation Work Permits, calibration of radiation detectors, and proper po; ting and observance of
4
_ _ _ _. _
_
_...._ _ _ _.
-,
.
.
.
radiation and/or contaminated areas.
The inspectors observed site security measures including access control of personnel and vehicles, proper display of identification badges for personnel within the protected area, and compensatory measures when security equipment had a failure or impairment.
No violations or deviations were identified in this area.
8.
Temporary Instructions g
(0 pen) Temporary Instruction (TI) 2515/104):
" Fitness-For-Duty:
Inspection of Initial Training Programs." The purpose of the TI was for resident inspectors to attend selected licensee Fitness for Duty (FFD)
training sessions to determine that required training was being conducted to implement the program and to provide Reactor Safeguards Branch, Division of Reactor Inspection and Safeguards, and the Office of Nuclear Reactor Regu'lation with information to determine acceptability of general
{
industry FFD Program implementation.
The senior resident inspector attended a training session conducted by the licensee on December 22, 1989.
As required by 10 CFR Part 26, the following areas were addressed in the licensee's FFD Policy Awareness and Escort Training Session:
Licensee policy and procedures, including the methods used to
implement the policy.
The personal and public health and safety hazards associated with
abuse of drugs and misuse of alcohol.
The effect of prescription drugs, over-the-counter drugs, and
dietary conditions on job performance and chemical test results.
The role of the Medical Review Officer,
Employee assistance programs provided by the licensee; what is o
expected of employees and what consequences may result from lack of adherence to the policy.
Technic for recognizing drugs and indications of the use, sale,
or posse on of drugs.
Techniqun for recognizing aberrant behavior; and the procedures
for reporting problems to supervisory or security personnel.
The senior resident inspector will attend a training session for supervisory personnel on January 22, 1990.
This TI will be closed in a subsequent inspection report.
_ _ _ _ - - - - _ - - -
->
..
'..
4 '
9.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection period and summarized the scope and findings of the inspection activities. The licensee acknowledged these findings. The inspectors also discussed the-:
likely informational content of.the inspection report with regard to documents or processes reviewed by the inspectors during the inspection.-
The licensee did not identify.any such documents or processes as proprietary.
.
,
-
i
.
...
..
..
..
.
..
..
- J
.