IR 05000155/1982006
| ML20053C754 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/18/1982 |
| From: | Boyd D, Parker M, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20053C748 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM 50-155-82-06, 50-155-82-6, NUDOCS 8206020535 | |
| Download: ML20053C754 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-155/82-06(DPRP)
Docket No. 50-155 License No. DPR-6
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Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At: Charlevoix, MI Inspection Conducted: March 7 - April 23, 1982
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S-/h]L Inspectors:
G. C. Wr ght b/d'N-M. E. Par r Approved By:
D. C. Boy hi b'l Projects Section 1A Inspection Summary Inspection on March 7 - April 23, 1982 (Report No. 50-155/82-06(DPRP))
Areas Inspected: Routine safety, resident inspection involving Operational Safety Verification, IE Circular Followup, Refueling Activities, Containment Integrated Leak Rate Test Review, Surveillance, Refueling Maintenance, Inspection During Long Term Shutdown, Review of f.'nscaeduled Unit Shutdown, Review of NUREG-0737 Items, and Independent Inspection Effort. The inspection involved a total of 155 inspector-hours onsite by two NRC inspectors including 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during offshifts.
j Results: No items of noncompliance were identified in the areas inspected.
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J DETAILS
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1.
Persons Contacted I
- D. P. Hoffman, Plant Superintendent (Acting)
C. E. Axtell, Health Physicist
- A. C. Sevener, Operations Supervisor D. D. Wilks, Maintenance Supervisor J. A. Johnson, Instrument & Control Supervisor i
D. D. Blanchard, Technical Engineer
- D. E. DeMoor, Technical Engineer L. F. Monshor, Reactor Engineer
- J. Popa, Maintenance Superiisor
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- E. W. Raciborski, Q. A. Supervisor l
The inspectors also contacted other licensee personnel including shift supervisors, control room operators, maintenance personnel and shift technical advisors.
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- Denotes those present at exit interview i
2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the
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inspection period. The inspector verified the operability of selected
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emergency systems, reviewed tagout records and verified proper return j
to service of affected components. Tours of the reactor building and j
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. The inspector by observation verified that the l
physicc1 security plan was being implemented in accordance with the station security plan.
l The inspector observed plant housekeeping / cleanliness conditions and j
verified implementation of radiation protection controls. During the i
inspection period, the inspector walked down the accessible portions of the core spray / containment spray systems to verify operability.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
No items of noncompliance were identified.
3.
IE Circular Followup For the IE Circulars listad below, the inspector verified that the Circular was received by the licensee management, that a review for
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applicability was performed, and that if the circular were applic-able to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC 81-05 (Closed):
"Self-Aligning Rod End Bushings for Pipe Supports" f
IEC 81-14 (Closed):
" Main Steam Isolation Valve Failures to Close" 4.
Refueling Activities The inspector verified that prior to the handling of fuel in the core, i
all surveillance testing required by the technical specifications and j
licensee's procedures had been completed; verified that during the outage the periodic testing of refueling related equipment was performed
as required by technical specifications; observed fuel handling opera-tions (removal, inspection and insertion) and verified the activities were performed in accordance with the technical specifications and
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approved procedures; verified that containment integrity was maintained
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j as required by technical specifications; verified that good housekeeping
was maintained on the refueling area; and, verified that staffing during refueling was in accordance with technical specifications and approved procedures.
Containment Integrated Leak Rate Test
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a.
Procedure Review
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The inspectors reviewed Surveillance Procedure No. TV-02, Revision
10, " Containment Integrated Leak Rate Test," and verified that the j
procedure was technically adequate and consistent with regulatory requirements.
l-b.
Instrumentation
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The inspectors reviewed the calibration data associated with
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performing the CILRT. All the instruments used in the CILRT had been calibrated as required. The instrument calibration coefficients, RTD weighting factors, and volume weighting factors l
were placed into the CILRT Computer Program as required. The
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following instrumentation was used in the CILRT:
l Type Quantity RTD's
Flowmeter
Pressure Gauge
j Dewcells
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c.
Witness of Test l
The inspectors witnessed portions of the CILRT on March 28-30, 1982, and noted that:
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Appropriate revisions of the procedure were in use by test personnel Test prerequisites were met.
Proper plant systems were in service.
d.
Valve Lineups The inspectors verified that the valve lineups were conducted and documented in accordance with the approved test procedure.
In addition, the inspectors verified, by direct observation, proper
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valve lineups in accessible areas.
e.
Blowdown and Containment Inspection The inspectors verified that blowdown was within technical specification radioactivity release limits, analysis and calcula-tions were completed before the release started, and that required environmental monitoring equipment was functional before the release began. The inspectors also conducted an independent post CILRT containment inspection for equipment degradation after blowdown and did not identify any problems.
f.
CILRT Data Evaluation The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reduced pressure CILRT was started on March 28, 1982.
The inspectors independently monitored and evaluated leak rate data to verify the licensee's calculation of the leak rate.
There was acceptable agreement between the inspectors' and li-censee's leak rate calculations as indicated in the following summary (units are in weight percent per day):
Measurement Licensee Inspector Leakage rate measured (Ltm)
0.0201 0.0197 Ltm at 95% confidence level 0.0232 0.0229 Appendix J Acceptance Criteria at 95% confidence level = 0.75 Lt
= 0.75 (0.3416%/ day = 0.2562%/ day. As indicated above, the Ltm at the 95% confidence level was less than the maximum allowable by 10 CFR Part 50, Appendix J.
However, the inspectors noted that this value did not include Type B and C leakage penalties.
As the results of the local leak rate tests were unavailable, no conclusions as to the acceptability of the CILRT were reached.
g.
Supplemental Test Data Evaluation Af ter the satisfactory completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test on March 29, 1982, a known leakage of 3.249 SCFM or 0.266 weight percent per day was induced. The inspectors independently monitored and evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate. There was acceptable agreement between the inspectors' and the licensee's leak rate calculations
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as indicated in the following summary (units are in weight per cent per day):
Measurement Licensee Inspector Measured Leakage (Lc) rate during supplemental test 0.2030 0.2029 Induced Leakage rate (Lo) =
3.240 scfm (0.2662 day)
Appendix J Acceptance Criteria:
Lo + Ltm - 0.25 LTs Les Lo +
Ltm + 0.25 Lt.
As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identified.
5.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the reactor protection system and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for opera-tion were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical speci-fications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate mans;ement personnel.
The inspector also witnessed portions of the following test activities:
standby diesel generator load test Upon completion of Standby D. G. Load Test when the power switch was switched off the load was dropped off the generator as the field voltage was lost.
The A.O. assumed that the switch was for metering (voltage /ampherage) indication only. The S.S. has implemented pro-cedure changes to T7-21 to designate cautions in the procedure to denote switch purpose also the power switch itself will be designated with a caution.
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6.
Maintenance - Refueling The inspector verified maintenance procedures include administrative approvals for removing and return of systems to service; hold points for inspection / audit and signoff by QA or other licensee personnel; provisions for operational testing following maintenance; provisions for special authorization and fire watch responsibilities for activi-ties involving welding, open flame, and other ignition sources; re-views of material certifications; provisions for assuring LC0 require-r gnts were met during repair; provisions for housekeeping during and following maintanence; and responsibilities for reporting defects to management.
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The inspector observed the maintenance activities listed below and verified work was accomplished in accordance with approved procedures and by qualified personnel.
Disassembly and Reassembly on Control Rod Drives (CRD)
In observing the CRD rebuild activities the inspector noted the follow-ing items from an AhARA standpoint.
a.
If the present rebuild area is going to be used the licensee should consider rearranging the support equipment such that a majority of the work can be performed away from the storage tank which is a hot spot.
b.
One individual knowledgeable in rebuild should be assigned to direct the activity. This would reduce the amount of time spent on rebuild.
c.
More training on CRD rebuild should be provided prior to perform-ance of the activity again reducing time.
d.
Procedure should be reviewed with attention towards including more detail in the area of rebuilding the moving piston.
No items of noncompliance were identified.
7.
Inspection During Long Term Shutdown The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the inspection period.
The inspector verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrety. Tours of site access-ible areas, including exterior areas were made to make independent assessments of equipment conditions, plant conditions, radiological controls, safety, and adherence to regulatory requirements oad to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspector observed plant housekeeping /
cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The inspector by observation verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector reviewed the licensee's jumper / bypass controls to verify there were no conflicts with technical specifications.
8.
Review of Unit Shutdown The inspector reviewed the circumstances surrounding the Unit Shutdown on April 19, 1982.
In clearing the switching and tagging order to return the reactor water cleanup system to operation after pump maintenance the operator
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attempted to open isolation valve VCU-3.
As soon as the operator started to open the valve a steady flow of steam eminating from the valve packing area was observed. The cperator immediately left the area and informed the control room. Subsequent attempts to open and backseat the valve were unsuccessful and it was decided to shut the unit down.
An orderly shutdown was commenced, starting at approximately 15 MWe and the unit was subcritical at 4:07 p.m. on April 19th and all rods were in by 5:12 p.m. the same day.
Although no direct measurement of the leak rate was available it is known that the leakage was Icss than 2.5 gpm.
Throughout the entire evolution no Technical Specifications were exceeded and there were no safety system cha11anges.
Subsequent evaluation by the licensee indicates that, although the velve was finally backseated and the stem repacked, that the oper-ability of the valve was questionable and the licensee decided to initiate an outage to add another valve to the reactor cleanup suction line and not rely upon VCU-3.
No items of noncompliance were identified.
9.
Review of NUREG-0737 Task Action Items The inspector reviewed the following NUREG-0737 items for closeout in accordance with Three Mile Island Temporary Instructions:
II.E.4.2.(5b)
" Containment Isolation Pressure Set Point Modification."
The inspector verified that pressure switches PS-664, 665, 666 and 667 were calibrated to less than or equal to 1 psig as required by Amendment 45 to the station Technical Specification.
Note that this also closes out open Inspection Item 155/81-10-02.
No items of noncompliance were identified.
10.
Other Inspector Activities During the inspection period the inspector also functioned as an observer, in the control room, for the annual Emergency Plan Drill (for further details on the drill refer to IE Inspection Report 82-05).
The inspector also attended the SALP meeting with the licensee for the evaluation period of July 1, 1980 to June 30, 1981.
The Resident Inspector for Big Rock Point has been temporarily re-assigned to a Special Team Inspection at Commonwealth Edison's Dresden facility for a majority of the inspection period.
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11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection on April 23, 1982 and summarized the scope and findings of the inspection activities. The licensee acknowledged the inspectors comments.
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