IR 05000155/1976018
| ML20002D521 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/14/1976 |
| From: | Boyd D, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002D518 | List: |
| References | |
| 50-155-76-18, NUDOCS 8101210292 | |
| Download: ML20002D521 (13) | |
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UNITG STATES NL. EAR REGULATORY CCMXISSION OFFICE CF INSPECTION A!O DiFORCDT;I
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. REGION III V
Report of Operations Inspection
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IE Inspection Report No. 050-155/76-18 Licensee:
Consumers Power Conpany 212 ' dest Michigan Avenue Jackson, Michigan 49210 Big Rock Point Nuclear Plant'
. License No. DFR-6 Charlevoix, MichiE2n'
. Category:-
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Type of Licensee:
E'n'a (GE), 240 'd:
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Type of Inspection:
Routine, Anr.ounced Dates of Inspection:
Septenbe..!O-24, 1976
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Principal Inspector:
D e
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t Acco=panying Inspectors: None Other Accompanying Personnel: None.
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Reviewed By:
D. C. Soyd, Acting Chief
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Reactor Projects Section 2 (Date)
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Y SUMMARY OF FINDINGS Insrection Summary
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Inspection on September 20-24, 1976, (76-18): Review of reportable occurrences, review and audits, plant cleanliness, operations, annual report, organization and administration, item of noncompliance,
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and outstanding inspection items. One ~ 'em of noncompliance was identified concerning the failure to prowide adequate design control measures.
Enforcement Items
.13we following item was identified during the inspection:
Infraction Contrary to Criterion III of Appendix B to 10 CFR 50, adequate
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design control measures were not employed during a modification to a safety related control circuit.
(Paragraph 7, Report Details)
Licensee I.ction on Previously Identified Enforcement Items A review of the licensee's corrective actions _ concerning the plant modification controls indicates that the procedure reviews and revisions are not complete.
(Paragraph 6. Report Details)
Other Significant Items A.
Systems and Components None.
3.
Facility Items (Plans and Procedures)
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The licensee completed two shipments of irradiated fuel pins to the Argonne National Laboratory during the week of September 20, 1976.
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Managerial Items
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None.
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Noncompliance Identified and Corrected by Licensee None.
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Devictions None.
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Status of Previously Reported Unresolved Items 1.
The design review concerning the emergency diesel generator control circuit has been completed. This item is considered resolved.
(Paragraph 7.a. Report Details)
2.
The vacuum relief function of the containment ventilation valves has been evaluated, and a modification to provide an alternate
. path for vacuum relief is being planned.
This item is con-sidered resolved.
(Paragraph 7.b, Report Details)
Management Interview The management interview was conducted on September 24, 1976, by Mr. Hunter with the following persons present:
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R. B. DeWitt, Manager, Production and Transmission D. E. DeMoor, Technical Engineer T. W. Elward, Technical Superintendent J. P. Flynn, Maintenance Superintendent A. C. Sevener, Operations Supervisor
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A.
The inspector stated that a review of plant operations, reportable occurrences, review and audits, selected outstanding items, un-resolved items, organization and administration, annual report, and plant cleanliness revealed no discrepancies.
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B.
The inspector stated that during the review of the updating of the Q-list concerning the electrical bus loads and tripping
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functions revealed inadequacies including certain trip functions omitted and the Q-list not being maintained up-to-date.
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The licensee stated that the items had been added to the Q-list, the Q-list reviewed for updating and Administrative Procedure l
1.10 revised to maintain the Q-list currently pending completion of
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the document control procedures.
(Paragraph 5.c, Report Details)
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C.
The inspector stated that the review of the corrective actions concerning the design control during minor and major modifications l
at the plant, including the Administrative Proy Jurcs and Engineering l
Department Procedures, appeared adequate.
The inspector also stated that an offsite review of the design control procedures will be required to close out the items of noncompliance.
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The licensee acknowledged the. statements made by the inspector.
.The licensee stated that Quality Assurance Procedure 3-53 for minor =
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modifications was presently under final review and nearing completion.
j (Paragraph.6. Report Details)
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REPORT DETAILS
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I 1.
Persons Contseted
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C. J. Hartman, Plant Superintendent D. E. DeMoor, Technical Engineer C. R. Abel, Operations Superintendent T. W. Elward, Technical Superintendent J. P. Flynn, Maintenance Superintendent G. B. Szczotka, Quality Assurance Superintendent A.'C.
Sevener, Operations Supervisor-T. K. Pence, Shift Supervisor P. M. Donnely, Control Operator E. M. Evans, Plant Engineer 2.
Review of Operations
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The inspector reviewed selected records and activities to be in accordance with Technical Specifications and Administrative Procedures.
The review included the Shift Supervisors Log, Control Room Log, Reactor Log, Operating Memos, Control Rcom Status Board, Logging and Switching Orders, and Plant Annunciators.
s No discrepancies were noted.
3.
Reportable Occurrences The inspector reviewed the following reportable occurrences to assure adequate review, evaluations, corrective actions and reporting:
a.
LER R0-15-76, Station battery charger failed resulting in a reduced battery voltage and specific gravities of 120 volts and 1.175,
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respectively.
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1! that the, station battery charger The licensee reported l
failed due to defective silicon rectifiers.
The silicon
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rectifiers were replaced and the unit returned to service.
The inspector reviewed the event with the licensee rep-resentative. The failure was determined to be normal equip-ment malfunction.
The inspector verified that hourly ampere readings and voltage
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readings were taken durin7 the reduced load operation for i
13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
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No discrepancies were noted.
l J/ Ltr, CP to IE:III, dtd 7/30/76.
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- LER RO-17-76, Ststien battery ep;cific gr;vity rarding2 1sta than 1.200.
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The licensee reported that the specific gravities taken following addition of water to the station battery revealed-many cells at less than 1.200 specific gravity.
The inspector reviewed the event with the licensee representa-tive..Apparently water had been added to the battery cells on September 17, 1976, resulting in the low specific gravity readings.
The licensea has provided procedure changes to note watering dates, decreased water level changes and specific gravity readings on all cells if the pilot cell specific gravity reading is found low.
No discrepancies were noted.
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LER RO-18-76, Emergency diesel generator starting time' in excess of 15 seconds.
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The licenses reported that the emergency diesel generator failed to start within 15 seconds during routine weekly testings.
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The inspector reviewed the event with the licensee representative.
and determined that the starting failures are under review and the diesel surveillance has recently (September 20, 1976) been increased in an attempt to identify the intermittent failure to start problem with the. diesel engine.
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The inspector vxtified that the diesel started on September 20, 1976, during the special manual start test in approximately four seconds; and also that on September 23, 1976, the diesel started in approximately four seconds.
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No further questions are required of this matter at this time.
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LER RO-19-76, Reactor Depressurization System battery D pilot cell was below specification of 1.200 specific gravity.
The licensee reported 4/ that the specific gravity of the reactor depressurization system battery D was found below 1.200 during normal monthly surveillance.
t 2/ Ltr, CP to IE:III, dtd 8/4/76.
3/ Ltr, CP to IE:III, dtd 8/19/76.
4/ Ibid.
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The inspectcr rcviewed th3 cv nt with the.lic:n=ro r:precente-tive. The corrective actions, include procedure changes to reduce the water'1evel changes in-the cells, provide for
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specific gravity readings on all cells if the pilot cell is below 1.200, logging of water. additions and cell voltage readings when the cell specific gravity is low'.
No discrepancies were noted.
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LER RO-20-76 Recc*or Depressurization Syst am battery C pilot cell was below specification of 1.200 specific gravity.
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The licensee reported that.the specific gravity of th'e reactor depressurization system battery C was found below 1.200 during normal monthly surveillance.
The inspector reviewed the event with the licensee representa-tive. The corrective actions include procedure changes to t
reduce the water level in the cells, provide for specific
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gravity readings on all cells if the pilot. cell is below 1.200, logging of water additions and cell voltage' readings when the cell siecific gravity is low.
No discrepencies were noted.
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LER RO-21-76, The emergency diesel generator failed to start within the required 15 second criteria.
b The licensee reported that the emergency diesel generator (
failed to start within the required 15 second criteria during weekly testing.
The inspector reviewed the event with the licensee representa-tive and determined that the starting failures are under review
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and the diesel surveillance has recently (September 20, 1976)
been increased in an attempt to identify the intermittent failure to start problems with the diesel engine.
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The inspector verified subsequent starts on the emergency diesel generator during the week of September 20, 1976.
No further questions are required of this matter at this time.
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LER RE-22 '6, The Emergency Diesel Generator failed to start due to a starting battery cable failure.
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L The licensee reported that the emergency diesel generator failed to start during the routine weekly tests.
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5/ Ibid.
l/Ltr,CPtoIE:III,dtd9/3/76.
2/ Ltr, CP to IE:III, dtd 9/7/76.
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-Th2'inap;ctor r;vi:wed tha event with thm lic neca representative. The battery cable was repaired and the diesel retested, the battery cable was inspected, and (-
the voltage drop taken across the connection.
No discrepancies were noted.
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LER RO-23-76, Failure to retest the emergency diesel generator after an outage.
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The licensee reported that the emergency diesel generator was not retested following the failure to start within the 15 second criteria.
The inspector reviewed the event with~the licensee represen-tative and verified that procedure changes were made on the weekly test procedure to prevent recurrence.
The inspector verified t the diesel generator did start
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during the routine test No discrepancies were noted, i.
LER R0-24-76, Failure of the power range channel to respond during startup low power operation.
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The licensee reported that the power range monitor, number 2, did not respond properly during startup operation following corrective maintenance on the neutron detector cables.
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tative. The licensee issued a training memo on September 1, 1976, and posted specific instr.uctions at the detector location to assure proper connections in the future.
The corrective action. appear adequate and no discrepancies were noted.
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Review and Audits The inspector reviewed selected plant records and procedures concerning review and nudit requirements to be performed in accordance with Adchsistrative Procedures, Quality Assurance Procedures and regulatory requirements.
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8/ Ltr, CP to IE:III, dtd 9/3/76.
9/ LER R0-21-76.
}0/Ltr,CPtoIE:III,dtd9/7/76.
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The inspector's review included:'
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Selected onsite Plant Review Committee Minutes.
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Selected offsite Safety Audit Review Board Minutes.
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Audit-plans.
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Audit schedules.
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Quality Assurance Program Procedures.
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Selected department procedures.
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Technical Specifications.
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Administrative Proc-lures.
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The inspector discussed the review and audit responsibilities.
with the appropriate department heads and other personnel.
No discrepancies were noted.
5.
Outstanding Itens Selected outstanding inspection items were reviewed by the inspector for co=pletion.
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The inspector reviewed the energency shutdown gypcedure, D2.25, to include subsequent operator actions.--
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No discrepancies were noted and'this item is considered closed.
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b.
The inspector reviewed Administrative Procedure 1.9.E controllingtheuseoffunctig3p7equivalentsubstituticns in safety related activities 11/ IE Inspection Rpt No. 050-155/76-13.
12/ IE Inspection Rpt No. 050-155/76-10.
13/ IE Inspection Rpt No. 050-155/76-13.
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. Tha inspector diteu:::d with th5 lic;n 2'tha u:2 cf ths FES procedure for temporary changes and additive-items and chapter 16.6 of the Engineering Manual.
I No discrepancies were noted and this item is considered closed.
The inspector reviewed gpe licensee engineering evaluation c.
and correctivu actions 7-taken to update the plant Q-list - concerning the safety related bus loads and tripping functions.
The inspector's review of the associated electrical prints - with the licensee's representatives revealed that a nu=ber of trip devices were not included in the evaluation and corrections made to the Q-list.
The items were added to the Q-list.
The inspector discussed with tne licensee representative the _use of the Q-list in.its present status and noted that the control of the Q-list during the interim period, until the new document control procedures are implemented later - this year, needed to be addressed immediately. Adminis-trative Procedure 1.10 was revised to provide updating of the Q-list during plant changes and modifications based on the DCN (drawing change notice).
The licensee evaluated the Q-lis? drawings and updated the Q-list during the inspection.
No other discrepancies were noted and the item is considered closed.
d.
Theinspectorverifiedthatacceptancecygperiahadbeen included on the control room log sheets.-- No discrepancies were noted and this item is considered closed.
e.
The insp ctor reviewed the Technical Data Book, Section 15.5. A, and Operating Procedure, Step Bl.3.3.2, to verify that the rod withdrawal insertion and withdrawal sequence wasadequatelyspecifiedandcontrolledbymanagemenI6f assure proper rod movement within individual groups.-- No discrepancies were noted and this item is considered closed.
(J4/ IE Inspection Rpt No. 050-155/76-12.
Jji/ IE Inspection Rpt No. 050-155/75-15.
J6/ IE [nspection Rpt No. 050-155/76-13.
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Itemn of N2ncomplienew Theinspectorreviewed.theplantcorrectiveact17758paken associated with previous items of noncompliance-- -- concerning design control during minor and major modifications.
, ' . The inspector's review included: Quality Assurance Program Policy No. 3, Design Control.
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Quality Assurance Program Procedure No. 3-52, Major
Modifications.
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Administrative Procedure 1.9, Plant Modifications, d.
Plant Engineering Manual Procedures; Section 16.5, Engineering Design Control-Minor Modifications and Section 16.6, Project Engineer Engineering Interfaces - Major Modifications.
' The inspector's review included review of the Quality Assurance Procedure and Administrative Procedure requirements and Engineer-ing Manual Procedures for performance of the design nctivities.
No discrepancies were noted during the review.
The close out of the items of noncompliance will be completed following further review of offsite procedures for major and minor modifications, including Quality Assurance Procedure 3-53 for minor modifications.
During the interim period, the plant is continuing to consider each facility change as safety related until deemed otherwise by the Plant Review Committee action juggjn5)2I/ o authorization t of implementation of the fccility work . 7.
Previous Unresolved Items The inspector reviewed the status of the unresolved items.
Facility Change SPS-76-C-358,22./ Emergency Diesel Generator s.
Control Circuit. The design, design review and safety l 17/ IE Inspection Rpt No. 050-155/75-15.
l J8/ IE Inspection Rpt No. 050-155/76-01.
J9/ 050-155/A0 24'75.
! 20/ IE Inspection Rpt No. 050-155/75-15.
'21/ Ltr, CP to NRR, dtd 12/19/75.
][[/ IE Inspection Rpt No. 050-155/76-13.
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._ evaluatitn for th2 fccility changa wera r;vi we'd.
Th2 design and design review were performed onsite on July 20, 1976, subsequent to the completion of the facilit" change ( on June 13, 1976, following an attempt to locate the reviews offsite.
, The inspector verified the current loading on the emergency diesel generator control circuit during review of testing documentation performed by the plant staff on July 1, 1976.
' The fixed load on the circuit was 0.1 amperes with a transient load' of approximately.2 seconds of 8.3 amperes maximum.
This circuit was fused.by a 2.0 ampere fuse. Thus, a condition existed that could have resulted in the loss of the diesel generator control circuit which would render the diesel . generator inoperable. This deficiency was not identified during the company reviews of this facility change. The supply breaker test data was reviewed and appeared adequate, including the normal loading and the trip testing.
- The failure to provide adequate desxgn control measures during this facility change is considered an item of noncompliance pursuant to Criterion III of Appendix B to 10 CFR 50.
No response is necessary for this item of noncompliance since the area of major and minor modification control noncompliance. 7!gyctive actions for previous items of is included in23 - The corrective actions being presently taken by the licensee should prevent a recurrence of this type administrative breakdown.
b.
The vacuum rel;ef functiva of the containment ventilation system has been evaluated and a modification ' to provide an alternate containment vacuum relief path is being pursued concurrently with thg7pngineering and . design of the cask drop modifications which are planned to be completed during a future outage.
Ko further questions are required of this matter at this time and this item is considered ' resolved.
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Organization and Administration The inspector reviewed selected items concerning the plant staff including qualifications, job descriptions an' training requirements.
73/ IE Inspection Rpt No. 050-155/75-15.
24/ IE Inspection Rpt No. 050-155/76-01.
25/ IE Inspection Rpt No. 050-155/75-05.
26/ IE Inspection Rpt No. 050-155/76-04.
27/ NRC to CPR, Ltr dtd 2/6/76.
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.. The it:pecter c tcd that the plant io is the proca:s of preparing formalized overall plant training and Quality Assurance training.
t No discrepancies were noted.
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Annual Repor't The. inspector completed the review of the annual report- /
- submitted by Consumera Power Company in accordance with regulatory requirements.
No discrepancies were noted.
10.
Plant Cleanliness The inspector reviewed the plant established controls on cleanliness and housekeeping.
- Storage and handling requirements are provided during procure-ment of materials and these requirements are considered during storage and use of the materials. Maintenacce procedures are utilized to provide the necessary controls during plant activities.
Operations Department instructions are provided (cleaning assignments) to maintain the equipment and areas clean and free'of fire hazards.
A plant cleaning group maintains the general plant cleanliness.
No discrepancies were noted.
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28/ CP to NRR, Ltr dtd 2/26/76.
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