IR 05000155/1978012
| ML19281A161 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/11/1979 |
| From: | Ridgway K, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19281A159 | List: |
| References | |
| 50-155-78-12, NUDOCS 7903070118 | |
| Download: ML19281A161 (9) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-155/78-12 Docket No. 50-155 License No. DPR-6 Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At:
Big Rock Point Site, Charlevoix, MI Inspection Conducted: December 11-14, 1978 Accompanied an NRR Fire Prevention Review Team on October 10-13, 1978
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/ /// / 7-i Inspector:
K. R.
ay R F UJA Approved By:
R. F. Warnick, Chief
_/-//- 7 9 Reactor Projects Section 2 Inspection Sumrary Inspection on October 10-13 and December 11-14, 1978 (Report No. 50-155/78-12)
Areas Inspected:
Routine, unannounced, offshift inspection of plant oper-ations, Quality Assurance program, organization and administration, reviews and audits, reportable occurrences, electrical equipment qualifications, IE Bulletins and Circulars and outstanding inspection items.
The inspection involved 29 inspector-hours by one NRC inspector and 28 onsite inspector-hours by one NRC inspector for a NRR Fire Prevention Program review team meeting.
Results: No items of noncompliance were identified in the areas inspected.
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7903070112
DETAILS
1.
Persons Contacted
- C. J. Hartman, Plant Superintendent
"D. E. DeMoor, Technical Engineer R. E. Schrader, Technica'l Superintendent
- C.
E. Axtell, Health Physicist A. C. Sevener, Operations Superintendent L. A. Cappell, Administrative Supervisor T. K. Pence, Shift Supervisor W. F. Blisset, Shift Supervisor T. C. Bordine, Superintendent, Plant QA
- G. D. Gilbody, QA Engineer
- T.
R. Fisher, QC Inspector
- T. M. Brun, Chemistry and Radiation Protection Supervisor D. G. LaCroix, Control Room Operator No. 2 C. A. Dougherty, Control Room Operator No. 1 H. Madison, Auxiliary Operator
- K.
M. Brun, Senior Secretary The inspecter contacted several other licensee employees, including members of the technical, operations, and administrative groups.
- Denotes those attending the management exit interview on December 14, 1978.
2.
Plant Operations The inspector observed plant operating conditions and controls, control room manning and equipment tagout status during a plant tour which was conducted shortly after arrival on the 4-12 shift.
Additionally, selected operating records were reviewed as follows:
a.
Shift Supervisor Log (November-December 1978)
b.
Control Room Log (November-December 1978)
c.
Control Room Log Sheets (December 1978)
d.
Reactor Log Book (December 1978)
Daily Order Eook (through December 1978)
e.
f.
Switching Orders and Lockout and Jumper Controls Operating Memo Book (through December 1978)
g.
h.
Deviation Reports 1.
Event Reports No items of noncompliance or deviations were identified by the inspector.
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2.
Quality Assurance Program Changes made in the QA Program since the last inspection were reviewed to verify that they conformed with 10 CFR 50, Appendix B, applicable codes, standards, and Regulatory Guides.
It was noted that the revised policy, procedures and temporary changes had been reviewed and approved.
Organization was the only QA Program Policy change; however, several other section revisions had been submitted to NRR for their review.
The following QA Program Procedures had been revised in entirety:
QAPP 1 Organization, January 5,1978.
QAPP 3-53 Design Control, October 2,1978.
QAPP 6-51 Distribution and Control of Quality Related Items, July 5, 1978.
QAPP 7-52 Source Surveillance and Inspection, June 12, 1978.
QAPP 16-51 Deviation Reporting and Corrective Action, June 27, 1978.
QAPP 17-52 Collection, Storage and Maintenance of QA Records, July 5, 1978.
No items of noncompliance or deviations were identified by the inspector.
4.
Organization and Administration The licensee's onsite organization was reviewed for confermance with the Technical Specification description.
The only significant onsite organization t ange in the past year has been the combining of the responsibilities of Operations and }bintenance under one Superintendent.
The new position does not require a senior operator license (SOL) if the person filling the subordinate position, Operations Supervisor, is licensed and responsible for directing the activities of licensed operators. The present holder of the Superintendent position does not possess a 50L.
The onsite organization was also reviewed for conformance to qualifi-cations, authorities and responsibilities, minimum shift crew require-ments, and review and approval requirements.
No items of noncompliance were identified.
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5.
Review and Audits
a.
Safety and Audit Review Board (SARB)
The inspector reviewed SARB meeting minutes for 1978.
It appeared that the meeting frequency and quorum requirements of the Technical Specifications were being met.
Other requirements i.e. composition and qualification of the SARB and review responsibilities could not
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be determined from the information available at the site.
This will be considered an open item to be completed in a subsequent inspection.
b.
Plant Review Committee (PRC)
The inspector reviewed PRC meeting minutes since the last inspection to ascertain that the PRC composition, meeting frequency, quorum requirements and responsibilities were being carried out as required by Technical Specifications.
Tb5 inspector noted that 20 meetings of the PRC had been called so far in 1978 and meetings had been held on a monthly frequenc/.
c.
Periodic QA Program Review The licensee had contracted with General Electric Company's Nuclear Supply Services to perform an overall review of the Corporate QA Program.
The review was conducted on July 12-21, 1978 and closed on October 10, 1978.
The review indicated nine deficiencies in corporate areas and three at the Big Rock Point site.
The licensee had initiated corrective action for the three site deviations. The inspector will review the corrective actions taken at corporate beadquarters during a later inspection.
d.
Corporate Technical Audits The Operating Services Department is required by Technical Specifications (TS 6.5.2.9) to audit operations for con-formance with TS requirements, staff training and qualifi-cations, emergency plans and procedures, fire protection plan,procypuresandimplementationofthem.
A recent inspection-carried out at the corporate headquarters indi-cated these audits were not being fully carried out as required in the areas of TS compliance and qualifications of staff.
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IE. Report No. 50-255/78-30.
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e.
QA Audits The Director of QA-Production and Transmission is responsible for scheduling and conducting QA audits of suppliers, Production Department, Operating Services Dcpartment, fuel Supply Depart-ment, System Protection and Laboratory Services Department, Property Protection,.and Purchasing for implementation of and conformance to the QA Program Policy and corporate and site procedures. The audits are carried out on a 24 month schedule to review all 20 QA Criteria, security requirements, fuel handling and accounting, core loading, radiation monitoring and fire protection.
The licensee plans to combine the tech-nical and QA audits into one system in order to reduce dupli-cations in the program as it is now constituted.
The inspector reviewed the audit schedule and the following onsite audit reports:
QB-78-07 Document Control, 6 findings QB-78-08 Identification and Control of Material, Parts and Components, Handling and Storage, 3 findings QB-78-09 Q List, 2 findings QB-78-10 Receiving Inspection, 2 findings QB-78-11 QA Records, 2 findings Findings are significant departures from specified requirements or a deficiency in characteristics, documentation, or procedure which are considered significant to safety or renders an iten unacceptable.
Findings are reported and corrected in the Deviatio:. Reporting system and carried in the Action Item Reccrd System until the required corrective action has been completed.
The inspector reviewed the tracking of these items for timely corrective action.
No items of noncompliance were identified.
6.
Followup on Previous Noncompliance (Closed) Infraction (Inspection Report No. 78-07)
Failure to follow procedures in four instances.
The inspector reviewed revisions to procedures that were part of corrective actions taken. Other corrective action involving operator retraining was essentially complete.
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7.
Followup on Open Inspection Items
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a.
(Closed) Steam Drum Low Level Sensor Setpoint Drift There has been no further problem-of nonconservative setpolat drifting.
(Closed) Control Rod E-4 Withdrawal Problem /
b.
The E-4 drive was replaced and there has been nc further problem.
8.
Review of Licensee Event Reports (LER's)
The inspector reviewed the following LER's to verify that they had been reviewed and the indicated corrective action had been or was being taken:
R0-78-33 Excessive leakage of fuel, pit drain isolation valves, during test.
R0-78-34 RDS UPS battery specific gravity below limits.
R0-78-36 Condensate Storage Tank below low level limit.
R0-78-37 Excessive leakage of Mainsteam Isolation Valve, during test.
R0-78-38 Control rod drives D-3 and D-6 exceeded temperature limit.
R0-78-39 Control rod drives removed with reactor mode switch not in shutdown position.
R0-78-40 Containment vacuum relief valve control power inverter blown fuse.
R0-78-41 Transfer cask safety sling trip device, to prevent cask drop, defeated by excessive gear wear.
R0-78-42 Control rod drive coupling integrity test found to be invalid.
R0-78-43 Control rod drive scram time limit exceeded, during test.
R0-78-44 Weld leak on 3/4-inch stub on 3-inch cleanup line.
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IE Inspection Report No. 50-155/77-12, 3/
LER'No.' 50-155/77-23.
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IE Inspection Report No. 50-155/78-07.
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RO-78-46 Control rod drive scram test, A-2 exceeded time limit, during test.
R0-78-49 Reactor low water level did not provide the required RDS trip, during test.
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No ite=s of noncompliance ~'were identified.
Followup inspections will be conducted to review corrective action taken on R0-78-35, which has been a repeative problem, and R0-76-44, the repair of the 3-inch cleanup line.
9.
IE Circular Review The inspector verified that the licensee had received and appropriately evaluated the following IE Circulars:
IEC 78-03 Packaging greater than type A quantities of low specific activity radioactive materials for transport.
IEC 78-04 Installation errors that could prevent closing of fire doors.
IEC 78-09 Arcing of General Electric Company size 2 contactors.
IEC 78-11 Recirculation M-G set overspeed stops.
IEC 78-13 Inoperability of service water pumps.
IEC 78-18 UL fire test.
10.
Electrical Cable Splicing Environmental Qualifications On October 2, 1978 the licensee reported that during a Systematic Evaluation Program review of cable splicing inside containment, 5/
several splices were deemed to be marginal in moisture resistance.--
The plant was shutdown at the time and the licensee made repairs to 312 splices inside containment and 70 splices outside containment.
Repairs and testing were completed on October 30, 1978 before the plant was restarted.
The inspector reviewed the repair and taping procedure, FDBE-3 and QA check sheets for certification of this repair and the splicers.
Scotch tape 23 (ethylene-propylene) was wrapped first and overwrapped with Scotch 33+ (vinyl).
The tape radiation qualification was n
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LER No. 78-45.
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provided by Minnesota Mining and Manufacturing Company and the licen-seehadonhandapregpminaryqualificationreport for the splices from Wyle Laboratory.-
The final qualification r,eport will be reviewed at a later date.
No items of noncompliance,were identified.
11.
Primary Coolant Boundary Leak On October 18, 1978, the licensee reported the discovery of a small leak from a 3/4-inch stub of the 3-inch cleanup system return line leading to the No. 2 recirculation pump suction, during a startup leak ch The reactor was immediately shutdown and repairs com-pleted.9yk.Repair consisted of cutting out and replacing 12 inches of the 3-inch line.
Preliminary cause of the crack from metal-lurgical examination was determined to be fatigue cracking caused by vibration of the 12 inch long stub.
Repairs to the line will be reviewed at a later time.
No items of noncompliance were identified.
12.
Deviation Report No. 78-84 Broker. Glass in Reactor In September 1978 while shutdown and correcting a sticking control rod problem, a flood light bulb was broken inside the reactor vessel.
Af ter moving about one fourth of the core, only 66% of the glass was recovered. A safety analysis resulted in the following conclu-sions:
a.
If the missing glass was in one piece, it could restrict coolant flow. The flow restriction would not be a safety problem with a 2MWe reduction of power for fuel cycle 15.
b.
No power reduction would be required for fuel cycle 16 since all core components will be removed and cleaned and the glass would have been pulverized.
The glass would not adversely affect the operation of the c.
The inspector reviewed the safety analysis and also noted that procedures had been revised to prevent further use of unprotected bulbs within the reactor vessel.
The reactor is being operated at reduced power.
No items of noncompliance were identified.
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Wyle Laboratory Report, 58316, September 15, 1978 7/
LER No. 78-44-3-
a 13.
Exit Interview
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The inspector conducted a management exit interview with licensee representatives (denoted in Paragraph 1) at the plant on December li, 1978. The inspector reviewed the scope and findings of the inspection.
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