IR 05000155/1980010
| ML19351E470 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/25/1980 |
| From: | Boyd D, Parker M, Wright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19351E466 | List: |
| References | |
| 50-155-80-10, NUDOCS 8012100176 | |
| Download: ML19351E470 (6) | |
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U.S.. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-155/80-10 License No. DPR-6-Docket No. 50-155
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Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson MI 49201 Facility Name: Big Rock Point Nuclear Plant j
Inspection At:
Charlevoix, MI Inspection Conducted: August 4 - September 5, 1980 Inspectors:
N60 9W"
% /so b5[6 o Approved by:
f Projects Section 4 Inspection Summary Inspection 'on August - 4 - September 5,1980 (Report No. 50-155/80-10)
Areas Inspected: Routine Resident Inspector inspection of operational safety, bulletin review, circular review and LER 80-23 initial followup.
The inspection involved 76 inspector-hours onsite, including 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off-shif t inspection, by two 'NRC inspectors.
Results: No apparent items of noncompliance were identified in the areas inspected.
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DETAILS-1.
Persons Contacted
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- C. J. Hartman, Plant Superintendent J. S. Rang, Operations & Maintenance Superintendent
- D. E. DeMoor, Technical Engineer
- A. C. Sevener, Operations Supervisor D. P. Blanchard, Reactor Engineer
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- J. J. Popa, Maintenance Engineer
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- R. E. Schrader, Technical Superintendent The inspector also contacted additional licensee personnel including shift supervisors and control room operators.
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- Denotes those present at the exit interview.
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2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs-and conducted discussions with control room operators during the month of August. The inspector verified the operability of selected emergency systems, reviewed tagcut records and verified proper return to sgrvice of'affected components. Tours of the reactor buildings and tu'rbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and exces-sive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the stal' ion security plan.
The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the month of August, the inspector walked down the accessible portions of the core spray and fire water systems to verify operability. The inspector also witnessed portions of the radioactive waste system con-trols associated with radwaste shipments and barreling.
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.
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No apparent items of noncompliance vere identified.
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3.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical speci-fications.
LER 80-23:
" Reanalysis of Containment Atmosphere Temperature and-Pressure for Steam Line Breaks (SLB)".
The inspector verified that Operations Memo 20-80, which detailed
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operator actions in the event of a small steam line break, was implemented and appropriate training conducted.
The inspector has requested that the licensee provide a written evaluation of equipment availability and contain-ment integrity if the calculated temperatures in the LER
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are reached. The long term resolution to the situation has been referred to NRR for their review.
4.
I.E. Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation in the bulletin and the licensee's_ response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written respcuse.
a.
(Closed)
I.E. Bulletin 80-01:
" Operability of ADS Valve Pneumatic Supply". The inspector noted that although Big Rock Point does not have ADS valves in the sense that the bulletin was intended to address, the response did evaluate the bulletin as it was perceived to apply to BRP.
-b.
(Closed)
1.E. Bulletin 80-02:
" Inadequate QA for Nuclear Supplied Equipment".
c.
(Closed)
I.E. Bulletin 80-03:
" Loss of Charcoal from Standard
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Type II 2" Tray Absorber Cells".
BRP does not use
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charcoal tray absorbers.
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d.
(Closed)
I.E. Bulletin 80-06: " Engineered Safety Feature Reset Controls". The~ inspector notes that the licensee
'has taken exception to the bulletin for the Containment Vent Isolation Valves and the Off-Gas Isolation Valve.
The testing required by Item 2 of the bulletin is considered an outstanding inspection item and will be inspected at a later date.
(155/80-10-01)
e.
(Closed)
I.E.-Bulletin 80-07 and 80-07 Supplement 1:
"BWR Jet Pump Assembly Failure".
BRP does not have jet pumps.
f.
(Closed)
I.E. Bulletin 80-08:
" Examination of Containment Liner Penetration Welds".
g.
(Closed)
I.E. Bulletin 80-09:
"Hydramotor Actuator Deficiencies",
h.
(Closed)
I.E. Bulletin 80-14:
" Degradation of BWR Scram Discharge Volume Capability". The testing required
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by Item 6 is considered an outstanding inspection item and will be inspected at a later date.
(155/80-10-02).
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(Closed)
I.E. Bulletin 80-15:
"Possible Loss of Emergency Notification System with Loss of Off-site Power".
The licensee indicated that the HP phone currently does not meet the emergency power requirement and that efforts
-.are under way to correct this situation. This is con-sidered an outstanding inspection item and will be inspected at a later date.
(155/80-10-03).
j.
(Closed)
I.E.Bulletin 80-17 Supplement 3:
" Failure of Control Rods to Insert During a Scram at a BWR".
The licensee's response indicates that no modifications or testing is being. instituted due to unique design of BRP's scram discharge piping and instrumentation. Discussions with the-licensee, Region III and IE Headquarters confirm this is an acceptable response.
k.
(Closed)
I.E. Bulletin 80-19:
" Failures of Mercury-Wetted Matrix Relays in Reactor Protective System of Operating Nuclear Power Plants Designed by Combustion Engineering".
1.
(Closed)
I.E. Bulletin 80-20:
" Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches".
No apparent items of noncompliance were identified.
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15.
IE Cir'ular Followup For the IE Circulars listeo below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.
a.
(Closed)
I.E. Circular 80-01: " Service Advise for GE Induction Disc Relays".
b.
(Closed)
I.E. Circular 80-02: " Nuclear Power Plant Staff
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Working Hours". The inspector notes that the licensee has taken exception to the suggestivns made in the circular, and as such does not intend to !aplement any changes to their current scheduling practices, c.
(Closed)
I.E. Circular 80-03:
" Protection From Toxic Gas Hazards". The inspector notes that the topic of control room habitability is being reviewed in the SEP program.
d.
(Closed)
I.E. Circular 80-04:
" Securing of Threaded Locking Devices on Safety Related Equipment".
e.
(Closed)
I.E. Circular 80-05:
Lube Oil Addition and Onsite Supply". The inspector i
notes that the licensee does not have and does not
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intend to generate procedures for the addition of oil to the Emergency Diesel Generator. The inspector verified that the licensee has marked the oil addition location indicating the type of oil to be used.
f.
(Closed)
I.E. Circular 80-07: " Problem with HPCI Turbine Oil System". Big Rock Point does not have a HPCI Turbine.
g.
(Closed)
I.E. Circular 80-08:
"BWR Technical Specification Inconsistancy - RPS Response Time".
h.
(Closed)
I.E. Circular 80-09: " Problems with Plant Internal Communication Systems". The inspector notes that the licensee has determined that although all internal communication equipment would be operable during a loss of off-site power the-plant PA system, the ROS evacuation alarm and the site emergency alarm are subject to a single failure of emergency lighting transformer #3 and associated breakers. Licensee indicates no plans exist to modify this power supply.
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d.
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(Closed)
I.E. Circular 80-10:
' Failure to Maintain Environmental Qualifications of Equipment".
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(Closed)
I.E. Circular 80-12: '" Valve-Shaft-to Actuator key may fall.out of' place when~ mounted below horizontal axis".
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k.
(Closed)
I.E. Circular 80-16:
" Operational Deficiencies in
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Rosemont Model 510 DU Trip Units and Model 1152 Pressure Transmitters".
'No apparent. items of noncompliance were identified.
6.
Independent Inspection Report The inspectors witnessed fire brigade training being. conducted on-site.
The training consisted of classroom instruction and actual fxeld use of portable fire extinguishers and water hoses on four different types of fires.
7.
Licensee's Plans for Coping with Strikes The inspector verified that the licensee's plans for dealing with a strike were adequate and consistant with regulatory requirements.
8.
Exit Interview The inspector met with the individuals denoted in Paragraph I at the conclusion of the inspection and summarized the scope and finding of the inspection.
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