IR 05000155/1980009
| ML19347B472 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/20/1980 |
| From: | Boyd D, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19347B469 | List: |
| References | |
| 50-155-80-09, 50-155-80-9, IEB-80-17, NUDOCS 8010150126 | |
| Download: ML19347B472 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report No. 50-155/80-09 j
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Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201
- 1 Facility Name:
Big Rock Point Nulcear Plant l
Inspection At:
Charlevoix, MI i
I Inspection Conducted: July 3-August 4, 1980 GH hh PA6 Mn
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Inspector:f f
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/4////g, grg2 Chief 8/2o/s?
Approved By:
D. C.
oyd
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rojects Section 4
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Inspection Summary
i Inspection on July 3-August 4, 1980 (Report No. 50-155/80-09)
Areas Inspected: Routine Resident Inspector inspection of operational l
safety, bulletin review and activities pertaining to Bulletin 80-17.
i The inspection involved 93 inspector hours onsite including 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> off-shift inspection by one hTC inspector.
I Results:
No apparent items of noncompliance were identified in the areas inspected.
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DETAILS 1.
Persons Contacted
- J. Rang, Operations Maintenance Superintendent R. Abel, Technical Engineer A. Sevener, Operations Supervisor
- R. Schrader, Technical Superintendent
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The inspector also contacted other licensee personnel from the l
Operations Department.
- Denotes those present at the exit interview.
2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operstors during the month of July, 1980. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of af fected components. Tours of the reactor buildings and turbine buildings 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 and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector observed plant housekeeping / cleanliness conditions and verified implementation of sdiation protection controls. During the month of July, 1980, the inspector walked down the accessible portions of the Core Spray and Liquid Poison systems to verify operability.
These reviews and observations were conducted to verify thet facil-ity operations were in conformance with the requirements tstablished under technical specifications, 10 CFR, and administrative procedures.
No apparent items of noncompliance were identified.
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IE Bulletin Follosup 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 bullet'.n and the licensee's response, that licensee management forwarded
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f copies of the written response to the appropriate onsite management l
representatives, that information discussed in the licensee's
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written response was accurate, and that corrective action taken by l
the licensee was as described in the written response.
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IE Bulletin 79-27, " Loss of Nonclass 1-E Instrumentation and Control Power System Bus During Operation."
(Closed). The inspector reviewed the licensee's response of March 19,1980 to the bulletin and verified that procedure revisions as indicated l
in the response were made to the following
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procedures:
a.
EMP 3.1 " Loss of DC Power System" b.
ONP 2.36 " Loss of Station Power" IE Bulletin 80-17, " Failure of 76 of 185 Control Rods to Fully Insert Du ring a Scram at a BWR".
The inspector witnessed and/or reviewed documentation to verify that the following items were performed:
a.
IEB 80-17 Item I b.
IEB 80-17 Item 2: Item 2.j is not applicable to Big Rock Point.
c.
IEB 80-17 Item 3 d.
IEB 80-17 Item 4
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e.
IEB 80-17 I!em 5 f.
IEB 80-17 Item 6a.
Items 6b & 6c are not applicable to Big Rock Point g.
IEB 80-17 Item 7
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IEB 80-17 Item 8
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IEB 80-17 Supplement 2 Item 1 j.
IEB 80-17 Supplement 2 Item 2 As indicated in Item 3.b. above, Big Rock Pcint does not have a
time delay associated with the reset of a Reactor Protection System i
trip. The inspector discussed the item with licensee personnel and it was agreed that a review for feasibility of implementing such a time delay and methods of performing the system change would be undertaken. This will remain an open item to be reviewed during a subsequent inspection (155/80-09-01)
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No items of noncompliance were identified.
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4.
Independent Inspection The inspector attended a meeting between the licensee and W. Paulson, D. Cruchfield and J. Oshiaski from NRR pertaining to requirements of NUREG 0578.
5.
Exit Interview The inspector met with the individuals denoted in Paragraph 1 at the conclusion of the inspection and summarized the scope and findings of the inspection.
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