IR 05000324/1979033
| ML19210B836 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/04/1979 |
| From: | Messitt B, Moon B, Ruhlman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19210B830 | List: |
| References | |
| 50-324-79-33, 50-325-79-34, NUDOCS 7911120507 | |
| Download: ML19210B836 (4) | |
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Rf00 UNITED STATES
o,'n NUCLEAR REGULATORY COMMISSION
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REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303
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Report Nos. 50-324/79-33 and 50-325/79-34 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick Units 1 and 2 Docket Nos. 50-324 and 50-325 License Nos. DPR-71 and DPR-62 Inspection at B nswick
'te near S thport: North Carolina Inspectors:
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B.T. Messitt f
Date Signed
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B. T. ' Moon /
Date Sign 6d Approved by: D
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.A W. A. Ruhlman, Acting Section Chief Date Sigr5 d RONS Branch SUMMARY Inspection on August 29-31, 1979 Areas Inspected
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This routine, unannounced inspection involved 37 inspector-hours onsite in the areas of calibration of inplant, technical specification required instrumenta-
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tion, and followup of previous inspection findings.
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Results Of the two areas inspected, no apparent items of noncompliance or deviations
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were identified in one area; one apparent item of noncompliance was found in one area (Deficiency.
Inadequate review of comple~ted data - 324/79-33-01 and
j 325/79-34-01).
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DETAILS 1.
Persons Contacted Licensee Employees
- A. C. Tollison, Plant Manager
- D. N. Allen, QA Supervisor J. Bishop, Plant Engineer
- J. H. Brown, Operations and Maintenance Superintendent
- K. E. Enzor, I & C Maintenance Superviso-Other licensee employees contacted included technicians, operators, mechanics and office personnel.
Other Organizations
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- C. A. Julian, NRC f
NRC Resident Inspector
- J. Ouzts
- Attended exit interview.
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Exit Interview The inspection scope and findings were summarized on August 31, 1979 with those persons indicated in Paragraph I above. The item of noncompliance discussed in Paragraph 5b was acknowledged by the licensee.
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Licensee Action on Previous Inspection Findings Noncompliance (0 pen) (324-325/79-02-09): Failure to establish calibration measures. The inspector reviewed licensee progress on this item. No items of noncompli-ance or deviations were identified.
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Unresolved Items
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Unresolved items were not identified dur'ing this inspection.
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Calibration a.
Review Conducted
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The inspectors conducted a review of the calibration procedures and results as follows:
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PT 1.8, APRM Calibration PT 1.9, LPRM Calibration MI 3-IP, Reactor Low Water Level # 3 (B21-LIS-N024AB, NO31ABCD)
MI 3-3A, Generator Pressure Switch (B21-N023ABCD & 172-N002ABCD)
MI 3-12B, Time Delay Relays (E21-K16AB)
MI 3-15B, Source Range Monitor (D12-K603ABCD)
MI 2-11, Integrator Type 561, Box # 2 (G16F0K603)
CAC-AR-12601262, Drywell Radiation Count Ratemeter Module and Recorder
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CAC-AQH-1260-1,2,3, Containment Atomosphere Particulated and Gaseous Radioactivity Monitor
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The inspectors also monitored the performance of portions of the
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following calibrations performed on 8/29/76:
PT 4.1.6PC, Containment Rad Monitors Channel Calibration PT 1.1.9PC, Average Power Range Monitor-Flow Units The calibration above were reviewed to verify:
Reviews and approvals were being conducted, and data was recorded and evaluated.
Test instruments were listed and identified in test results.
Adherence to Technical Specifications required and limiting conditions for operations.
Technical contents were correct and verification of return of equipment to service and removal of test equipment was being done.
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The inspectors used one or more o~f the following acceptance criteria for evaluating the above items in the calibration program:
Technical Specifications Brunswick Plant Operating Manual Volume XI, " Quality Assurance"
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(Vel. XI)
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ANSI N18.7 (1972)
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Brunswick Plant Operating Manual Volume XII, " Maintenance Proceduras" b.
Failure to Adequately Review Data As required by 10 CFR 50, Appendix B, Criterion XI, ANSI N18.7 (1972)
and implementing document Vol.XI test results are required to be evaluated and approved and out of specification test results require correction.
During a review of PT 1.1.12PC " Reactor Protection System-Main Steamline Hi Radiation", the inspector noted that come data sheets had discrepancies. These oiscrepancies included (1) "as left" not meeting
acceptance criteria, (2) missing minus signs in exponentials and (3)
missing exponentials altogether.
During discussion with licensee pe.aonnel it was established that the type of equipment being used for this calibration (picoammeter) might be contributory to these discrepancies.
Nonetheless these documents had received tro levels of review (Supervisor and QA) and were filed in the vault with these discrepancies. Neither review had identified a problem.
This is an item of noncompliance (324/79-33-01, 325/79-34-01).
Failure to Signoff Steps in Sequence c.
During the monitoring cf PT 4.1.6PC " Containment Radiatica Monitor Channel Calibration", the inspector neted that certain steps prior to the one being performed had not been signed off. Daring discussion with the licensee it was verified that these steps had been performed.
Due to the concern that nonperformance cf procedural steps could result if this practice continued this ic designated an inspector followup itam (324/79-33-02, 325/79.-34-02).
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Inclusion of Consumable Items on the "Q" List (324-325/79-02-12)
During discussion with the licensee and the lead inspector involved a new
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target date of November 1, 1979 vas agreed upon for action on this item.
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