IR 05000263/1977006
| ML20024G314 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/26/1977 |
| From: | Choules N, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G310 | List: |
| References | |
| 50-263-77-06, 50-263-77-6, NUDOCS 9102110283 | |
| Download: ML20024G314 (6) | |
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U.S. NUCl EAR RECl" '. TORY COMMISSION OFFICE OF INSPECTION M4D ENFORCEMENT
REGION III
Report No. 50-263/77-06
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Docket No. 50 263 1.icense No. DPR-22 Licensect Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401
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Facility Namet Monticello Nuc1 car Cencrating Plant
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Inspection att Monticello Site, Monticello, MN
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Inspection Conducted: May 9-13, 1977 h/// / hh, /f 22 Inspectort N.
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Approved By:
R. F. Warnick, Chief f/e?//pp Reactor Projects Section 2 d' ate 61gned
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Inspection Summary Inspection on May 9-13. 1977 (Report No. 50-263/77-06)
Areas Inspected: Routine, unannounced inspection of surveillance testing, procedures, annual report, nonroutine event reports, and outstanding items.
The inspection involved 32 inspector-hours on site by one NRC inspector.
Results:
Of the five areas inspected, no items of noncompliance or
_ deviations were identified in four areas; one apparent item of noncompli-ance (inf raction - f ailure to approve temporary changes to two procedures,
Paragraph 2) was identified in one area.
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9102110283 770526 PDR ADOCK 05000263
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DETAILS
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1.
Person Contacted
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R. Eliason, Plant Manager
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- H. H. Clarity, Superintendent, Plant Engineering and
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Radiation Protection
- W. E. Anderson, Superintendent, Operations and Maintenance W. A. Sparrow, Operations Supervisor
- D. D. Antony, Plant Engineer, Operations W. A. Shamla, Plant Engineer Technical
'The inspector also talked with and interviewed several other licensee employees, including members of the Operations, Engineering, and
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Instrument and Control section.
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- denotes those present at exit interview.
2.
Procedures The following procedures were reviewed by the inspector:
a.
Operating Procedures (
B.3.3 Automatic Pressure Relief B.3.5 Standby Liquid Control B.4.1 Primary Containment (Inerting and Deinerting Sections)
B.S.2 Rod Worth }iinimiter B.S.7 Reactor Level Control B.6.6 Condensate Demineralizer B.8.2 Plant Makeup B.8.7 lleating and Ventilation
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B.9.9 250 Volt DC System B.9.10 125 Volt AC System C.2 Power Operations C.3 Shutdown Procedures b.
Emergency Procedures C.4.III.G Reactor Building Closed Cooling Water System C.4.III.H Feedwater Syst em Pailure C.4.IV Acts of Nature C.4.V Procedures for Plant Shutdown from Outside the Control Room
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c.
Preventive Maint.enence Procedures OCD and PM** 4280 Auto "cessure Relief Maintenance OCD! ena PM 4840 SDLC System E1cetrical Maintenance OCD' and PM 4400 Condensate Demineralizer Element Replacement OCD and PM 4851 Safeguards Bus Source Breaker Maintenance OCD and PM 4104 Emergency Diesel Cencrator Inspection OCD and PM 4842 Emergency Service Water System Electrical Maintenance OCD and PH 4855 Essential MCC Tie Breaker Electrical Maintenance PH 4120 RCIC System Inspection
- 0perations Control Document
- Preventive Maintenance
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d.
Administrative Procedures
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4ACD 3.1 Monticello Plant Organization 4 ACD 4. 7 Plant Operato. and Control Room Activities The procedures listed above were reviewed to verify that:
a.
Procedures and changes to procedures are reviewed and approved in accordance with Technical Specifications.
b.
Procedure changes were made to reflect Technical Specifications
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revisions.
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Changes made to these procedures were in conformance with c.
10 CPR 50.59 requirements.
d.
The overall content of procedures listed in a, b, and c, above, are in conformance with the Technical Specifications.
e.
The technical content of selected procedures listed in a, b, c, and d, above, are adequate to control safety-related oper-ations within applicable regulatory requirements.
In the review of OCD 4840 completed on October 10, 1975, and OCD 4855 completed on March 29, and April 1, 1974, it was noted that changes were made to these procedures without the apparent concurrence of two individuals holding senior operator licenses as required by Technical Specification 6.5.D.
For OCD 4840, a change was made to correct the SBLC pump motor breaker identification number on page 4 of the DCD.
Por OCD 4855, changes were made on the Isolation Tabic 1.
There was no documentation that the changes had been concurred in by the two senior licensed operators.
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From review of these changes, it appeared that they should have been made permanent changes to the procedures.
Permanent changes had not been made at the time of the inspection even though each procedure had received a biannual review by the Operations Committee since the changes were made.
While the inspector was still at the site the licensee initiated action to have OCDs 4840 and 4855 changed.
At the exit interview, the licensee stated that in addition to changing the procedutes they would instruct their personnel on the requirements for making changes to safety-related maintenance procedures. The inspector stated that this action should be adequate and no reply to the noncompliance item would be required.
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As a result of the inspector's review and discussion with the licensee's
representatives, the licensee will make the revision to procedures as follows.
This was discussed in the exit interview.
a.
B. 9.9 and B. 9.10 Add an abnormal procedure for switching from
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the normally lined up battery charger to the backup battery charger in case of failure to the normal battery charger.
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b.
C.4.V Add instructions for the use of an alternate relief valve
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in the depressurization of the reactor.
c.
PM 4280 - Add a requirement to record "as found" safety valve /
relief valve settings.
3.
Surveillance a.
The inspector selected a sampling of Technical Specifications test-ing requirements and verified that the licensee has surveillance test procedures which accomplished the required surveillance testing.
The review of the following surveillance test procedures showed that prerequisites and preparation for test are specified, acceptance critiera is specified, and operational checks prior to returning equipment to service are specified when required.
b.
The following surveillance tests performed during the past year were reviewed.
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Procedure Number Title or Requirement 0013 and 0043 1RM Rod Block Calibration and Scram Test 0042 1RM Functional Test j
0052 and 0155 HPCI High Steam Flow Sensor Test and Calibration 0058 HPCI Steam Line Area Temperature Test (
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0085 Standby Liquid Control Pump F1cw Rute Check 0112 Safety Valve / Relief Valve Testing 0126 Reactor Coolant and Drywell Leak Check 0144 Primary Containment 0 Concentration
0185 and 0186 Substation Weekly and Quarterly Battery checks 0199 24 Volt Battery Monthly Check
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0200 24 Volt Battery Quarterly Check 0212 Rod Worth Minimizer Operability Verification
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The inspector reviewed selected completed surveillance tests f rom the above and determined from the sample reviewed that tests are being performed at their required frequency. The inspector observed the performance of Surveillance Test 0085.
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No items of noncompliance or deviations were identified in the review of the above surveillance testing.
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4.
1976 Annual Operating Report The subject report was reviewed and indicated that the information required by the Technical Specification had been reported.
Review of the shift supervisor's logbook indicated that the forced outages during 1976 were as reported.
No items of noncompliance or deviations were identified.
5.
Reportabic occurrences The following report.able occurrences were reviewed by examination of logs, records, internal reports, and through discussions with plant personnel. Occurrences were reviewed for completion of reporting requirements, investigation and determination of cause, proposed corrective measures, and completion of corrective actions.
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RO 77-02,1! Failure to Review Standby Gas Treatment Surveillance Test a.
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This occurrence was reviewed in a previous inspection.
For this inspection, the inspector reviewed the licensee's corrective action in regard to assuring that Technical Specifications changes are
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impicmented into affected procedures. The licensee has impicmented procedure No. 3071 Technical Specification Requirement Control Procedures, to assure the above. This procedure should assure l
Technical Specification changes are implemented into procedures and will provide a good record of action taken for each change.
l_/ RO 50-263/77-02, NSP to RIII, dtd 2/247/77.
2_/ IE Inspection Rpt No. 50-263/77-05.
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b.
RO 77-05,E! Torus Water Volume Less than Technical Specification Limit This occurrence was the result of a failure in the differential pressure transducer bellows giving an erroneous level indication.
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This was discovered when a redundant level indicator was installed showing a difference between the two 1cvel indicators.
Routine i
comparison of the readings of the two installed level indicators
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should prevent recurrence, RO 77-07,b HPCI Isolation Temperature Switch Setpoint Drift c.
As a result of this and other switch setpoint drifts, the i
licensee is looking at other type switches which have a rmaller temperature range and less potential for setpoint drift.
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No items of noncompliance or deviations were identified.
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Outstanding Item In a previous inspection, the licensee stated they would prepare an LPRM calibration procedure.
The licensee has revised Operations Hanual Section C.2 to include an LPRH calibration procedure.
No items of noncompliance or deviations were identified.
7.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the ' conclusion of the inspection on May 13, 1977.
The inspector summarized the scope and findings of the inspection.
The licensee acknowledged statements made by the inspector with respect to the item of noncompliance, and presented his corrective action (Paragraph 2).
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3/ RO 50-263/77-05, NSP to RIII, dtd 3/15/77.
4/ RO 50-263/77-07, NSP to RIII, dtd 4/22/77.
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1/ IE Inspection Rpt No. 50-263/76-18.
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