IR 05000263/1977016
| ML20024G541 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/28/1977 |
| From: | Barker J, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G537 | List: |
| References | |
| 50-263-77-16, NUDOCS 9102120629 | |
| Download: ML20024G541 (5) | |
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s U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report.No. 50-763/77-16 Docket No. 50-263 License No. DPR-22 Licensee:
Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401
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Facility Name:
Monticello Nuclear Generating Plan't Inspection at:
Monticello Site, Monticello, MN Inspection Conducted:
September 12-16, 1977 yJ.&J.~
7/#7#7 Inspector:
J. L. Barker
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fj.2 7 Approved by: W.
S. Little, Chief
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Nuclear Support Section Inspection Summary Inspection on September 12-16, 1977 (Report No. 50-263/77-16)
Areas Inspected:
Routine, unannounced inspection of main steam line iso-lation valve local leakrate testing, preparation for a refueling outage, pre-fuel handling activities, fuel handling activities, maintenance dur-ing a refueling outage, and preparation for startup following a refueling outage. The inspection involved 30 inspector-hours onsite by one NRC inspector and included inspection effort conducted during offshift hours.
Results:
No items of noncompliance or deviations were identified.
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9102120629 770928 PDR ADOCK 05000263 G
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DETAILS 1.
Persons Contacted
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Eliason, Plant Manager
- W. Anderson, Superintendent, Operations and Maintenance
- H. Clarity, Superintendent, Plant Engineering and Radiation Protection D. Antony, Plant Engineer, Operations W. Shamla, Plant Engineer, Technical
- R. Scheinost, Quality Engineer S. Pearson, Operations Supervisor
D. Nevinski, Engineer Nuclear R. Van Dell, Engineer D. Wegener, Engineer The inspector also contacted eleven other licensee employees.
They included three shift supervisors, two lead plant equipment opera-tors, and six plant equipment operators.
- Denotes those present at the exit interview.
2.
Main Steam Line Isolation Valve (MSIV) Local Leak Rate Testing k
The inspector reviewed licensee procedure OCD Ol37-7A, " Reactor Stean Supply Valve Leak Rate Testing by Pressurizing the Reactor with Air" and Test No. 0137, " Local Leak Rate Test."
He reviewed the results of MSIV local leak rate test and verified adherence to approved pro-cedures and proper acceptance criteria.
All MSIV's except A0-2-86A and A0-2-80A, which will be retected af ter proper repairs during the refueling outafe, received satisf actory results.
No items of noncompliance or deviations were identified.
3.
Preparation for a Refuelinn Outape The inspector verified that approved procedures are available for new fuel receipt and inspection, fuel tr/nsfer and core verifica-tion, recycled fuel inspections, and fuel sipping operations; and that new fuel was received and inspected in accordance with the licensee's procedures.
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The inspector reviewed licensee procedures No. 9001, " Reactor Well and Dryer-Separator Storage Pool Filling Procedure," No. 9006,
" Reactor Well and Dryer-Separator Storage Pool Draining Procedure,"
No. 9007B, " Shift Supervisor's Refueling Checklist," No. 9008, (
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"In-Core Sipping Procedure," No. 9008A, "Out-of-Core Sipping Pro-cedure," No. 9012 " Fuel Receiving Procedure," No. 9015. "Inspec-tion of New Fuel and Channels Followed by Placement Into the Vault, Placement into the Pool, or Transfer from the Vault to the Pool,"
No. 9023, " Refueling Bridge Load Cell Calibration," No. 9024, " Core Reload Verification Procedure," No. 9026 " Refueling Bridge Fune-tional Test," and Operations Manual Sections C.3, " Shutdown Procedures,"
D.I., " Accountability" and D.4., "Re fueling Outage Procedures." Th e inspector noted that a great deal of beneficial preplanning had been
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accomplished by the licensee which tended to make the refueling outage follow in a continuous manner.
No items of noncompliance or deviations were identified.
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, Pre-Fuel Handling Activities The inspector verified that surveillance testing had been completed on Technical Specification requirements, refueling machine opera-tion and indexing, ventilation requirement in fuel storage areas, refueling interlocks, crane testing, refueling deck radiation monitors, and communication systems.
The it.spector reviewed the Shif t Supervisor's Log and the Control Room Operator's Daily Log for the dates September 9-11, 1977.
Uc also reviewed licensee surveillance tests No. 0201/0202, "Re-k fueling Interlocks Weekly Tests," No. 2164, " Plant Pre-Shutdown Checklist," No. 9007B, " Shift Supervisor's Refueling Checklist,"
and No. 9026, "Re fueling Bridge Functional Test."
No items of noncompliance or deviations were identified.
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Fuel Handling Activities The inspector verified by direct observations that core monitoring during refueling operations was in accordance with Technical Specifications, that fuel bundle insertion and removal were in accordance with established procedures, that core interncis were stored to protect against damage, that housekeeping was proper, that vessel level was in accordance with Technical Specifications, that the mode switch was as required by Technical Specifications, that control blade checks were in accordance with approved proce-dures, that the individual directing fuel handling activities held a senior operator license and was present directly supervising
ac t iv it ie s, and that a licensed reactor operator was present in the control room and in constant direct conmunications with a member of the fuel handling crew when work was being performed that could affect the reactivit y of the reac tor.
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The inspector noted that all activities conducted by operations personnel both in the control room and on the refueling bridge were conducted in a professional manner with core safety as the primary objective.
No items of noncompliance or deviations were identified.
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Maintenance Durinr, a Re fueling Outage The inspector verified that maintenance activities conducted during the refueling outage were being conducted by qualified personnel in accordance with approved procedures.
lie verified the procedures written to control work activities contained administrative
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approvals for removing a system from service and returning it to service, hold points for inspection and signoff by quality assur-ance personnel, provisions for testing following maintenance, pro-visions for jumper removals, and responsibility for reporting
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to licensee management details concerning design or construction related deficiencies identified during maintenance.
The inspector reviewed licensee procedure 4-ACD-3.6, " Work Request Authorization." l{e also witnessed the maintenance and calibration activities conducted on the Target Rock Safety / Relief Valves.
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No items of noncompliance or deviations were identified.
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Preparations for Startup Following a Re fueling Outare The inspector verified that systems that were disturbed or tested during the refueling outage will be returned to an operating status prior to plant startup and that plant startup precedures require adherence to the licensee's Technical Specifications and commitments, as they pertain to startup testing and power operation prerequisites.
The inspector reviewed licensee procedures No. 2100, "Ma ster Systems Checklist," No. 2150, " Pre-Startup Master Checklist,"
2167, "Startup Checklist," and Operation Manual Section C.I.,
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"Startup procedures."
No items of noncompliance or deviations were identified.
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Exit I n t e rv i ew 1hc inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on September 16, 1977.
The inspector summcrized the scope and findings of the inspection.
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