IR 05000263/1975014
| ML20024G586 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/29/1975 |
| From: | Kohler J, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G584 | List: |
| References | |
| 50-263-75-14, NUDOCS 9102120704 | |
| Download: ML20024G586 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
OITICE OF INSPECTION AND ENTORCDiC(T
REGION III
Report of Operations Inspection IE Inspection Report No. 050-263/75-14 Licensee:
Northern States Power Conpany 414 Nicollet Mail Kinneapolis, Minnesota 55401 Monticello Nuc1 car Generating Plant License No. DPR-22 hor $icello, Minnesota Category:
C
- h t$s Type of Licensee:
BWR (GE) 575 MWe Type of Inspection:
Routine, Announced Dates of Inspection:
September 17-19, 1975 h$.LV
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Principal Inspector:
J. E. Kohler 3 12 (Date)
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Accompanying Inspector:
W. S. Little Other Accompanying Persennel:
None
?se lt0'c.' hlb k//
r Reviewed By:
W.
S,.
Little Senior Irapector (Date)
Nucicat Support Section
Reactor Operations Branch
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kD lhOCK05000263 704 751003 C
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SUMMARY OF FINDINGS
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Inspection Summary The inspection on September 17-19 (75-14) consisted of review of the following items:
(a) pre-refueling activities. (b) refueling activities, (c) maintenance, (d) review of plant operations, (c) local leak rate test and integrated leak test data from previous containment leak tests.
Enforeceent Items None.
Licensee Action on Previously Identified Enforcenent Items Not inspected.
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Other cignificant Items A.
Systems and Corponents None.
B.
Facility Items The licensee commenced a planned 35 day outage on September 11, 1975, in order to replace the 268 7x7 fuel bundles with 8xS fuel, making Monticello the lead 8x8 fuel BVR. At the conclusion of'the present outage, the Monticello core sill consist of 464 8x8 assem-
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blies, and 20 7x7 improved assemblies.
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C.
Managerial Items None.
D.
Noncompliance Identified and Corrected by Licensee None.
E.
Deviations None.
F.
Status of Previously Reported Unresolved Items Eo unresolved items reported.
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Manaaement Interview
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A management interview was conducted by Mr. Kohler and Mr. Little with Mr. Larson, Plant Superintendent and other members of his staf f at the conclusion of the inspection.
The following items were discussed.
A.
The inspector stated that refueling procedures 9007 and 9009 should specify an acceptable time interval prior to refueling for checkout of-the fuel prep machine, fuel handling jib crane, and the channel handling boom. Tbc licensee agreed that the coc= cat was valid and stated that appropriate changes will be made.
(Paragraph 2, Report Details)
B.
The inspector discussed the licensee's emergency plans for a dropped fuel element. The licensee agreed to consider adding some additional precautionary words in the daily refueling check sheet advising against emergency evacuation of the refueling floor with a fuel element suspended over the refueling pool.
(Paragraph 2, Report Details)
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REPORT DETAIL 5_
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1.
Persons Contacted C. Larson, Plant Manager D. Nevinski, Nuclear Engineer J.,Heneage, Engineer
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B. Jenness. Engineer M. Hammer, Engineer M. Clarity, Superintendent, Plant Engineering and Radiation
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Protection W. Anderson, Superintendent, Operation and Maintenance
.R. Seibel, Shif t Supervisor W. Sparrow, Operations Supervisor
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2.
, Preparation for Refueling The licensee's pre-refueling activities vera inspected to determine
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whether technical specifications and approved refueling proceduras were being followed. The inspector reviewed procedures relating to movement of fuci into and out of the pool and the core, as well as daily and weekly refueling check sheets, and ascertained that surveillance of the following items had been included in approved procedures:
Refueling Machine Operation Ventilation Requirements in Fuel Storage Areas Refueling Interlocks
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Crane Testing Radiation Monitors on the Refueling Floor
Communication Systems Between the Refueling Deck and
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the Control Room Fuci Pool Cooling Capability for Stored Fuel Fuel Transfer and Core Verification The licensee plans to sip all the original core 7x7 fuel prior to discharge to General Electric Company. Additionally, the licensee was in the process of determining how many of the 8x8 fuel bundles from cycles three and four were going to be sipped.
As of September 1 1975, the lead 8x8 fuel assemblies have accumulated about 8000 M'n'd/NTs
Refueling procedures 9007 and 9009 specify checkouts of the fuel handling jib crane, the fuel prep machine, the channel handling boom, and'the channel handling tool.
However, there was no time interval
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specified prior to refueling for completion of these checkouts.
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Several checkouts for the September outage were completed in July,
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1975. The licensee will modify the refueling procedures to in-clude an acceptable time interval, prior to refueling, in which these checkouts can be completed.
The inspector discussed the licensee's emergency recovery plans with respect to an emergency on the refueling floor. Present plans call for immediate personnel evacuation when the radiation alare sounds.
The licensee agreed to consider adding additional precaut'.onary words to the drily refueling check sheets advising against emergency evacuation of the refueling deck with a fuel element suspended from the grapple over the refueling pool.
The inspector has no further questions regarding this item at this time.
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3.
Refueling Activities
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The inspector observed activities on the refueling deck and in the control room, and verified that the following itens were being con-ducted according to approved procedures:
Source range instrumentatien had a minimum of 3 CPS.
a.
b.
Secondary containment integrity existed consisting of routine supply and exhaust systems operating, and the stand-by gas treatment systems operabic.
Fuel bundic movement on the refueling deck was in accordance c.
with fuel movement procedures approved by the station nuclear engineer.
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d.
Core internals were protected with polyurethane, and house-
Precautions were taken to limit the keeping was acceptable.
numberoflooseobjectsthatcouldfallintothereactordool.
Refueling crew was under the direct supervision of a e.
shift supervisor holding a valid senior reactor operation's license.
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Pool water Icvel was at 33 feet and fuel pool cooling was being monitored in the control room.
The reactor mode switch was in the refueling mode.
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During the refueling activities observed in the control room, a licensed operator was present in direct communication with a member of the fuel handling crew, i
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Fuel accountability measures were being taken, core maps, status
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boards, and checks were maintained in accordance with established
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procedures.
Control rod movement during refueltag was in accordance with j.
technical specification.
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4.
Maintenance _
The master outage plan was obtained from the licensee and three maintenance activities were selected for review. The inspector determined that approved procedures existed for the following:
Main Steam Line Isolation Valve Leak Testing.
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Leak Rate Testing of Feedwater Check Valves.
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Inspection of Four-Inch Recirculation Piping.
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5.
Review of Plant Operations for plant startup was obtained and it was (
The master.:heckout sheet determined that procedures ex!.sted for returning systems disturbed The or tested during refueling to operating status prior to start up.
following system checkout sheats were reviewed:
a.
Main Steam b.
Reactor Protection Condensate Feedwater c.
d.
High Pressurs Core Injection c.
Control Rod Drive
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Containment Local Leak Rate Tests Icak-The inspector reviewed the results of two previous containment in preparation for the containment leak test rate' tests (1973, 1974)
scheduled for the September,1975 outage and noted that feedwater check I
valves, which had been found to be Icaking excessively, had been repaired.
The repair consisted of benu!ng the disc hinge am.08 inches (allowing the disc to racet with the ' r.it unifomly), and regrinding and lapping the disc seating surfaces. The repaired feedwater check valves have Modifications are planned for subsequently been found to be Icak tight.
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l valves in two other lines that have been found to leak excessively in These lines are the Reactor Core Isolation Cooling and previous tests.
the High Pressure Injection Cooling lines.
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