ML20039F383
| ML20039F383 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/29/1981 |
| From: | Guldemond W, Hague R, Konklin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20039F361 | List: |
| References | |
| 50-266-81-22, 50-301-81-22, NUDOCS 8201120400 | |
| Download: ML20039F383 (6) | |
See also: IR 05000266/1981022
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION III
Report No. 50-266/81-22; 50-301/81-22
Docket No. 50-266; 50-301
Licensee: Wisconsin Electric Power Company
231 Fest Michigan
Milwaukee, WI 53203
Facility Name: Point Beach Nuclear Power Plant, Units 1 & 2
Inspection At: Point Beach Site
Inspection Conducted: , November 2-30, 1981
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Inspectors
'W.
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. ldemond.
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Approved By
-fJ.' E'.7 Konklin, Chief
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Reactor Projects Section 2A
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Inspection Summary
Inspection on November 2-30, 1981 (Report No. 50-266/81-22; 50-301/81-22)
Areas Inspected: Routine resident inspection of Operational Safety
Verification, Monthly Maintenance Observation, Monthly Surveillance
Observation, Followup on Licensee Event Reports, IE Bulletin and Circular
Followup, Followup on Items of Noncompliance, Inspection During Long-Term
Shutdown, Refueling Activities, Review of Periodic and Special Reports.
The inspection involved a total of 136 inspector-hours onsite by two
inspectors including 20 inspector-hours onsite during off-shifts.
Results: Of eight areas inspected, no items of noncompliance were
identified in seven areas. Two items of noncompliance were identified
(Failure to establish a fire watch - Paragraph 8; failure to follow
ignition control permit procedures - Paragraph 8).
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-DETAILS
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1.
Persons Contacted
- G. A. Reed, Manager,-Nuclear-Operations
J. J. Zach, General Superintendent
T. J. Koehler, Superintendent - Operations
J. C. Reisenbuechler, Superintendent - I,& C
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W. J. Herrman,JSuperintendent - Maintenance and Construction
R. S. Bredvad, Health Physicist
- R. E. Link, Superintendent - EQR
- F. A. Zeman, Supervisor - Staff Services
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The inspectors also talked with and interviewed members of the
. Operations, Maintenance, Health Physics and Instrument and Control
Sections.
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2.
Operational Safety Verification
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The inspector observed control room operations, reviewed applicable
logs and conducted discussions with control room operators during
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the month of November 1981. The. inspector verified the operability
of selected emergency systems, reviewed tagout records and: verified
proper return to service of'affected components. Tours of Unit 1
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containment, the auxiliary. buildings and turbine buildings wereLcon-
ducted to observe plant equipment conditions,; including potential
fire hazards, fluid leaks, and excessive vibrations.and to verify
that maintenance requests had been. initiated forLequipment 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 radiation protection controls. During the
month of November 1981, the inspector walked down the accessible
portions of the safety injection, containment spray, auxiliary feed-
water, service water, and emergency electrical systems to verify
operability. The inspector also witnessed portions of the radio-
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active waste system controls associated with radwaste shipments and-
barreling.
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These reviews and observations were conducted to verify that facility
operations were in conformance with the requirements established
under technical specifications, 10 CFR, and administrative procedures.
No items of noncompliance were identified.
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3.
Monthly Maintenance Observation
Station maintenance activities of safety related systems and com-
ponents listed below were observed / reviewed to ascertain that they
were conducted in accordance with approved procedures, regulatory
guides and industry codes or standards and in conformance with
technical specifications.
Repair of Unit 1 RHR valve MOV-700.
The following items were considered during this review:
the-limit-
ing conditions for operation were met while components or systems
were removed from service; approvals were obtained prior to initiat-
ing the work; activities were accomplished using approved procedures
and were inspected as applicable; functional testing and/or calibra-
tions were performed prior to returning components or systems to
service; quality control records were maintained; activities were
accomplished by qualified personnel; parts and materials used were
properly certified; radiological controls were implemented; and,
fire prevention controls were implemented.
No items of noncompliance were identified.
4.
Hopthly Surveillance Observation
The inspector observed the technical specification required the Unit
1 Safety Injection with Loss of A.C. Test and verified that testing
was performed in accordance with adequate procedures, that test
instrumentation was calibrated, that limiting conditions for opera-
tion were met, that removal and restoration of the affected compon-
ents were accomplished, that test results conformed with technical
specifications and procedure requirements _and were reviewed by
personnel other than the individual directing the test, and that
any deficiencies identified during the testing were properly re-
viewed and resolved by appropriate management personnel.
No items of noncompliance were identified.
5.
Licensee Event Reports Followup
Through direct observations, discussions with licensee personnel,
and review of records, the following event reports were reviewed to
determine that reportability requirements were fulfilled, immediate
corrective action was accomplished, and corrective action to prevent
recurrence had been accomplished in accordance with technical speci-
fications.
50-266/81-016/01T-0
Defective Westinghouse NBFD Relays
50-266/81-015/01T-0
Low Head SI Event V Check Valve Leaking
By Seat
50-301/81-008/01T-0
Inadvertent Isolation of Train A High
Head Safety Injection
50-266/81-018/03L-0
Failure to Perform Area Fire Inspections
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No items of noncompliance were identified.
5.
IE Bulletin Followup
All outstanding IE Bulletins were reviewed.
It was determined that
none could be closed out.
6.
IE Circular Followup
All outstanding IE Circulars were reviewed.
It was determined that
none could be closed out.
7.
Followup on Items of Noncompliance
Licensee actions in response to the items of noncompliance documented
in the inspection reports below were reviewed to ascertain that the
actions were completed as committed and were in conformance with
regulatory requirements.
Docket Number
Inspection Report
Subject
Number
50-266 & 50-301
81-08 & 81-07
Instrument calibrations
left outside test accep-
tance criteria without
adequate documentation
8.
Inspection During Long Term Shutdown
The inspector monitored Unit 1 shutdown operations, reviewed applic-
able logs, and conducted discussions with operators during November
1981. Tours of Unit 1 areas were conducted to verify tagout procedure
implementation and to observe plant equipment conditions including
potential fire hazards, fluid leaks and excessive vibrations. Also
monitored were housekeeping / cleanliness conditions, implementation
of radiation protection controls and implementation of the station
security plan.
On November 6, 1981,-the inspector reviewed the refueling book for
Unit I with particular attention to the phase-by-phase list. This
list records the prerequisites established prior to major changes in
plant conditions and has corresponding initial blocks to document
completion. For the existing plant conditions at the time of review,
twenty prerequisites had not been initialled as complete. Of these,
one concerned the establishment of containment integrity prior to
reactor vessel head removal, one documented calibration of installed
radiation monitors, and one documented a secondary to primary leak
test as a prerequisite to steam generator eddy current inspection.
Subsequent review showed that the uninitialled items had been com-
pleted. These discrepancies were brought to the attention of li-
censee management.
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On November 6,1981, thd inspector monitored work activities related
to the installation of sleeves in the Unit 1."A" steam generator
tubes in the Unit I containment. During the course of this inspec--
tion, sparks were noted to be dropping into_the work entry area from
the overhead. Significant amounts of combustible material was stored
in the work entry area. No fire watch was posted. The sparks were
coming from hanger modification ~ work taking place on the level
immediately above the steam generator work area. The requirement
for a fire watch was brought to the attention of the workers per-
forming the hanger modification work by~a1 contractor health physics
supervisor. However, several minutes later sparks were again obser-
ved falling into the steam generator work area. The lack of a fire
watch is contrary to procedure PBNP 3.30.
This is an item of noncom-
pliance (266/81-22-01).
During the period November 6 - 12, 1981, the inspector, while perform--
ing routine plant tours, noted seven instances in which expired ignition
control permits were posted at job sites in the plant. The failure to
clear the expired permits is in violation of procedure PBNP 3.30.
This
is an item of noncompliance (266/81-22-02).
9.
Refueling Activities
Prior to Unit I fuel loading operations, the inspector verified that
all surveillance testing required by technical specifications and
licensee procedures for fuel handling had been completed. The
inspector witnessed several shifts of fuel handling during the core
reload November 23 - 25.
Staffing during the reload was in accordance
with technical specifications. Good housekeeping practices were
observed in the fuel handling areas and containment integrity was
maintained as required by technical specifications.
The licensee conferred with Westinghouse on the broken bottom grid
strap referenced in Inspection Report 50-266/81-19. The resolution
agreed upon was to attempt to bend the strap back to its original
position. This was accomplished by the licensee and a caution step
was added to the refueling procedure to ensure extra care was taken
while installing the assembly immediately adjacent to the broken
strap. No problems were encountered while performing this step.
No items of noncompliance were~ identified.
10.
Review of Periodic and Special Reports
On November 10, 1981, the licensee issued a special report document-
ing actuation of the overpressure mitigating system on Unit I during
cold shutdown. The inspector reviewed this report for technical
accuracy and compliance with reporting requirements.
Based on this
review it was determined that the report was descriptive of the
circumstances surrounding the event and that the reporting require-
ments of Technical Specification 15.6.9.2.E were-satisfied. The
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event did result in an item of noncompliance with respect'to pro-
cedural compliance'(See IE Inspection Report 50-266/81-19).
11.
Exit Interview
The inspector met with licensee representatives (denoted ~in Paragraph
1)-throughout the month and at the conclusion of the inspection period
and summarized the scope and findings of the inspection activities.
The licensee acknowledged the findings.
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