ML20207H938
| ML20207H938 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/17/1986 |
| From: | Dubois D, Jaudon J, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20207H904 | List: |
| References | |
| 50-298-86-14, NUDOCS 8607250138 | |
| Download: ML20207H938 (15) | |
See also: IR 05000298/1986014
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APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-298/86-14
License:
Docket:
50-298
Licensee:
Nebraska Public Power District (NPPD)
P. O. Box 499
Columbus, NE 68601
Facility Name:
Cooper Nuclear Station (CNS)
Inspection At:
Cooper Nuclear Station, Nemaha County, Nebraska
Inspection Conducted:
April 1 through May 31
986
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Inspectors:
o_,
A.{e ner, Resident'Inspe or, (RI)
Dats
E
,/
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&
O
L.
u
s, Senior Resident Inspector, (SRI)
Date
Approved:
%
"7
7 N
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J/ P./Jaudo
Chief, Project Section A,
Date
LRe6ctor
oject Branch
Inspection Summary
Inspection Conducted April 1 through May 31, 1986 (Report 50-298/86-14)
Areas Inspected:
Routine, unannounced inspection of previously identified
inspection findings, Licensee Event Reports, spent fuel shipments, operational
safety verification, and monthly surveillance and maintenance activities.
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'Results: Within the six areas inspected, no violations or deviations were
identified (violations - deficient as-built instrument drawings, paragraph 5;
failure to adhere to procedures paragraph 6; inadequate procedure, paragraph 6;
Deviations (see attachment) - lack of contingency equipment; lack of required
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dosimetry.
Two unresolved items are also identified in the attachment.
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Details
1.
Persons Contacted
Principal Licensee Personnel
- +G. Horn, Division Manager of Nuclear Operations
- +J. Meacham, Technical Manager
+G. Smith, Senior QA Specialist
- +J. Sayer, Technical Staff Manager
+R. Black, Operations Supervisor
+E. Mace, Plant Engineering Supervisor
+M. Hamm, Security Supervisor
,
+J. Flaherty, Assistant Plant Engineering Supervisor
- +H. Hitch, Acting Advisory Manager
- R. Brungardt, Operations Manager
- R. Koeppel, Security Operations Supervisor
- V. Wolstenholm, Quality Assurance Manager
J. Scheuerman, Lead Reactor Engineer
P. Ballinger, Operations Engineering Supervisor
S. Jobe, EQ Project Engineer
The NRC inspectors also interviewed other licensee operations,
maintenance, and administrative personnel.
NRC Personnel
- D. DuBois, Senior Resident Inspector
- +E. Plettner, Resident Inspector
+W. McNeill, Project Inspector.
+ Indicates presence at exit meeting held April 10, 1986.
- Indicates presence at exit meeting held May 30, 1986.
2.
Licensee Action on Previous Inspection Findings
(Closed) Open Item (298/8204-02):
" Storage Of Squib Valves As Hazardous
Material"
This item involved improper storage of hazardous material, (i.e. Squib
valves) in the warehouse.
The RI reviewed Administrative Services
Procedure 1.7, " Warehouse Storage," Revision 2, dated March 6, 1986.
The
procedure was changed to include storage of hazardous explosive devices
(i.e. Squibs).
The RI verified proper storage in the warehouse.
This item is closed.
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(Closed) Open Item (298/8316-01):
" Interim Contract With General Electric
On Shift Technical Advisor (STA) Training"
This item required a followup inspection on overall progress of STA
training.
The RI reviewed licensee STA training records during the period
of September 3, 1985, through January 24, 1986.
The records indicated
that STA training was completed by required individuals.
This item is closed.
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(Closed) Open Item (298/8409-02):
" Errors In Purchase Requisitions"
This item involved the lack of post-superscripts on essential purchase
orders.
The RI reviewed licensee Quality Assurance records in the area of
purchase requisitions.
The records revealed that a full audit of
essential purchase orders was performed by the licensee.
Discrepancies
found during the audit were corrected by the licensee.
A checklist
titled, " Purchase Order Review Checklist," was revised by the licensee to
prevent a recurrence.
This item is closed.
(Closed) Open Item (298/8409-03):
" Expanded Warehouse Facilities For
Receipt and Storage of Essential Parts"
This item involved inadequate storage space to separate " Essential" parts
from " Nonessential" parts.
The licensee built a 4700 square foot addition
onto the present warehouse to correct the discrepancy.
The warehouse
addition was completed in March 1986.
The RI verified adequate separation
of " Essential" parts from " Nonessential" parts.
This item is closed.
(Closed) Open Item (298/8409-04):
" Lack Of Required Documentation For
Essential Materials"
This item involved the licensee's previous practice of nct initiating a
Nonconformance Report as required when an item was quarantined and tagged
" hold".
The licensee made a revision to two Administrative Service
Procedures.
The RI reviewed procedures 1.5, " Warehouse Receiving,"
Revision 3, dated January 30, 1986, and 1.6, " Warehouse Marking and
Tagging," Revision 1, dated January 30, 1986.
Both procedures were
changed to correct the discrepancy.
This item is closed.
(Closed) Violation (298/8515-02):
" Superseded Procedures Located In The
Control Room"
Licensee corrective actions included removing all superseded documents
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from the control room, implementing a quarterly control room procedure
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audit, and revising station Procedure 2.0.2, " Operations Logs and
Reports." Procedure 2.0.2 was revised to include a section devoted to
ensuring that all station procedures located in the control room and
designated operating areas within the plant are of the latest revision.
This item is closed.
(Closed) Violation (298/8515-04):
" Failure to Follow Procedures"
This item involved the licensee's failure to adhere to CNS
Procedures 2.2.30, " Fire Protection System," Revision 22, Section K; and
7.01, " Work Item Tracking-Corrective Maintenance." Each failure to follow
procedure is discussed below.
The SRI reviewed all of the revisions that the licensee made to
Procedure 2.2.30 and determined that it was an error to have cited a
violation against Revision 22 of that procedure.
The event date
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referenced in LER 84-007, on which this violation was based, was April 19,
1984.
Revision 21 to Procedure 2.2.30 was in effect on that date.
Revision 22 was approved on June 1, 1984, and implemented the new
Section K that was referenced above.
Procedure 7.0.1 provides procedural
guidance for identifying and accomplishing repair or resolution of work
items.
I & C Personnel had failed to follow the requirements of
Procedure 7.0.1 while performing troubleshooting activities on a reactor
feedwater pump.
Subsequent licensee corrective actions included reviewing
Procedure 7.0.1 for adequacy and counselling all shift supervisors and I
& C personnel on the need for initiating an approved maintenance work
request (MWR) prior to commencing work on plant equipment or systems. The
SRI reviewed the licensee's actions and determined the immediate and
follow up corrective steps were completed.
These items are closed.
(Closed) Open Item (298/8515-05):
This item concerns apparent
inadequacies of station procedures discussed below:
System Operating Procedure (50P) 2.2.30, " Fire Protection System,"
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Revision 21, dated February 3, 1984, incorrectly documented as
Revision 22 in NRC Inspection Report 50-298/8515-15, did not provide
procedural guidance for recovery from a major loss of fire protection
system water pressure.
Revision 22, dated June 1, 1985, added a new
Section K, " Recovery from Header Inadvertent Depressurization," which
provides information to methodically refill and repressurize the fir'e
"
system water headers.
Alarm Procedure 2.3.2.1, " Panel A-Annunicator A-1," Revision 7, dated
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October 21, 1983, did not provide a CAUTION to alert operators that
restarting a tripped reactor feedwater pump with a low reactor level
could start a cold water injection transient if feedwater addition is
not held at an acceptable rate.
The annunciator action statement
refers the operator to S0P 2.2.28 if a feedwater pump is to be
,
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restarted.
S0P 2.2.28, "Feedwater System," Revision 35, dated
November 14, 1985, provided detailed instructions for starting a
reactor feedwater pump including the CAUTION statement mentioned
above.
Alarm Procedure 2.3.2.40, " Fire Protection - Annunciator 4,"
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annunciators 4-4 and 5-2, " Fire Header Pressure Low and Diesel Fire
Pump 1C Running respectively," Revision 8, dated February 25, 1985,
did not state operator actions that should be performed to correct
the alarming condition, except if the cause of annuniciation was an
actual fire.
Revision 9 to Procedure 2.3.2.40 dated August 8, 1985,
added an additional statement to the annunciator 4-4 action statement
that referred the operator to S0P 2.2.30 if the fire water header was
inadvertently depressurized.
The SRI determined that the required
action statement for annunciator 5-2 was acceptable as written.
Abnormal Procedure 2.4.9.4.3, " Loss of Single Feed Pump," Revision 6,
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dated July 25, 1984, did not provide the operator with sufficient
guidance for use during a restart of a tripped reactor feedwater
pump.
Procedure 2.4.9.4.3, Revision 7, dated August 1, 1985, added a
statement that referred the operator to S0P 2.2.28, "Feedwater
System," for restarting a tripped reactor feedwater pump once the
cause for trip is known and corrected.
Abnormal Procedure 2.4.9.4.4, " Loss of Feedwater," Revision 7, dated
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August 16, 1984, assumed that the reactor would trip because of a
reactor 1cv water level condition if a complete loss of feedwater
occurred.
Therefore, guidance was not provided to the operator for
attempting the prevention of that reactor trip.
Through discussions
with operations personnel, the SRI determined that corrective action
could not be performed rapidly enough to prevent the low-level
reactor trip from occurring; therefore, Procedure 2.4.9.4.4 provides
adequate guidance for immediate and subsequent operator actions.
These items are closed.
(Closed) Violation (298/8516-01):
This item involved the licensee QA
Department's failure to follow procedure for dispositioning " findings,"
(e.g., nonconformances).
CNS Procedure 0.5, "Nonconformance and Corrective Action," Revision 0,
dated September 28, 1984, requires that if any individual believes a
nonconformance condition exists he is to identify the nonconformance and
ensure its disposition.
In actual practice, QA Department personnel
utilized quality assurance instructions (QAIs) in lieu of Procedure 0.5 to
identify and disposition QA audit findings.
Due to inadequate wording in
the QAls and their required distribution lists, the Station Operations
Review Committee (50RC) and the NPPD Safety Review and Audit Board (SRAB),
failed to conduct required reviews and make necessary recommendations to
management concerning numerous Technical Specification (TS) violations
identified in the QA audits.
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The SRI verified that the licensee has taken the following corrective
actions:
Procedure 0.5 is being revised to ensure that QA audit findings will
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be identified and dispositioned in accordance with QAIs 4, 5, and 10,
in lieu of Procedure 0.5.
Also, paragraph III.A.7 of Procedure 0.5
will be deleted because QA findings presently receive the same
distribution as nonconformance reports (NCRs) including the 50RC and
SRAB.
" Audit / Surveillance Finding Report," Form QAl-4, Attachment 5.3, is
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used by QA personnel in lieu of Procedure 0.5, Attachment A,
"Nonconformance Report," and receives an equivalent management,
distribution, review, and disposition.
QAIs 4, 5, and 10 were revised to ensure that QA findings would be
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identified on form QAI-4, Attachment 5.3.
Also, the distribution
lists contained in those QAls were updated to ensure the same
distribution as the NCRs.
This item is closed.
(Closed) Open Item (298/8516-03):
This item identified minor design
change packages that lacked formal closure (e.g. completion, review, and
approval, of the associated Design Change Completion Reports).
The SRI conducted a followup inspection in this area during June 1 through
July 31, 1985, and documented satisfactory completion of the minor design
change packages completion reports in NRC Inspection Report 50-298/85-18.
This item is closed.
(Closed) Unresolved Item (298/8610-01) See paragraph 5 for details
3.
Licensee Event Reports Followup
The following Licensee Event Reports (LERs) were closed on the basis of
the NRC inspectors inoffice reviews, review of licensee documentation, and
discussions with licensee personnel:
LER 85-003, Revision 1, "Setpoint Drift of Safety and Safety Relief
Valves"
LER 85-005, " Excessive Primary Containment Local Leakage Rate"
LER 85-005, Revision 1, " Excessive Primary Containment Local Leakage Rate"
LER 85-006, "High Pressure Coolant Injection System Inoperability"
LER 85-007, "High Pressure Coolant Injection System Low Suction Pressure
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LER 85-008, "High Pressure Coolant Injection System Inoperability"
LER 85-009, "High Pressure Coolant Injection System Inoperability"
LER 85-010, " Group I Isolation"
LER-85-011, "High Pressure Coolant Injection System Inoperability"
LER 85-012, "High Pressure Coolant Injection System Inoperability"
LER 85-013, " Inadvertent Opening of 125 Volt DC Feeder Breaker"
LER 85-015, " Prevention of Group VI Isolation"
LER 85-016, " Inoperable Snubbers Due to Inadequate Inspection Procedure"
LER 85-017, "High Pressure Coolant Injection System Inoperability"
LER 85-018, " Group 3 Isolation"
LER 85-019, "RWCU Group III Isolation"
No violations or deviations were identified in this area.
4.
Spent Fuel Shipment
The NRC inspectors inspected the licensee's activities associated with
three shipments of spent fuel from CNS.
Included in those inspections
were observations and reviews of applicable procedures, documentation,
surveys, inspections, and shipping document preparation.
Each shipment consisted of two spent fuel shipping casks--each of which
contained 18 spent fuel bundles.
The shipments were transported to the
General Electric (GE) Morris Operation Complex, Morris, Illinois.
The
spent fuel shipment numbers, cask identification numbers, and shipping
dates were:
Shipmeat No. 1 - Casks IF-302 and IF-304; April 8, 1986
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Shipment No. 2 - Casks IF-301 and IF-302; April 29, 1986
.
Shipment No. 3 - Casks IF-301 and IF-302; May 20, 1986
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The SRI verified by review of licensee documentation, through discussions
with responsible personnel, and by independent inspection that the
licensee completed the following:
Receiving inspection of railcars and shipping casks
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Shipping documents
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Advance notification of and approval by affected state and federal
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agencies
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Proper placarding of the transport vehicles
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Appropriate labeling of the spent fuel shipping _ casks
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Establishment of provisions for response by escorts and local law
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enforcement agencies
Training of escort personnel-
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Testing of communications systems
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Continual manning of the licensee's communications center (Movement
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Control)
Testing of fuel and cask handling cranes, hoists, and tools
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Proper loading and sealing of the spent fuel shipping casks
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Surveillance of area radiation monitors, ventilation systems, and
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spent fuel pool water level and chemistry
Update of fuel location and accountability records
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Applicable quality assurance audits and inspections
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U.S. Department of Energy and U.S. NRC, " Nuclear Material Transaction
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Report," DOE /NRC Form' 741
Bill of lading
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CNS Health Physics Procedure 9.5.3.7, " Cask IF-300 Shipment,"
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Revision 3, dated December 26, 1985
CNS Nuclear Performance Procedure 10.27, " Cask IF-300 Handling and
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Shipping," Revision 3, dated November 12, 1985
CNS HP-138, " Contamination Survey - Sample Count Data Sheets"
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CNS HP-141, " Contamination Survey - Railroad Car for IF-300
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Irradiated Fuel Shipping Cask"
CNS HP-142, " Contamination Survey of IF-300 Shipping Casks"
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CNS HP-143, " Radiation Survey of IF-300 Shipping Cask"
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CNS HP-608, " Spent Fuel Shipment Checkoff Sheet and Certificate of
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Compliance of Number 9001 Conditions for Shipping Spent Fuel"
CNS HP 14a, " Radioactive Material Shipment Record"
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On April 5, 1986, the RI observed th'e movement of fuel from the spent fuel
storage pool to the shipping Cask IF-302.
The following fuel assemblies
movements were observed:
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Serial Number
Spent Fuel Pool
Cask Position-
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CZ217
4-I-4
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CZ110
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CZ271
8-G-1
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CZ193
8-H-1
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The following independent radiation and contamination surveys were
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performed by the NRC inspectors and verified to be satisfactory:
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Contact radiation surveys of the shipping casks
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Radiation' surveys at a distance of 2 meters from the cask transport
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vehicles
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Contamination surveys of the shipping cask surfaces
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Contamination surveys of the cask transport vehicles
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The SRI reviewed CNS Procedure 10.27, Revision 4, dated February 21, 1986.
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The licensee incorporated into Procedure 10.27 specific handling
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instructions for the GE Type IF-300 SPENT FUEL SHIPPING CASK.
Also
included within Procedure 10.27 was Attachment "A", " Handling and Loading
of IF-300 Spent Fuel Shipping Cask Check Off Sheet." The check off sheet
provided two functions:
it identified important steps usedsin the
receipt, inspection, preparation, movement, loading with fuel, leak
testing, decontamination, loading of the cask onto the transport vehicle,
and final preparation for shipping; and it provided a check off list
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including spaces for signatures and/or initials of personnel who performed
or witnessed the performance of key steps of the procedure.
The SRI
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verified that Attachment "A" of Procedure 10.27 was properly completed,
signed, and dated.
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The observations, reviews, and independent measurements were conducted to
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verify that spent fuel handling and shipment operations were in
conformance with the requirements established in the CNS Operating License
and Technical Specifications.
Two deviations and two unresolved items were identified in this area.
These. items are discussed in Appendix B and the at6ichment to Appendix C
of this report.
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5.
Operational Safety Verification
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The NRC inspectors observed control room operations, instrumentation and
controls reviewed plant logs and records, conducted discussions with
control room personnel, and performed system walk-downs to verify that:
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Minimum shift manning requirements were met.
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TS requirements were observed.
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Plant operations were conducted using approved procedures.
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Plant logs and records were complete, accurate, and indicative of
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actual system conditions and configurations.
System pumps, valves, control switches, and power supply breakers
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were properly aligned.
Licensee systems lineup procedures / checklists, plant drawings, and
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as-built configurations were in agreement.
Instrumentation was accurately displaying process variables and
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protection system status to be within permissible limits for
operation.
When plant equipment was found to be inoperable or when equipment was
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removed from service for maintenance, it was properly identified, and
redundant equipment was verified to be operable.
It was also
verified that and applicable limiting conditions for operation were
identified and maintained.
Equipment safety clearance records were complete and indicated that
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affected components were removed from and returned to service in a
correct and approved manner.
Maintenance work requests were initiated for equipment discovered to
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require repair or routine preventive upkeep, appropriate priority was
assigned, and work commenced in a timely manner.
Plant equipment conditions such as cleanliness, leakage, lubrication,
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and cooling water were controlled and adequately maintained.
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Areas of the plant were clean, unobstructed, and free of fire
hazards.
Fire suppression systems and emergency equipment were
maintained in a condition of readiness.
Security measures and radiological controls were adequate.
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The NRC inspectors performed a lineup verification of the following
systems:
"A" Core Spray
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"B" Core Spray
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Service Water Pump House-Pumps and distribution headers
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In preparation for performing the system walk-down of the "A" core spray
system, the RI conducted a review of and comparison between the licensee's
"A" core spray system valve checklist and applicable as-built drawings.
The following documents were reviewed:
System Operating Procedure (SOP) 2.2.9, " Core Spray System,"
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Revision 26, dated August 1,1985; Appendix A, " Valve Checklist."
As-built drawing - NPPD 1.D.-7; for the core spray system
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As-built drawing - NPPD 1.D.-21; for the core spray system
.
As-built drawing - GE 117C3303; for the core spray system
.
S0P 2.2.74, " Standby Liquid Control System," Revision 15, dated
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August 1,1985; Appendix A, " Valve Checklist."
As-built drawing - B&R 2045; for the standby liquid control system
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As-built drawing - NPPD 1.D.-13; for the standby liquid control
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system
As-built drawing - GE 117C3314; for the standby liquid control system
.
The above review identified the following discrepancies:
50P 2.2.9, Appendix A, listed 32 instrument-related valves that were
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not numbered or labeled on applicable as-built drawings 1.D.-7,
1.D-21, or 117C3303.
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50P 2.2.74, Appendix A, listed 4 instrument related valves that were
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not numbered or labeled on applicable as-built drawings 2045,
1.D.-13, 117C3314.
The RI included a review of the documents associated with the standby
liquid control (SLC) system during this inspection period as a followup to
an unresolved item (298/8610-01) that was identified in NRC Inspection
Report 50-298/86-10.
As noted above, the "A" core spray system and SLC
system exhibit similar deficiencies in their respective as-built drawings.
10 CFR Part 50, Appendix B, Criterion V, requires that activities
affecting quality shall be accomplished in accordance with these drawings.
The licensee's failure to have instrument valves labeled on as-built
drawings is an apparent violation.
(298/8614-01)
Based upon the above violation, Unresolved Item 298/8610-01 is closed for
record purposes.
The tours, reviews, and observations are conducted to verify that facility
operations were performed in accordance with the requirements established
in the CNS Operating License and TS.
One violation was identified in this area.
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6.
Monthly Surveillance Observations
The NRC inspectors observed TS required surveillance tests.
The
observations verified that:
Tests were accomplished by qualified personnel in accordance with
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approved procedures.
Procedures conformed to TS requirements.
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Test prerequisites were completed including conformance with
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applicable limiting conditions for operation, required administrative
approval, and availability of calibrated test equipment.
Test data was reviewed for completeness, accuracy, and conformance
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with established criteria and TS requirements.
Deficiencies were corrected in a timely manner.
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The system was returned to service.
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The RI observed the following surveillance tests on the dates indicated:
April 10, 1986; SP 6.1.25, Revision 18, dated August 22, 1985, "RBM
.
Calibration and Functional / Functional Test"
April 5, 1986; SP 6.2.2.5.12, Revision 10, dated November 13, 1984,
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"RHR Loop A & B Pump and Valve Control Logic Functional Test"
April 10, 1986; SP 6.3.1.8, Revision 4, dated October 9, 1984,
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" Electrical Penetrations Leak Check"
During the RI's observation of Procedure SP 6.1.25, he observed that the
individual performed channel "A" of the surveillance test correctly.
The
same individual failed to follow the procedure during performance of the
channel "B"
test.
During the RI's observation of Procedure SP 6.2.2.5.12,
another individual performed the surveillance test on RHR loop "A",
pump
"A" correctly; however, that individual failed to follow the procedure
during performance of the RHR loop "A", pump "B"
test.
During the
observation of SP 6.3.1.8, the RI observed that a third individual failed
to follow the procedure.
CNS Procedure 0.4, " Preparation, Review, and
Approval of Procedures," Revision 4, dated February 21, 1986, states that
approved written procedure shall be adhered to by all station personnel.
The licensee's failure to follow procedures is an apparent violation.
(50-298/8614-02)
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During this inspection period, the SRI observed that licensee
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administrative personnel did not ensure the review, approval, and
distribution of corrected pages to numerous safety-related surveillance
procedures in accordance with the requirements of CNS Procedure 0.4,
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" Preparation, Review, and Approval of Procedures," Revision 5.
Procedure 0.4 required that revisions to station procedures be initiated
using a Procedure Change Notice (Attachment A to Procedure 0.4).
The
change notice is to identify required changes, affected plant procedures,
and required reviews and approvals including the originating individual,
responsible section manager, 50RC, and Division Manager of Nuclear
<
Operations.
Upon completion of necessary reviews and approvals, the
revision is typed, printed, and distributed.
Controlled distribution is
accomplished using an attached Document Transmittal form which includes
signature and date blanks to signify that the identified revisioa is
received and incorporated into the appropriate controlled document (s).
The transmittal sheet is then returned to the document custodian.
.
i
Procedure 0.4 took exception to using a Procedure Change Notice for
clerical errors discovered after the original procedure was reviewed and
approved.
However, clerical changes were not defined, and it was found
that technical corrections had been made to the following procedures
without the same review and approval as the original documents received.
50P 2.1.10, " Station Power Changes," Attachment B
.
SP 6.1.19, "LPRM Calibration Test," Attachment B, Page 5 of 6
.
SP 6.1.21A, "SRM Calibration and Functional Test (Reactor In Run),"
.
Step 15.C
SP 6.3.8.2, "SLC Pump Operability Test," Attachment C
.
SP 6.4.8.6, " Reactor Building Differential Pressure Loop Checks,"
.
Attachment A, Page 2 of 2
10 CFR Part 50, Appendix B, Criterion VI and the licensee's approved QA
plan require that procedure changes be reviewed and approved by the same
organization that performed the original review.
Although the provision
of Procedure 0.4 which allowed clerical changes is acceptable, the failure
to define clerical changes led to technical information corrections which
were not reviewed and approved as required.
This.is an apparent
violation.
(298/8614-03)
The reviews and observations were conducted to verify that facility
surveillance operations were performed in accordance with the requirements
established in the CNS Operating License and TS.
Two violations were identified in this area.
7.
Monthly Maintenance Observation
i
The SRI observed preventive and corrective maintenance activities.
These
observations verified that:
4
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Limiting conditions for operation were met.
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Redundant equipment was operable.
.
Equipment was adequately isolated and safety-tagged.
.
Appropriate a6ministrative approvals were obtained prior to
.
commencement of work activities.
Work was performed by nualified personnel in accordance with approved
.
procedures.
Radiologic &l controls, cleanliness practices, and appropriate fire
.
prevention prec.autions were implemented and maintained.
Quality control checks and postmaintenance surveillance testing were
.
performed as required.
Equipment was properly returned to service.
.
Those reviews and cbservations were conducted to veri,fy that facility
maintenance operations were performed in accordance with the requirements
established in the CNS Operating License and TS.
No violations or deviations were identified in this area.
8.
Unresolved Items
An unresolved item is an item about which additional information is
required in order to determine if the item is a violation, a deviation,
or acceptable. There are two unresolved items in the attachment to
Appendix C of this report.
9.
Spent Fuel Shipment
Included as safeguards attachment to this report.
10.
Exit Meetings
Exit meetings were conducted at the conclusion of each portion of the
inspection. The NRC inspectors summarized the scope and findings of each
inspection segment at those meetings.
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