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{{Adams | |||
| number = ML20195F263 | |||
| issue date = 06/03/1986 | |||
| title = Partially Withheld Insp Rept 50-285/86-07 on 860301-31 (Ref 10CFR73.21).Violation Noted:Failure to Maintain Vital Area Security Barrier in Accordance W/Regulations | |||
| author name = Harrell P, Hunter D | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000285 | |||
| license number = | |||
| contact person = | |||
| document report number = 50-285-86-07, 50-285-86-7, NUDOCS 8606110263 | |||
| package number = ML20195F258 | |||
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | |||
| page count = 10 | |||
}} | |||
See also: [[see also::IR 05000285/1986007]] | |||
=Text= | |||
{{#Wiki_filter:_ _ . _ . _ _ _ _ _ - | |||
' | |||
. | |||
APPENDIX B | |||
U. S. NUCLEAR REGULATORY COMMISSION | |||
REGION IV | |||
NRC Inspection Report: 50-285/86-07 Licensa: DPR-40 | |||
Docket: 50-285 | |||
Licensee: Omaha Public Power District | |||
1623 Harney Street | |||
Omaha, Nebraska 68102 | |||
Facility Name: Fort Calhoun Station | |||
Inspection At: Fort Calhoun Station, Blair, Nebraska | |||
Inspection Conducted: March 1-31, 1986 | |||
Inspector: _ | |||
4 p4 | |||
P.' H. HarreYl, Tenipf Resident Reactor D6ter | |||
Inspector | |||
Approved: | |||
D. R. Hunter, Chief, Project Section B, Date | |||
3/8 | |||
Reactor Projects Branch | |||
, | |||
Inspection Sumary | |||
Inspection Conducted March 1-31, 1986 (Report 50-285/86-07) | |||
Areas Inspected: Routine, unannounced inspection including operational safety | |||
verification, maintenance, surveillance, plant tours, safety-related system | |||
walkdowns, followup on previously identified items, followup on licensee event | |||
reports, and review of plant procedures program. | |||
Results: Within the eight areas inspected, one violation (failure to maintain | |||
a vital area security barrier in accordance with regulations, Appendix A) was | |||
identified. | |||
S | |||
TION. | |||
NI102s3 $ | |||
ENCLOSURE CONTAINSAFEGUAR | |||
HIS | |||
Q | |||
ADOC8 | |||
p | |||
$ UPON | |||
PAGE | |||
SEPARATION TIS DE00NTROLL | |||
. . . . . . . . . . . | |||
* | |||
. | |||
-2- | |||
DETAILS | |||
1. Persons Contacted | |||
*R. Andrews, Nuclear Production Division Manager | |||
*C Brunnert, Quality Assurance Supervisor | |||
*M. Core, Maintenance Supervisor | |||
J. Foley, I&C and Electrical Field Maintenance Supervisor | |||
W. Gates, Plant Manager | |||
R. Johansen, Test Engineer | |||
M. Kallman, Security Supervisor | |||
L. Kusek, Operations Supervisor | |||
*T. McIvor, Technical Supervisor | |||
R. Mueller, Plant Engineer | |||
*D. Hunderloh, Licensing Engineer | |||
*G. Roach, Chemical and Radiation Protection Supervisor | |||
J. Tesarek, Reactor Engineer | |||
*D. Trausch, Operations Engineer | |||
*S. Willrett, Administration Services and Security Supervisor | |||
* Denotes attendance at the monthly exit interview. | |||
The inspector also contacted other plant personnel, including operators, | |||
technicians, and administrative personnel. | |||
' | |||
2. Followup on Previously Identified Items | |||
(Closed) Unresolved Item 285/8002-01: Licensee to provide data for | |||
containment leakrate test. | |||
The licensee has provided the data as requested by the NRC | |||
l | |||
inspector. No additional action is required. | |||
l (Closed) Severity Level IV Violation 285/8415-01: Failure to inspect | |||
critical quality equipment (CQE) material. | |||
' | |||
The licensee has reviewed all open CQE requisitions / purchase | |||
orders to verify that no other material, other than that | |||
identified by the NRC inspector, had entered the plant without | |||
the proper receipt inspection. The results of the review | |||
, | |||
indicate that no other material was installed in the plant | |||
' | |||
without the proper receipt inspection being performed. The | |||
licensee has also taken actions to prevent recurrence of this | |||
problem. The actions taken include installing a sign at the | |||
plant entrance to warn personnel not to bring material in the | |||
plant without the proper receipt inspection, enhancing CQE | |||
receipt inspection requirements at general employee training | |||
sessions, and instructing security guards not to allow material | |||
received during off-normal hours to enter the plant. The | |||
l | |||
ENCLOSUF2 CONIAINS | |||
SAFEGUARDS INFOR'IATIO:!. | |||
UPON SEPARATION THIS | |||
PAGE IS DECONTROLLED. | |||
l | |||
. - _ _ _ _ . - _ | |||
I | |||
. | |||
-3- | |||
licensee has made the appropriate procedure changes to include | |||
the requirements. The NRC inspector has reviewed the actions | |||
listed above to verify that the actions were appropriately | |||
completed. No problems were noted. | |||
(Closed) Severity Level IV Violation 285/8515-03: Failure to perform | |||
routine surveillance for toxic gas monitors. | |||
The licensee has revised Form FC-71 to include a requirement for | |||
recording toxic monitor readings on a shift basis. The NRC | |||
inspector reviewed Form FC-71 and verified the form was changed | |||
and that the readings were being recorded. The NRC inspector | |||
also reviewed other changes in the Technical Specification | |||
amendments to verify that the licensee has properly incorporated | |||
the requirements into appropriate procedures. No problems were | |||
noted during the review. | |||
(Closed) Deviation 285/8527-01: Failure to meet a commitment relative | |||
to the cleanliness of fluid systems. | |||
To ensure that personnel involved in establishing cleanliness | |||
control conditions are aware of all the applicable program | |||
requirements, the licensee issued a memorandum to quality | |||
control, plant engineering, and maintenance personnel. This | |||
memorandum explains what actions are required for maintaining | |||
system cleanliness. The NRC inspector reviewed routine | |||
operational and maintenance activities during this inspection | |||
period to verify tne requirements for system cleanliness were | |||
being met. No problems were noted. | |||
, | |||
(Closed) Severity Level V Violation 285/8527-03: Failure to display | |||
l security badge while in protected area. | |||
The licensee has issued a memo to each badge holder to remind | |||
them of the requirement for displaying their security badges | |||
while inside the protected area. The licensee has also posted | |||
signs .it the entrance to the protected area to remind | |||
individuals of the requirement. The NRC inspector has reviewed | |||
the wearing of security badges by personnel while in the | |||
protected and vi?.al areas. No problems were no+,ed. | |||
j 3. Licensee Event Report (LER) Followup | |||
1 | |||
Through direct observation, 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 has | |||
been accomplished in accordance with Technical Specifications. | |||
The LERs listed below are closed: | |||
ENCLOSURE CONTAINS | |||
SAFEGUARDS INFOR.VATION. | |||
UPON SEPARATION THIS | |||
PAGE IS DECONTROLLED. | |||
- . - - . . , _ . - - _ - _ _ | |||
- | |||
. | |||
-4- | |||
84-020 85-002 | |||
84-023 85-003 | |||
84-025 85-007 | |||
85-001 | |||
LER 84-020 reported the inoperability of hydrogen analyzer VA-81A due to | |||
improper replacement of the catalyst bed / cell. During performance of the | |||
calibration procedure for VA-81A, it was discovered that the analyzer | |||
would not calibrate properly. An investigation was performed and it was | |||
determined that the analyzer catalyst bed / cell had been installed | |||
incorrectly during modification activities. The investigation also noted | |||
that the calibration performed after the modification was completed had | |||
been performed incorrectly by the technician due to the technician failing | |||
to follow the procedure. The catalyst bed / cell was immediately | |||
reinstalled correctly and calibrated to verify operation. The licensee | |||
appropriately disciplined the technician for failing to correctly follow | |||
procedure. The licensee revised the analyzer calibration procedure to | |||
provide further assurance against a recurrence of the problem. The | |||
licensee also issued a postmaintenance operability check procedure for the | |||
analyzers. To ensure that postmaintenance operability checks are | |||
performed on plant equipment, the licensee has added a blank to the | |||
maintenance order form for quality control personnel to sign to verify the | |||
necessary operability checks have been performed. The NRC inspector | |||
reviewed the actions taken by the licensee in this area and noted no | |||
problems. | |||
LERs 84-023, 84-025, and 85-002 reported initiation of the ventilation | |||
isolation actuation system (VIAS) due to leaks in various systems caused | |||
by different problems. LER 84-023 discussed five VIAS initiations due to | |||
leakage from the pressurizer spray valve. The initiation occurred while | |||
shutting down the plant to repair the spray valve leakage. | |||
LER 84-025 reported a VIAS initiation due to a leaking valve in the waste | |||
: gas vent header. LER 85-002 discussed an initiation of the VIAS due to a | |||
l leak on a charging pump suction line. In each of the above cases, when | |||
l the VIAS initiation occurred, all activities associated with venting | |||
operations were suspended. A search was conducted to locate the source of | |||
the activity and immediate action taken to stop the leak. In each of the | |||
above occurrences, none of the releases experienced exceeded Technical | |||
Specification or 10 CFR Part 20 limits. This was confirmed by analyses | |||
performed by the licensee. | |||
LER 85-001 reported a case where the VIAS was initiated due to a chemistry | |||
technician purging the reactor coolant sample line in preparation for | |||
drawing a sample. The chemistry technician purged the line too long, | |||
causing a buildup of radioactive gasses released by the reactor coolant. | |||
This buildup of gasses initiated a VIAS. There was no release exceeding | |||
Technical Specification or 10 CFR Part 20 limits as determined by a | |||
l | |||
licensee analysis. A review of procedures and sampling operations was | |||
performed. No problems were identified. The importance of not greatly | |||
exceeding minimum purge times was emphasized to the plant staff. | |||
ENCLOSURE CONTAINS | |||
' | |||
SAFEGUARDS INFORMATION. | |||
( UPON SEPARATION THIS | |||
PAGE IS DECONTRnT m. | |||
. | |||
-5- | |||
LER 85-003 reported an actuation of the VIAS during the transfer of spent | |||
resin. The VIAS initiation was caused when the ion exchanger was purged | |||
with nitrogen gas after the resin had been transferred to the spent resin | |||
storage tank. When the nitrogen gas purge was performed, a mixture of | |||
nitrogen / radioactive gas carried through the drain line, causing an | |||
actuation of the VIAS. During this transfer operation, the VIAS was | |||
initiated twice, each time for the same reason. In each case, the | |||
licensee performed an analysis to verify the release to the atmosphere did | |||
not exceed Technical Specification or 10 CFR Part 20 limits. A review was | |||
performed of the controlling procedure and the actual operation. No | |||
problems were noted. This evolution has been performed since this | |||
occurrence without a VIAS initiation. | |||
LER 85-007 reported the initiation of the VIAS during a refueling | |||
shutdown. The licensee was in the process of testing the containment | |||
stack gas monitor to prove operability. The test was being performed in | |||
accordance with Si approved procedure. The procedure required that | |||
containment pressure be reduced to atmospheric before opening the purge | |||
valves. Due to an inaccurate indication, containment pressure was | |||
slightly greater than atmospheric when the purge valves were opened. This | |||
caused a VIAS initiation. The licensee performed an analysis to determine | |||
the magnitude of the release. The results indicated that no Technical | |||
Specification or 10 CFR Part 20 limits were exceeded. | |||
No violations or deviations were identified. | |||
4. Operational Safety Verification | |||
The NRC inspector conducted the reviews and observations described below | |||
to verify that facility operations were performed in conformance with the | |||
requirements established under 10 CFR, administrative procedures, and the | |||
Technical Specifications. The NRC inspector made several control room | |||
observations to verify: | |||
. Proper shift staffing. | |||
. Operator adherence to approved procedures and Technical | |||
Specifications. | |||
. Operability of reactor protective system and engineered safeguards | |||
equipment. | |||
. Logs, records, recorder traces, annunciators, panel indications, and | |||
switch positions complied with the appropriate requirements. | |||
. Proper return to service of components. | |||
. | |||
Maintenance orders had been initiated for equipment in need of | |||
maintenance. | |||
ENCLOSURE CONTAINS | |||
SAFEGUARDS INFOITATION. | |||
UPON SEPARATION THIS | |||
PAGE IS DE00NTROI.LF' . | |||
. | |||
-6- | |||
. Appropriate conduct of control room and other licensed operators. | |||
No violations or deviations were noted. | |||
5. Plant Tours | |||
The NRC inspector conducted plant tours at various times to assess plant | |||
and equipment conditions. The following items were observed during the | |||
tours: | |||
. General plant conditions. | |||
. Equipment conditions including fluid leaks and excessive vibration. | |||
. Plant housekeeping and cleanliness practices including fire hazards | |||
and control of combustible material. | |||
. The physical security plan was being implemented in accordance with | |||
the station security plan. | |||
. Adherence to the requirements of radiation work permits. | |||
. Work activities being performed in accordance with approved | |||
procedures. | |||
During a tour of the plant, the NRC inspector noted that a vital area | |||
security barrier was not being maintained in accordance with regulations. | |||
The discussion of the details of this occurrence contains safeguard | |||
information, as defined by 10 CFR Part 73.21; therefore, the details are | |||
discussed in Appendix A of this inspection r6 port. | |||
6. Safety-Related System Walkdowns | |||
l The NRC inspector walked down accessible portions of the following | |||
safety-related systems to verify system operability. Operability was | |||
i determined by verification of valve and/or switch positions. The systems | |||
were walked down using the drawings and procedures noted: | |||
. Fire protection system (Drawing 11405-M-266, Revision 31 and | |||
Procedure OI-FP-6, Revision 46). | |||
t | |||
' | |||
. | |||
Electrical distribution, 480-volt system (Drawing 8.1-1, Revision 21, | |||
and Procedure OI-EE-2, Revision 8). | |||
i . Electrical distribution, 125 volt DC system (Drawing 8.1-1, | |||
Revision 21, and Procedure OI-EE-3, Revision 17). | |||
: | |||
l M CONTATNS | |||
l SAFEGUARDS INFORMATION, | |||
UPON SEPARATION THIS | |||
l PAGE IS DE00NTROI.LFD. | |||
L | |||
. | |||
-7- | |||
. Electrical distribution, 125-volt AC system (Drawing 8.1-1, | |||
Revision 21 and Procedure OI-EE-4, Revision 24). | |||
During the walkdown of the fire protection system, the NRC inspector noted | |||
minor discrepancies of an editorial nature between the drawings, | |||
procedures, and plant as-built conditions. None of the conditions noted | |||
affected the operability or safe operation of the system. Licensee | |||
personnel stated that the noted minor discrepancies would be corrected. | |||
During the walkdown of the electrical distribution system, numerous | |||
apparent discrepancies were noted on the procedures and the electrical | |||
distribution one-line diagram. None of the noted discrepancies affected | |||
the operability or safe operation of the system. However, the apparent | |||
discrepancies affect the correctness of the procedures and the drawing. | |||
At the end of this inspection period, the discussion regarding the | |||
apparent discrepancies had not been completed. For this reason, this | |||
portion of the inspection will be completed during the next inspection | |||
period. | |||
No violations or deviations were identified. | |||
7. Monthly Maintenance Observation | |||
The NRC inspector reviewed station maintenance activities of | |||
safety-related systems and components to verify the maintenance was | |||
conducted in accordance with approved procedures, regulatory requirements, | |||
and the Technical Specifications. The following items were considered | |||
during the reviews: | |||
. The limiting conditions for operation were met while systems or | |||
components were removed from service. | |||
. Approvals were obtained prior to initiating the work. | |||
. Activities were accomplished using approved maintenance orders (MO) | |||
and were inspected, as applicable. | |||
. Functional testing and/or calibrations 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 and fire prevention controls were implemented. | |||
The NRC inspector reviewed the following maintenance activities: | |||
NSURE CONTAINS | |||
SAFEGUARDS INFORMATION | |||
MR SEPARATION THIS | |||
PAGE IS DECONTROTm. | |||
- | |||
. | |||
-8- | |||
, | |||
. Repairing of a gasket leak on high pressure safety injection valve | |||
HCV-383-4 (M0 854112). | |||
. Repairing of a fire barrier penetration (M0 854210). | |||
. Cleaning of letdown control valve LCV-101-1 (M0 854227). | |||
. Rebuilding air regulator for steam supply to auxiliary feed pump | |||
valve YCV-1045A (M0 857014). | |||
. Repairing seal leaks on charging pump CH-1A (M0 861214). | |||
. Packing leak repair on high pressure safety injection valve HCV-315 | |||
(MO 854361). | |||
. Repairing of jockey fire pump discharge check valve (M0 861214). | |||
. Adjusting alarm on containment stack monitor RM-051 (M0 854586). | |||
. Repairing of high pressure safety injection isolation valve HCV-2987 | |||
(M0 860725). | |||
No violations or deviations were noted. | |||
8. Monthly Surveillance Observation | |||
The NRC inspector observed the Technical Specification required | |||
surveillance testing on safety-related systems and components. The NRC | |||
inspector verified the following items during the testing: | |||
I . Testing was performed using approved procedures. | |||
. Test instrumentation was calibrated. | |||
. Limiting conditions- for operation were met. | |||
. Removal and restoration of the affected system and/or component were | |||
accomplished. | |||
. Test results conformed with Technical Specification and procedure | |||
requirements. | |||
. Test results were reviewed by personnel other than the individual | |||
directing the teet. | |||
. Deficiencies identified during the testing were properly reviewed and | |||
resolved by appropriate management personnel. | |||
The NRC inspector witnessed the following surveillance test activities. | |||
The procedures used for the test activities are noted. | |||
1 | |||
ENCLOSURE CONTAINS | |||
SAFEGUARDS INFOR'ZATION. | |||
UPON SEPARATION THIS | |||
PAGE IS DECONTROLLED. | |||
. _- - -- - - _ , | |||
- . _ . | |||
- | |||
. | |||
-9- | |||
. Containment monitoring isolation valves (ISI-VA-1-F.1). | |||
. Process monitors (ST-RM-2-F.5). | |||
. Emergency diesel generator monthly test (ST-ESF-6-F.2). | |||
The NRC inspector also reviewed the results of other surveillance tests | |||
performed during this inspection period. The review was performed to | |||
verify the tests were completed as required by the Technical | |||
Specifications, regulations, and procedure. No problems were noted with | |||
the 27 completed surveillance tests reviewed. | |||
No violations or deviations were identified. | |||
9. Review of Plant Procedures Program | |||
The NRC inspector performed a review of the plant procedures program to | |||
verify overall plant procedures are in accordance with regulatory | |||
requirements, temporary procedures and procedure changes are made in | |||
accordance with Technical Specification requirements, and the technical | |||
adequacy of the reviewed procedures is consistent with desired actions and | |||
modes of operation. The review included the following items: | |||
. Procedure changes were made to reflect Technical Specification or | |||
license revisions. | |||
; . Changes made to procedures were in conformance with 10 CFR | |||
' | |||
Part 50.59 requirements. | |||
. Temporary procedures were properly approved and did not conflict with | |||
Technical Specification requirements. | |||
The NRC inspector reviewed the procedures listed below: | |||
Number Title Revision | |||
OP-1 Master Checklist for Startup or Trip 24 | |||
Recovery | |||
0P-3 Plant Startup from Hot Standby to 22 | |||
Minimum Load | |||
01-SI-l Safety Injection (Normal Operation) 34 | |||
OI-CH-1 Chemical and Volume Control System 12 | |||
(Normal Operation) | |||
OI-MS-2 Operating Instructions in Steam System 14 | |||
Cold St rtup | |||
OI-RC-4 Reactor Coolant System Normal Shutdown 42 | |||
BCLOSURE CONTAINS | |||
SAFEGUARDS INFORMATION. | |||
UPON SEPARATION THIS | |||
PAGE IS DECONTROLLm. | |||
._. | |||
. | |||
* | |||
, | |||
-10- | |||
. | |||
01-RPS-1 Rea-tor Protective System (Normal 7 | |||
Operation) | |||
A0P-6 Emergency Fire Procedure 0 | |||
A0P-18 Loss of Raw Water 0 | |||
A0P-1 Acts of Nature 0 | |||
A0P-7 Forced Evacuation of Control Room 0 | |||
OP-10-Al Raw Water Supply Header Flow Low 8 | |||
G-17 Maintenance Orders 35 | |||
3 0-22 Containment Access & Egress 2 | |||
MP-CH-24 Letdown Strainer Cleanout 1 | |||
' | |||
MP-IC-2 Incore Instrumentation Guide Tube 1 | |||
Cleaning | |||
MP-MS-1 Main Steam Safety Valve Inspection 11 | |||
and Repair | |||
MP-N0ZDAM-1 Steam Generator Nozzle Dam 2 | |||
Installation Procedure | |||
MP-SCIV-1-B Repacking of HCV-347 and HCV-348 1 | |||
No violations or deviations were identified. | |||
10. Exit Interview | |||
i | |||
The NRC inspector met with Mr. R. L. Andrews and other members of the OPPD | |||
staff at the end of this inspection. At this meeting, the inspector | |||
summarized the scope of the inspection and the findings. | |||
i | |||
l | |||
! | |||
pSURE CONTAINS . | |||
SAFEGUARDS INFORMATI | |||
UPON SEPARATION DilS | |||
PAGE IS DECONTROGG- | |||
. - . - . .-. . - . _. . - - - _--._. | |||
}} |
Latest revision as of 13:49, 16 December 2020
ML20195F263 | |
Person / Time | |
---|---|
Site: | Fort Calhoun ![]() |
Issue date: | 06/03/1986 |
From: | Harrell P, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | |
Shared Package | |
ML20195F258 | List: |
References | |
50-285-86-07, 50-285-86-7, NUDOCS 8606110263 | |
Download: ML20195F263 (10) | |
See also: IR 05000285/1986007
Text
_ _ . _ . _ _ _ _ _ -
'
.
APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-285/86-07 Licensa: DPR-40
Docket: 50-285
Licensee: Omaha Public Power District
1623 Harney Street
Omaha, Nebraska 68102
Facility Name: Fort Calhoun Station
Inspection At: Fort Calhoun Station, Blair, Nebraska
Inspection Conducted: March 1-31, 1986
Inspector: _
4 p4
P.' H. HarreYl, Tenipf Resident Reactor D6ter
Inspector
Approved:
D. R. Hunter, Chief, Project Section B, Date
3/8
Reactor Projects Branch
,
Inspection Sumary
Inspection Conducted March 1-31, 1986 (Report 50-285/86-07)
Areas Inspected: Routine, unannounced inspection including operational safety
verification, maintenance, surveillance, plant tours, safety-related system
walkdowns, followup on previously identified items, followup on licensee event
reports, and review of plant procedures program.
Results: Within the eight areas inspected, one violation (failure to maintain
a vital area security barrier in accordance with regulations, Appendix A) was
identified.
S
TION.
NI102s3 $
ENCLOSURE CONTAINSAFEGUAR
HIS
Q
ADOC8
p
$ UPON
PAGE
SEPARATION TIS DE00NTROLL
. . . . . . . . . . .
.
-2-
DETAILS
1. Persons Contacted
- R. Andrews, Nuclear Production Division Manager
- C Brunnert, Quality Assurance Supervisor
- M. Core, Maintenance Supervisor
J. Foley, I&C and Electrical Field Maintenance Supervisor
W. Gates, Plant Manager
R. Johansen, Test Engineer
M. Kallman, Security Supervisor
L. Kusek, Operations Supervisor
- T. McIvor, Technical Supervisor
R. Mueller, Plant Engineer
- D. Hunderloh, Licensing Engineer
- G. Roach, Chemical and Radiation Protection Supervisor
J. Tesarek, Reactor Engineer
- D. Trausch, Operations Engineer
- S. Willrett, Administration Services and Security Supervisor
- Denotes attendance at the monthly exit interview.
The inspector also contacted other plant personnel, including operators,
technicians, and administrative personnel.
'
2. Followup on Previously Identified Items
(Closed) Unresolved Item 285/8002-01: Licensee to provide data for
containment leakrate test.
The licensee has provided the data as requested by the NRC
l
inspector. No additional action is required.
l (Closed) Severity Level IV Violation 285/8415-01: Failure to inspect
critical quality equipment (CQE) material.
'
The licensee has reviewed all open CQE requisitions / purchase
orders to verify that no other material, other than that
identified by the NRC inspector, had entered the plant without
the proper receipt inspection. The results of the review
,
indicate that no other material was installed in the plant
'
without the proper receipt inspection being performed. The
licensee has also taken actions to prevent recurrence of this
problem. The actions taken include installing a sign at the
plant entrance to warn personnel not to bring material in the
plant without the proper receipt inspection, enhancing CQE
receipt inspection requirements at general employee training
sessions, and instructing security guards not to allow material
received during off-normal hours to enter the plant. The
l
ENCLOSUF2 CONIAINS
SAFEGUARDS INFOR'IATIO:!.
UPON SEPARATION THIS
PAGE IS DECONTROLLED.
l
. - _ _ _ _ . - _
I
.
-3-
licensee has made the appropriate procedure changes to include
the requirements. The NRC inspector has reviewed the actions
listed above to verify that the actions were appropriately
completed. No problems were noted.
(Closed) Severity Level IV Violation 285/8515-03: Failure to perform
routine surveillance for toxic gas monitors.
The licensee has revised Form FC-71 to include a requirement for
recording toxic monitor readings on a shift basis. The NRC
inspector reviewed Form FC-71 and verified the form was changed
and that the readings were being recorded. The NRC inspector
also reviewed other changes in the Technical Specification
amendments to verify that the licensee has properly incorporated
the requirements into appropriate procedures. No problems were
noted during the review.
(Closed) Deviation 285/8527-01: Failure to meet a commitment relative
to the cleanliness of fluid systems.
To ensure that personnel involved in establishing cleanliness
control conditions are aware of all the applicable program
requirements, the licensee issued a memorandum to quality
control, plant engineering, and maintenance personnel. This
memorandum explains what actions are required for maintaining
system cleanliness. The NRC inspector reviewed routine
operational and maintenance activities during this inspection
period to verify tne requirements for system cleanliness were
being met. No problems were noted.
,
(Closed) Severity Level V Violation 285/8527-03: Failure to display
l security badge while in protected area.
The licensee has issued a memo to each badge holder to remind
them of the requirement for displaying their security badges
while inside the protected area. The licensee has also posted
signs .it the entrance to the protected area to remind
individuals of the requirement. The NRC inspector has reviewed
the wearing of security badges by personnel while in the
protected and vi?.al areas. No problems were no+,ed.
j 3. Licensee Event Report (LER) Followup
1
Through direct observation, 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 has
been accomplished in accordance with Technical Specifications.
The LERs listed below are closed:
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LER 84-020 reported the inoperability of hydrogen analyzer VA-81A due to
improper replacement of the catalyst bed / cell. During performance of the
calibration procedure for VA-81A, it was discovered that the analyzer
would not calibrate properly. An investigation was performed and it was
determined that the analyzer catalyst bed / cell had been installed
incorrectly during modification activities. The investigation also noted
that the calibration performed after the modification was completed had
been performed incorrectly by the technician due to the technician failing
to follow the procedure. The catalyst bed / cell was immediately
reinstalled correctly and calibrated to verify operation. The licensee
appropriately disciplined the technician for failing to correctly follow
procedure. The licensee revised the analyzer calibration procedure to
provide further assurance against a recurrence of the problem. The
licensee also issued a postmaintenance operability check procedure for the
analyzers. To ensure that postmaintenance operability checks are
performed on plant equipment, the licensee has added a blank to the
maintenance order form for quality control personnel to sign to verify the
necessary operability checks have been performed. The NRC inspector
reviewed the actions taken by the licensee in this area and noted no
problems.
LERs84-023, 84-025, and 85-002 reported initiation of the ventilation
isolation actuation system (VIAS) due to leaks in various systems caused
by different problems. LER 84-023 discussed five VIAS initiations due to
leakage from the pressurizer spray valve. The initiation occurred while
shutting down the plant to repair the spray valve leakage.
LER 84-025 reported a VIAS initiation due to a leaking valve in the waste
- gas vent header. LER 85-002 discussed an initiation of the VIAS due to a
l leak on a charging pump suction line. In each of the above cases, when
l the VIAS initiation occurred, all activities associated with venting
operations were suspended. A search was conducted to locate the source of
the activity and immediate action taken to stop the leak. In each of the
above occurrences, none of the releases experienced exceeded Technical
Specification or 10 CFR Part 20 limits. This was confirmed by analyses
performed by the licensee.
LER 85-001 reported a case where the VIAS was initiated due to a chemistry
technician purging the reactor coolant sample line in preparation for
drawing a sample. The chemistry technician purged the line too long,
causing a buildup of radioactive gasses released by the reactor coolant.
This buildup of gasses initiated a VIAS. There was no release exceeding
Technical Specification or 10 CFR Part 20 limits as determined by a
l
licensee analysis. A review of procedures and sampling operations was
performed. No problems were identified. The importance of not greatly
exceeding minimum purge times was emphasized to the plant staff.
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LER 85-003 reported an actuation of the VIAS during the transfer of spent
resin. The VIAS initiation was caused when the ion exchanger was purged
with nitrogen gas after the resin had been transferred to the spent resin
storage tank. When the nitrogen gas purge was performed, a mixture of
nitrogen / radioactive gas carried through the drain line, causing an
actuation of the VIAS. During this transfer operation, the VIAS was
initiated twice, each time for the same reason. In each case, the
licensee performed an analysis to verify the release to the atmosphere did
not exceed Technical Specification or 10 CFR Part 20 limits. A review was
performed of the controlling procedure and the actual operation. No
problems were noted. This evolution has been performed since this
occurrence without a VIAS initiation.
LER 85-007 reported the initiation of the VIAS during a refueling
shutdown. The licensee was in the process of testing the containment
stack gas monitor to prove operability. The test was being performed in
accordance with Si approved procedure. The procedure required that
containment pressure be reduced to atmospheric before opening the purge
valves. Due to an inaccurate indication, containment pressure was
slightly greater than atmospheric when the purge valves were opened. This
caused a VIAS initiation. The licensee performed an analysis to determine
the magnitude of the release. The results indicated that no Technical
Specification or 10 CFR Part 20 limits were exceeded.
No violations or deviations were identified.
4. Operational Safety Verification
The NRC inspector conducted the reviews and observations described below
to verify that facility operations were performed in conformance with the
requirements established under 10 CFR, administrative procedures, and the
Technical Specifications. The NRC inspector made several control room
observations to verify:
. Proper shift staffing.
. Operator adherence to approved procedures and Technical
Specifications.
. Operability of reactor protective system and engineered safeguards
equipment.
. Logs, records, recorder traces, annunciators, panel indications, and
switch positions complied with the appropriate requirements.
. Proper return to service of components.
.
Maintenance orders had been initiated for equipment in need of
maintenance.
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. Appropriate conduct of control room and other licensed operators.
No violations or deviations were noted.
5. Plant Tours
The NRC inspector conducted plant tours at various times to assess plant
and equipment conditions. The following items were observed during the
tours:
. General plant conditions.
. Equipment conditions including fluid leaks and excessive vibration.
. Plant housekeeping and cleanliness practices including fire hazards
and control of combustible material.
. The physical security plan was being implemented in accordance with
the station security plan.
. Adherence to the requirements of radiation work permits.
. Work activities being performed in accordance with approved
procedures.
During a tour of the plant, the NRC inspector noted that a vital area
security barrier was not being maintained in accordance with regulations.
The discussion of the details of this occurrence contains safeguard
information, as defined by 10 CFR Part 73.21; therefore, the details are
discussed in Appendix A of this inspection r6 port.
6. Safety-Related System Walkdowns
l The NRC inspector walked down accessible portions of the following
safety-related systems to verify system operability. Operability was
i determined by verification of valve and/or switch positions. The systems
were walked down using the drawings and procedures noted:
. Fire protection system (Drawing 11405-M-266, Revision 31 and
Procedure OI-FP-6, Revision 46).
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Electrical distribution, 480-volt system (Drawing 8.1-1, Revision 21,
and Procedure OI-EE-2, Revision 8).
i . Electrical distribution, 125 volt DC system (Drawing 8.1-1,
Revision 21, and Procedure OI-EE-3, Revision 17).
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. Electrical distribution, 125-volt AC system (Drawing 8.1-1,
Revision 21 and Procedure OI-EE-4, Revision 24).
During the walkdown of the fire protection system, the NRC inspector noted
minor discrepancies of an editorial nature between the drawings,
procedures, and plant as-built conditions. None of the conditions noted
affected the operability or safe operation of the system. Licensee
personnel stated that the noted minor discrepancies would be corrected.
During the walkdown of the electrical distribution system, numerous
apparent discrepancies were noted on the procedures and the electrical
distribution one-line diagram. None of the noted discrepancies affected
the operability or safe operation of the system. However, the apparent
discrepancies affect the correctness of the procedures and the drawing.
At the end of this inspection period, the discussion regarding the
apparent discrepancies had not been completed. For this reason, this
portion of the inspection will be completed during the next inspection
period.
No violations or deviations were identified.
7. Monthly Maintenance Observation
The NRC inspector reviewed station maintenance activities of
safety-related systems and components to verify the maintenance was
conducted in accordance with approved procedures, regulatory requirements,
and the Technical Specifications. The following items were considered
during the reviews:
. The limiting conditions for operation were met while systems or
components were removed from service.
. Approvals were obtained prior to initiating the work.
. Activities were accomplished using approved maintenance orders (MO)
and were inspected, as applicable.
. Functional testing and/or calibrations 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 and fire prevention controls were implemented.
The NRC inspector reviewed the following maintenance activities:
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. Repairing of a gasket leak on high pressure safety injection valve
HCV-383-4 (M0 854112).
. Repairing of a fire barrier penetration (M0 854210).
. Cleaning of letdown control valve LCV-101-1 (M0 854227).
. Rebuilding air regulator for steam supply to auxiliary feed pump
valve YCV-1045A (M0 857014).
. Repairing seal leaks on charging pump CH-1A (M0 861214).
. Packing leak repair on high pressure safety injection valve HCV-315
(MO 854361).
. Repairing of jockey fire pump discharge check valve (M0 861214).
. Adjusting alarm on containment stack monitor RM-051 (M0 854586).
. Repairing of high pressure safety injection isolation valve HCV-2987
(M0 860725).
No violations or deviations were noted.
8. Monthly Surveillance Observation
The NRC inspector observed the Technical Specification required
surveillance testing on safety-related systems and components. The NRC
inspector verified the following items during the testing:
I . Testing was performed using approved procedures.
. Test instrumentation was calibrated.
. Limiting conditions- for operation were met.
. Removal and restoration of the affected system and/or component were
accomplished.
. Test results conformed with Technical Specification and procedure
requirements.
. Test results were reviewed by personnel other than the individual
directing the teet.
. Deficiencies identified during the testing were properly reviewed and
resolved by appropriate management personnel.
The NRC inspector witnessed the following surveillance test activities.
The procedures used for the test activities are noted.
1
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. Containment monitoring isolation valves (ISI-VA-1-F.1).
. Process monitors (ST-RM-2-F.5).
. Emergency diesel generator monthly test (ST-ESF-6-F.2).
The NRC inspector also reviewed the results of other surveillance tests
performed during this inspection period. The review was performed to
verify the tests were completed as required by the Technical
Specifications, regulations, and procedure. No problems were noted with
the 27 completed surveillance tests reviewed.
No violations or deviations were identified.
9. Review of Plant Procedures Program
The NRC inspector performed a review of the plant procedures program to
verify overall plant procedures are in accordance with regulatory
requirements, temporary procedures and procedure changes are made in
accordance with Technical Specification requirements, and the technical
adequacy of the reviewed procedures is consistent with desired actions and
modes of operation. The review included the following items:
. Procedure changes were made to reflect Technical Specification or
license revisions.
- . Changes made to procedures were in conformance with 10 CFR
'
Part 50.59 requirements.
. Temporary procedures were properly approved and did not conflict with
Technical Specification requirements.
The NRC inspector reviewed the procedures listed below:
Number Title Revision
OP-1 Master Checklist for Startup or Trip 24
Recovery
0P-3 Plant Startup from Hot Standby to 22
Minimum Load
01-SI-l Safety Injection (Normal Operation) 34
OI-CH-1 Chemical and Volume Control System 12
(Normal Operation)
OI-MS-2 Operating Instructions in Steam System 14
Cold St rtup
OI-RC-4 Reactor Coolant System Normal Shutdown 42
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01-RPS-1 Rea-tor Protective System (Normal 7
Operation)
A0P-6 Emergency Fire Procedure 0
A0P-18 Loss of Raw Water 0
A0P-1 Acts of Nature 0
A0P-7 Forced Evacuation of Control Room 0
OP-10-Al Raw Water Supply Header Flow Low 8
G-17 Maintenance Orders 35
3 0-22 Containment Access & Egress 2
MP-CH-24 Letdown Strainer Cleanout 1
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MP-IC-2 Incore Instrumentation Guide Tube 1
Cleaning
MP-MS-1 Main Steam Safety Valve Inspection 11
and Repair
MP-N0ZDAM-1 Steam Generator Nozzle Dam 2
Installation Procedure
MP-SCIV-1-B Repacking of HCV-347 and HCV-348 1
No violations or deviations were identified.
10. Exit Interview
i
The NRC inspector met with Mr. R. L. Andrews and other members of the OPPD
staff at the end of this inspection. At this meeting, the inspector
summarized the scope of the inspection and the findings.
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