IR 05000285/1986030: Difference between revisions

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{{Adams
{{Adams
| number = ML20212E706
| number = ML20207S331
| issue date = 12/19/1986
| issue date = 03/16/1987
| title = Insp Rept 50-285/86-30 on 861101-30.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Plant tours,safety-related Sys Walkdown & Security Observations
| title = Ack Receipt of Informing NRC of Actions Taken to Correct Unresolved Item 285/8630-01 Noted in Insp Rept 50-285/86-30
| author name = Harrell P, Hunter D
| author name = Gagliardo J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =  
| addressee name = Andrews R
| addressee affiliation =  
| addressee affiliation = OMAHA PUBLIC POWER DISTRICT
| docket = 05000285
| docket = 05000285
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-285-86-30, NUDOCS 8701050413
| document report number = NUDOCS 8703190280
| package number = ML20212E680
| title reference date = 02-05-1987
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 6
| page count = 2
}}
}}


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=Text=
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APPENDIX U.S. NUCLEAR REGULATORY COMISSION
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3ei MAR 181967 k
In Reply Refer To:
h Docket: 50-285/86-30 Omaha Public Power District
' ATTN:
R. L. Andrews, Division Manager-Nuclear Production i
1623 Harney Street Omaha, Nebraska 1 68102 Gentlemen:
Thank you for your letter of February 5,1987, in response to our letter and notification of Unresolved Item 285/8630-01, dated December 22, 1986. We have reviewed your reply and find it responsive to the concerns raised in the unresolved item. 'We will review the implementation of your actions during a future inspection to determine that full compliance has been achieved and will be maintained.


==REGION IV==
,
NRC Inspection Report:
:
50-285/86-30 License: DPR-40 Docket:
50-285 Licensee:.0maha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name:
Fort Calhoun Station Inspection At:
Fort Calhoun Station, Blair, Nebraska Inspection Conducted:
November 1-30, 1986 Inspector:
'
/ 7--
1 P4 p. H. HarrelV, S#nig Resident Reactor
[ Tate /
'
Inspector Approved:
M iMIifk D. R. Hunter, Chief, Project Section B Date Reactor Projects Branch Inspection Summary Inspection Conducted November 1-30, 1986 (Report 50-285/86-30)
Areas Inspected:
Routine, unannounced inspection including operational safety verification, maintenance, surveillance, plant tours, safety-related system walkdown, and security observations.


Results: Within the six areas inspected, no violations or deviations were identified.
Sincerely,
 
,
8701050413 861222 PDR ADOCK 05000285
Dt18fnal Signed By 2 E. Gaellardo J. E. Gagliardo, Chief Reactor Projects Branch cc:
 
W. G. Gates, Manager
PDR
-
Fort Calhoun Station P. O. Box 399 Fort Calhoun, Nebraska 68023
,
Harry H. Voigt, Esq.


LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW
,
!
Washington, DC 20036 Kansas Radiation Control Program Director
'
flebraska Radiation Control Program Director bec:
(see next page)
SRI PI C
C:RPB
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8703190'280 870316 k
 
PDR ADOCK 05000285
DETAILS 1.
'
 
G PDR
Persons Contacted
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*W. Gates, Plant Manager C. Brunnert, Supervisor, Operations Quality Assurance M. Core, Supervisor, Maintenance J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs J. Foley, Supervisor, I&C and Electrical Field Maintenance M. Kallman, Supervisor, Security L. Kusek, Supervisor, Operations
_ _ _ - - _.
*D. Munderloh, Licensing Engineer T. McIvor, Supervisor, Technical R. Mueller, Plant Engineer G. Roach, Supervisor, Chemical and Radiation Protection J. Tesarek, Reactor Engineer S. Willrett, Supervisor, Administration Services and Security
_ _. _, - - _ _ _, _ _. _. _ ~, -.
* Denotes attendance at the monthly exit interview.
..
 
..
The inspector also contacted other plant personnel, including operators, technicians, and administrative personnel.
..
 
2.
 
Operational Safety Verification The NRC inspector conducted reviews and observations of selected activities to verify that facility operations were performed in conformance with the requirements established under 10 CFR, administrative procedures, and the TS.
 
The NRC inspector made several control room observations to verify:
Proper shift staffing
.
.
Operator adherence to approved procedures and TS requirements
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.
.
Operability of reactor protective system and engineered safeguards
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.
.
equipment Logs, records, recorder traces, annunciators, panel indications, and
.
.
switch positions complied with the appropriate requirements Proper return to service of components
.
.
Maintenance orders (M0) initiated for equipment in need of
.
maintenance Appropriate conduct of control room and other licensed operators
.
.
y.
During an emergency planning (EP) inspection performed by Region IV personnel, the NRC EP inspector noted that the individual designated on the watchbill as the shift supervisor and emergency site director had impaired vision.
This individual had eye surgery for cataracts in the recent past and his vision had not fully recovered to a point where he could pass an eye examination.
The licensee had elected to provide an additional individual licensed as a senior reactor operator onshift with the designated shift supervisor.
The licensee stated that the purpose of adding the individual to the shift was to provide the shift supervisor with assistance, should the need arise, due to the shift supervisor's vision problems.
Following discussions between the licensee management and the NRC SRI on November 21, 1986, the licensee designated the additional senior reactor operator on shif t as the acting shift supervisor.
On November 26, 1986, the licensee filed a report with the NRC in accordance with 10 CFR Part 55.41.


This report provided the NRC with a netification of disability related to the vision impairment of the shift supervisor.
a-N.
 
~ Omaha Public Power District-2-bcctoDMB(IE01)
This item remains unresolved pending review during a subsequent inspection.
bec distrib. by RIV:
 
RPB RRI
(285/8630-01)
No violations or deviations were noted.
 
3.
 
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 Adherence to the requirements of radiation work permits
.
.
Work activities performance in accordance with approved procedures
.R.'D. Martin, RA -
R&SPB Section Chief (RPB/B)
MIS System RIV File DRSP RSTS Operator RSB Project Inspector D. Weiss, RM/ALF R. Hall
.
.
During tours of the plant, the NRC inspector noted the following:
On two different occasions, compressed gas cylinders were observed to
.
be stored in the plant that were not properly secured.


Upon notification by the inspector, the licensee immediately secured the cylinders.
v


During replacement of fire doors, the individuals performing the
_ _ _.. _
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.
.
replacement failed to reinstall the appropriate personnel warning signs.
'i
 
This included signs such as no smoking, no two-way radio
 
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,
EGSM_EI4 MET YdbM kiE
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 1"
,t February 5',
1987
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LIC-87-070
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s transmission allowed, and evacuation when halon fire system alarm j
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sounds. The licensee stated that the signs would be reinstalled in
.
.
s
Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.
'
the appropriate locations.


,
20555 REFERENCE: Docket No. 50-285 Gentlemen:
No violations or deviations were identified.
SUBJECT:
IE Inspection Report 86-30 The Omaha Public Power District received the subject inspection report dated December 22, 1986 containing unresolved item 285/8630-01. This unresolved item concerned the reporting of disabilities of licensed operators in accord-ance with 10 CFR 55.41, as is explained in greater detail within that in-spection report. Of concern was whether the Company had an adequate aware-ness of 10 CFR 55.41 and whether its criteria were being appropriately applied.


.
Ine specifics of the case (relating to a vision impairment of a Fort Calhoun
!tation Shift Supervisor)'rters.were discussed during a meeting on December 22, 1986 at Region IV headqua Present at this meeting were Eric Johnson, Ray Hall, and Ralph Cooley of the NRC and Richard Andrews and Gary Gates of
,
,
4.
l the Company.


Security Observations
The Company has always been aware of the reporting requirements I
,
of 10 CFR 55.41, but lacked the procedural mechanisms to assure a high level of sensitivity to the issue. At this meeting, the Company indicated that actions would be taken to ensure timely NRC notification of any licensed oper-
The NRC inspector verified the physical security plan was being t.
 
<
implemented by selected observation of the following items:
l
'
'
u The security organization is properly manned.
l ator disabilities pursuant to 10 CFR 55.41.


.
The actions taken are as follows:
Personnel within the protected area (PA) display their identification
1.
.
badges.


.
A new administrative standing order has been implemented which pro-l vides clear direction to licensed operators for ensuring the reporting of disabilities.
Vehicles are properly authorized, searched, and escorted or
.
controlled within the PA.


Persons and packages are properly cleared and checked before entry
,
.
.x
into the PA is permitted.


An observation, made by the SRI on November 20, 1986, regarding the apparent failure to search a package, was referred to the NRC physical security inspector, onsite at the time.
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The effectiveness of the security program is maintained when security
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equipment failure or impairment requires compensatory measures to be employed.
,,
 
No violations or deviations were identified.
 
5.
 
Safety-Related System Walkdowns The NRC inspector walked down accessible portions of the following safety-related system to verify system operability. Operability was determined by verification of selected valve and switch positions.
 
The system was walked down using the following drawing and procedure:
Raw water system (Drawing 11405-M-100, Revision 27, and
.
.
Procedure 01-RW-1-CL-A, Revision 14).
Document Control Desk LIC-87-070
 
During the walkdown, the NRC inspector noted minor discrepancies of an editorial nature between the drawing, procedure, and plant as-built conditions for the selected areas checked.
 
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.
 
No violations or deviations were identified, s
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Page Two
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A training " hotline" has been issued to all licensed operators to en-sure an awareness of the requirements of the new standing order.
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7.


Monthly Maintenance Observation
)'
The NRC inspector reviewed and/or observed selected station maintenance activities on safety-related systems and components to verify the maintenance was conducted in accordance with approved procedures,
-
regulatgy requirements, and the TS.
The following items were considered during the reviews and/or observations:
The TS limiting conditions for operation were met while systems or
.
,
,
components were removed from service.
3.


.s Approvals were obtained prior to initiating the work.
Allcurrentlylicensedoperatorshavebeencontactedtofuktherensure.


Activities were accomplished using approved M0s and were inspected,
awareness of and compliance with 10 CFR 55.41.


as applicable.
No additional condi-tions warranting reporting were found during this process.


Functional testing and/or calibrations were performed prior to
The actions taken by the Company will ensure compliance with 10 CFR 55.41 in the future.
.
returning components or systems to service.


Quality control records were maintained.
If you have further questions concerning this matter, please do not hesitate to contact us.


y,
Sincerely,
.
--
fI
k in ? '
.N Activities were accomplished by qualified personnel.
R. L. Andrews Division Manager Nuclear Production RLA/DJM:jmm
'
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LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.


j Parts and materials used were properly certified.
Washington, D.C.


20036
.
.
Radiological and fire prevention controls were implemented.
W. A. Paulson w
 
.
.
The NRC inspector reviewed and/or observed the following maintenance activities:
f~.ETdagliardo
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Intake structure cell valve stem repair (M0 864194)
.
.
a Repair of various plant fire doors (M0 863229)
P.'H''Harrell
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.
Repair of the chemical and volume control system totalizer
,
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l
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(M0 860346)
t Repair of the steam generator pressure alarm circuit (M0 857709)
.
No violations or deviations were noted.
 
8.
 
Monthly Surveillance Observation The NRC inspector observed selected portions of the performance of and/or reviewed completed documentation for the TS required surveillance testing on safety-related systems and components.
 
The NRC inspector verified the following items during the testing:
Testing was performed by qualified personnel using approved
.
procedures.


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Test instrumentation was calibrated.
 
.
The TS limiting conditions for operation were met.
 
.
Removal and restoration of the affected system and/or component were
.
accomplished.
 
Test results conformed with TS and procedure requirements.
 
.
Test results were reviewed by personnel other than the individual
.
directing the test.
 
Deficiencies identified during the testing were properly reviewed and
.
resolved by appropriate management personnel.
 
Thc NRC inspector observed and/or reviewed the documentation forsthe
;
following surveillance test activities.
 
The procedures usea for the test-activities are noted in parenthesis.
 
,
Acoustic monitor circuit check (ST-AC00STIC-1-F.1)
.
Containment narrow-range water level check (ST-CWL-1-F.1)
.
Containment wide-range water level checA (ST-CWL-2-F.1)
.
Containment wide-range pressure indication check (ST-CWP-1-F.1)
.
No violations or deviations were identified.
 
9.
 
Exit Interview The NRC' inspector met with Mr. W. G. Gates (Plant Managsr) and anot'er h
member of the licensee staff at the end of this inspection. At this meeting, the NRC inspector summarized the scope of the inspection and the findings.
 
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Revision as of 19:27, 6 December 2024

Ack Receipt of Informing NRC of Actions Taken to Correct Unresolved Item 285/8630-01 Noted in Insp Rept 50-285/86-30
ML20207S331
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/16/1987
From: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Andrews R
OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8703190280
Download: ML20207S331 (2)
v • d • e


Text

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.

. - - -

-

-.

3ei MAR 181967 k

In Reply Refer To:

h Docket: 50-285/86-30 Omaha Public Power District

' ATTN:

R. L. Andrews, Division Manager-Nuclear Production i

1623 Harney Street Omaha, Nebraska 1 68102 Gentlemen:

Thank you for your letter of February 5,1987, in response to our letter and notification of Unresolved Item 285/8630-01, dated December 22, 1986. We have reviewed your reply and find it responsive to the concerns raised in the unresolved item. 'We will review the implementation of your actions during a future inspection to determine that full compliance has been achieved and will be maintained.

,

Sincerely,

,

Dt18fnal Signed By 2 E. Gaellardo J. E. Gagliardo, Chief Reactor Projects Branch cc:

W. G. Gates, Manager

-

Fort Calhoun Station P. O. Box 399 Fort Calhoun, Nebraska 68023

,

Harry H. Voigt, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW

,

!

Washington, DC 20036 Kansas Radiation Control Program Director

'

flebraska Radiation Control Program Director bec:

(see next page)

SRI PI C

C:RPB

/

j PHHF

cs RPMullikin D N nter JEGagl, tardo 3/l y 3/Q/87 3/)}l81 3/ %/

~

t

,,

.

8703190'280 870316 k

PDR ADOCK 05000285

'

G PDR

,

_ _ _ - - _.

_ _. _, - - _ _ _, _ _. _. _ ~, -.

..

..

..

.

..

-.

.

-.

.

.

.

a-N.

~ Omaha Public Power District-2-bcctoDMB(IE01)

bec distrib. by RIV:

RPB RRI

.

.R.'D. Martin, RA -

R&SPB Section Chief (RPB/B)

MIS System RIV File DRSP RSTS Operator RSB Project Inspector D. Weiss, RM/ALF R. Hall

.

v

_ _ _.. _

_

. *.

.

'i

.

EGSM_EI4 MET YdbM kiE

.-

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 1"

,t February 5',

1987

.4

-

hj ji i gg l ) 1087 j

LIC-87-070

'

j J

t

.

Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.

20555 REFERENCE: Docket No. 50-285 Gentlemen:

SUBJECT:

IE Inspection Report 86-30 The Omaha Public Power District received the subject inspection report dated December 22, 1986 containing unresolved item 285/8630-01. This unresolved item concerned the reporting of disabilities of licensed operators in accord-ance with 10 CFR 55.41, as is explained in greater detail within that in-spection report. Of concern was whether the Company had an adequate aware-ness of 10 CFR 55.41 and whether its criteria were being appropriately applied.

.

Ine specifics of the case (relating to a vision impairment of a Fort Calhoun

!tation Shift Supervisor)'rters.were discussed during a meeting on December 22, 1986 at Region IV headqua Present at this meeting were Eric Johnson, Ray Hall, and Ralph Cooley of the NRC and Richard Andrews and Gary Gates of

,

l the Company.

The Company has always been aware of the reporting requirements I

of 10 CFR 55.41, but lacked the procedural mechanisms to assure a high level of sensitivity to the issue. At this meeting, the Company indicated that actions would be taken to ensure timely NRC notification of any licensed oper-

'

l ator disabilities pursuant to 10 CFR 55.41.

The actions taken are as follows:

1.

A new administrative standing order has been implemented which pro-l vides clear direction to licensed operators for ensuring the reporting of disabilities.

,

.x

l ff;G f

-.- = p _

m s,.

o

.s,..-

,,

.

Document Control Desk LIC-87-070

.

Page Two

,

..

2.

A training " hotline" has been issued to all licensed operators to en-sure an awareness of the requirements of the new standing order.

,

3.

Allcurrentlylicensedoperatorshavebeencontactedtofuktherensure.

awareness of and compliance with 10 CFR 55.41.

No additional condi-tions warranting reporting were found during this process.

The actions taken by the Company will ensure compliance with 10 CFR 55.41 in the future.

If you have further questions concerning this matter, please do not hesitate to contact us.

Sincerely,

--

k in ? '

R. L. Andrews Division Manager Nuclear Production RLA/DJM:jmm

'

c:

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C.

20036

.

W. A. Paulson w

.

f~.ETdagliardo

-

.

P.'HHarrell

.

,

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