ML19248D094
| ML19248D094 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/24/1979 |
| From: | Kelley D, Madsen G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19248D093 | List: |
| References | |
| 50-285-79-07-01, 50-285-79-7-1, NUDOCS 7908020105 | |
| Download: ML19248D094 (11) | |
See also: IR 05000285/1979007
Text
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U. S. NUCLEAR REGULATORY COT!ISSION
OFFICE OF INSPECTION AND ENFORCEllENT
REGION IV
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Report No. 50-285/79-07
Docket No. 50-285
License No. DPR-40
Licensee:
Omaha Public Power District
1623 Harney Street
,
Omahs, Nebraska
68102
Facility Name:
Fort Calhoun Station - Unit 1
Inspection At:
Fort Calhoun Station, Blair, Nebraska
Inspection Conducted: April 30 - May 3, and May 5-10, 1979
D. L. Kelley, Reactor Inspector
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Inspector:
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Reviewed by:
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T. F. Westerman, Chief, Reactor Operations Section
'Date
Approved by: )
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5/2 '//77
G 7L. Madsen, Chief, Reactor Operations and Nuclear
Date
Support Branch
Inspection Summary
Inspection on April 30 - May 3, and May 5-10, 1979 (Report No. 50-285/79-07)
Areas Inspected:
Routine, unannounced inspection of the licensee's response
to IE Bulletin 79-06B.
The inspection consisted of seventy-nine (79) inspector-
hours on site by one (1) NRC inspector.
Results:
Of the area inspected, no apparent item of noncompliance or deviations
were identified.
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DETAILS
1.
Persons Contacted
- R. L. Andrews, Manager, Fort Calhoun Station
'AW. C. Jones, Section Manager, Operations
- F. A. Thurtell, Division Manager, Environmental and Regulatory Af fairs
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- K. J. Morris, Manager, Administrative Services
- R. L. Jaworski, Manager, Reactor and Computer Technical Services
- S. C. Stevens, Manager, Operations Technical Support Services
W. G. Gates, Supervisor, Operations
- Denotes those attending the exit interview.
The inspector also interviewed other members of the licensee's staff.
2.
Follow-up on IE Bulletin 79-06B
This inspection consisted of on-site and in-office review of the licensee's
respcase to IE Bulletin 79-06B and those actions and changes made by the
licensee resulting from the THI-2 incident. The following areas were
examined and are dicussed in detail in the following paragtaphs:
-Review training sessions given to plant operators and staff.
-Interviews with licensed operators.
-Verification of Engineered Safety Features alignment.
-Review of Surveillance and Emergency Procedures.
-Review and evaluation of licensee's response to IE Bulletin 79-06B.
3.
Training
The inspector reviewed the records of the training sessions attended by
station operators and staff. The topics discussed at these training
sessions were:
-IE Bulletin 79-05 and 79-05A.
-Commission Preliminary Notices.
-IE Bulletin 79-06 and 06B.
-Comparisons of Three Mile Island with Fort Calhoun.
-Review of station emergency procedures.
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-Discussion of Transients that were run of the Combustion Engineering
simulator at the request of the Omaha Public Power District.
-Changes to procedures aed philosophies.
-Review of Special Order No. 27 which describes the dt. ties and responsi-
bilities of the Auxiliary Feedwater System Watch.
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The inspector also r*cended the special training session attended by all
licensed and unlicetc,ed operators presented by the IE and NRR task group
covering the sequence of events.
Strip charts from TMI-2 and IE Bulletin
79-06B.
4.
Operator Interviews
The inspector interviewed a minimum of two (2) licensed operators on each
of the six (6) operating shif ts.
The operators interviewed were both
Senior Reactor Operator rad Reactor Operator licensed personnel.
The areas discussed in the operator interviews were:
-Procedural changes and training resulting from IEB79-06 and '9-06B.
-Provisions for verifying ESF systems would be available if required and
measures for ensuring " Return to Operable" status following maintenance
and testing.
-Circumstances when automatic actuation of ESF may be over-ridden.
-Any reset actions of ESF that could affect control of radioactive liquids
and gases.
-Emphasis on early notification of the NRC in case of serious events and
the need for a continuous communication channel.
The inspector concluded that the operators were fully aware of the above
listed items.
5.
Engineered Safety Features
The inspector compared the ESF System alignment check sheets against the
appropriate Piping and Instrument Diagrams (P&ID's) to verify that the
ESF systems were operable according to Technical Specifications, and that
licensee procedural and administrative controls provide adequate assurance
of continued operability.
The alignment check sheets verified are listed
below:
-Auxiliary Feedwater System.
-Hi Pressure Safety Injection System.
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-Low Pressure Safety Injection System.
-Containment Spray System.
-Safety Injection Tanks and Leakage System.
-Raw Water System.
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-Component Cooling Water System.
-No. 1 Diesel Generator - Air Starting and Fuel Oil System.
-No. 2 D'.esel Generator - Air Starting and Fuel Oil System.
The inspector found only minor typographical errors on the alignment sheet.
Using the above verified alignment sheets the inspector independently
verified that the ESF systems above were lined up in accordance with pro-
cedures. The inspector noted that some (very few) brass valve tags were
missing on vent and drain valves. This and the above mentioned typo-
graphical errors were brought to the licensee's attention. The licensee
indicated that these items will be corrected.
6.
Surveillance and Emergency Procedures
The inspector reviewed the following procedures to verify that they adequately
provide verification of " return service" status and to identify changes
made to the procedures since the last surveillance tests:
- -ST-ESF-1, R12, May 1, 1979, " Pressurizer Pressure Low Signal."
- -ST-ESF-2, R13, April 30, 1979, " Safety Injection Actuation."
- -ST-ESF-3, R14, April 30, 1979, " Containment Pressure High Signal."
-ST-ESF-4, R7, November 24,1978, " Containment Spray Logic."
- -ST-ESF-6, R34, April 30, 1979, "Diese'
~( Art and Diesel Fuel Oil Transfer
Pumn
- -ST-ESF-7, R9, April 30, 1979,
k Low Level Signal."
-ST-ESF-8, R4, September 29, 19,,
um
ection Tank Level and
Pressu
.ustruments."
-ST-ESF-9, R8, November 29, 1977, " Boric A:Id Tank Level."
-ST-ESF-10, R3, July 29, 1974, " Boric Acid Heat Tracing."
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- -ST-ESF-11, R10, April 30, 1979, " Steam Generator Low Pressure Signal."
- -EP-1, R2, April 21, 1979, " Reactor Trip."
- -EP-2, R2, April 21, 1979, " Loss of Load."
- -EP-3, R7, April 21, 1979, " Complete Loss of Off-Site AC Power."
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- -EP-4, R3, April 21, 1979, " Loss of Reactor Coolant Flow."
- -EP-5, R4, April 20, 1979, " Loss of Coolent Accident (PPLS Unblocked)."
- -EP-5A, RS, April 29, 1979, " Loss of Coolant Accident (PPLS Blocked)."
- -EP-6, R7, April 21, 1979, " Uncontrolled Heat Extraction."
- -EP-7, R3, April 21, 1979, " Loss of Feedwater."
- -EP-8, R3, April 24, 1979, " Loss of Component Cooling Water."
- -EP-9, R4, March 31, 1979, " Emergency Boration."
-EP-10, R3, January 5,1977, " Fire Reactor Safeguards Equipment, Reactor
Protective System Equipment, or other Equipment
Vital to Safe Operation of the Plant."
- -EP-11, R2, April 21, 1979, "High Radioactivity."
- -EP-12, R3, April 20, 1979, " Loss of Instrument Air."
- -EP-13, R6, April 21, 1979, "CEDM Malfunction."
-EP-14, R3, September 8, 1975, " Fuel Handling Incident."
- -EP-15, R3, April 21, 1979, " Waste Cas Incident."
- -EP-16, R4, April 21, 1979, " Turbine Generator Malfunction."
-EP-17, R1, November 24, 1972, " Uncontrolled CEA Withdrawal."
- -EP-18, R1, April 21, 1979, " Loss of DC Power."
-EP-19, R1, November 27, 1977, " Loss of Instrument Bus Power."
- -EP-20, R2, April 21, 1979, " Loss of Turbine Plant Cooling Water."
- -EP-21, R2, April 21,1979, " Loss of Circulating Water."
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- -EP-22, R2, April 21, 1979, " Loss of Raw Water."
- -EP-23, R2, April 21, 1979, " Reactor Coolant System High Activity."
- -EP-24, R6, April 21,1979, " Forced Evacuation of Control Room."
- -EP-25, RS, April 21, 1979, " Loss of Containment Integrity."
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-EP-26, R1, October 30, 1973, " Loss of Flux Indication."
- -EP-27, R3, April 21, 1979, " Acts of Nature."
- -EP-28, R4, April 20, 1979, " Reactor C'oolant Leak."
- -EP-29, R9, April 21, 1979, " Steam Line Rupture with a Complete Loss of
Off-site AC Power."
- -EP-30, R8, April 21, 1979, " Steam Generator Tube Leak / Rupture (PPLS
Unblocked)."
- -EP-30A, R0, April 24, 1979, " Steam Generator Tube Rupture (PPLS Blocked)."
- -EP-31, R1, April 21, 1979, " Loss of Control Room Air Conditioner."
-EP-32, R2, September 30, 1974, " Emergency Shutdown."
- -EP-33, R4, April 21, 1979, " Complete Loss of Off-site and On-site AC Power."
- -EP-34, R0, July 28,1976, " Emergency Boration of Safety Injection and
Refueling Water Storage Tank."
- -EP-35, R0, April 24,1979, " Reset of Engineered Safeguards."
-0I-CO-1, R6, January 11, 1977, " Containment."
-0I-CO-2, R4, April 24, 1974, " Personnel Air Lock."
-0I-CO-4, R6, November 3, 1977, " Containment Isolation Status During
Refueling Operations."
-0I-CO-5, R3, August 11, 1975, " Containment Integrity."
The * denotes those procedures that have been changed to address those
items of concern in IEB 79-06B.
No areas of concern were identified.
In addition, the inspector reviewed the Engineered Safety Features Test
performed during the November, 1978 refueling outage. The test consisted
of the following:
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-ST-ESF-6, Section F.3, " Diesel Generator Automatic Operation - Diesel
Generator D-1."
-ST-ESF-2, Section F.3, " Channel A Automatic Engineered Safeguards Actuation,
Manual Safety Injection Initiation, Manual Con-
tainment Spray Initiation and Manual Containment
Isolation Initiation."
.
-ST-ESF-4, Section F.3, " Containment Spray Logic."
-ST-ESF-6, Section F.2, " Diesel Generator Check."
-ST-ESF-6, Section F.5, " Diesel Generator Inspection."
-ST-ESF-6, Section F.4, "Same ST-ESF-6, Section F.3, but for Diesel
Generator No. 2.
-ST-ESF-2, Section F.4, Same as ST-ESF-2, Section F.3, but for Channel B.
The results of the above tests verified that diesel start time, sequencer
times and HPSI and LPSI flow rates within specified limits.
7.
Assessment of Operating Procedures
The results of the procedure review are as follows:
-Routine operation event induced pressurizer level transients do not
require " partial" actuation of Safety Injection to assist in level control.
-The licensee has changed the appropriate Emergency Procedures to reflect
the concerns expressed in IEB 79-06B.
In addition, a new Emergency
Proce*!ure, EP-35, " Reset of Engineered Safeguards," has been issued to
direct the operators in the resetting of automatic ESF Actuations. The
changes made to existing procedures and the new procedure discuss:
(1)
when to secure Reactor Coolant Pumps, (2) how to verify natural circulation,
and (3) criteria for securing HPSI and LPSI.
-The procedure for loss of feed water includes instruction for feeding
dry steam generators.
-Current tagging policies used at the plant do not obscure status indicators.
8.
Review of Licensee's Response to IE B':lletin 79-06B
The inspector's conclusions to licensee's written response are that all areas
were factually addressed and that the response is valid.
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Other Conclusions and Comments
-The licensee does not use an " independent verification" of system line-ups,
i.e., two independent alignment checks.
Further, the licensee has made no
commitments to make such checks.
-During the time of this inspection the licensee had scheduled an emergency
plan off-site support group meeting. This meeting was held on May 8,
"
1979 at Fort Calhoun Station.
The inspector attended the meeting and
attached is the meeting agenda and list of attendees.
10.
Exit Interview
The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on Mcy 10, 1979.
The inspector
summarized the scope and results of the inspection.
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C=aha Public Power District
Fort Calhoun Station Energency Plan
Offsite Support Group Meeting
May 8, 1979
AGENDA
EOST:
Fred F. Franco, Supervisor-Chenistry and Radiation Protec ica
R. L. And evs
10:00 s..=.
i4ELCCME
.............
. . . .
Plant Ma ager
10:15 a.:.
So-
,r of E=ergency Plan
M. F. Cassada ,
. . . . . . . .
Plant Eealth
Physicist
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-E=ergency Conditions-
a
Classification
b.
Postulated Accidents
-Organi::ationa.1 Control-
c.
.Yor=nl Plan: Orgaci:stion
b.
Onsite Energency Organization
d.
Onsite Energency Facilities & Equipment
11:30 a.s.
Coordination With Local Support & Agencies - F. F. Franco
a.
Co==.:nication
b.
Authority & Responsibility
Offsite Energency Facilities L Equipment
c.
-Ecergency' Measures-
a.
Alert / Activation Process
b.
Radiclogical Data
c.
Protective Actions
12:30 p.=.
LU: ICE - Fort Canous Statice Cafeteria
1:30 p.c.
Review of Three Mile Island Accident .
L. T. Euseh
. .
Supervisor-Technical
2:00 p.m.
Round Ta'cle Discussion .
F. F Franco
. . . . . . . . .
Moderator
3:00 p.n.
Adl,curn
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OPPD/ SUPPORT GRCUPS MEETING
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Fort Calhsun Station
May 8, 1979
10:00 AM
HP.n e
Organization
Title
1.
Sob Piercy
Nebraska State Patrol '
Captain
2.
Gene Morrissey
Nebraska State Patrol
Major
3
Zovard Swieter
Iowa State Patrol
Sargeant
L.
Robert A. Janett
Iowa State Patrol
Lieutenant
5
Cecil C. Scott
Fort Calhoun Fire & Rescue
Ass't Chief
6.
Holfe Hahne
Univ. of Iowa Fygenic Lab.
Ass't Director
T.
Eatie Royal
Iowa Dept. of Environnent Quality
Envirornental
Specialist
8.
Henrf J. Boccella
Iowa Office of Disaster Serrices
Energency
Planner
9
Beth marsen
Iowa State Patrol
Secretary
10.
Jin Hein
Iowa State Patrol
Sargeant
11.
Roy Brown
Washington Co. Civil Defense
Director
12.
Dave Jacobson
Uebr-Radiologica' Waa'th
Rad'n Health
Physicist
13
Allan Montganer/
U. S. Fish & Wildlife Service
Collections
Manager
lb.
Robert L. :Q aushaar
Modale Fire Dept.
Chief / Council:2.
15
Walter Graves
31 air Police Departnent
Chief
16.
ett Rogen
Washington Co. Board
Chairr.an
17
M. Stanley Jensen
City of Blair
Mayor
13.
Gary E. Handley
Iowa State Dept. of Health
Sanitarian
19
Lloyd Doane
Iowa State Dept. of Health
Sanitarian
20.
Sr. Anna-Maria Coverdell
RADEF Cfficer
21.
Don Csterhaus
Hebraska Wing Civil Air Patrol
Energ. Services
Officer
22.
David M. Halperin
Nebraska Wing Civil Air Patrol
Chief of Staff
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23.
Louis Allstat
Harrison County, Iowa
Sheriff
2h.
Merle Sass
Harrison County, Iowa
Deputy Sheriff
RADEF Officer
25
Gary Rodevald
Mayor
26. John 'Jatson
Harrison Co. Civil Defense
Coordinator
27
Richard Dunlop
Pott. Co. Civil Defense
Director
28. Richard G. Biondi
Dept. of Public Health-Co. Bluffs, Iowa
Director Public
Health
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Mc.rvin E. Hafits
Region 5/6 Civil Defense
Coordinator
30. John '4. Tracy
IIebraska State Civil Defense Agency
ITCP Planner
31.
Gordon P. Lintt, Jr.
?!ebraska State Civil Defense Agency
Con =o & Warn.
32.
Bob 0'Brien
C=aha/ Douglas Co. Civil Defense
Director
33
Ralph A. Medina
IIebr. Civil Defense Agency
Operations
Cfficer
3h. Ernest D. Jones
Univ. of IIebr. Med. Center
Rec. & Eval.
Rad. Health
Center
35
Merton A. Quaife, M.D.
Radiation Health Center
Director
Univ. of iE Medical Center
36. Jcces L. Kelley
Washington Co. , ?iebraska
Sheriff
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A. E. Tanos
U. S. Coast Guard
Con =ander
33.
R. L. Andrevs
CPPD
M. nager-?CS
39
L. T. Kusek
Supv.-Technical
LO.
Dennis L. Kelley
U. S. :I. R. C.
Reactor Inspect
bl.
Maxey F. Cassada
Plant Health
Physicist
h2.
Fred F. Franco
Supv.-Chen/ Rad.
Protection
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