ML20244C090

From kanterella
Jump to navigation Jump to search
Insp Rept 50-285/89-24 on 890508-12.No Violations or Deviations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Including Changes to Emergency Plan & Implementing Procedures & Supplies
ML20244C090
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/02/1989
From: Everett R, Terc N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20244C078 List:
References
50-285-89-24, NUDOCS 8906140120
Download: ML20244C090 (7)


See also: IR 05000285/1989024

Text

_ , . - .

_ _ _ . - _ .

_ - - _ _ - _

_

_ - _

_ _ - _ _ - - _ _ _ _ _ _

_ _ - _ _ _ _ - _ - _ - _ _ _ - _ _ _ _ _ _ _

m .-

W.

. . .

'

.

.

.

14

.

APPENDIX-

U.S. NUCLEAR REGULATORY COMMISSION'

REGION IV

L,

NRC Inspection Report:

50-285/89-24'

Operating License:

NPF-40

. Docket:

50-285

-Licensee: Omaha Public'. Power District (OPPD)

' Facility Name:

Fort Calhoun Station (FCS)

Inspection At:

FCS, Omaha, Nebraska

_

Inspection Conducted: May 8-12, 1989

l

1

b#~N

Inspector:

j a-

-

.

Nemen M. Terc, Emergen'cy Prepared Speciali

Date

,

Approved:

[. ) ,.

[

4,/E[U

R. J. Eve' rett, Chief, Security and Emergency

Date

Preparedness Section

4-

Inspection Summary

'

Inspection Conducted May 8-12,1989 (Report 50-285/89-24)

Areas Inspected:

Routine, announced' inspection of the operational status of.the

emergency preparedness program', including changes to the Emergency P.lan and

implementing procedures, and changes to emergency facilities, equipment,

instrumentation, and supplies. The inspection also included organization and

. management control,. independent audits of the emergency preparedness program,

training of emergency response personnel, and their proficiency.

Results: Within the areas-inspected, no violations or deviations were

identified. Two open items were identified (paragraphs 4 and 5). One open

item refers to the discrepancies in inventory accountability checklists, and

the other to ambiguous emergency response organizational titles.

Interviews

conducted with a sample of emergency responders indicated personnel were

knowledgeable of their emergency duties. Other aspects of the inspection

showed that the licensee is presently making a good effort to improve their

emergency readiness.

hljDOCKo120 e9060s

"

05000295

!

Q

PDC

!

. . _ - .

.

.__

_ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - _ - _ _ _ _ _ _ _ _ _ - - _ - _ _ _ _ _ - _ _ _ - - _ _ _ _ -

_-_ - - __-_

. ..

- - . - _-_ _____ _ __

__--

-

y

.

,

.

2

DETAILS-

1.

Persons Contacted

OPPD

  • G..Peterson, Plant Manager
  • F; Franco, Manager, Radiological Services
  • J. Gasper, Manager, Training
  • R. Jaworski, Manager, Station Engineering

.,

  • W. Orr, Manager, Quality Assurance

"

  • T. Matthews, Station Licensing Engineer

'*L.-Generette, Acting Supervisor, Emergency Planning

  • S

Gebers,' Supervisor, Radiological Services

  • C..Simmons, Licensing Engineer

!

NRC

l

  • P. Harrell, NRC Senior Resident Inspector. FCS

' Denotes those present at exit interview.

2.

Followup on Previous Inspection Findings (92701)

(Closed) Deficiency (50-285/8820-05):

Inadequate. Emergency Notification

I

Procedure.- This item is concerned with the lack of instructions for

i

informing plant personnel of hazardous conditions during emergencies,

!

I

evacuation routes, and sounding emergency alarms. The NRC inspector noted

that the licensee modified Procedures EPIP-2, " Emergency Plan Activation

j

and Notifications," and EPIP-14, " Shift Supervisor / Site. Director Actions,"

i

to include instructions on informing plant personnel of hazardous

1

conditions, evacuation routes, and the duration of sounding the nuclear

!

emergency alarms.

'

(Closed) Deficiency (50-285/8820-06):

Inadequate.Information Flow -

l

This item is concerned with the failure of the chemistry technicians to

j

'

communicate the results of critical radiochemistry samples to appropriate

i

members of the emergency response organization during simulated emergency

l

J

conditions, and the failure of the control room (CR) staff to communicate

critical plant conditions to the technical support center (TSC). The NRC

inspector noted that memor ..i... had been written advising technicians who

.

perform analyses of samples and operations personnel in the CR to relay

l

the results of analysis and plant conditions to appropriate emergency

,

response organizational elements.

In addition, lesson plans were

i

developed addressing these needs, and training was provided to the

chemistry staff to make them aware of the need to promptly communicate

radiochemistry results.

,

l

1

L

-.__ _ ____ _

_ _ _ _ _ _ _ _ _

__

. _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _

. . _ _

_

_ ___ _ - _ _ - _ _ _ - _ - _

1!

c

.

,

.

.

3

(Closed)' Deficiency (50-285/8820-08):

Inadequate Appropriation of

Responsibilities by the Recovery Manager - This item is concerned with the

Recovery Manager's appropriation of dose assessment responsibilities prior

j

to the formal transition of responsibilities. The NRC inspector noted

q

that Procedures EPIP-RR-24, " Emergency Coordinator," EPIP-RR-10, " Recovery -

Manager," .and EPIP-EOF-14, " Site Director To Recovery Manager Transition,"

were changed to add a caution note aovising Recovery Managers to abstain

from appropriating responsibilities before a formal transition of-

responsibilities takes place.

l

(Closed) Deficiency (50-285/8820-09):

Erroneous Entries Made by Dose

!

Assessor - This item is concerned with erroneous estimates of release

duration. The NRC inspector noted that the licensee' modified Dose

Assessment Procedure EPIP-EOF-6, "Onsite/Offsite Dose Assessment," to

incorporate additional instructions'for determining mass steam flow.' In

addition, Operation Instruction 01-PAP-8, " Post Accident Procedures," and

Procedure EPIP-RR-14, " Technical Support Supervisor," were modified to

provide estimated release durations to the dose assessment operator.

(Closed) Deficiency (50-285/8820-10):

Failure to Classify General

Emergency Condition - The NRC inspector noted that the cause of this-

deficiency was' lack of-timely information concerning the release duration

and anticipated mass steam flow from the TSC supervisor to the dose

assessors in the EOF.

Procedure EPIP-EOF-06, "Onsite/Offsite Dose

Assessment," was revised to add a caution statement to make dose assessors

aware of incorporating the most recent plant conditions in dose

assessment. Additionally, guidance memoranda were distributed to dose

assessors, and emergency managers to emphasize the.need for prompt action

in making suggestions-to decision-makers pertaining to protective action

recommendations.

(Closed) Deficiency (50-285/8820-11):

Inadequate Operating Support-

Center (OSC) Briefings of In-Plant Teams - The NRC inspector noted that

the licensee conducted training and revised Procedure EPIP-OSC-20,

" Radiation Protection Guidelines," to specifically address necessary

briefings in the OSC.

In addition, Procedure EPIP-RR-21, " Maintenance

Supervisor," was revised to include a briefing checklist for plant repair

teams.

Drills were conducted to train personnel to perform adequate

briefings.

(Closed) Deficiency (50-285/8820-12):

Lack of Continuous Accountability

Instructions for In-Plant Teams - The NRC inspector noted that

Procedure EPIP-OSC-20, " Radiation Protection Guidelines," was revised to

include instructions for performing continuous accountability of in plant

teams.

(Closed) Deficiency (50-285/8719-08):

Lack of Scenario Realism - The

NRC inspector noted that the 1988 scenario was generally adequate,

technically sound, and for the most part, found to be realistic.

- - - _ -

_ -

_ _ _ _ _ _ _ -

_ - - __

!

.

.

.

.

{

'

<

4

l

(Closed) Deficiency (50-285/8619-03):

Inadequate Radiation Protection

for Onsite Emergency Personnel - The NRC inspector noted that re-entry

personnel were retrained on October 1986; self-reading dosimeters were

added to the emergency kits available to in plant teams; and a

!

computerized listing of personnel exposures was made available in the TSC.

In addition, Procedure EPIP-05C-20 was developed (see Deficiency Items

50-285/8820-11 and 12 above).

(Closed) Violation (50-285/8631-01):

Inadequate Training of Personnel -

The NRC inspector noted that the licensee had devoted considerable effort

to the retraining of the operations staff and other emergency response

personnel by means of drills, walk-throughs, and classroom lectures.

(Closed) Unresolved Item (50-285/8620-05):

Instrument for Measuring

Sump Water Temperature Not Available - The NRC inspector noted

that the licensee installed a temperature monitor in

December 1988.

3.

Emergency Plan and Implementing Procedures (82701-02.01)

The NRC inspector reviewed changes to the Emergency Plan and implementing

procedures and determined that they had been submitted to the NRC within

the 10 CFR 50.54 (q) statutory limit of 30 days after implementation of

the changes.

The NRC inspector also noted that the licensee's Administrative

Procedure, Standing Order-G-30, "Setpoints/ Procedure Changes and

Generation," requires that changes to the Emergency Plan and implementing

procedures be submitted to the NRC as required.

No violations or deviations were identified in this program area.

4.

Emergency Facilities, Eouipment, Instrumentation and

Supplies (82701-02.02)

The NRC inspector toured the licensee's emergency response facilities

and noted that they were adequately maintained and that equipment and

supplies were in place in accordance with inventories. No changes to

facilities, equipment, instrumentation and supplies have adversely

affected the licensee emergency response posture.

The NRC inspector noted that there were some discrepancies in the

procedures and methods to perform inventories as follows:

The operational checks of radiation survey instruments are not

clearly defined in the procedures.

Procedure ST-RM-3,

" Emergency Plan Radiation Instruments and Equipment," does not

clearly explain the exact meaning of terms, or the actual

operations involved when inventorying items on the check list.

_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ -

_ - _ - _ _ _

.

.

.

.

~

.

.

5-

The instrument functional ranges established for each instrument _

on the calibration stickers cannot be readily-verified by the person

conducting the instrumentation inventory because he does not have the

proper check sources. Operational checks should be developed for the

operability ranges that can be verifiable by the user.

Conversion factors for the instruments are not listed in the

verification column of the test record check list.

The type of high range instruments to be stocked are not specified so

the person conducting the inventory can determine which instruments

should be available.

An inventory of instruments consisting of more than one part (e.g.,

lapel air samplers consist of main unit, plastic hose and probe)

shcold describe and specify the number of separate parts in order to

ensure that the complete instrument is there.

It is not clear how the size of the inventory of the different items

(e.g., high range dosimeters, anticontamination clothing, radiation

detection instruments, respirators, air samplers) was determined.

The licensee should determine how many of each item may be needed

during emergency conditions and ensure that the proper number are

available in the inventory.

The licensee should consider adding additional items to inventory

such as phones, personal computers, and other such equipment that are

easily removable to ensure that they remain available in the TSC.

There is a continued traffic of personnel through the TSC and a

history of items being taken out and not being replaced (e.g.,

computer printer).

The licensee should consider placing an additional inventory listing

in each storage area.

The surveillance sheets lack a space for the date surveillance was

made and the initials of persons verifying that the inventory is

correct and instruments and equiptent are in place and operable.

The above is an open item pending licensee evaluation.

(285/8924-01)

5.

Organization and Management Control (82701-02.03)

i

The NRC inspector noted that the licensee had augmented their emergency

'

planning administr-tive staff to include a new onsite supervisor and a

clerk. This chang; should improve the emergency preparedness planning.

l

'

The NRC inspector noted that some job titles within the emergency response

organization were ambiguous or misleading.

- _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _

_ _ - _

- _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _

- . _ _ - - -

- __ - - - - - - . - _ _ _

_ _ . _

- - - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ .

_ _ _ _

.-

.

,

..

,

.

6

There was inconsistent use of position titles for similar work performed

'in the CR, TSC, and EOF.

For example, the individual responsible for

manning the telephone in the CR is designated as the " communicator,"

where as this same position in the TSC is the " phone talker / recorder."

'

In an another example, the roles and responsibilities of the emergency

coordinator and recovery manager were not clearly defined.

The above is an open item pending licensee evaluation.

(285/8924-02)

No violations or deviations were identified in this program area.

6.

Training (82701-02.04)

The NRC inspector he'd discussions with the emergency preparedness

I

training staff, contractors, and training and procedure development

groups to discuss recent changes in the licensee's training program.

The NRC inspector noted that the licensee plans to implement performance

based training for responsible members of the emergency response

organization.

The NRC inspector held interviews with two CR communicators, two TSC

communicators, two TSC recorders / phone talkers, two dose assessment

coordinators, one OSC manager, two maintenance supervisors, and one

offsite monitor to ascertain their knowledge of duties and

responsibilities as emergency responders.

The NRC inspector

determined that all emergency organizational members interviewed

appeared to be competent and proficient in their specific tasks.

No violations or deviations were identified in this program area.

7.

Independent Audits (82701-02.05)

The NRC inspector reviewed audits of the emergency preparedness program

in order to determine compliance with 10 CFR 50.54(t).

l

The NRC inspector noted that the last independent audit of the

emergency preparedness program was performed by the quality assurance

department during the period March 6-16, 1989. The audit was performed

by six auditors, including one from Wolf Creek Nuclear Operating

Corporation. The audit included evaluation of dose projections methods,

verification of letters of agreement, interactions with offsite groups,

l

evaluation of current emergency call lists, and emergency procedures.

The NRC inspector determined that the scope and depth of tae audit

appeared to be adequate.

No violations or deviations were identified in this program area.

I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

. - _ . . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _

.. ..

,

.

,

.

7

8.

Information Notices and Bulletins

The NRC inspector noted that licensee's Quality Procedure N0D-QP9,

" Processing of NRC, INPO, NUMARC, DEC, DOE, and EPA Correspondence and

Other Pertinent Licensing Documents," provides instructions to facilitate

the flow and handling of bulletins, circulars, notices, and proposed

rules.

The NRC inspector noted that the licensee had received bulletins,

circulars, and information notices, and distributed them to the

responsible personnel for appropriate action.

9.

Open Items

An open item is a matter that requires further review and evaluation

by the inspector, including an item pending specific action by the

licensee on a previously identified violation, deviation, unresolved

item, and programmatic weakness.

Open items are used to document,

track, and ensure adequate followup on matters of concern to the

inspector. Open items are identified on paragraphs 4 and 5 of this

report.

10.

Exit Interview

The NRC inspector met with the NRC resident inspector and licensee

representatives noted in paragraph 1 on May 12, 1989, and summarized

the scope and findings of the inspection as presented in this report.

<