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{{Adams | {{Adams | ||
| number = | | number = ML20207T152 | ||
| issue date = | | issue date = 03/18/1987 | ||
| title = Insp Rept 50-285/86-31 | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/86-31. Implementation of Corrective Actions Will Be Reviewed During Future Insp to Determine That Full Compliance Achieved | ||
| author name = | | 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 = | | document report number = NUDOCS 8703230256 | ||
| | | title reference date = 02-18-1987 | ||
| document type = | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | ||
| page count = | | page count = 2 | ||
}} | }} | ||
| Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:... | {{#Wiki_filter:.-- | ||
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In Reply Refer To: | |||
- | |||
'- | |||
" | |||
i Docket: | |||
50-285/86-31' | |||
y | |||
, | |||
MAR 181987 | |||
' | |||
' | |||
-Omaha Public Power District? | |||
w ATTN: | |||
R. L. Andrews, Division Manager- | |||
'', | |||
' | |||
- | |||
Nuclear Production 1623 Harney Street | |||
. | |||
' | |||
. On:aha,. Nebra ska 68102-t | |||
- | |||
.. | |||
s' | |||
. Gentlemen: | |||
- | - | ||
- | - | ||
, | |||
Thank you for your letter of February 18,, 1987, in response to our letter | |||
.and Notice of Violation dated January 22, 1987. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of-your corrective actions during a future U | |||
inspection to determine that full compliance has been achieved and will be maintained. | |||
Sincerely, | |||
.... | %fnal s,a.,e y | ||
, | |||
A E. nAu.~ | |||
f J. E. Gagliardo, Chief c | |||
Reactor' Projects Branch s | |||
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, D. C. | |||
20036 Kansas Radiation Control Program Director Nebraska Radiation Control Program Director b c: (see next page) | |||
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Inspector. | |||
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Section Chief | |||
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. n 9. L. Fisher i | |||
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' R.-L. Bangart pl- | |||
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,3.-Project Inspector,.RPB D. B. Matthews,'IE | |||
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68102 2247;:- - -e75[~5,.....;..I. ', i | |||
,1i-N 1623 Hamey Omaha. Nebraska | |||
' '( | |||
i 402/536 4000 FEB 2 7 ggg k.: !O February 18, 1987 | |||
; | |||
h | |||
- | |||
LIC-87-105 | |||
- | |||
. | . | ||
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-.: | |||
J. E. Gagliardo, Chief Reactor Projects Branch U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Reference: | |||
Docket No. 50-285 Gentlemen: | |||
SUBJECT: | |||
Inspection Report 86-31 The subject inspection report, dated January 22, 1987, identified one (1) | |||
; | |||
violation concerning the training of personnel assigned to the Emergency l | |||
Response Organization. | |||
Please find attached the Omaha Public Power l | |||
District's response to this violation. | |||
. | |||
Sincerely, G..i b | |||
l R. L. Andrews Division Manager Nuclear Production RLA:bjb c: | |||
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W. | |||
Washington, D.C. | |||
20036 Mr. A. C. Thadani, Project Director Mr. W. A. Paulson, HRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector Mr. R. D. Martin, Regional Administrator f | |||
TID o09 | |||
- | |||
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., | |||
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ATTACHMENT | |||
- | |||
, | |||
During an NRC inspection conducted on November 17-21, 1986, a violation of | |||
. | |||
NRC requirements was identified. The violation involved inadequate train-ing for personnel assigned to the emergency response organization. | |||
The | |||
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation is listed below: | |||
Violation | |||
, | , | ||
Inadeauate Trainina of Personnel 10 CFR 50.54(q) requires that licensees authorized to operate a nuclear power reactor follow and maintain in effect emergency plans which meet the standards in 10 CFR 50.47(b) and in Appendix E. | |||
10 CFR 50.47(b)(15) requires that radiological emergency response training be provided to those who may be called to assist in an | |||
. | |||
emergency. | |||
10 CFR 50, Appendix E, paragraph IV.F requires, in part, that employ- | |||
- | |||
ees of the licensee be trained to ensure that they are familiar with | |||
' | |||
their specific emergency response duties. | |||
Contrary to the above, the NRC inspector determined during emergency preparedness walkthroughs and training interviews that radiological emergency. response training had not been provided adequately as evi-denced by the following examples: | |||
1. | |||
One of two shift supervisors failed to notify the NRC that a station blackout was in progress, as required by 10 CFR 50.72(b) | |||
(iii) and by Section E(1.1) of the Radiological Response Emer-gency Plan (RERP) for Fort Calhoun Station. | |||
2. | |||
The two shift supervisors and two site direc. tors interviewed failed to demonstrate a basic understanding of the design, oper-ation, capabilities and emergency uses of the post accident sampling system (e.g., ability to perform in situ versus grab sample analysis). | |||
3. | |||
The two shift supervisors and two site directors interviewed failed to demonstrate a basic understanding of those aspects of meteorology (e.g., difference between stable and unstable conditions) that would have a major impact on the effects of a radioactive release and on their decisions pertaining to protective action recommendations. | The two shift supervisors and two site directors interviewed failed to demonstrate a basic understanding of those aspects of meteorology (e.g., difference between stable and unstable conditions) that would have a major impact on the effects of a radioactive release and on their decisions pertaining to protective action recommendations. | ||
4. | |||
One of two shift supervisors incorrectly understood that the containment atmosphere monitoring system discharged to the auxiliary | One of two shift supervisors incorrectly understood that the containment atmosphere monitoring system discharged to the auxiliary buildin, - | ||
. | |||
s' | |||
* | |||
. | |||
* | |||
5. | |||
One of two shift supervisors failed to demonstrate an understand-ing of the differences between site area and general emergency classifications and was not aware of the requirement to-make protective action recommendations at a general emergency declaration. | |||
6. | |||
of | One of two shift supervisors failed to relate challenges to fail- | ||
~ | |||
ure of fission product barriers to emergency classifications. | |||
7. | |||
One of two shift supervisors | One of two shift supervisors exhibited a general weakness in the knowledge and performance of his emergency preparedness dui.ies, in that a number of forceful prompts from the shift technical advisor and senior reactor operator were needed in order for him to make classification and notification decisions. | ||
8. | |||
. | |||
Both chemistry technicians failed to demonstrate a knowledge of the order of severity of the different levels of emergency class-ification (e.g., failed to name them and confused the order of severity).- | |||
- | |||
, | , | ||
9. | |||
One chemistry technician could not find an alternate procedure in OI-PAP-8 to estimate the magnitude and consequences of offsite radioactive releases. The other technician had ~ difficulty in | |||
' | |||
finding the procedure. Neither was able to perform dose pro-jections when given the situation.sf failed process monitors. | |||
' | |||
This is a Severity Level IV violation. | |||
(Supplement VII.D) | |||
, | |||
(285/8631-01). | |||
OPPD's Response The Reason for the Violation if Admitted OPPD personnel have been involved in training programs and testing procedures which were developed based on NUREG 0654, 10 CFR 50 and reasonable training requirements. All personnel must pass an appro-priate test for their respective positions prior to approval for an | |||
, | , | ||
; | |||
emergency response organization. | |||
Employees interviewed by the NRC had I | |||
received this training. The NRC interviews have disclosed a weakness in the retention of the subject materials as taught and tested, and | |||
' | |||
the individuals ability to retain and recall this information. | |||
OPPD intends to improve emergency preparedness training by administering | |||
, | |||
' | |||
more difficult tests and conducting more difficult drills to prevent repetition of this violation. | |||
, | |||
The Corrective Steps Which Have Been Taken and the Results Achieved | |||
; | ; | ||
: | : | ||
a | All current shift chemistry / radiation protection technicians have been retrained in emergency classification levels by distribution of a training information hotline on October 8, 1986. | ||
l l | |||
_.... | |||
. | |||
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ | |||
_ _ _ _ _ _ _ _ _ _ _ _ _ _ | |||
.... s' | |||
The shift supervisor who performed poorly during the walkthough and | |||
[, | |||
training interviews was removed from his position on the shift. | |||
The shift supervisors and chemistry technicians presently manning the operation shift at Fort Calhoun Station satisfy the training and per.- | |||
! | ! | ||
formance requirements established by OPPD documents. | |||
The Corrective Steos Which Will be Taken to Avoid Further Violations The shift supervisor who performed poorly during the walkthrough and training interviews will be retrained in the " Licensing Operator Train-ing" program prior to being allowed to resume' shift supervisor duties. | |||
The shift supervisors and site directors interviewed will be given supplemental training concerning the subjects of post accident sam-pling system and meteorology, and all shift supervisors and site directors will receive additional training to these topics during their annual requalification training. | |||
The | |||
- | |||
During the 1987 annual training cycle for shift supervisors and site directors, the following training items identified by the NRC in- | |||
," | |||
spector as weak will be reviewed with the proper emergency actions stressed: | |||
1. | |||
NRC notification 2. | |||
Post accident sampling system capabilities 3. | |||
Basic meteorological knowledge 4. | |||
Containment atmosphere monitoring 5. | |||
Protective Action recommendations for Site Area and General Emergency classifications 6. | |||
7. | Emergency classification related to loss of fission product barriers 7. | ||
Basic emergency preparedness duties During the 1987 annual training cycle for shift chemistry / radiation protection technicians, the basis for the four emergency classifica-tions will be stressed. | |||
For an improved alternate method to estimate the magnitude and effects of offsite radioactive releases when monitor indication is not available, Operating Instruction 01-PAP-8, Post Acci-dent Procedures, is currently under revision. Shift C/RP technicians are scheduled for training on this procedure after its approval by the Plan Review Committee and prior to formal issuance. Training for items 1,2,3,4 and 6 are being accomplished by the Training Department; items 5,7,8 and 9 are provided in the annual training cycle of the Emergency Planning Group. | |||
The Date When Full Comoliance will be Achieved Based upon the above review and training programs, OPPD believes these personnel have sufficient ability to perform their emergency duties and OPPD is now in compliance with 10CFR50 requirements. ~However, the improved procedures and annual training described above will be accom-plished by the end of the annual training cycle on December 31, 1987. | |||
I | |||
}} | }} | ||
Revision as of 19:07, 6 December 2024
| ML20207T152 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 03/18/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8703230256 | |
| Download: ML20207T152 (2) | |
Text
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In Reply Refer To:
-
'-
"
i Docket:
50-285/86-31'
y
,
MAR 181987
'
'
-Omaha Public Power District?
w ATTN:
R. L. Andrews, Division Manager-
,
'
-
Nuclear Production 1623 Harney Street
.
'
. On:aha,. Nebra ska 68102-t
-
..
s'
. Gentlemen:
-
-
,
Thank you for your letter of February 18,, 1987, in response to our letter
.and Notice of Violation dated January 22, 1987. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of-your corrective actions during a future U
inspection to determine that full compliance has been achieved and will be maintained.
Sincerely,
%fnal s,a.,e y
,
A E. nAu.~
f J. E. Gagliardo, Chief c
Reactor' Projects Branch s
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, D. C.
20036 Kansas Radiation Control Program Director Nebraska Radiation Control Program Director b c: (see next page)
p
- EP&SPS C:EP&!g C:R&SPB C: PB/
- R B
.
'
3/)gliardo
.
JEGa N T rc:cd LAYandelt WLFisher DRHunter-
'
/g /87 3/p/87
-) /I7/87
/87
/87
-
l 8703230256 870318 l
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ts 19 3 '
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-.Res; dent-In;spector
',
'
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. R.lD. Martin,:RA R&SPB;
,.
~ Section Chief (RPB/B)~... '
s
'
,.
MIS System
.S' '
.
,
f' '
- RIV File
'!/
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-- RSTS.0perator ~
RSB '
Inspector.
.
-.
,
,..
Section Chief
-
. n 9. L. Fisher i
-,
'
'
' R.-L. Bangart pl-
'
..
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R; E.. Hall
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,3.-Project Inspector,.RPB D. B. Matthews,'IE
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-
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68102 2247;:- - -e75[~5,.....;..I. ', i
,1i-N 1623 Hamey Omaha. Nebraska
' '(
i 402/536 4000 FEB 2 7 ggg k.: !O February 18, 1987
h
-
LIC-87-105
-
.
j
-.:
J. E. Gagliardo, Chief Reactor Projects Branch U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
Inspection Report 86-31 The subject inspection report, dated January 22, 1987, identified one (1)
violation concerning the training of personnel assigned to the Emergency l
Response Organization.
Please find attached the Omaha Public Power l
District's response to this violation.
.
Sincerely, G..i b
l R. L. Andrews Division Manager Nuclear Production RLA:bjb c:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. A. C. Thadani, Project Director Mr. W. A. Paulson, HRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector Mr. R. D. Martin, Regional Administrator f
TID o09
-
g,aem
-==-
.,
. -.
--
ATTACHMENT
-
,
During an NRC inspection conducted on November 17-21, 1986, a violation of
.
NRC requirements was identified. The violation involved inadequate train-ing for personnel assigned to the emergency response organization.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation is listed below:
Violation
,
Inadeauate Trainina of Personnel 10 CFR 50.54(q) requires that licensees authorized to operate a nuclear power reactor follow and maintain in effect emergency plans which meet the standards in 10 CFR 50.47(b) and in Appendix E.
10 CFR 50.47(b)(15) requires that radiological emergency response training be provided to those who may be called to assist in an
.
emergency.
10 CFR 50, Appendix E, paragraph IV.F requires, in part, that employ-
-
ees of the licensee be trained to ensure that they are familiar with
'
their specific emergency response duties.
Contrary to the above, the NRC inspector determined during emergency preparedness walkthroughs and training interviews that radiological emergency. response training had not been provided adequately as evi-denced by the following examples:
1.
One of two shift supervisors failed to notify the NRC that a station blackout was in progress, as required by 10 CFR 50.72(b)
(iii) and by Section E(1.1) of the Radiological Response Emer-gency Plan (RERP) for Fort Calhoun Station.
2.
The two shift supervisors and two site direc. tors interviewed failed to demonstrate a basic understanding of the design, oper-ation, capabilities and emergency uses of the post accident sampling system (e.g., ability to perform in situ versus grab sample analysis).
3.
The two shift supervisors and two site directors interviewed failed to demonstrate a basic understanding of those aspects of meteorology (e.g., difference between stable and unstable conditions) that would have a major impact on the effects of a radioactive release and on their decisions pertaining to protective action recommendations.
4.
One of two shift supervisors incorrectly understood that the containment atmosphere monitoring system discharged to the auxiliary buildin, -
.
s'
.
5.
One of two shift supervisors failed to demonstrate an understand-ing of the differences between site area and general emergency classifications and was not aware of the requirement to-make protective action recommendations at a general emergency declaration.
6.
One of two shift supervisors failed to relate challenges to fail-
~
ure of fission product barriers to emergency classifications.
7.
One of two shift supervisors exhibited a general weakness in the knowledge and performance of his emergency preparedness dui.ies, in that a number of forceful prompts from the shift technical advisor and senior reactor operator were needed in order for him to make classification and notification decisions.
8.
Both chemistry technicians failed to demonstrate a knowledge of the order of severity of the different levels of emergency class-ification (e.g., failed to name them and confused the order of severity).-
-
,
9.
One chemistry technician could not find an alternate procedure in OI-PAP-8 to estimate the magnitude and consequences of offsite radioactive releases. The other technician had ~ difficulty in
'
finding the procedure. Neither was able to perform dose pro-jections when given the situation.sf failed process monitors.
'
This is a Severity Level IV violation.
(Supplement VII.D)
,
(285/8631-01).
OPPD's Response The Reason for the Violation if Admitted OPPD personnel have been involved in training programs and testing procedures which were developed based on NUREG 0654, 10 CFR 50 and reasonable training requirements. All personnel must pass an appro-priate test for their respective positions prior to approval for an
,
emergency response organization.
Employees interviewed by the NRC had I
received this training. The NRC interviews have disclosed a weakness in the retention of the subject materials as taught and tested, and
'
the individuals ability to retain and recall this information.
OPPD intends to improve emergency preparedness training by administering
,
'
more difficult tests and conducting more difficult drills to prevent repetition of this violation.
,
The Corrective Steps Which Have Been Taken and the Results Achieved
All current shift chemistry / radiation protection technicians have been retrained in emergency classification levels by distribution of a training information hotline on October 8, 1986.
l l
_....
.
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _
.... s'
The shift supervisor who performed poorly during the walkthough and
[,
training interviews was removed from his position on the shift.
The shift supervisors and chemistry technicians presently manning the operation shift at Fort Calhoun Station satisfy the training and per.-
!
formance requirements established by OPPD documents.
The Corrective Steos Which Will be Taken to Avoid Further Violations The shift supervisor who performed poorly during the walkthrough and training interviews will be retrained in the " Licensing Operator Train-ing" program prior to being allowed to resume' shift supervisor duties.
The shift supervisors and site directors interviewed will be given supplemental training concerning the subjects of post accident sam-pling system and meteorology, and all shift supervisors and site directors will receive additional training to these topics during their annual requalification training.
During the 1987 annual training cycle for shift supervisors and site directors, the following training items identified by the NRC in-
,"
spector as weak will be reviewed with the proper emergency actions stressed:
1.
NRC notification 2.
Post accident sampling system capabilities 3.
Basic meteorological knowledge 4.
Containment atmosphere monitoring 5.
Protective Action recommendations for Site Area and General Emergency classifications 6.
Emergency classification related to loss of fission product barriers 7.
Basic emergency preparedness duties During the 1987 annual training cycle for shift chemistry / radiation protection technicians, the basis for the four emergency classifica-tions will be stressed.
For an improved alternate method to estimate the magnitude and effects of offsite radioactive releases when monitor indication is not available, Operating Instruction 01-PAP-8, Post Acci-dent Procedures, is currently under revision. Shift C/RP technicians are scheduled for training on this procedure after its approval by the Plan Review Committee and prior to formal issuance. Training for items 1,2,3,4 and 6 are being accomplished by the Training Department; items 5,7,8 and 9 are provided in the annual training cycle of the Emergency Planning Group.
The Date When Full Comoliance will be Achieved Based upon the above review and training programs, OPPD believes these personnel have sufficient ability to perform their emergency duties and OPPD is now in compliance with 10CFR50 requirements. ~However, the improved procedures and annual training described above will be accom-plished by the end of the annual training cycle on December 31, 1987.
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