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| number = ML18082B310
| number = ML18082B310
| issue date = 08/19/1980
| issue date = 08/19/1980
| title = Responds to NRC 800729 Ltr Re Violations Noted in IE Insp Repts 50-272/80-14 & 50-311/80-10.Corrective Actions: Training Group Is Developing Formal Means of Evaluating Operator Response on Simulator
| title = Responds to NRC Re Violations Noted in IE Insp Repts 50-272/80-14 & 50-311/80-10.Corrective Actions: Training Group Is Developing Formal Means of Evaluating Operator Response on Simulator
| author name = Schneider F
| author name = Schneider F
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 8010100061
| document report number = NUDOCS 8010100061
| title reference date = 07-29-1980
| package number = ML18082B309
| package number = ML18082B309
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
| page count = 3
}}
}}
See also: [[followed by::IR 05000272/1980014]]


=Text=
=Text=
{{#Wiki_filter:.erick W. Schneider  
{{#Wiki_filter:.erick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production August 19, 1980 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of -Prussia, PA, 19406 Attention:
Vice President  
Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Gentlemen:
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373  
COMBINED NRC INSPECTION 50-272/80-14 AND 50-311/80-10 SALEM GENERATING STATION, UNITS NOS. l AND 2 We have reviewed the report of your inspection conducted by Dr.
Production  
L. H. Bettenhausen during the period June 18-20, 1980.
* August 19, 1980 Mr. Boyce H. Grier, Director Off ice of Inspection  
Our response to the two items of noncompliance identified in Appendix A of your report is as follows:
and Enforcement  
Item 1, Infraction 10 CFR 55, Appendix A, Requalification Programs for Licensed Operators of Production and Utilization Facilities, states, in
Region 1 U.S. Nuclear Regulatory  
: part, "3.
Commission  
On-the-job training.
631 Park Avenue King of -Prussia, PA , 19406 Attention:  
The requalification program shall include on-the-job train;i,ng so that:"  
Mr. Eldon J. Brunner, Chief Reactor Operations  
"3c. Each licensed operator and senior operator is cognizant of facility design change~ **. "
and Nuclear Support Branch Gentlemen:  
Contrary to the above, no evidence was found that all licensed operators and senior operators review facility design changes nor is there a system in place to insure these reviews occur.*
COMBINED NRC INSPECTION  
Reply to Item 1
50-272/80-14  
: 1.  
AND 50-311/80-10  
-A formal procedure was being developed to address this area; however, for a while we had to postpone completion of this procedure due to a more pressing priority.
SALEM GENERATING  
80101000(,/  
STATION, UNITS NOS. l AND 2 We have reviewed the report of your inspection  
 
conducted  
Boyce H. Grier, Dir.
by Dr. L. H. Bettenhausen  
2 -
during the period June 18-20, 1980. Our response to the two items of noncompliance  
8-19-80 work has resumed on the training procedure.*
identified  
Design change information will be transmitted to the Training group via an updated computer printout and through distribution of the SORC minutes.
in Appendix A of your report is as follows: Item 1, Infraction  
The training group will evaluate each design change and issue a written explanation to each licensed operator or conduct formal classroom training as appropriate.
10 CFR 55, Appendix A, Requalification  
Design change information is presently being transmitted to the licensed operators by issuance of a letter~
Programs for Licensed Operators  
This action will continue until the procedure is approved and implemented.
of Production  
: 3.
and Utilization  
The approval and implementation of the training procedure will prevent recurrence of this item.
Facilities, states, in part, "3. On-the-job  
: 4.
training.  
Date for full compliance is September 30, 1980.
The requalification  
Item.2 Deficiency Salem Generating Station Training Procedure 10, Revision 2, NRC "Licensed Operator Requalificatl.on Program", paragraph IV re-quires an individual training folder maintained for each licensed operator and senior operator.
program shall include on-the-job  
These folders shall contain, in part, records. of simulator training received.
train;i,ng  
The 12 October 1979 letter from Mr. H. J. Midura to Mr. Paul Collins of Operator Licensing Branch, NRC, indicated that simulator training would still be required as part of the Unit 1 modified requalification program.
so that:" "3c. Each licensed operator and senior operator is cognizant  
Contrary to the above, no record of simulator training, other than reactivity manipulations, was found in the records of either the three licensed operators or the *four senior operators reviewed.
of facility design  
Reply to Item 2
**. " Contrary to the above, no evidence was found that all licensed operators  
: 1.
and senior operators  
The NRC has, in the past, expressed concern as to the method used to evaluate operator response to simulated accidents.
review facility design changes nor is there a system in place to insure these reviews occur.* Reply to Item 1 1. -A formal procedure  
In response, PSE&G requested the various simulator instruc-tors in other utilities to evaluate our operators perform-ance during simulator training at those utilities.
was being developed  
These instructors have been reluctant to evaluate operators em-ployed by another utility, unless an acceptance criteria is established.
to address this area; however, for a while we had to postpone completion  
: 2.
of this procedure  
The training group is developing a formal means of evalu-ating operator response on the simulator.
due to a more pressing priority.  
A check list will be utilized to document this evaluation.
80101000(,/
The completed check lists will remain in the individual's training folder.
Boyce H. Grier, Dir. -2 -8-19-80 work has resumed on the training procedure.*  
: 3.
Design change information  
The completion of the Salem simulator will allow more ef-fective evaluation of the performance of our operators.  
will be transmitted  
 
to the Training group via an updated computer printout and through distribution  
Boyce H. Grier, Director 3 -
of the SORC minutes. The training group will evaluate each design change and issue a written explanation  
: 4.
to each licensed operator or conduct formal classroom  
The formal*. procedure and check list will be established by October 15, 1980.
training as appropriate.  
If you have any further questions with regard to this matter~ we will be pleased to discuss them with.you.
Design change information  
cc Director, Office of Inspection and Enforcement NRC Washington, DC 20555}}
is presently  
being transmitted  
to the licensed operators  
by issuance of a  
This action will continue until the procedure  
is approved and implemented.  
3. The approval and implementation  
of the training procedure  
will prevent recurrence  
of this item. 4. Date for full compliance  
is September  
30, 1980. Item .2 Deficiency  
Salem Generating  
Station Training Procedure  
10, Revision 2, NRC "Licensed  
Operator Requalificatl.on  
Program", paragraph  
IV quires an individual  
training folder maintained  
for each licensed operator and senior operator.  
These folders shall contain, in part, records. of simulator  
training received.  
The 12 October 1979 letter from Mr. H. J. Midura to Mr. Paul Collins of Operator Licensing  
Branch, NRC, indicated  
that simulator  
training would still be required as part of the Unit 1 modified requalification  
program. Contrary to the above, no record of simulator  
training, other than reactivity  
manipulations, was found in the records of either the three licensed operators  
or the *four senior operators  
reviewed.  
Reply to Item 2 1. The NRC has, in the past, expressed  
concern as to the method used to evaluate operator response to simulated  
accidents.  
In response, PSE&G requested  
the various simulator tors in other utilities  
to evaluate our operators ance during simulator  
training at those utilities.  
These instructors  
have been reluctant  
to evaluate operators ployed by another utility, unless an acceptance  
criteria is established.  
2. The training group is developing  
a formal means of ating operator response on the simulator.  
A check list will be utilized to document this evaluation.  
The completed  
check lists will remain in the individual's  
training folder. 3. The completion  
of the Salem simulator  
will allow more fective evaluation  
of the performance  
of our operators.
.. Boyce H. Grier, Director -3 -4. The formal*. procedure  
and check list will be established  
by October 15, 1980. If you have any further questions  
with regard to this  
we will be pleased to discuss them with.you.  
cc Director, Office of Inspection  
and Enforcement  
NRC Washington, DC 20555
}}

Latest revision as of 05:29, 6 January 2025

Responds to NRC Re Violations Noted in IE Insp Repts 50-272/80-14 & 50-311/80-10.Corrective Actions: Training Group Is Developing Formal Means of Evaluating Operator Response on Simulator
ML18082B310
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/19/1980
From: Schneider F
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18082B309 List:
References
NUDOCS 8010100061
Download: ML18082B310 (3)
v • d • e


Text

.erick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production August 19, 1980 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of -Prussia, PA, 19406 Attention:

Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Gentlemen:

COMBINED NRC INSPECTION 50-272/80-14 AND 50-311/80-10 SALEM GENERATING STATION, UNITS NOS. l AND 2 We have reviewed the report of your inspection conducted by Dr.

L. H. Bettenhausen during the period June 18-20, 1980.

Our response to the two items of noncompliance identified in Appendix A of your report is as follows:

Item 1, Infraction 10 CFR 55, Appendix A, Requalification Programs for Licensed Operators of Production and Utilization Facilities, states, in

part, "3.

On-the-job training.

The requalification program shall include on-the-job train;i,ng so that:"

"3c. Each licensed operator and senior operator is cognizant of facility design change~ **. "

Contrary to the above, no evidence was found that all licensed operators and senior operators review facility design changes nor is there a system in place to insure these reviews occur.*

Reply to Item 1

1.

-A formal procedure was being developed to address this area; however, for a while we had to postpone completion of this procedure due to a more pressing priority.

80101000(,/

Boyce H. Grier, Dir.

2 -

8-19-80 work has resumed on the training procedure.*

Design change information will be transmitted to the Training group via an updated computer printout and through distribution of the SORC minutes.

The training group will evaluate each design change and issue a written explanation to each licensed operator or conduct formal classroom training as appropriate.

Design change information is presently being transmitted to the licensed operators by issuance of a letter~

This action will continue until the procedure is approved and implemented.

3.

The approval and implementation of the training procedure will prevent recurrence of this item.

4.

Date for full compliance is September 30, 1980.

Item.2 Deficiency Salem Generating Station Training Procedure 10, Revision 2, NRC "Licensed Operator Requalificatl.on Program", paragraph IV re-quires an individual training folder maintained for each licensed operator and senior operator.

These folders shall contain, in part, records. of simulator training received.

The 12 October 1979 letter from Mr. H. J. Midura to Mr. Paul Collins of Operator Licensing Branch, NRC, indicated that simulator training would still be required as part of the Unit 1 modified requalification program.

Contrary to the above, no record of simulator training, other than reactivity manipulations, was found in the records of either the three licensed operators or the *four senior operators reviewed.

Reply to Item 2

1.

The NRC has, in the past, expressed concern as to the method used to evaluate operator response to simulated accidents.

In response, PSE&G requested the various simulator instruc-tors in other utilities to evaluate our operators perform-ance during simulator training at those utilities.

These instructors have been reluctant to evaluate operators em-ployed by another utility, unless an acceptance criteria is established.

2.

The training group is developing a formal means of evalu-ating operator response on the simulator.

A check list will be utilized to document this evaluation.

The completed check lists will remain in the individual's training folder.

3.

The completion of the Salem simulator will allow more ef-fective evaluation of the performance of our operators.

Boyce H. Grier, Director 3 -

4.

The formal*. procedure and check list will be established by October 15, 1980.

If you have any further questions with regard to this matter~ we will be pleased to discuss them with.you.

cc Director, Office of Inspection and Enforcement NRC Washington, DC 20555

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