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=Text=
=Text=
{{#Wiki_filter:4-
{{#Wiki_filter:4-s l OUISIANA P O W E R & L i G H T! P O BOX 6008
* s
* NEW OnLEANS. LOUISIANA 70174 242 OeLanONOe stater
* l OUISIANA           242 OeLanONOe stater P O W E R & L i G H T! P O BOX 6008
* (504) 366-2345 MlOOLE SOUTH uTiuriES SYSTEM July 28, 1983 W3183-0248 Q-3-A35.07.72
* NEW OnLEANS. LOUISIANA           70174
, -f_= &
                                                                                  * (504) 366-2345 MlOOLE SOUTH uTiuriES SYSTEM                               July 28, 1983 W3183-0248 Q-3-A35.07.72
t Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission tj
                                                                                      -f_= &
.L!0,1 611 Ryan Plaza Drive, Suite 1000 AIS - 31983 1
t Mr. John T. Collins, Regional Administrator, Region IV                 .
hg Arlington, Texas 76012 as
U. S. Nuclear Regulatory Commission                                                           tj 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 1    AIS - 31983 .L!0,1   hg as


==SUBJECT:==
==SUBJECT:==
Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 72
Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 72
                        " Radiation Monitoring System RM-23 Control Modules" Final Report
" Radiation Monitoring System RM-23 Control Modules" Final Report


==REFERENCE:==
==REFERENCE:==
Line 34: Line 33:


==Dear Mr. Collins:==
==Dear Mr. Collins:==
In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 72,
In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 72,
        " Radiation Monitoring System RM-23 Control Modules".
" Radiation Monitoring System RM-23 Control Modules".
If you have any questions, please advise.
If you have any questions, please advise.
Very truly ours, V **'
Very truly ours, V **'
F. J. Drummond Project Support Manager - Nuclear Attachment FJD/WAC/ MAL:keh cc:     1) Director                                         3)   Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (w/15 copies)
F. J. Drummond Project Support Manager - Nuclear Attachment FJD/WAC/ MAL:keh cc:
: 2) Director                                         4)   Mr. W. M. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (w/1 copy)
: 1) Director 3)
F308090018 830728 OPDR ADOCK 05000382 PDR
Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
                                                                                                        \{
20555 (w/15 copies)
: 2) Director 4)
Mr. W. M. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.
20555 (w/1 copy)
F308090018 830728 PDR ADOCK 05000382 O
PDR
\\{


      .t -   ,
.t -
o-       '
o-s FINAL REPORT OF SIGNIFICANT CONSTRUCTION = DEFICIENCY NO. 72-
s FINAL REPORT OF SIGNIFICANT CONSTRUCTION = DEFICIENCY NO. 72-
-, - '' RADIATION MONITORING SYSTEM RM 23 CONTROL MODULES"
                                                                          ~
~
                                  - , - '' RADIATION MONITORING SYSTEM RM 23 CONTROL MODULES" INTRODUCTION Thisreportissubmittedpursuantto10CFR50.5$(e).. It describes deficiencies
INTRODUCTION Thisreportissubmittedpursuantto10CFR50.5$(e).. It describes deficiencies
                                                                                    ~     '
~
which existed in the radiation monitoring system RM-23 modules. This deficiency fis considered reportable under the: requirements of'10CFR50.55(e).
which existed in the radiation monitoring system RM-23 modules. This deficiency fis considered reportable under the: requirements of'10CFR50.55(e).
                    . General Atomic Technologies, Inc. of San Diego, California has informed LP&L-
. General Atomic Technologies, Inc. of San Diego, California has informed LP&L-
                    .that-this problem has been reported to the Nuclear Regulatory Commission. pursuant' cto'10CFR21.
.that-this problem has been reported to the Nuclear Regulatory Commission. pursuant' cto'10CFR21.
DESCRIPTION GA Technologies Inc.-(the vendor) informed us that1 uring         d    start-up of a GA-Radiation Monitoring: System at a nuclear' plant, an intermittent lock-up of the RM-23 display was observed. This lock-up apparently causes the " Channel
DESCRIPTION GA Technologies Inc.-(the vendor) informed us that1 uring start-up of a GA-d Radiation Monitoring: System at a nuclear' plant, an intermittent lock-up of the RM-23 display was observed. This lock-up apparently causes the " Channel Activity" display to freeze at the most recent activity value for each channel.
                                                        ~
~
Activity" display to freeze at the most recent activity value for each channel.
Initially it was thought that-this condition was an anomaly related to the.
Initially it was thought that-this condition was an anomaly related to the.                         ,
specific castallation. However, as the RM-23 modules are safety related, further studies were conducted, and the results of these studies indicated that a. general-
specific castallation. However, as the RM-23 modules are safety related, further studies were conducted, and the results of these studies indicated that a. general-
                    -design. problem within the RM-23 modules did exist.
-design. problem within the RM-23 modules did exist.
SAFETY IMPLICATIONS The main control board alarms for. safety-related radiation monitors are connected to the RM-23 alarm contacts, which are dependent on RM-23 processed data.- These monitors include the containment radiation monitors, the plant--
SAFETY IMPLICATIONS The main control board alarms for. safety-related radiation monitors are connected to the RM-23 alarm contacts, which are dependent on RM-23 processed data.- These monitors include the containment radiation monitors, the plant--
stack radiation monitors, the Fuel Handling Building radiation monitors, and other post-accident radiation monitors. Without operational RM-23 modules, the
stack radiation monitors, the Fuel Handling Building radiation monitors, and other post-accident radiation monitors. Without operational RM-23 modules, the
                      ~ control room. audible and visual alarms1 based on these monitors cannot be i                     initiated. Although there are safety-related recorders which would provide L'
~ control room. audible and visual alarms based on these monitors cannot be 1
                    . radiation level information from these monitors as well as other indirect s                indications of the alarm condition, the primary alarm would be lost-and therefore' plant' safety would be affected if this deficiency were left uncorrected.
i initiated. Although there are safety-related recorders which would provide L
. radiation level information from these monitors as well as other indirect indications of the alarm condition, the primary alarm would be lost-and s
therefore' plant' safety would be affected if this deficiency were left uncorrected.
CORRECTIVE ACTION
CORRECTIVE ACTION
                    -Nonconformance Report W3-5744 was initiated to track and document corrective
-Nonconformance Report W3-5744 was initiated to track and document corrective
                    . action.
. action.
The vendor modified'the RM-23 modules to provide them with more memory capacity which permits computer software changes to eliminate lock-ups.
The vendor modified'the RM-23 modules to provide them with more memory capacity which permits computer software changes to eliminate lock-ups.
1 All corrective action.is complete and Ebasco (Engineering and Quality Assurance)
1 All corrective action.is complete and Ebasco (Engineering and Quality Assurance)
                    ;has reviewed and accepted all the supporting documentation.
;has reviewed and accepted all the supporting documentation.
This report is submitted as the Final Report.
This report is submitted as the Final Report.
h
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Latest revision as of 00:28, 21 December 2024

Final Rept of Significant Const Deficiency 72 Re Radiation Monitoring Sys RM-23 Control Modules Mfg by Ga Technologies, Inc.Nonconformance Rept W3-5744 Initiated & Modules Modified.Also Reported Per Part 21
ML20024E006
Person / Time
Site: Waterford 
Issue date: 07/28/1983
From: Drummond F
LOUISIANA POWER & LIGHT CO.
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, W3I83-0248, W3I83-248, NUDOCS 8308090018
Download: ML20024E006 (2)
v • d • e


Text

4-s l OUISIANA P O W E R & L i G H T! P O BOX 6008

  • NEW OnLEANS. LOUISIANA 70174 242 OeLanONOe stater
  • (504) 366-2345 MlOOLE SOUTH uTiuriES SYSTEM July 28, 1983 W3183-0248 Q-3-A35.07.72

, -f_= &

t Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission tj

.L!0,1 611 Ryan Plaza Drive, Suite 1000 AIS - 31983 1

hg Arlington, Texas 76012 as

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 72

" Radiation Monitoring System RM-23 Control Modules" Final Report

REFERENCE:

LP&L letter W3183-3225 dated July 5, 1983

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 72,

" Radiation Monitoring System RM-23 Control Modules".

If you have any questions, please advise.

Very truly ours, V **'

F. J. Drummond Project Support Manager - Nuclear Attachment FJD/WAC/ MAL:keh cc:

1) Director 3)

Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 (w/15 copies)

2) Director 4)

Mr. W. M. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 (w/1 copy)

F308090018 830728 PDR ADOCK 05000382 O

PDR

\\{

.t -

o-s FINAL REPORT OF SIGNIFICANT CONSTRUCTION = DEFICIENCY NO. 72-

-, - RADIATION MONITORING SYSTEM RM 23 CONTROL MODULES"

~

INTRODUCTION Thisreportissubmittedpursuantto10CFR50.5$(e).. It describes deficiencies

~

which existed in the radiation monitoring system RM-23 modules. This deficiency fis considered reportable under the: requirements of'10CFR50.55(e).

. General Atomic Technologies, Inc. of San Diego, California has informed LP&L-

.that-this problem has been reported to the Nuclear Regulatory Commission. pursuant' cto'10CFR21.

DESCRIPTION GA Technologies Inc.-(the vendor) informed us that1 uring start-up of a GA-d Radiation Monitoring: System at a nuclear' plant, an intermittent lock-up of the RM-23 display was observed. This lock-up apparently causes the " Channel Activity" display to freeze at the most recent activity value for each channel.

~

Initially it was thought that-this condition was an anomaly related to the.

specific castallation. However, as the RM-23 modules are safety related, further studies were conducted, and the results of these studies indicated that a. general-

-design. problem within the RM-23 modules did exist.

SAFETY IMPLICATIONS The main control board alarms for. safety-related radiation monitors are connected to the RM-23 alarm contacts, which are dependent on RM-23 processed data.- These monitors include the containment radiation monitors, the plant--

stack radiation monitors, the Fuel Handling Building radiation monitors, and other post-accident radiation monitors. Without operational RM-23 modules, the

~ control room. audible and visual alarms based on these monitors cannot be 1

i initiated. Although there are safety-related recorders which would provide L

. radiation level information from these monitors as well as other indirect indications of the alarm condition, the primary alarm would be lost-and s

therefore' plant' safety would be affected if this deficiency were left uncorrected.

CORRECTIVE ACTION

-Nonconformance Report W3-5744 was initiated to track and document corrective

. action.

The vendor modified'the RM-23 modules to provide them with more memory capacity which permits computer software changes to eliminate lock-ups.

1 All corrective action.is complete and Ebasco (Engineering and Quality Assurance)

has reviewed and accepted all the supporting documentation.

This report is submitted as the Final Report.

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