ML19318A850: Difference between revisions

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| number = ML19318A850
| number = ML19318A850
| issue date = 05/20/1980
| issue date = 05/20/1980
| title = Responds to NRC 800423 Ltr Re Violations Noted in IE Insp Repts 50-259/80-13,50-260/80-11 & 50-296/80-12.Corrective Actions:Personnel Instructed to Keep Shift Engineer Informed of Work Status & Sys Status Procedure Revised
| title = Responds to NRC Re Violations Noted in IE Insp Repts 50-259/80-13,50-260/80-11 & 50-296/80-12.Corrective Actions:Personnel Instructed to Keep Shift Engineer Informed of Work Status & Sys Status Procedure Revised
| author name = Mills L
| author name = Mills L
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 8006240258
| document report number = NUDOCS 8006240258
| title reference date = 04-23-1980
| package number = ML19318A846
| package number = ML19318A846
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
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{{#Wiki_filter:.
{{#Wiki_filter:.
TENNECSEE VALLEY AUTHORITY
TENNECSEE VALLEY AUTHORITY
        ,,)
,,)
t                                           CHATTANOOGA TENNESSEE 374o1 400 Chestnut Street Tower II                 .
t CHATTANOOGA TENNESSEE 374o1 400 Chestnut Street Tower II
: r. v   .
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May 20, 1980 t
x.
Mr. James P. 'O'Reilly, Director Office of Inspection and Enforcement A"
May 20, 1980                     $
U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street f
t       ,
Atlanta, Georgia 30303
Mr. James P. 'O'Reilly, Director                                           **
Office of Inspection and Enforcement                                       A U.S. Nuclear Regulatory Commission                                           "
Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303                                                                 f


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==
Enclosed is our response to R. C. Lewis' April 23, 1980, letter, RII:RFS 50-259/80-13, 50-260/80-11, and 50-296/80-12, concerning activities at Browns Ferry Nuclear Plant which appeared to be in noncomplidnce with NRC requirements.
Enclosed is our response to R. C. Lewis' {{letter dated|date=April 23, 1980|text=April 23, 1980, letter}}, RII:RFS 50-259/80-13, 50-260/80-11, and 50-296/80-12, concerning activities at Browns Ferry Nuclear Plant which appeared to be in noncomplidnce with NRC requirements.
We have reviewed the above inspection report and find no proprietary information in it. If you have any questions, please call Jim Domer at FTS 854-2014.
We have reviewed the above inspection report and find no proprietary information in it.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure l
If you have any questions, please call Jim Domer at FTS 854-2014.
l i
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure i
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* i. - g                                             ENCLOSURE RESPONSE TO R. C. LEWIS' LETTER DATED APRIL-23, 1980,  
* i. -
ENCLOSURE g
RESPONSE TO R. C. LEWIS' LETTER DATED APRIL-23, 1980,  


==REFERENCE:==
==REFERENCE:==
RII:1)FS 50-259/80-13, 50-260/80-11, 50-296/80-12
RII:1)FS 50-259/80-13, 50-260/80-11, 50-296/80-12
                                                                                              ~'
~'
INFRACTION As required by Technical Specification 3.5.F.2, the Reactor Core
INFRACTION As required by Technical Specification 3.5.F.2, the Reactor Core
                                        ~
~
Isolation Coolant System (RCICS) may be inoperable for a period
Isolation Coolant System (RCICS) may be inoperable for a period
                                                      ~
~
                                    . not to exceed 7 days if 'the High Pressure Coo.' ant Injection System I ,3                       (HPCIS) is operable during such time period. In addition, Browns Ferry Standard Practice 12.2 requires the shif t engineer, assistant
. not to exceed 7 days if 'the High Pressure Coo.' ant Injection System I,3 (HPCIS) is operable during such time period. In addition, Browns Ferry Standard Practice 12.2 requires the shif t engineer, assistant
                                    .shif t engineer, and unit operator to keep journais and these journais shall contain significant equipment malfunctions.
.shif t engineer, and unit operator to keep journais and these journais shall contain significant equipment malfunctions.
Contrary to the above, on December 8,1979, RCICS was inoperable for approximately 4 hours for replacement and calibration 'of the Electro Governor-Mechanical (EGM) box and HPCIS was not determined to be operable.       In addition, neither the unit operator, assistant
Contrary to the above, on December 8,1979, RCICS was inoperable for approximately 4 hours for replacement and calibration 'of the Electro Governor-Mechanical (EGM) box and HPCIS was not determined to be operable.
                                . shif t cu;;ineer, nor the shif t engineer documented in their journals that RCICS was inoperable for replacement and calibr,ation
In addition, neither the unit operator, assistant shif t cu;;ineer, nor the shif t engineer documented in their journals that RCICS was inoperable for replacement and calibr,ation of the ECM box.
* of the ECM box.                                                 .
 
RESPONSE                                                                             -
===RESPONSE===
                          ' Corrective Steos Taken and Results Achieved                                                 ;
' Corrective Steos Taken and Results Achieved At the time of the occurrence, unit 3 was in the initial startup testing phase of operation following refueling outage.
At the time of the occurrence, unit 3 was in the initial startup testing phase of operation following refueling outage.
.Before startup, the RCICS and HPCIS were proven operable on auxiliary boiler steam by-appropriate MOV and flow test surveillance instructions. The refueling test instructions' require MOV and flow test on HPCIS and RCICS with rated reactor conditions. The RCICS MOV and flow test data was acceptable for the test condition, however, the flow controller was erratic which resulted in oscil-
                          .Before startup, the RCICS and HPCIS were proven operable on auxiliary boiler steam by-appropriate MOV and flow test surveillance instructions. The refueling test instructions' require MOV and flow test on HPCIS and RCICS with rated reactor conditions. The RCICS MOV and flow test data was acceptable for the test condition, however, the flow controller was erratic which resulted in oscil-           )
)
lation of discharge flow. The shift engineer, assistant shift engineer and                 4 l
lation of discharge flow. The shift engineer, assistant shift engineer and 4
unit operator were aware of the flow controller problem, but did not consider the RCICS inoperable. Plant engineering and maintenance personnel were summoned to correct the probleu. However, poor communications between operations and. maintenance personnel resulted in an understanding by the shift engineer,               l I
unit operator were aware of the flow controller problem, but did not consider the RCICS inoperable. Plant engineering and maintenance personnel were summoned to correct the probleu. However, poor communications between operations and. maintenance personnel resulted in an understanding by the shift engineer, 4;-
4
assistant shif t engineer, and unit operator that only minor adjustments were
;-                           assistant shif t engineer, and unit operator that only minor adjustments were
-required and, therefore, they did not declare the RCICS to be inoperable. The-HPCIS operability surveillance instruction was not performed and the event was
                            -required and, therefore, they did not declare the RCICS to be inoperable. The-             !
~
;                                                                                                                        l HPCIS operability surveillance instruction was not performed and the event was
not logged in' journals because.of the communication error and misunderstanding.
                                                                            ~
+
not logged in' journals because .of the communication error and misunderstanding.
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                                                                                  ~
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                    .l''2 g ;i -;
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Corrective Steps Taken and Results Achieved (Continued) e Personnel involved in the error have been reminded of the consequences of poor communications and instructed to keep the shift engineer informed of status as
.l''2 Corrective Steps Taken and Results Achieved (Continued) e Personnel involved in the error have been reminded of the consequences of poor communications and instructed to keep the shift engineer informed of status as work progresses. ~ Planti procedures have been revised to require more detailed
      ; ;,,                work progresses. ~ Planti procedures have been revised to require more detailed
. documentation and monitoring of systes s tatus.
                          . documentation and monitoring of systes s tatus.
Corrective Steps Taken to Avoid Further Noncomo11ance Operations personnel will review this incident in supplemental training.
Corrective Steps Taken to Avoid Further Noncomo11ance                                     -
?!aintenance and engineering personnel have discussed the incident and were made aware of related problems.
Operations personnel will review this incident in supplemental training.
                          ?!aintenance and engineering personnel have discussed the incident and were made aware of related problems.                          ..
Date Full Comoliance Achieved Supplemental training sessions will be completed by June 17, 1980.
Date Full Comoliance Achieved Supplemental training sessions will be completed by June 17, 1980.
                                                  \
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Latest revision as of 20:54, 1 January 2025

Responds to NRC Re Violations Noted in IE Insp Repts 50-259/80-13,50-260/80-11 & 50-296/80-12.Corrective Actions:Personnel Instructed to Keep Shift Engineer Informed of Work Status & Sys Status Procedure Revised
ML19318A850
Person / Time
Site: Browns Ferry  
Issue date: 05/20/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19318A846 List:
References
NUDOCS 8006240258
Download: ML19318A850 (3)


Text

.

TENNECSEE VALLEY AUTHORITY

,,)

t CHATTANOOGA TENNESSEE 374o1 400 Chestnut Street Tower II

r. v i-x.

May 20, 1980 t

Mr. James P. 'O'Reilly, Director Office of Inspection and Enforcement A"

U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street f

Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Enclosed is our response to R. C. Lewis' April 23, 1980, letter, RII:RFS 50-259/80-13, 50-260/80-11, and 50-296/80-12, concerning activities at Browns Ferry Nuclear Plant which appeared to be in noncomplidnce with NRC requirements.

We have reviewed the above inspection report and find no proprietary information in it.

If you have any questions, please call Jim Domer at FTS 854-2014.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure i

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ENCLOSURE g

RESPONSE TO R. C. LEWIS' LETTER DATED APRIL-23, 1980,

REFERENCE:

RII:1)FS 50-259/80-13, 50-260/80-11, 50-296/80-12

~'

INFRACTION As required by Technical Specification 3.5.F.2, the Reactor Core

~

Isolation Coolant System (RCICS) may be inoperable for a period

~

. not to exceed 7 days if 'the High Pressure Coo.' ant Injection System I,3 (HPCIS) is operable during such time period. In addition, Browns Ferry Standard Practice 12.2 requires the shif t engineer, assistant

.shif t engineer, and unit operator to keep journais and these journais shall contain significant equipment malfunctions.

Contrary to the above, on December 8,1979, RCICS was inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for replacement and calibration 'of the Electro Governor-Mechanical (EGM) box and HPCIS was not determined to be operable.

In addition, neither the unit operator, assistant shif t cu;;ineer, nor the shif t engineer documented in their journals that RCICS was inoperable for replacement and calibr,ation of the ECM box.

RESPONSE

' Corrective Steos Taken and Results Achieved At the time of the occurrence, unit 3 was in the initial startup testing phase of operation following refueling outage.

.Before startup, the RCICS and HPCIS were proven operable on auxiliary boiler steam by-appropriate MOV and flow test surveillance instructions. The refueling test instructions' require MOV and flow test on HPCIS and RCICS with rated reactor conditions. The RCICS MOV and flow test data was acceptable for the test condition, however, the flow controller was erratic which resulted in oscil-

)

lation of discharge flow. The shift engineer, assistant shift engineer and 4

unit operator were aware of the flow controller problem, but did not consider the RCICS inoperable. Plant engineering and maintenance personnel were summoned to correct the probleu. However, poor communications between operations and. maintenance personnel resulted in an understanding by the shift engineer, 4;-

assistant shif t engineer, and unit operator that only minor adjustments were

-required and, therefore, they did not declare the RCICS to be inoperable. The-HPCIS operability surveillance instruction was not performed and the event was

~

not logged in' journals because.of the communication error and misunderstanding.

+

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L j

._.g-77

~ ~ ~

- _ _ = _ _

.=. :....,

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.l2 Corrective Steps Taken and Results Achieved (Continued) e Personnel involved in the error have been reminded of the consequences of poor communications and instructed to keep the shift engineer informed of status as work progresses. ~ Planti procedures have been revised to require more detailed

. documentation and monitoring of systes s tatus.

Corrective Steps Taken to Avoid Further Noncomo11ance Operations personnel will review this incident in supplemental training.

?!aintenance and engineering personnel have discussed the incident and were made aware of related problems.

Date Full Comoliance Achieved Supplemental training sessions will be completed by June 17, 1980.

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