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| issue date = 09/04/1985
| issue date = 09/04/1985
| title = Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
| title = Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
| author name = SPECTOR S N
| author name = Spector S
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:GlNNA STAmpg UNlT¹S COMPt Eon OATE:-ROCHESTER GAS AND ELECTRIC CORPORATIO T!IVIE;'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO.J A-25.4 REV.NO.8 REACTOR POST TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW PLANT S ERINTENDENT EFFECTIVE DATE QA~NON-QA CATEGORY 1.0 REVIEWED BY: THIS PROCEDURE CONTAINS 7 PAGES S509>00077 S50903'-PDR ADOCK,05000244'
{{#Wiki_filter:GlNNA STAmpg UNlT ¹S COMPt Eon OATE:-
."..P.: "",PDR 1 i 1 A-25':1 A-25.4 REACTOR POST TRIP REVIEW 1~0 PURPOSE: 1~2 To define duties and responsibilities for the conduct of a reactor post trip review.This review will be conducted to determine the causes of all unplanned reactor trips (i.e.opening of trip breakers without all control rods fully inserted)at Ginna Station.To define the scope of the review and the records that must be reviewed to perform this assessment.
ROCHESTER GAS AND ELECTRIC CORPORATIO       T!IVIE;
2'
                                    'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. J A-25.4                       REV. NO. 8 REACTOR POST TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW                             PLANT S ERINTENDENT EFFECTIVE DATE QA~     NON-QA             CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS     7   PAGES S509>00077 S50903'-
.".. P.:     ",PDR PDR "ADOCK,05000244'
 
i 1
1
 
A-25 ':1 A-25.4 REACTOR POST   TRIP REVIEW 1~0     PURPOSE:
To define duties and responsibilities for the conduct of a reactor post trip review. This review will be conducted to determine the causes of all unplanned reactor trips (i.e. opening of trip breakers without all control rods fully inserted) at Ginna Station.
1~2      To define the scope of the review and the records that must be reviewed to perform this assessment.
2 '    


==REFERENCES:==
==REFERENCES:==


2.1 2.2 2'2'2.5 Facility Technical Specifications A-25"Reporting of Unusual Plant Conditions" A-25.1"Ginna Station Event Report" ,0-9.3"NRC Immediate Notification" Internal NRC Memo From R.W.Starostecki, Director,.DPRP 3.0 INSTRUCTIONS:
2.1     Facility Technical Specifications 2.2     A-25 "Reporting   of Unusual Plant Conditions" 2 '      A-25.1 "Ginna Station Event Report" 2 '    ,0-9.3 "NRC Immediate   Notification" 2.5      Internal NRC Memo From R.W. Starostecki, Director, .DPRP
3.1 Control Room 0 erator 3~1~1 Submit an A-25.1,"Unusual Event Report"'.3~1.2 Inform Shift Supervisor of unusual conditions or observations made during the event.3'Shift Technical Advisor 3.2.1 The Shift Technical Advisor shall perform a preliminary assessment of the event.This shall be documented by completion of the attached Post-Trip Review Form.
 
A-25~4 2 3''Upon completion of the form, forward it to the Shift Supervisor for inclusion with the A-25.4 Review.3.2.3 The Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.
==3.0 INSTRUCTIONS==
3.3 Other Plant Personnel 3~3~1 Any other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.)should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.3'3'.1 Shift Su ervisor The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any other information available to make a prelim-inary assessment of the cause of the Reactor Trip.The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment.
3.1     Control Room 0 erator 3~1~1   Submit an A-25.1, "Unusual Event Report"'.
The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.
3 ~ 1.2 Inform Shift Supervisor of unusual conditions or observations   made   during the event.
3.4.2 3''.1 The Shift Supervisor shall review the event and assign one of the following classifications to the event.(Mark other classifications N/A).Condition One-the cause of the trip is positively known.All safety-related and other important equipment functioned properly during the trip.3''.2 Condition Two-the cause of the trip is positively known.Some sa f ety-related and/or other important equipment functioned in an abnormal or degraded manner.3.4.2'Condition Three-the cause of the trip is not positively known.
3 '     Shift Technical Advisor 3.2.1   The Shift Technical Advisor shall perform a preliminary assessment of the event. This shall be documented by completion of the attached Post-Trip Review Form.
A-25.4:3 3'Dut En ineer 3~5~1 The Duty Engineer shall review the Shift Supervisor's"assessment of the eve'nt.If the computer post trip review'rintout is available it shall also be review-ed.The Duty Engineer shall make an assessment of the cause of the event.The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.
 
3.5.2 The Duty Engineer shall review the event classificat-ion.If the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.3.6 Plant Su erintendent 3.6~1 The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC)with the purpose of reviewing the event.3~6.2 All events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.
A-25 ~ 4 2 3 ' '     Upon completion of the form, forward   it to the Shift Supervisor for inclusion with the A-25.4 Review.
3.6.3 In the event that the cause of the trip is positively known and all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.
3.2.3     The Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.
3'PORC 3.7.1 Reports shall be presented by Subcommittee Chairman as identified on Attachment B.3.7'3''PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event.Attachment C identifies necessary criteria for plant restart.I PORC shall determine if all safety or Tech Spec.que-stions are resolved.3.7.4 PORC shall recommend to the Plant Superintendent whether or not to allow a Reactor restart.
3.3       Other Plant Personnel 3 ~ 3 ~ 1 Any other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.) should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.
l A-25.4:4 3'0 erations Mana er 3.8~1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.3.9 Corrective Actions 3.9.1 Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.
3 '       Shift Su ervisor 3 '.1     The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any other information available to make a prelim-inary assessment of the cause of the Reactor Trip. The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment. The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.
3.9'The plant shall not be made critical after a trip until the event has been reviewed and the cause is known.4.0 RECORDS: 4.1 4.2 Records of the review shall be noted in the minutes of the PORC meeting.The PORC minutes shall be the permanent record of the review.4.3 All material used in the Post Trip Review shall be attached to this procedure and forwarded to Central Records.COMPLETION DATE COMPLETED BY: OPERATIONS MANAGER:
3.4.2     The   Shift Supervisor shall review the event and assign one of the following classifications to the event. (Mark other classifications N/A) .
A-25.4:5 A-25.4 REACTOR POST-TRIP REVIEW (Refer to A-25.4 for Instructions)
3 '  '.1 Condition One the cause of the trip is positively known. All safety-related and other important equipment functioned properly during the trip.
TIME OF TRIP: DATE: II.DESCRIPTION OF EVENT: III.ACTIONS PERFORMED BY STA: a)Procedures referred to: b)Parameters observed: c)Recognition/Diagnosis reached: d)Advice given to Shift Supervisor:
3 '   '.2 Condition Two - the cause of the trip is positively known. Some sa fety-related and/or other important equipment functioned in an abnormal or degraded manner.
IV.CAUSE OF EVENT: V.ADDITIONAL COMMENTS: SHIFT TECHNICAL ADVISOR:
3.4.2 '   Condition Three - the cause of the         trip is   not positively known.
A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet Technical and Tech.S ec.uestions and Review A ainst A licable Information from the UFSAR and Prior Transients Technical Manager alternates:
 
Nuclear Engineer Duty Engineer Evaluation of E i ment Malfunctions and Re air Plans Maintenance Manager alternates:
A-25.4:3 3 '       Dut   En ineer 5~1   The Duty Engineer shall review the Shift Supervisor's 3 ~
I&C Supervisor Maintenance Supervisor Post Tri Review Cause Identification A-25.4 Re ort Summar Operations Manager P alternates:
        "assessment of the eve'nt.
Operations Supervisor Duty Engineer Startu Plans and Se uence Planner A-25':7 ATTACHMENT C PORC REVIEW CRITERIA 2~3~4~5~6.7~8.Root cause of problem(s) has been identified.
review'rintout is available Ifit shall the computer post trip also be review-ed. The Duty Engineer   shall make an assessment of the cause of the event. The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.
A clear sequence of events has been determined.
3.5.2     The Duty Engineer   shall review the event   classificat-ion. If the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.
All near term corrective actions have been taken to resolve the root cause of the trip.Long term corrective actions are outline and a method for tracking them has been established.
3.6       Plant Su erintendent 3.6 ~ 1 The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC) with the purpose of reviewing the event.
All ma j or sa f ety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.
3 ~ 6.2   All   events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.
Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any f ailures are repetitive in nature or involve common mode failures.Separate tracking documents may be initiated to follow corrective action on these items.Items 6, 7, and 8 should include the information being used for comparison.}}
: 3. 6.3   In the event that the cause of the trip is positively known and     all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.
3 '       PORC 3.7.1     Reports shall be presented by Subcommittee Chairman as identified on Attachment B.
3.7 '     PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event. Attachment C identifies necessary   criteria for plant restart.
I 3  ' '    PORC   shall determine stions are resolved.
if all safety or Tech Spec. que-3.7.4     PORC   shall recommend to the Plant Superintendent whether or not to allow a Reactor     restart.
 
l A-25.4:4 3 '     0 erations   Mana er 3.8 ~ 1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.
3.9     Corrective Actions 3.9.1   Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.
3.9 '   The plant shall not       be made   critical after   a trip until   the event has been reviewed       and the cause is known.
 
==4.0 RECORDS==
4.1     Records   of the review shall     be noted   in the minutes of the   PORC meeting.
4.2    The PORC minutes shall be the permanent record of the review.
4.3     All material     used in the Post Trip   Review to shall be attached to this procedure and       forwarded       Central Records.
COMPLETION DATE COMPLETED BY:
OPERATIONS MANAGER:
 
A-25.4:5 REACTOR POST TRIP REVIEW (Refer to A-25.4 for Instructions)
A-25.4 TIME OF TRIP:                       DATE:
II. DESCRIPTION OF EVENT:
III. ACTIONS PERFORMED BY STA:
a)   Procedures referred to:
b)   Parameters observed:
c)   Recognition/Diagnosis reached:
d)   Advice given to   Shift Supervisor:
IV. CAUSE OF EVENT:
V. ADDITIONAL COMMENTS:
SHIFT TECHNICAL ADVISOR:
 
A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet       Technical and Tech. S ec. uestions and Review A ainst A   licable Information from the   UFSAR and   Prior Transients Technical Manager             alternates: Nuclear Engineer Duty Engineer Evaluation of   E i ment Malfunctions and Re air Plans Maintenance Manager           alternates: I&C Supervisor Maintenance Supervisor Post Tri Review   Cause Identification A-25.4   Re ort Summar P
Operations Manager           alternates: Operations Supervisor Duty Engineer Startu   Plans and Se uence Planner
 
A-25 ':7 ATTACHMENT C PORC REVIEW CRITERIA Root cause of problem(s) has been identified.
2 ~    A clear sequence of events has been determined.
3 ~    All near term corrective actions have been taken to resolve the root cause of the trip.
4 ~    Long term corrective actions are outline and a method for tracking them has been established.
5 ~    All ma j or sa fety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.
: 6. Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.
7  ~  Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.
: 8. Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any failures are repetitive in nature or involve common mode failures. Separate tracking documents may be initiated to follow corrective action on these items.
Items 6, 7, and 8 should include the information being used for comparison.}}

Latest revision as of 19:56, 29 October 2019

Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
ML17254A536
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/04/1985
From: Spector S
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17254A535 List:
References
A-25.4, NUDOCS 8509100077
Download: ML17254A536 (10)


Text

GlNNA STAmpg UNlT ¹S COMPt Eon OATE:-

ROCHESTER GAS AND ELECTRIC CORPORATIO T!IVIE;

'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. J A-25.4 REV. NO. 8 REACTOR POST TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW PLANT S ERINTENDENT EFFECTIVE DATE QA~ NON-QA CATEGORY 1.0 REVIEWED BY:

THIS PROCEDURE CONTAINS 7 PAGES S509>00077 S50903'-

.".. P.: ",PDR PDR "ADOCK,05000244'

i 1

1

A-25 ':1 A-25.4 REACTOR POST TRIP REVIEW 1~0 PURPOSE:

To define duties and responsibilities for the conduct of a reactor post trip review. This review will be conducted to determine the causes of all unplanned reactor trips (i.e. opening of trip breakers without all control rods fully inserted) at Ginna Station.

1~2 To define the scope of the review and the records that must be reviewed to perform this assessment.

2 '

REFERENCES:

2.1 Facility Technical Specifications 2.2 A-25 "Reporting of Unusual Plant Conditions" 2 ' A-25.1 "Ginna Station Event Report" 2 ' ,0-9.3 "NRC Immediate Notification" 2.5 Internal NRC Memo From R.W. Starostecki, Director, .DPRP

3.0 INSTRUCTIONS

3.1 Control Room 0 erator 3~1~1 Submit an A-25.1, "Unusual Event Report"'.

3 ~ 1.2 Inform Shift Supervisor of unusual conditions or observations made during the event.

3 ' Shift Technical Advisor 3.2.1 The Shift Technical Advisor shall perform a preliminary assessment of the event. This shall be documented by completion of the attached Post-Trip Review Form.

A-25 ~ 4 2 3 ' ' Upon completion of the form, forward it to the Shift Supervisor for inclusion with the A-25.4 Review.

3.2.3 The Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.

3.3 Other Plant Personnel 3 ~ 3 ~ 1 Any other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.) should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.

3 ' Shift Su ervisor 3 '.1 The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any other information available to make a prelim-inary assessment of the cause of the Reactor Trip. The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment. The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.

3.4.2 The Shift Supervisor shall review the event and assign one of the following classifications to the event. (Mark other classifications N/A) .

3 ' '.1 Condition One the cause of the trip is positively known. All safety-related and other important equipment functioned properly during the trip.

3 ' '.2 Condition Two - the cause of the trip is positively known. Some sa fety-related and/or other important equipment functioned in an abnormal or degraded manner.

3.4.2 ' Condition Three - the cause of the trip is not positively known.

A-25.4:3 3 ' Dut En ineer 5~1 The Duty Engineer shall review the Shift Supervisor's 3 ~

"assessment of the eve'nt.

review'rintout is available Ifit shall the computer post trip also be review-ed. The Duty Engineer shall make an assessment of the cause of the event. The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.

3.5.2 The Duty Engineer shall review the event classificat-ion. If the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.

3.6 Plant Su erintendent 3.6 ~ 1 The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC) with the purpose of reviewing the event.

3 ~ 6.2 All events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.

3. 6.3 In the event that the cause of the trip is positively known and all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.

3 ' PORC 3.7.1 Reports shall be presented by Subcommittee Chairman as identified on Attachment B.

3.7 ' PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event. Attachment C identifies necessary criteria for plant restart.

I 3 ' ' PORC shall determine stions are resolved.

if all safety or Tech Spec. que-3.7.4 PORC shall recommend to the Plant Superintendent whether or not to allow a Reactor restart.

l A-25.4:4 3 ' 0 erations Mana er 3.8 ~ 1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.

3.9 Corrective Actions 3.9.1 Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.

3.9 ' The plant shall not be made critical after a trip until the event has been reviewed and the cause is known.

4.0 RECORDS

4.1 Records of the review shall be noted in the minutes of the PORC meeting.

4.2 The PORC minutes shall be the permanent record of the review.

4.3 All material used in the Post Trip Review to shall be attached to this procedure and forwarded Central Records.

COMPLETION DATE COMPLETED BY:

OPERATIONS MANAGER:

A-25.4:5 REACTOR POST TRIP REVIEW (Refer to A-25.4 for Instructions)

A-25.4 TIME OF TRIP: DATE:

II. DESCRIPTION OF EVENT:

III. ACTIONS PERFORMED BY STA:

a) Procedures referred to:

b) Parameters observed:

c) Recognition/Diagnosis reached:

d) Advice given to Shift Supervisor:

IV. CAUSE OF EVENT:

V. ADDITIONAL COMMENTS:

SHIFT TECHNICAL ADVISOR:

A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet Technical and Tech. S ec. uestions and Review A ainst A licable Information from the UFSAR and Prior Transients Technical Manager alternates: Nuclear Engineer Duty Engineer Evaluation of E i ment Malfunctions and Re air Plans Maintenance Manager alternates: I&C Supervisor Maintenance Supervisor Post Tri Review Cause Identification A-25.4 Re ort Summar P

Operations Manager alternates: Operations Supervisor Duty Engineer Startu Plans and Se uence Planner

A-25 ':7 ATTACHMENT C PORC REVIEW CRITERIA Root cause of problem(s) has been identified.

2 ~ A clear sequence of events has been determined.

3 ~ All near term corrective actions have been taken to resolve the root cause of the trip.

4 ~ Long term corrective actions are outline and a method for tracking them has been established.

5 ~ All ma j or sa fety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.

6. Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.

7 ~ Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.

8. Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any failures are repetitive in nature or involve common mode failures. Separate tracking documents may be initiated to follow corrective action on these items.

Items 6, 7, and 8 should include the information being used for comparison.