ML20138N365
| ML20138N365 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/31/1985 |
| From: | Marquette Rogers Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20138N351 | List: |
| References | |
| NUDOCS 8511050172 | |
| Download: ML20138N365 (27) | |
Text
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s HOPE CREEK GENERATING STATION OP-AP.2Z-101(Q)
POST REACTOR SCRAM /ECCS ACTUATION REVIElf AND APPROVAL REQUIREMENTS Remarks:
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-2/1/83 Prepared By:
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Revieue_d By:
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N fperating Engr - Hope Creek Dhte ALARA Review:
Radiation Protection Dept.
Date Reviewed By:
SQAE Da te SORC Review:
Chairman Date Mtg. No.
Approved By:
Operations Mgr - Hope Creek Da te P
A O P-AP. Z Z -101 ( O)
Re v. B
OP-AP.ZZ-101(Q)
POST REACTOR SCRAM /ECCS ACTUATION REVIEW AND APPROVAL REOUIREMENTS TABLE OF CONTENTS SECTIOd-TITLE PAGE 1.0 PURPOSE..........................................,
2
2.0 REFERENCES
2 3.0 DEFINITIONS......................................
2 4.0 RESPONSIBILITIES.................................
2 5.0 PROCEDURE........................................
3 5.1 Data Collection.............................
3 I
5.2 Data Evaluation.............................
5 i
e 5.3 Approval Requirments for Reactor Startup following a Reactor Scram /ECCS Actuation....
6 5.4 Data Filing and Distribution................
6 ATTACHMENTS 1
Post Reactor Scram /ECCS Actuation Review 2
Fact Finding Questionnaire 3
Sequence of Events Checklists (later) 4 Sequence of Events Standards'(later) 5 Simplified Logics and Instrument Tables (,l a te r )
OP-AP.ZZ-101(0) 1 Rev. B
OP-AP.22-101(Q)
POST REACTOR SCRAM /ECCS ACTUATION REVIEW AND APPROVAL REQUIREMENTS 1.0 PURPOSE The purpose of'this procedure is to establish the requirements to perform and document a formal review for all Reactor Scram /ECCS Actuation events.
It also provides a systematic method for diagnosing the causes of Reactor Scram /ECCS Actuations, ascertaining the proper functio'ning of safety-related and other important equipment prior to restart, and making the determination that the plant can be restarted safety.
This procedure also establishes the requirements and criteria that must be met prior to startup following any Reactor Scram /ECCS Actuation.
2.0 REFERENCES
2.1 INPO GOOD PRACTICE, OP-211, POST TRIP REVIEWS.
September 1984 (INPO 84-029).
1 2.2 SALEM GENERATING STATION AD-16, Post Reactor Trip / Safety Injection Review, Rev. 5 2.3 Generic Lette r 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events", July 8, 1983.
2.4 SA-AP.ZZ-002(O), " Station Organization and Operating Practices", Re v.
1.
3.0 DEFINITIONS 3.1 Data Package - a collection of information used to conduct an investigation and review of any Reactor Scram /ECCS Actuation.
The data package includes the.
completed Post Scram /ECCS Actuation Review Report, and any hard copy recorded data such as strip charts, computer printouts, fact finding questionnaires, etc.
4.0 RESPONSIBILITIES 4.1 Senior Nuclear Shift Supervisor - Investigates and evaluates the cause of the Reactor Scram /ECCS Actuation and notifies the Operations Manager of his findings.
OP-AP.22-101(0) 2 Rev. B
OP-AP.ZZ-101(0)
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4.2 Shif t Technical Advisor - Assists and advises the Senior Nuclear Shift Supervisor in the compiling of the Data Package and evaluation of the report.
4.3.
Operations Manager - Reviews the findings with the SNSS and presents them to the SORC.
7 4'. 4 SORC - Reviews the results of the investigation and makes recommendations to the General Manager.
4.5 General Manager - After satisfactory completion o'f SORC recommendations, may either grant or deny approval for reactor startup.
4.6 Designees for all positions shall be in accordance with SA-AP.Z Z-00 2(O).
5.0 PROCEDURE 5.1 Data Collection 5.1.1 As soon as plant conditions permit, the Senior Nuclear Shif t Supervisor shall finitia,te data collection.
5.1.2 The STA is responsible for collecting the data necessary to complete Attachment 1 Post Reactor Scram /ECCS Actuation Review.
5.1.3 The STA shall obtain a copy of the sequence of events printout and attach it to the data package.
5.l.4 Have the Shift Technician remove any recorder charts that are found to indicate important information with regard to the event.
Ensure that all tracings are. identified on the charts and the time is clearly marked.
Attach the original charts to the data package.
5.1.4.1 Examples of important recorder charts include:
a.
APRMs b.
Reactor Vessel Level c.
Recirculation Pump Suction Temperature OP-AP.ZZ-101(O) 3 Rev. B
4 OP-AP.ZZ-101(Q) d.
Core Flow e.
Rx Vessel Pressure f.
Steam Flow g.
Drywell Pressure.
h.
Suppression Chamber Level i.
Suppression Chamber Water Temperature j.
Feedwater flow k.
Condenser Vacuum 1.
S.R.V.
Tailpipe Temperature m.
Drywell Temperature 5.1.5 The STA will conduct fact finding sessions with the appropriate personnel to determin.e the cause of the event, actions taken, and observed sequence of. events. should be used as a guide for these sessions.
5.1.5.1 Any corrective actions taken during the event to investigate the consequences of the event and bring the unit to a stable condition should be included.
5.1.6 Any corrective actions that hre required prior to the units return to service shall be recorded.
5.1.7 Any alarms received which were out of the ordinary for the event and alarms which should have been received but were not have been recorded.
5.1.8 The STA shall confer with the Senior Nuclear Shif t Supervisor in order to review and evaluate the report.
OP-AP.ZZ-101(0) 4 Rev. B
OP-AP.ZZ-101(Q) 5.2 Data Evaluation 5.2.1 The Senior Nuclear Shift Supervisor shall I
evaluate the Post Scram /ECCS Actuation Data Package when completed by the STA.
The purpose of this evaluation is to determine the c
following:
5.2.1.1 All major safety-related and other equipment required to function during the event operated as anticipated or expected.
.2.1.2 The cause of the event has been clearly identified.
5.2.1.3 Any corrective actions that are required prior to the unit's return to service have been identified.
5.2.2 The simplified logic diagrame and accompanying ins trume nt tables (Attachment 5) will be used for verification of the Scram and safety-related equipment operation.
5.2.3 The verification of performance of safety-related equipment during the Post Scram Review process will be limited to the verification that the-equipment did or did not operate.
The detailed manner in which the equipment operated is sufficiently verified during surveillance testing.
5.2.4 When both the Senior Nuclear Shift Supervisor and the STA are satisfied with the conclusions, each shall sign and date the report.
5.2.5 The Senior Nuclear Shift Supervisor shall notify the Operations Manager of the event, and the subsequent findings of the report.
5.2.6 The Operations Manager reviews the Post Reactor Scram /ECCS Actuation Review Report with the Senior Nuclear Shift Supervisor.
(The Operations Manager may elect to conduct this review by telephone in direct conference with the Senior Nuclear Shif t Supervisor).-
The purpose of the Operations Manager's Review is to verify the following:
OP-AP.ZZ-101(O) 5 Rev. B
OP-AP.ZZ-101(Q) 5.2.6.1 The Post Reactor Scram /ECCS Actuation Report was properly prepared and evaluated.
5.2.6.2 The cause of the event has been c
properly identified.
5.2.6.3 All equipment and systems required to function during the event did function as designed.
5.2.6.4 Any corrective actions that are required prior to the unit's return to service have been identified, doc ume n ted, and the required corrective actions have been initiated.
5.3 Approval Requirements for Reactor Startup following a Reactor Scram /ECCS Actuation 5.3.1 Prior to requesting approval to startup the reactor af ter any Reactor Scram /ECCS Actuation, the Post Reactor Scram /ECCS Actuatiop Review must be completed and evaluated.
5.3.2 Upon satisf actory review and evaluation of the Post Reactor Scram /FrCS Review, the results shall be presented to the Station Operations Review Committee.
Upon completion of the.
evaluation of the event by the Station Operations Review Committee, the SORC shall make recommendations to the General Manager.
5.3.3 Approved for taking the reactor critical shall be granted by the General Manager ortly af ter recommendations have been made by the SORC.
The Assistant General Manager may grant the necessari approval for taking the reactor critical in the absence of the General Manager but, again, only after recommendations have been made by the SORC.
5.4 Data Filing and Distribution S.4.1 When all required reviews and approvals have been completed the data package will be forwarded to the Senior Operating Technical Supervisor (SOTS).
OP-AP.ZZ-101(0) 6 Rev. B
OP-AP.ZZ-101(Q) 5.4.2 The SOTS will incorporate the event into the Post Reactor Scram /ECCS Actuation history file.
5.4.3 -The original data package-will be forwarded to the Technical Document Room.
5.4.4 A copy of the data package will remain in the Operations Shift files for future reference.
5.4.5 Copies of the data package will be forwarqed to the following individuals.
5.4.5.1 The Technical Engineer for assistance in preparing the License Event Repor t or other reports as appropriate.
5.4.5.2 The Manager Nuclear Training for review and. inclusion in the applicable training programs.
5.4.5.3 The General Manager - Nuclear Support in order to conduct an independent review of the event. '
i 5.4.6 The SOTS will prepare a summary report on the event and issue it to all pertinent personnel in accordance with OP-AP.ZZ-105 Operations Depar tme n t Information System.
5.4.7 Make th'e appropriate revisions to any procedure which had deficiencies identified during this event.
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OP-AP.ZZ-101(Q) 7 (LAST PAGE)
Rev. B 1
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OP-AP.ZZ-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW Date of Occurrence Time of Occurrence PART A. INITIAL CONDITIONS 1.
personnel Assignments SNS'S NSS NCO ( Boa rd ) -
NCO ( Desk )
Rx Bldg Operator Aux & Services Bldg Operator Turbine Bldg Operator Shift Technician Shift Electrician Others _
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2.
Plant.sta tus Reactor Power Generator Load MW Mode Switch Position Reactor Vessel Pressure (PR 6238)
Reactor Vessel Level (LR 36838)
Reactor Feed Pumps AP101 BP101 CP101 Pri Cond Pumps AP102 BP102 CP102 Sec Cond Pumps AP137 BP137 CP137 ATTACHMENT 1 O P-AP. Z Z-101( 0 )
1 of 14 Re v. B
OP-AP.ZZ-101(0) i -
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW PART A INITIAL CONDITIONS (cont.)
CircWhr. Pumps AP501 BP501 CP501 DP501 Recir Pump Speed'AP201
% BP201 4
3.
. Evolutions in Progress at the onset of the Event.
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Surveillance Testing Yes No Trouble Shooting or Maintenance Yes No Plant Startup or Shutdown Yes No Other Activities which could have contributed to 'the event
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If the answer to any of the above questions is yes, describe the circumstances in detail.
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ATTACHMENT 1 O P-AP. Z Z-101 ( Q )
2 of 14 Rev. B l
OP-AP.22-101(0)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW PAP.T A INITIAL CONDITIONS (cont.)
4.'
hquipment/systemsoutofserviceorinoperableattheonsetof the event.
Reactor Protection System Ye s No ECCS Systems Ye s No Control Systems Ye s No Electrical Systems Yes No Major Equipment Yes No If the answer to any of the above questions is yes, describe the circumstances in detail.
i 5.
Provide any additionsal information which may have led to the initiation of the event.
ATTACHMENT 1 OP-AP.22-101(O) 3 of 14 Re v. B 9-s-
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OP-AP.ZZ-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW PART B DESCRIPTION OF THE EVENT 1.
R,eactor Protection System type of Scram:
Manual Automatic Actuation Time Cause: (if automatic)
Reason: (if manual) a.
Verify the following:
(1.)
All Rods fully inserted (2.)
Scram Discharge Volume isolated Inboard Outboard b.
From the computer printout, determine the scram initiating signal.
Scram initiated by c.
Comments:
ATTACHMENT 1 OP-AP.ZZ-101(0) 4 of 14 Re v. B l
OP-AP.ZZ-101(0)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 2.
ECCS Actuations a. Were any ECCS System Actuations required during the event Yes No b.
Provide the actuation signal dnd time for any ECCS Systems which actuated.
Actuation Signal Time HPCI RCIC CS LPCI ADS c.
If any discrepancies were noted in the operations of the ECCS Systems, expla.in in detail.
ATTACHMENT 1 OP-AP.ZZ-101(0) 5 of 14 Re v. B
OP-AP.ZZ-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 3.
Isolations a.
Were any PCIS isolations required during the event?
Yes No Actuation Signal Time b.
If any discrepancies were noted in the operation df the PCIS isolation, explain in detail.
c.
Were any NSSSS isolations required during the event?
i Yes No Actuation Signal Time d.
If any discrepancies were noted in the operation of the NSSS isolation, explain in detail.
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f.
ATTACHMENT 1 O P-AP. Z Z-101( Q )
6 of 14 Rev. B
OP-AP.ZZ-101(Q)
ATTACBMENT 1 POST -REACTOR SCRAM /ECCS ACTUATION REVIEW 4.
ATWS Related functions a.
Were any RRCS actuations required during this event?
Yes No Actuation Signal Time
.b.
Were any discrepancies noted in the operation of 6ny of the following systems for the given actuation signal?
Yes No N/A A.R.I.
Rx Feed Pmp Runback SLC Actuation RWCU Isolation RPT Breakers c.
Comments:
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ATTACHMENT 1 OP-AP.ZZ-101(Q) 7 of 14 Rev. B
OP-AP.ZZ-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 5.
What. is the classification of the event as defined in the Event Classification Guide?
Time declared Time terminated a.
Were all of the required notifications made?
Yes No b.
If no, explain why 6.
Identify any discrepancies noted in the review of the sequence of events print out.
l ATTACHMENT 1 OP-AP.ZZ-101(O) 8 of 14 Re v. B
OP-AP.22-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 7.
List any alarms received which were out of the ordinary for the event and alarms which should have been received, but were not.
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8.
Describe.any corrective actions that are required prior to the units return to service.
g d-9.
Reconstruct the event.
Include the plant conditions prior to the event, indications that a problem existed and actions performed to place the plant in a stable condition.
Describe any equipment malfunctions or inadequacies noted, and any identified procedure deficiencies.
Attach additional pages if required.
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ATTACHMENT 1 OP-AP.ZZ-101(0) 9 of 14 Rev. B l-
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OP-AP.ZZ-101(Q)
ATTACIBiENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 4
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ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 10.
Identif y which strip chart traces are included.
Parameter Recorde r 4k d
4 11.
Transient data for pertinent plant parameters.
Maximum Minimum Steam Dome Pressure Reactor Vessel Water Level Reactor Core Flow Reactor Power N/A Drywell Pressure Drywell Temperature Suppression Chamber Water Level Suppression Chamber Water Temp.
ATTACHMENT 1 OP-AP.ZZ-101(0) 11 of 14 Rev. B
OP-AP.ZZ-101(0)
ATTACBMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW 12.
Final Plant Conditions Reactor Power SRM IRM Range Mode Switch Position
" Reactor Vessel Pressure Drywell Temperature Drywell Pressure Suppression Chamber Water Level Suppression Chamber Water Temp..
Any additional parameters or remarks:
ATTACHMENT 1 O P-AP. Z Z-101 ( 0 )
12 of 14 Re v. B
OP-AP.22-101(Q)
ATTACHMENT 1 POST REACTOR SCRAM /ECCS ACTUATION REVIEW Prepared By:
Date Time Reviewed and Evaluated By:
STA Date Time f
SNSS Date Time Reviewed with Operations Manager Date Tiine Operations Manager (Signature)
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I ATTACHMENT 1 OP-AP.22-101(0) 13 of 14 Re v. B
C-OP-AP.ZZ-101(Q)
ATTACHMENT 1 POST' REACTOR SCRAM /ECCS ACTUATION REVIEW i
SORC and-GENERAL MANAGER Review a
Major findings of Investigations.
4
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( Attach additional sheets if necessary) i Recommendations by SORC.
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( Attach additional sheets if necessary)
Startup Authorization:
SORC Chairman Date General Manager Date' i
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ATTACHMENT 1 O P-AP. 2 2-101( 0 )
14 of 14 Rev. B i
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OP-AP.22-101(O)
ATTACliMENT 2
-FACT. FINDING QUESTIONNAIRE 1.
What was the first indication that a problem existed?
4 2.
What actions did you take as a result of the indications?
i 3.
What were the subsequent indications and plant response, including any manual actions taken?
t 4.
Were any equipment malfunctions or inadequacies noted?
OP-AP.22-101(Q) 1 of 2 Re v. B
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OP-AP.ZZ-101(Q)
ATTACRMENT 2 FACT FINDING QUESTIONNAIRE i
5.
Were any procedure deficiencies identified during the
' transient?
6 6.
Additional Questions or Information:
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J Interviewer Title In terv iewee Title Date 1
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OP-AP.ZZ-101(Q) 2 of 2 Rev. B
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F OP-AP.22-101(Q) i ATTACHMENT 3 SEQUENCE OF EVENTS CHECKLIST (LATER) e 4
OP-AP.ZZ-101(0) 1 of 1 Rev. B
c OP-AP.ZZ-101(Q)
ATTACHMENT 4 SEQUENCE OF EVENTS STANDARDS 4
(LATER)
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OP-AP.ZZ-101(Q) 1 of 1 Rev. B
r-OP-AP.22-101(Q) o ATTACHMENT 5 SIMPLIFII D IDGICS AND INSTRUMENT TABLES d
(LATER)
O P-AP. 2 2-101 ( 0 )
1 of 1 Rev. B