ML20077A632
| ML20077A632 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/14/1983 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20077A625 | List: |
| References | |
| SAP-132, NUDOCS 8307220383 | |
| Download: ML20077A632 (19) | |
Text
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS hlonCoarpoc%
Oo/Y STATION ADMINISTRATIVE PROCEDURE OFF-NORMAL OCCURRENCE EVALUATION, REPORTING AND RESOLUTION SAP-132 REVISION 1 JULY 12, 1983 Reviewed by:
A2 KQ ORIGINATOR E this gevision)
,l'a/c Dats o e" .- 7!/Y/f4
' A'S i (T . M G R . , Tr.,GENICAL SUPPORT Catfe Approved:
1 b%
PLAQy MANAGERe q [Date~
REV WD 3Y ?SRC-AIRMAN .
'N/e ATE hD b0 0 0 03 5 p PDR
F-SAP-132 PAGE 1
- - - REVISION 1 7/12/83
. LIST OF EFFECTIVE PAGES PAGE REVISION 1 1 11 1 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1
! 11 1 2'
12 1 I' ATTACHMENTS Attachinent I, Pages 1 and 2 1 l
i Attachment II 1 Attachment III 1
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SAP-132 PAGE 11 REVISION 1 7/12/83 TABLE OF CONTENTS PAGE List of Effective Pages i
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1.0 PURPOSE 1 2.0 SCOPE 1 3 0 REFERENCES 2
'4.0 DEFINITIONS 2 5 0 RESPONSIBILITY 3 6.0 PROCEDURE 5 7 0 FIGURES 12 8.0 RECORDS 12 ATTACHMENTS Attachment I - Of f-Normal Occurrence Report Form Attachment II - NRC One Hour Notifications ~
Attachment III - NRC Facsimile Data Transmittal s . + .
1.0 PURPOSE This procedure defines administrative controls used to gather information, materials, etc. to conduct investigations and
' evaluations, and for preparing reports for all off-normal occurrences including Reactor Trips at the Station.
2.0 SCOPE This procedure provides a standard approach for gathering information, conducting investigations and evaluations, and preparing applicable reports by documenting Off-Normal Occurrences at the Station. This procedure includes a mechanism for performing the following Technical Specification Requirements:
(1) Technical Specification 6.5 1.6(f) - Plant Safety Review Committee (PSRC) review of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.
(2) Technical Specification 6 5 1.6(g) - PSRC review of reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
(3) Technical Specification 6.5 1.6(h) - PSRC review of all written _ reports concerning events requiring 24-hour notification to the Commission.
(4) Technical Specification 6.5 1.6(1) - PSRC review of all recognized indications of an unanticipated deficiency in l some aspect of design or operation of safety related structures, systems, or components.
l (5) Technical Specification 6.5 1.6(1) - PSRC review of items I 'which may constitute a potential nuclear safety hazard as l
identified during review of facility operations.
f (6) Technical Specification 6.5 1.6(n) - PSRC review of the l
unexpected offsite release of radioactive material and the report as described in 6.9 1.13(e).
(7) Technical Specification 6.6 - NRC Reportable Occurrence Action Requirements
. . e PAGE 1 0F 12
e This procedures also includes provisions for the maintenance of a Master List of Reporting Requirements. ,
30 REFERENCES 31 Nuclear Operations Department Management Directive Numbers 9 and 10.
32 Virgil C. Summer Nuclear Station Technical Specifications (6.2 3 1, 6.5, 6.6, 6.7, 6.10).
33 ANSI 18 7, 1976, Paragraph 4 3 4(4).
3.4 NRC Regulatory Guide 1.16, Revision 4.
4.0 DEFINITIONS 4.1 Off-Normal Occurrences - An Off-Normal Occurrence is defined as an incident which could have a potentially adverse effect on the facility or the health and safety of staff or public.
4.2 Off-Normal Occurrence Report - The internal tracking mechanism utilized to document the cause of and means of prevention of tecurrences, as addressed in the scope of this procedure (Attachment I).
43 Licensee Event Report (LER) .A written report to the NRC, l
filed to provide notification, for specific types of occurrences as defined by Technical Spec'ification Section 6.6.
l l 4.4 Master List of Reporting Requirements - A compilation .of all reporting requirements as defined in Technical l Specifications, Operating License, Code of Federal Regulations, or other Licenses and permits, which are incumbent on the Station Manager for preparation and submittal.- The list shall include as a minimum the following:
(1) Identification of Reporting Requirements (2) Reference to specific requirements I (3) Designated originator of the report PAGE 2 OF 12 l
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(4) Frequency or other time restra nt f'r o submittal (5) Addressee of report -
45 Reactor- Trip Report - A compilation of 'specified documents and information initiated following a Beactor Trip.
50 RESPONSIBILITY
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51 Any station personnel who suspects or identifies an off-normal occurrence is required to complete Section I.,of Attachment I in accordance with this procedure..
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52 The Shif t Supervisor is responsible for:
5 2.1 Reviewing suspected or identified off-normal occurrences.
5 2.2 Implementing corrective action to place the plant in a safe condition as required.
523 Evaluating events for reportability per the Master List of Reporting Eequirements and initiating one hour notifications in accordan6s with 100FR50 72.
5 2.4 Advising the Management Duty Supervisor of existing conditions for reportability consicerations.
525 Completing Section II of the Off-normal Report Form (Attachment I).
5 2.6 Initiating Reactor Trip Reports.
l 53 Tae Management Duty Supervisor is responsible for:
531 Reviewing suspected or identified Off-normal Occurrences during other than normal working
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hours. ,
i 532 Evaluating occurrences for prompt notification to
. the NRC and performing notification as required.
533 Advising Station Management of reportable items , as required.
! 54 The Assistant Managers or designee (s) are responsible for:
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5 4.1 Evaluating Off-Normal Occurrences und'er-their scope.
PAGE 3 0F 12
4 4 SAP-132
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REVISION 1 7/12/83 5,4.2 Participating in decisions on possible reportable items under their scope, when available.
5 4.3' Providing Cause and Corrective Action to prevent recurrence when requested.
5 4.4 Initiate or verify existence of a Nonconformance Notice, or PAD MWR, as appropriate, for items that adversely affect hardware.
5.4 5 Insuring that all corrective actions within their assigned areas are completed within their required time frames.
5 4 5' Evaluating activities under their scope of responsibilities to determine if any occurrences warrant initiation of an Of f-Normal Occurrence r Report.
The Technict.1 Services Coordinator or designee is
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55 responsible for:
551 Logging, routing and tracking Off-Normal Occurrence Reportsj .
552 Coordinkting the preparation of the final draft LER's and transmitting them to Nuclear Licensing within the required time f rames.
553 Maintaining the Off-Normal Occurrence Report File and transmitting records to the Permanent Records System., -
! 4 554 Scheduling the required reports to the Plant Safety Review Committee (PSRC) for review.
5 5 52 Clarifying -any discrepancies that may surface as a 1
l 9 A ,, - r:esult of draft LER transmittals.
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5 5 6' Maintaining the Master Lis t of Reporting
- - Requirements.
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1 l , 557 Performing final evaluation of Off-Normal I Occurrences for reportability after all information
- - has been reviewed.
5.6 Th'e station Manager or designee is responsible for:
e
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SAP-132 REVISION 1
. . 7/12/83 5.6.1 Approval of the final disposition of Off-Normal Occurrences in accordance with Technical r.,,
Specification 6.5 3(d).
5.6.2 Assigning appropriate plant personnel to conduct investigations, etc., when responsibility is not predetermined.
563 Reviewing and authorifing transmittals of all reports to Nuclear Licensing.
5 6.4 Approving the Master List of Reportin's Requirements.
57 The Plant Safety Review Committee is > responsible f or:
571 Reviewing gli Off-Normal Occurrence Reports. ,
572 Reviewing all written ; reports of events which require 24-hone notification to the NRC prior to submittal.
S 573 Reviewing Reactor Trip Reports ' and associated
- > Independent Safety Engineering Group Reports within f
14 days of the Reactor Trip.
5 8. The Ikdependent Safety Engineering Group is e,esponsible fors reviewing all Reactor Trip Reports and preparing a writt'en report to be reviewed by the PSRC within 14 days ofLthe occurrence.
59 The Shidt Technical Advisor is responsible for performing a Preliminary Reactor Trip Reviews as described in 6.4.4.
I t 6.0 PROCEDURE 6.1 , Identification of an Off-normal Occurrence 6.1.1 Whenever an Of f-Normall Occurrence Condition is
- . identified, it shall be promptly documented by
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completing Section I o,C Attachment I as follows (if occurrence is a Reactor Trip, go to Section 6.4).
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-(; The description of the occurrence shall include as s applicable: , ,
A. Detailed description of Occurrence including
, , , time and date. _
PAGE 5 0F 12
SAP-132 REVISION 1
.. . 7/12/83 B. Any documents involved (i.e., STP's FSAR, Operating Procedures, applicable Technical l' Specifications, licenses, permits, etc. Attach copies of pertinent documents when possible).
C. Names of individuals knowledgeable of the event for future reference.
D. Name and Identif15ation Number of affected equipment, structures, components.
E. Plant Mode of operation including Power Level.
F. Other plant conditions that are pertinent to the occurrence.
6.1.2 Upon completion of Section I of Attachment I, the Off-Normal Occurrence (ONO) shall be taken to the Shift Supervisor.
6.1 3 The Shif t Supervisor shall review the occurrence and take the necessary immediate corrective action to place the plant in a s'fe a condition. Tais action is to be documented on Section II of Attachment I including identification of any requireL Removal and Restoration (R&R) entry, MWR or NCN.
6.1.4 The Shif t Supervisor shall evaluate the condition for reportability (see Master List of Reporting Requirements) and determine if NRC notification per 10CFR50 72 is required. If 100FR50 72 notification is required, the Shif t Supervisor shall ensure that Attachment II is completed, and notify the Management' Duty Supervisor (MDS) or the Assistant Manage r, Operations for concurrence. The Shift Supervisor shall ensure that the NRC Emergency Operations Center is notified within one hour of the occurrence.
NOTE: If the MDS cannot be reached, or if sufficient time is not available, the NRC Notification shall be made without MDS concurrence.
PAGE 6 0F 12
1 SAP-132 l REVISION 1
. . 7/12/83 6.1 5 If the occurrence is not reportable under 100FR50 72, the MDS or the Assistant Manager, l Operations shall be promptly notified. The MDS
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or the Assistant Manager, Operations shall review the occurrence for Prompt (24-hour) NRC reportability. If the occurrence requires Prompt notification, the MDS or Assistant Manager, Operations shall insure that the required telephone notification is made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and that the confirming facsimile (Attachment III) is submitted no later than the first working day subsequent to the occurrence.
6.1.6 All Of f-Normal Occurrence Reports are submitted to the Technical Services Coordinator (TSC) for logging, tracking, additional investigation, and NRC Report
- preparation.
6.2 Investigation and Report Preparation 6.2.1 Tne Technical Services Coordinator or designee receives the ONO, reviews it for reportability, assigns an ONO number, determines the due date for the NRC Report and logs the ONO into the Tracking System. A copy of the ONO will be cent to the applicable Assistant Manager (s) for information.
. The ONO is submitted to the Station Manager for his review.
6.2.2 The TSC shall be responsible for performing investigations as necessary to gather all facts concerning the occurrence. The appropriate Assistant Manager (s) may be requested to assist in the investigations, and assist in determining corrective actions as necessary.
6.2 3 The TSC shall be responsible for the preparation of a Final Report for submittal to the Station
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Manager. If the occurrence is reportable to the NRC, the report should be reviewed by the
. responsible discipline supervisor and submitted to the Manager, Nuclear Licensing, for transmittal to the NRC in accordance with Nuclear Licensing Procedures.
6.2.4 The TSC shall schedule Off-Normal Reports to the PSRC for review in accordance with Section 6 3 6I3 P1hnt SafeEy Review Committee Review PAGE 7 0F 12
SAP-132 REVISION 1 7/12/83 6.3 1 The PSRC shall review all Off-Normal Occurrence Reports.
6.3 2 The PSRC shall review all 14-day reports prior to submittal to Nuclear Licensing.
6.4 Reactor Trip Occurrences
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6.4.1 The Shif t Supervisor shall report each Reactor Trip in accordance with 10CFR50 72 (see Master Reporting List) as follows:
A. Complete Attachment II.
B. Notify the MDS or the Assistant Manager Operations and obtain his concurrence.
C. Notify the NRC Operations Center.
6.4.2 The MDS or the Assistant Manager Operations shall review the occurrence for Prompt reportability in accordance with 6.1 5 6.4.3 The following documentation shall be assembled to compile a Reactor Trip Report:
A. Section I of Attachment I (ONO).
B. Attachment II - NRC Notification.
C. Significant Plant Parameters'in addition to those on ONO Section I (see E0P-5, Attachment I).
- 1. Reactor Coolant System Tavg.
- 2. Reactor Coolant System Pressure.
- 3. . Operation (s) in progress at the time of trip.
- 4. First out annunciator.
5 The opening of any Pressurizer or Main Steam PORV's or safety valves.
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SAP-132 REVISION 1
. .. 7/12/83 D. Plant Process Computer Alarm Printout, if available.
E. Plant Process Computer Post Trip Review - If not available, include copies of Recorder Charts for (1) Pressurizer Level, (2)
Pressurizer Pressure, (3) Steam Pressure, (4)
Steam Generator Levels, (5) other pertinent
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parameters.
F. Technical Support Center Computer Post Trip Review Printout, if available.
G. Statements from personnel involved, as necessary.
6.4.4 Preliminary Review of Occurrence 6.4.4.1 The Shif t Supervisor, Control Room Foreman, and the Reactor Operator shall review the Reactor Trip Report and determine:
- 1. The cause of the trip, if possible.
- 2. If the cause of the trip still exists.
3 If the event requires implementation of the Emergency Plan.
- 4. If any Limiting Safety System settings have been exceeded.
5 If any Safety Limit has been exceeded.
6.4.4.2 The Shif t Technical Advisor (STA) shall independently review the following:
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I f . A. Plant Process Computer Sequence of
! Events Printout.
- 1. Ascertain the cause of each item on the printout.
- 2. Verify that Reactor Trip Breakers opened as required. _
PAGE 9 0F 12
SAP-132-REVISION 1 7/12/83 NOTE: If the Reactor Trip Breakers failed to operate as required, the NRC Licensing Project Manager shall be notified within.
the first working day after
'the fa.ilure.
3 Verify that the Manual Reactor Trip actuated.
- 4. Verify Turbine Trip, as required.
5 Verify Emergency Feedwater Start, cs required.
- 6. Verify Feedwater Isolation, as required.
7 Verify Steam Line Isolation, as required.
- 8. . Verify o'her t safety equipment, started as required.
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B. Plant Process Computer Alarm Printout for at least ten minutes before and thirty minutes following the trip to ascertain- the .cause of each alarm, and determine that-any required automatic actions. functioned properly.
C. Technical Support Center Post Trip Review Printout to verify that no.
discrepancies exist with the Plant Process. Computer Sequence of Events, and Alarm Printouts, and that there are no additional events that require explanation.
D. Plant Process Computer-Post Trip Review Printout to verify that critical plant parameters responded normally to the trip.
6.4.4.3 The STA shall then independently determine:
' The ultimate cause of the Trip.
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PAGE 10 0F l'2
- 2. If any Limiting Safety System Setting has been exceeded.
3 If any Safety Limit has been exceeded.
- 4. If the event requires implementation of the Emergency Plan.
6.4.4.4 If all of ths following conditions are satisfied, the Plant may be restarted and returned to Power:
A. The STA, and the Shift Supervisor, Control Room Foreman and Reactor Operator have independently determined and are in agreement as to the cause of the Trip.
B. All questions resulting from the Reactor Trip Report Review and any other discrepancies noted have been resolved with proper corrective actions taken.
C. There are no outstanding Technical Specification Limiting Conditions for Operations Action Statements that preclude Mode escalation.
D. Concurrence from Plant Management (either the Station Manager, Assistant Manager, Operations, or the Supervisor Operations).
6.4.4 5 If the cause of the trip cannot be l determined, or if there are outstanding i
discrepancies, entry into Mode 2 is prohibited until concurrence is obtained from the Station Manager. The Station Manager may, at his discretion, convene a
! . PSRC meeting to review the occurrence (if the Station Manager is not available, the next higher available level of management must approve the Restart).
6.4 5 Operating Experience and NRC Reportability Review s . ,s -
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SAP-132 REVISION 1
- - 7/12/83 6.4 5 1 The Reactor Trip Report shall be forwarded to the Technical Services Coordinator. He shall review the occurrence to identify if any NRC written reports are required. If any subsequent reports are required, they will be processed per Section 6.2.
6.4.5 2 The TSC shall transmit a copy of the Reactor Trip Report to the Independent Safety Review Group (ISEG) for review.
ISEG shall prepare a written report to be reviewed by the PSRC within 14 days following the trip.
6.4 5 3 The PSRC will review the Reactor Trip Report and the ISEG Report within 14 days
.following the trip.
70 FIGURES 71 None 8.0 RECORDS 8.1 All records generated in accordance with this procedure shall be maintained by the Technical Services Coordinator as part of the Off-normal Occurrence File, and will be
- - transmitted to the Permanent Records System as appropriate.
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SAP-132 ATTACHMENT I
' VIRGIL'C. SUMMER NUCLEAR STATION PAGE 1 0F 2
, , OFF-NORMAL OCCURRENCE REVISION 1 Report Number
.I. IDENTIFICATION OF OCCURRENCE Date Time. Plant Mode i
, Power Level Equip ID No. Equip Name
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Documents Involved Knowledgeable Personnel Involved , ,
l Activities in progress
.y Detailed Description of Occurrence C
- a l
l Report Originator i
II . . IMMEDIATE CORRECTIVE ACTION f
i i
l R&R No. MWR No. NON No.
[
REPORTABILITY DETERMINATI F AND NOTIFICATION Applicable Flegulation / / TECH. SPEG. / / OTHER l
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i y State Applicable Regulation & Report Requirement Type:of Report: / / - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / / - 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / / - 30 day / / - Other
/- / - Not-Reportable Conf?rming Telex Rettuired (MDS): / / Yes / / No Due By -
Followup Report Required.(TSC): / / Yes / / No Due By
SAP-13 2 -
ATTACHMENT I PAGE 2 OF 2 REVISION 1 III. STATION MANAGER REVIEW Responsible Asst. Manager y Comments E
4 5
STATION MANAGER IV. INVESTIGATION Cause of Occurrence Probable Consequences Y
E h Corrective Action Taken To Prevent Recurrence D
n r Technical Services Coordinator Asst. Mgr. (If Required) l V. STATION MANAGER REVIEW Licensee Event Report / / Yes / / No e
E Comments 4
Station Mgr. (Signature not required if Date Report Submitted to Nuclear Licensing)
VI. PSRC REVIEW l Meeting No. Meeting'Date
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g Comments x -
E Comments Resolved
_ l Asst. Mgr. PSRC Chairman
SAP-132 ATTACHMENT II
. . - PAGE 1 0F 1 REVISION 1 NRC ONE HOUR NOTIFICATION L
TIME /DATE OF NOTIFICATION /
NRC Contact Caller's Name Resident Inspector Informed / / Tes / / No Time /Date
- Event Time /Date 100FR50.72 Item j POWER REACTOR EVENT l Power Prior to Event Power at time of Report Reactor Trip / / Yes / / No Initiating Signal Safety Injection or ECCS / / Yes / / No Initiating Signal Applied to LCO Action Statement (s) l EVENT DESCRIPTION /CAUSE l i.
Radioactive Releases (Quantify):
- Other Major Problems Planned-Action / Press Release Outside Agency Notified by License: State Local
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Other - "
Shift Supervisor 4
- - - . - - - - - _ _ , _ , , . ._...,,_.,-.-...-._-.-._.,._..-,...m,
, . . . . - - . . . . . - - . . - - . _ - . . . . . . _ , , , , - . - . . - ., - . ~ . -
i SOUTH CAROLINA ELECTRIC & GAS COMPANY swS
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VIRGIL C. SUMMER NUCLEAR STATION
- EEdi$Ds.I'Eoss ATTACHMENT III PAGE 1 0F 1 REVISION 1 NRC FACSIMILE DATA TRANSMITTAL
(: DATE OF TELEPHONE REPORT ._
TIME DATE OF THIS REPORT TELEPHONE REPORT TO NRC BY NRC PERSON (S) CONTACTED
SUMMARY
OF TELEPHONE REPORT
. . e MANAGER, V. C. SUMMER NUCLEAR STATION /DATE
. . . . . . - . . - ,.