ML17298C061
| ML17298C061 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/05/1983 |
| From: | Byron O, Self J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17298C060 | List: |
| References | |
| 79AC-9ZZ08, 79AC-9ZZ8, DN-8349A-0680A, DN-8349A-680A, NUDOCS 8504230457 | |
| Download: ML17298C061 (5) | |
Text
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79AC-9ZZ08 REVISION page 2 of 5 TABLE OF CONTENTS SECTION PAl:E NUHBER 1.0 PURPOSE
2.0 REFERENCES
- 3. 0 DEFINITIONS AND ABBREVIATIONS 4.0 RESPONSIBILITIES 5.0 XNSTRUCTXONS 4
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FALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
79AC-9ZZ08 REVISION POST TRIP REVIEW REPORTING 1.0 PURPOSE The purpose of the Post Trip Review Reporting procedure is to provide a method to accomplish application of unit restart criteria after an unplanned reactor trip or actuation of Engineered Safety Features (ESF).
This includes the review responsibilities necessary to assure that safety-related equipment operated as designed or that deficiencies have been corrected prior to restart.
Reportability requirements will be met by conformance to 71AC-OZZOl, Event Related Reporting.
2.0 REFERENCES
2.1 Implementing References 2.1.1 79IS-OZZ03, Post Trip'Review 2.1.2 78AC-OZZ06, Document and Record Turnover Control.
2.2 Developmental References 2.2.1 70AC-OZZ01, Procedure
- Format, Content and Numbering, Rev.
4.
2.2.2 NRC Generic Letter 83-28, Required Actions Based on Generic Implementation of SALEM ATWS Events.
2.2.3 NRC NUREG 1000, Generic Implication of ATNS Events at the Salem Nuclear Power Plant, April 1983.
2.2.4 Salem Generating Station Response to NRC Generic Letter 83-28 Administrative Directive 16 Post Trip/Safety Injection Review, July 22, 1983.
3.0 DEFINTTIONS AND ABBREVIATIONS 3.1 ATMS Anticipated Transient Without Scram 3.2 PTRR Post Trip Review Report 3.3 PRB Plant Review Board 3.4 STA Shift Technical Advisor 3.5 ESF Engineered Safety Features PV216 00D AEV.6162 Co) D IFQoRMAyIQo~
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PALO VERDE NUCLEAR GENERATING STAT)ON MANUAL PROCEDURE NO.
79AC-9ZZ08 RFVISION POST TRIP REUIEW REPORTING 4.0 RESPONSIBILITIES Page 4 of 5 4.1 The on duty Shift Technical Advisor (STA) shall complete the Post Trip Review Report (PTRR),
when applicable, in accordance with 79IS-9ZZ03, Post Trip Review.
4.2 The Operations Shift Supervisor of the affected unit shall review the PTRR and concur with report conclusions prior to approval signature.
4.3 The Operations Manager or his designee shall authorize unit restart in cases where safety-related equipment responds as designed or in cases where a discrepancy occurred and has been corrected.
4.4 The Plant Review Board (PRB) shall perform the independent review required if anomalous performance of the reactor trip switchgear or any other safety-related equipment is noted.
4.5 The Manager of Nuclear Operations shall authorize unit restart after reviewing and concurring with recommendations and conclusions of the PRB's independent review.
5.0 INSTRUCTIONS 5.1 The PTRR shall be completed for unplanned reactor trips of actuations of Engineered Safety Feature (ESF) equipment.
.1.1 The PTRR consists of the completed PTRR form, Appendix A of the Post Trip Review Procedure, 79IS-9ZZ03, with any attachments as required.
This report includes the following sections:
5.1.1.1 The initial conditions of the unit are documented.
The intent is to clearly describe the operational configuration prior to the event.
This includes areas that may have contributing impact on event severity such as evolutions occurring, maintenance or equipment out of service.
5.1.1.2 All notifications made in accordance with the Emergency Plan are documented and reclassifications, if applicable, are included.
A synopsis of the event is also reported together with plant response.
This gives an overall picture of the event chronology as well as basic description of events.
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79AC-9ZZ08 REVISION POST TRIP REUIEW REPORTING Pa e
5 of 5 5.1.1.3 " A checklist is provided for the preparer of the report as a reminder to ensure that:
Reactor trip switchgear response was in accordance with Technical Specifications, Applicable Reactor Protection System (RPS) setpoints were within Technical Specification tolerance, ESP actuation system setpoints were within Technical Specification tolerance, if actuated.
5.1.1.4 The sequence of events is also analyzed and described.
Any unexpected or out of normal sequence events are explained
'in detail and evaluated for safety-related significance.
5.1.1,5 The Event Analysis provides a systematic checklist to assure that all safety-related equipment has performed as designed.
If safety-related equipment has failed to function as designed and corrective actions have been ineffective then further independent review is required per section 5.1.2.
5.1.2 The independent review by the PRB is conducted, when necessary, using the PTRR and any attached documentation.
Additional information may be deemed necessary by the Chairman of the PRB.
5.1.2.1 The PRB shall document the findings of its review and make recommendations to resolve any anomalous behavior found in the initial review.
Post maintenance tests and surveillance test performance should be specified if applicable.
A recommendation shall be made to the Manager of Nuclear Operations as to whether, a unit restart should be initiated.
5.1.3 Xf an independent review by the PRB is required, the Manager of Nuclear Operations shall determine the adequacy of corrective actions
- taken, any retests accomplished and authorize unit restart, if in his judgement it can be done so without compromising nuclear safety.
5.1.4 Completed PTRRs shall be forwarded to the Independent Safety Ehgineering Group for review in accordance with Operating Experience Review 73AC-9ZZ03.
5.1.5 Completed PTRRs shall be retained for a least five years in accordance with Drawing and Document Control procedure 78AC-OZZ06, Document and Record Turnover Control.
5.1.6 Completed PTRRs shall be forwarded to the Nuclear Safety Group for information.
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