ML20138J056
| ML20138J056 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/21/1985 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20138J026 | List: |
| References | |
| ACP-6.15, NUDOCS 8510290234 | |
| Download: ML20138J056 (8) | |
Text
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g-ACP 6.15 Page 2 Rev. 0 4
NUCIIAR ENGINEERING AND OPERATIONS PR02 DURE NEO S.02 POST-TRIP AND TRANSIENT REVIEW l
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- F. C APPROVED Scn2 W Vice Pres 20ent, l
Nuclear Ingineering and Operations I
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l DATE June 21. 1925
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Q ACP G.15 Page 3 Rev. O NUCEEAR 1 ENGINEERING AND OPERATIONS PROCEDURE NEO 8.02 POST-TRIP AND TRANSIENT REVIEW 1.0 PURPOSE The purpose of this procedure is to ensure consistent philosophy and practices for performing post-trip and transient-reviews. The objectives of such reviews are to:
(3) ensure plant safety, (2) evaluate equipment and personnel performance, (3) identify the root cause of the trip and/or transient,-(4) correct the cause, and (5) document the review including corrective action taken. Lower tier procedures are required to implement this purpose.
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2.0 APPEICASIEITY inis procedure applies to the Nuclear Engineering and Operations (NED) Group including the Northeast Nuclear Energy Cor:pany (NNECO) and the Connecticut Yankee Atomic Power Conpany (CYAPCO).
3.0 EFERENCES 3.1 Institute of Nuclear Power Operations (INFO) Good Practice No. OP-211, " Post-Trip Reviews."
l 3.2 " Evaluation of the Post-Reactor Trip and Transient Review Progran, Revision 1" (transmitted by G. D. Baston letter No. GDE-84151, dated June 7 1Q64).
3.3 (for NECO) Plant Tinal Safety Analvsis Renort (ISAR) or Tacilitt Descrintion and Safetr Analvsis (IDSA).
(for CIAPCO) IPIP 1.5-1, " Emergency Ass,esscient."
3.4 AKSI N18.7-1976, Administrative Controls and Quality Assurance for the Operational Pnase of Nuclear Power Plants.
3.5 10CFP30.36, " Technical Specifications."
3.6 10CFR50.72 and 103730.73, "Immediate Notification Requirements" and "I. ice.nsee Ivent Repcrt Syster.."
i 4.0 DITINITIONS
- 1. 1 Reactor Trin (Scram) t',
A manual or automatic full insertion of control rods into the
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reactor core to interrupt the reactor's ability to sustain a
~l chain reaction.
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4.2 Engineered Safety Teatures Equipment and systems unique to each operating plant as specified in Reference 3.3.
This equipment helps to prevent or limit both fuel damage anc any accidental release of fission products to the environment.
4.3 Reacto'r Transient Any event which results in a rapid reactor power increase or decrease.
4.4 Safety-Related Equipment /Other ]mportant Equipment Equipment unique to each operating plant which must be considered in each post-trip and transient review. This includes engineered safety features and the reactor protection syst.em.
4.5 F.I.R.
A systec and format used by the nuclear plants to follow up reported discrepancies or problems.
(for NNECO) Plant Incident Report (for CYAPCO) Plant Information Report 5.0 RESPONST3IIITIES 5.1 Vice President - Nuclear Operations Responsible for maintaining this procedure current.
5.2 Unit Detv officer Responsible to ensure completion of post-trip and transient reviews.
5.3 Sta-ion / Unit supe:intendents 5.3.1 Responsible to identify safety-related equipment and other important equipment to be included in post-trip and transient reviews.
5.3.2 Responsible to designate vte may authorize reactor s art-up and/or increasing reactor power.
5.3.3 Responsible to ensure completion cf post-trip and transient written reports and necessary subsequent a ctions.
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5.4 Plant Operations Review Committee (PORC) i Under the conditions of Section 6.3.4, P. ORC is responsible to review all pertinent plant data prior to a reactor start-up.
In such cases, PORC is also responsible to advise the station /
unit superintendent whether or not it is safe to start up the reactor and what acti,ons or precautions should be taken.
5.5 Control Roor Staff L
5.5.1 Responsible to maintain the plant in a safe condition.
5.5.2 Responsible to inform the unit duty officer of a trip or transient and to participate in the post-trip and transient review.
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1 5.5.3 Responsible to ensure that all applicable charts, logs, computer records, etc., are complete, s'ccurate,
'and available in the control room for review....
i 5.6 NEO Directors Responsible to assist the station / unit superintendents, as requested, f ollowing a plant trip or transient.
6.0 INSTRUCTIONS
, ' -6.1 General.-
This procedure applies only to crelanned reactor trip / transient events.
.6 3.1 The ac'ceptability of perforcing reactor restart er of continuing reactor operations shall be determined by the requirements of Technical Specifications plus appropriate Nuclear Plant Operating Company (EUPOC) procedures.
6.1. 2 NIO directors shall assist the station / unit superin-tendents as requested to complete post-trip / transient reviews and necessary follow-up action.
""6.2 Initiating Events for Reviews-Immediately following any unplanned reactor trip and/or unplanned reactor transient, the control room staff shall netify their respective unit duty officer.
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The duty officer is then responsible to ensure completion of
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the post-trip / transient review. This review shall not distract the control room staff from their primary responsibility of NEO 8.02 Rev. O Date: 06/21/25 Page 3 of 6
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maintaining the plant in a safe condition, but it requires their participation.
Per Reference 3.5, the staff must shut down.the reactor if reactor safety is in jeopardy or when operating parapeters exceed any reactor protection system set points and automatic shutdown has not occurred.
6.3 Recuirements to Cocmlete a Post-Trip or Transient Review The unit duty officer shall ensure that the following actions are completed:
6.3.1 Verify that the plant is in a safe condition.
6.3.2 Evaluate whether or not the plant responded to the trip / transient as expected. Specifically check whether or not all appropriate engineered safety features and the reactor protection syster performed as required. Also, compare actual overall plant performance to the best available data on expected plant performance.
6.3.3 Identify and document the root cause of the trip /
6.3.4 Correct the cause. Document the corrective action taken as well as the basis for any action to prevent reoccurrence (Reference 3.5).
6.3.5 Following a reactor shutdown (S/D), answer the f ollowing questions yes" or "no."
6.3.5.1 Is the root cause of the trip / :ansient known?
6.3.5.2 Did all safety-related equipnent and other import. ant ege peent function as expected?
l If not, have all malfuncticus been corrected?
6.3.6 If any of the answers are "no," a PORC review shall be conducted prior to reactor surt-up.
In such cases, POR: shall advise the st.ation/ unit superintendent whe her er not di is safe to start up the reactor and what actions er precautions should be taken.
6.3.7
.Prin: to reactor start-up or increasing reactor power, verify that the plant meetr all appropriate Technical Specifications, including permission from NEO S.02 Rev. O Late: 06/21/E5 Page 4 of 6
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Rev. 0 the Nuclear Regulatory Cour.ission (h'RC) if necessary (Reference 3.5).
6.4 Level of Detail Required in KL'POC procedures 1mtlementint post-Trir and Transtent heviews Each operating plant and/or station shall prepare a single procedure to govern post-trip and transient reviews which incorporates the requirements of Section 6.3 and the following:
6.4.1 This procedure shall define (or reference procedures which define) the responsibilities of individuals or groups involved in this review process.
'6.4.2 This procedure sball include (or reference procedures which include) NRC reporting requirements (see References 3.5 and 3.6).
6.4.2 * ' 7[ s procedure shall identify equipment which must be considered in the review process and reactor start-up decision, including safety-related equipment and other important equipment.
6.4.4 This procedure shall identify applicable charts,
- m logs, computer ' records, etc. which are necessary for
' ' e the review' process. Include any special methods N necessary for the control root staff to retrieve such records.
6.4.5
'This procedure shall identify (or reference documents which identify) the best estimate data on expected
, plant performance in a trip / transient.
6.4.6 This procedure shall identify (or reference procedures a:Lich identify) who may authertme a reactor start-up
. or an,incrwase.in reactor power.
6.4.7 This precedure shall require a final written trip /
transient report and shall specify the following:
- 6. 4.7.1 Bow the report is identified and scheduled for completion (such as a PIR system).
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6.4.7.2 Required contents of the report.
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6.4.7.3 Required routing for the report.
6.4.7.4 Retaining the report for the lifetime of the plant m;
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6.4.8 This procedure shall identify a method (such as the controlled routing syster.) by which any needed i
follow-up is snitiated, scheduled, and tracked.
6.5 Trip / Transient Writtee Report The station / unit superintendent shall ensure completion of trip /
transient written reports and necessary subsequent actions.
7.0 TICURES Tisure Ne.
Tirure Title t
I 7.1 Post-Trip and Transient Review Tiowchart 8.0 ATTACHkEKTS None f
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ACP 6.15 Page 9 Rev. 0 m.b Tirure 7.1 Post-Trip and Transient Review T1ovchart
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Unplanned Reactor Trip or Transient Y
Notification of Unit Control Room Staff Duty Officer If Insure Completion of the Duty Officer (With Post-Trip / Transient Review Control Room Staff Participation)
Reactor Shut Down Reactor Not Shut Down y
i f Ivaluation Duty Officer PCRC Review, If R:guired V
Review /
FORO Reco n dation t
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r Authorig to Start-Up As Designated by Reactor or increase Station / Unit Reactor Power' Superintendent Y
i Cor.plete Trip / Transient Station / Unit Writter. Report and Superintendent
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Tc11ov-Up Action
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P NIO 1.02 Rev. O Date: 06/21/85 Page 7.1-2 of 1