ML20203B600

Forwards Modified Response to SER Open Item 5 Re Paragraph 1.1 of Generic Ltr 83-28 on post-trip Review,Per 860409 Telcon.Rev 1 to Procedure 10006-C Re Reactor Trip Review Also Encl

ML20203B600
Person / Time
Site:	Vogtle
Issue date:	04/11/1986
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML20203B604	List: ML20203B600 ML20203B607
References
GL-83-28, GN-871, NUDOCS 8604180213
Download: ML20203B600 (3)

Text

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Georgia Power Company Routa 2. Box 299A

. Waynesboro, Georgia 30830 Telephone 404 554-9961 404 724 8114 Southern Company Services. Inc.

Post Office Box 2625 l Birmingham, Alabama 35202 l Telephone 205 870-6011 Vogtle Proj.ect April 11, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log: GN-871 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: GN-836, BAILEY TO DENTON, 3/17/85 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 5: GENERIC LETTER 83-28

Dear Mr. Denton:

In the referenced letter responses were provided for paragraphs 1.1 and 1.2 of Generic Letter 83-28. In a telephone discussion with your staff on April 9,1986, GPC agreed to modify- the referenced response to paragraph 1.1 and has done so as documented in Attachment A to this letter. Your staff also requested a current copy of the VFGP Reactor Trip Review Procedure.

Attachment B is a copy of the requested procedure.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely, J. A. Bailey Project Licensing Manager JAB /sm Attachment xc: R. E. Conway G. Bockhold, Jr.

R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper D. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2) L. T. Gucwa f p B. Jones (Esquire) Vogtle Project File

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( ATTACHMENT A () l

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GENERIC LETTER 83-28

, W 1.1 Post - Trip Review (Program Description and Procedure) l Position Licensees and applicants shall describe their program for ensuring that unscheduled

reactor shutdowns are analyzed and that a determination is made that the plant

. can be restarted safely.

Response

i 1. VEGP has developed an operational procedure 10006-C, " Reactor Trip Review,"

which is a systematic safety procedure that will ensure the following restart criteria are met before restart of the reactor is authorized.

!

• This procedure is used to identify the root cause of the trip and includes the sequence of events. If the cause of the trip is not apparent, a description of the evaluation in progress is required.

• The Rea:: tor Trip Review procedure requires corrective action to have been  ;

completed or in progress to correct the root cause of the trip.

• The post trip review reconstructs the sequence of events on data sheets.

This sequence of events is then analyzed to determine if the events occurred I out of normal sequence, degraded trends in equipment occurred, and/or failed i

or degraded response of equipment to control signals occurred.

• The review analyzes the trip to determine if safety-related and

• other equipment operated as expected.

The Reactor Trip Review looks at all of the above. VEGP classifies reactor trips as Condition I or Condition II. A reactor trip is classified as a Condition I when the cause of the trip is known and has been corrected; all safety-related equipment functioned properly during the trip.- A Reactor Trip is classified Condition II when the cause of the trip is not known and/or some safety-related equipment functioned in an abnormal or degraded manner during the trip. If the trip is classified as a Condition II, the Plant Review Board must review the report. The Plant General Manager may authorize a restart prior to Plant Review Board review of the report.

2

2. The responsibilities and authorities of personnel performing the review and 1

analysis is defined in The Shift Technical Advisor (STA) will procedure complete10000-C..

the Reactor" Conduct Trip Report. of Operations."

He has the authority to obtain the necessary personnel and equipment for the post trip review and for gathering and assessing the information.

The On-Shift Operations Supervisor (OSOS) functions as the senior management representative for plant operations on shift and must hold a SRO License.

He concurrently assesses the information for the Reactor Trip Report with the STA, and classifies the trip. He provides approval for startup after a Condition I trips.

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,' 3. The OSOS has the overall authority for directing the post trip review process.

The STA has the responsibility for the post trip analysis. They concurrently classify the trip as Condition I or Condition II,

4.

• The operating staff will make a report on data sheets, " Reactor Trip Personnel Statements," of the Reactor Trip Review procedure. If it is necessary for a more accurate analysis, the operating crew on duty during the trip may be available to the review team for interviews.

• A time history of the event is required in the Reactor Trip Review procedure on data sheet " Sequence of Events." The information for this should be I available from the Computer Alarm Printout, Pre / Post Trip Logs, and the ERF Computer Printout. Chart records will be included, where necessary.

5. The Reactor Trip Review procedure evaluates the plant response to a trip.

A detemination is made as to whether the response was within acceptable 1imits.a Daxdataxframtthuxrnimmhxxh.,ma<.tmxESPx:Tauduaix2pec4f4x:sticos<

1axxamyx'iropetxxqurattum If responses were within acceptable limits, the trip is classified as a Condition I trip.

I A sequence of events is reconstructed. This sequence is used to verify automatic functions and to identify any off normal occurrences.

6. If the plant response is not within acceptable limits, the transient is considered a Condition II event. For these events, the Plant Review Board reviews the Reactor Trip Review. The Post Trip review collects the  ;

information necessary for an independent assessment. This report is ,

maintained for the life of the plant. The Plant General Manager may authorize restart following a Condition II event.

7.

• The procedure which contains the criteria for determining the ' acceptability )

for a restart is 10006-C, " Reactor Trip Review." '

The procedure that has the responsibilities and authorities of key personnel )

involved in the Post Trip review process is 10000-C, " Conduct of Operations."  !

• The procedure that deals with determining whether the plant variables and system responses were within specified limits is 10006-C, " Reactor Trip Review."

• The procedure which has the criteria for determining the need for an independent review is 10006-C, " Reactor Trip Review."

The data from the review is compared to VEGP ~ schnical Specifications and applicable FSAR description of the system responses which should occur as various plant parameter or actuation setpoints are reached.

J l

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