ML17255A514
| ML17255A514 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/04/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17255A515 | List: |
| References | |
| GL-83-28, NUDOCS 8311150366 | |
| Download: ML17255A514 (8) | |
Text
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REGULATOR FORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR;8311150366 DOC ~ DATE'3/11/04 NOTARIZED: YES DOCKET FACIL:50 244 Robert Emmet Ginna Nuclear Planti Unit ii Rochester G
05000200 AUTH~ NAME AUTHOR AFFILIATION MAIER~J',E ~
Rochester Gas 8 Electric Corp, REC IP, NAME RECIPIENT AFFILIATION CRUTCHFIELOrD.
Operating Reactors Branch 5
SUBJECT:
Forwards response:to Generic Ltr 83-28~
"Required Actions Based o
Generic Implications of Salem ATWS Events,"
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,, "8E$ /SS'8/Ill'lll Z jIljlllllll 0 ROCHESTER GAS ANDELECTRIC CORPORATION baal OMIT j $1AM ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vice Preeident TCLEPHONL ARCA cQCK "/16 546.2700 November 4, 1983 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Generic Leetter 83-28 R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
The enclosure to this letter provides our response to Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. The current status of conformance with NRC positions and plans and schedules for any additional actions are identified. Very truly yours, QA ~ ~(pLL John E. Maier Enclosure Subscribed and sworn to before me on this 4th day of November 1983. WILLIS Le SCK ULZE NOTARY PUBUC, State of N.T., Monroe County My Cornrnlssion Expires March 30, 19.+4 83iii50366 83ii04 PDR ADOCK 05000244 'P PDR
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~ I POST-TRI P REVIEW ( PROGRAM DESCRI PTION AND PROCEDURE ) Attachment 1 to this letter is a copy of Ginna Procedure A-25.4. This procedure describes the process of conducting a reactor post-trip review and i'ncludes the criteria for determining the acceptability of restart. l II All unexpected reactor trips must be reviewed by the Plant Operations Review Committee (PORC). It is the PORC which determines and recommends acceptability of a reactor restart to the Plant Superintendent. Preliminary reviews and assessment of the cause of the reactor trip and the function of safety-related equipment are performed by the Shift Technical Advisor, Shift Supervisor and Duty Engineer. People responsible for post-trip review are experienced and knowledgeable of the plant and competent to recognize and determine the true causes of plant trips. The responsibilities and authority of personnel performing the post-trip review are included in procedure A-25.4. All personnel involved in performing a reactor post-trip review in accordance with procedure A-25.4 are familiar with the Ginna power plant. Their competence to function under the spirit and letter of this procedure comes from varying amounts of formal education, experience, retraining, and NRC licensing. Either by legal requirement or through Ginna procedure, the following positions also have the following minimum requirements. a. Control Room Operators have the necessary training and experience to hold the NRC Reactor Operators License. b. The Shift Technical Advisor must have a Bachelors degree in Engineering or a related field or 60 credit hours of Engineering courses. In addition, all have special training in Accident Analysis. c. All shift supervisors hold Senior Reactor Operator licenses. Sources of'lant information reviewed include 1) Pre/Post Trip Review,
- 2) Sequence of Event Printout and,
- 3) Control Room strip charts.
In addition, A-25.4 directs the Personnel performing the review to examine any other avail-able sources of data. These may include written accounts by Operators and/or other Plant Personnel, Computer Trend Printouts, Computer Alarm Printouts, Computer Log Print-
- outs, and other Operator and Auxiliary Operator Logs.
Sources of Plant information are detailed in response to Section 1.2.
~ t C:.-
Plant personnel performing a reactor post-trip review under procedure A-25.4 are experienced and trained such that an unexpected condition that occurred or an expected condition that did not occur would be noted and explained before a startup was permitted. The actual operation of safety-related equipment is reviewed against the appropriate documentation such as the plant Technical Specifications to insure proper functioning. Corrective action is taken when necessary. All unscheduled reactor trips at Ginna Station must be reviewed by the PORC prior to a reactor restart. The authority for allowing the restart rests with the Plant Superintendent. All records used for the analysis and review by PORC are passed on to PORC after the preliminary assessments are complete (see A-25.4 attached). Record of review is entered into PORC minutes. Control room strip charts are maintained for a period of at least five years. Attachment 1 is the procedure used to control reactor post-trip reviews.
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