ML20083L580

Affidavit of G Bockhold,Describing Decision Making Involved W/Util Determination as of 900409,that Plant Diesels Operable & Capable of Performing Intended Safety Functions

ML20083L580
Person / Time
Site:	Vogtle
Issue date:	05/11/1995
From:	Bockhold G GEORGIA POWER CO.
To:
Shared Package
ML20083L508	List: ML20083L516 ML20083L580
References
93-671-OLA-3, OLA-3, NUDOCS 9505180502
Download: ML20083L580 (118)

Text

{{#Wiki_filter:i -,[ l UNITED STATE 8 OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC 8AFETY AND. LICENSING BOARD In the Matter of a Docket Nos. 50-424-OLA-3 GEORGIA POWER COMPANY,11 AL, a 50-425-OLA-3 Re License Amendment (Vogtle Electric Generating Plant, 3 (Transfer to Units 1 and 2) Southern Nuclear) a A8LBP NO. 93-671-OLA-3 AFFIDAVIT OF GEORGE BOCKHOLD, JR. I, George Bockhold, Jr., having been duly sworn, state as follows: 1. I am over the age of 18 years and am competent to execute this Affidavit. I have testified previously in this proceeding and my professional qualifications were attached to my prefiled testimony as Exhibit A (GPC Exh. II-20). 2. In March and April of 1990, I was the General Manager of Plant Vogtle. Following the March 20, 1990 Site Area Emergency ("SAE"), I oversaw the efforts of the Plant Vogtle staff to j investigate the March 20 SAE, including the establishment of an Event Review Team, pursuant to Vogtle Procedure 00057-C, the revision of which that was in effect in March 1990 is attached hereto as Exhibit A. 3. The accompanying affidavit by Mr. Ken Holmes, the Event i Review Team Leader, describes the evolution of the diesel testing plan implemented following the March 20, 1990 SAE in order to determine the root cause of the 1A diesel failure. 9505100502 950512 PDR ADOCK 05000424 Q PDR

2 d. 4.= By April 9, 1990, following the completion of diesel testing, I was satisfied that the Vogtle diesels could be declared " operable," as that term was defined in Plant Vogtle Technical Specifications, and that there was reasonable assurance the diesels were capable of performing their intended safety function.' 5. Typically, the diesel generators are determined to be, or are verified, operable pursuant to the provision of Tech. Spec. S 3/4.8.1, the March 1990 version of which is attached hereto as Exhibit B. The Diesel Operability (surveillance) Test Procedure, No. 14980, attached hereto as Exhibit C, was used to satisfy the monthly and semiannual surveillance requirements of Tech. Spec. S 4.8.1.1.2.a, b., and g and could also be performed in order to verify operability of the diesel when it was returned to service following modification work or maintenance (agg Operations Procedure 10000-C, Section 3.10, a copy of which is attached hereto i as Exhibit D). Tech. Spec. Section 4.8.1.1.2.h also requires that Engineered Safety Features Actuation System ("ESFAS") testing be performed before declaring the diesel operable following an 18-month maintenance outage of the diesel. During the March 1990 outage, the ESFAS test of the 1A diesel was completed prior to March 20. In addition, before declaring a diesel operable from a maintenance outage, Operations Department personnel also verify that there are no outstanding unresolved items (e.g., Maintenance Testing of the Calcon sensors continued after April 9, 1990 at Wyle Laboratories with the approval and involvement of the NRC. Egg March 1, 1995 Affidavit of Milton D. Hunt, filed with Georgia Power Company's Motion for Summary Disposition of Intervenor's Air Quality Statements Allegation (March 3, 1995), at 1 36. 2 i r-w,- -w-y -r,. 3

. =. ( Work ord:ro, D ficiOncy Cards, or Cicercncoo) that cdvercely effect the diesel's operability. 133 operations Procedure 10008-C, Section 3.1.3.1.b, attached hereto as Exhibit E. 6. My determination on April 9, 1990 concerning the diesels was based on all the testing performed on the diesels following the I March 20 SAE, and not solely on the diesel operability test, Procedure No. 14980.8 I was satisfied that they could be declared operable based on consultation with operations Department l personnel, who were responsible for determining that equipment was " operable" in accordance with the Tech. speos., Engineering Department personnel, who were responsible for supervising and evaluating the various tests on the diesels, and the Event Review Team, which was ' responsible for the overall test plan for. the diesels. I hereby certify that the foregoing statements are true r. .f and'.@.orrect to the best of my personal knowledge and belief. [ . ). > ~'. y' t Oc ~~ George Bookhold, 'Jr. ' %c SworJtio and su ribed ' CDsYose me this /__ ay of May, 1995. M N. Notary PuM110 g My es on expi es: 0 The operability Test was performed on April 1,1990 and again 8 on April 7, 1990 (following additional testing) as a functional test, to confirm that the testing which had been undertaken on the diesel did not adversely affect its operability, and as a final confirmation of the Company's belief that the diesel was operable. 3 1 1 i 7

I '! *I" C (-{ iROCEDURENO. REV@ON PAQt NQ. I VECP 00057-C 4 37 of 37 Sheet 10 of 10 DATA SHEET 1 Event Report No. Report: Page _ of INVESTI0ATION QUESTIONS (CONT'D) f 12. WAS SUPERVISION INVOLVEMENT ADEQUATE FOR THE EVOLUTION BEING CONDUCTEDT YES/NO l-13. WERE THE PERSONNEL THAT INITIATED OR ADVERSELY CONTRIBUTED TO THE EVENT QUALIFIED TO PERFORM THEIR ACTIVITIES PRIOR TO AND DURIN0 THE EVENT 7 YES/NO 14. IF QUESTIONS 1, 4 OR 7 ARE ANSWERED YES, DESCRIBE IN DETAIL IN THE EVENT REPORT. 15. IF QUESTIONS 2, 3, 5, 6, 8, 9, 10, 11, 12 OR 13 ARE ANSWERED NO, DESCRIBE IN DETAIL IN THE EVENT REPORT. 1 l I SMO

.._...m_ .;9 Approc ProcedetD NS Yogtfe Elm Generating Plant 00057-C %Y.b NUCLEAR OPERATIONS j % g, Date 4 GeorgiaPower unit common io/w/st e a.. 1 of 37 s VOID EVENT INVESTICAT70N 1.0 PURPOSE j i l This procedure provides instructions for event investigations. It is to be performed for, but not limited to, the following events: l ~ i 1 a. Unplanned Reactor Trips, b. Unplanned Turbine Trips, c. Unplanned Engineered Safety Features (ESF) actuations, 4 d. Significant Radiological events. l e. Events identified by site management (Office of the General Manager) l NOTE Security related event investigations will be handled in accordance with procedure i 90142-C. "" Security Report Procedure. 4 i l 2.0 DEFINITION I EVENT A definite and separate occurrence that happens as a l result of, or in connection with, a planned evolution. f Reactor trips, engineered safeguard feature actuations and challenges, and other events deemed significant are examples. l l m,ca em

PROCEDURE NO. REVilloN PAQt NO. VEGP 00057-C 4 2 of 37 3.0 RESPONSIBILITIES 3.1 0FFICE OF THE GENERAL MANAGER The General Manager - Nuclear Plant (GMNP), Assistant Gereral Manager - Plant Operations (AGM-Ops), Assistant 1 General Manager - Plant Support (AGM-SPT) as appropriate, is responsible for the following: 3.1.1 Ensuring the Event Investigations are properly conducted 1 3.1.2 Directing aparopriate departments to provide necessary support to t'1e ERTL. 3.1.3 Reviewing the results of event investigations. 3.1.4 Recommending a review, as appropriate, by the Plant Review Board (PRB) of any reports. 3.1.5 Extending the seven day completion period for the investigation review, when appropriate. 3.2 MANAGER TECHNICAL SUPPORT l l The Manager Technical Support (HTS) will ensure l 3.2.1 Corrective actions resulting from Event Investigations are assigned and tracked to completion. 4 3.2.2 Appropriate processing of the completed event investigation report. 3.2.3 Providing information concerning similar in-house and related industry events. 1 l 3.3 MANAGER OPERATIONS i 3.3.1 The Manager Operations, or designee, determines if Operations shift personnel involved / associated with the Event should be relieved by additional personnel to l participate in the the Event Investigation. l b' 14 4 %

F l h M.oCEDUME ND. F.EylsioN PAGE No, VEGP 00057-C 4 3 of 37 ) 3.3.2 The Manager Operations is responsible for ensuring the event data is collected and provided to the ERTL. -3.4 ON SHIFT OPERATIONS SUPERVISOR i The on Shift Operations Supervisor (0505) has the following responsibilities: 3.4.1 Informing the Vogtle Duty Manager of events described l in 1.0. 4 3.4.2 Ensuring a Deficiency Card is initiated for the event in accordance with Procedure 00150-C, " Deficiency Control". l 3.4.3 Initially determining hardcopy data to be collected. 3.4.4 Designating the individual responsible for the collection of appropriate hard copy information listed in Data Sheet 1. I

1 3.4.5 Ennuring each appropriate individual involved in the Event initiates an Event Personal Statement.

3.4.6 Providing the event data to the Manager Operations for the Event Review Team. 3.5 DEPARTMENT MANAGERS l Department Managers are responsible for the following: 3.5.1 Supporting a thorough review of events and providing pertonnel to perform the Event Investigation. 3.5.2 Encuring corrective actions are sufficient to preclude j recurrence of events of the same nature. 3.5.3 Providing additional personnel to relieve shift personnel to allow the investigation to occur while the information is fresh. l 3.5.4 Review and approve /disaparove recommended corrective t actions. Disapprovals s,ould be accompanied by an explanation. mun

PROCCDUME No. REylsioN PAGE No. VEGP 00057-C 4 4 of 37 3.6 V0GTLE DUTY MANAGER l The Vogtle Duty Manager (in accordance with procedure 00007-C, "Vogtle Duty Manager / Response Team") is responsible for'the following: 3.6.1 Assignment of the ERTL (Critique Leader) for events l 1 listed in Section 1.0. 3.6.2 Determination if event review is required (and assignment of an ERTL) for those events not listed in Section 1.0. 3.6.3 Calling out the Event Review Team. I 3.7 EVENT REVIEW TEAM LEADER The Event Review Team Leader (ERTL) has the following responsibilities: 3.7.1 Designating an individual for Event Data Collection, if-the data has not already been compiled. 3.7.2 Ensuring personnel involved /associsted with the Event fill out an Event Personal Statemert, when not already completed. 3.7.3 Obtaining Event Review Team membern from other departments including, as necessary, representation from Operations, and an Engineer to ensure an overall plant perspective. For some events HPES, NSAC, or QA representation may be appropriate. 3.7.4 Assigning specific duties and responsibilities to Event Review Team members in order to complete the review and report. 3.7.5 Providing recommendations to the CMNP, AGM-OPS, AGM-SPT l for consideration in determining readiness to restarting the work or the reactor, unless a restart 4 decision has already been made per step 4.1.4. 3.7.6 Informing the CMNP, AGM-OPS, AGM-SPT, Manager Operations and the Manager Engineering Support when an Event is classified as being of unknown cause or when safety-related equipment did not function properly during the event. t I l i Su.i

PROCEDURE No. REYlSloN PAGE No. VEGP 00037-C 4 5 of 37 3.7.7 Completing the Event Report per Data Sheet 1 (Data Sheet 2 for security events). The ERTL will designate someone to coordinate completion of required forms. 3.7.8 Determining root cause(s) per Procedure 00058-C, " Root Cause Determination". 3.7.9 Recommending corrective actions. i 3.7.10 Reviewing investigation results with responsible department managers and site management within seven days sf the event. 3.7.11 Obtain approvals and expected completion dates for corrective actions to be performed. 3.7.12 Requesting, by memo, an extension of the seven day requirement, when appropriate, from the Office of the General Manager. Documentation of extention is to be retained as part of the Event Report. 3.7.13 Ensuring a copy of the full report is sent to the Technical Support Department within 3 days of submission to the GMNP/AGM-OPS /AGM-SPT so that necessary NRC reports can be completed, when applicable. 4 ~ 3.8 EVENT REVIEW TEAM 3.8.1 The Event Review Team is responsible for conducting and documenting Event Investigation, Root Cause i Determination, Recommended Corrective Actions, and preparing final report for the General Manager-Nuclear Plant. 3.8.2 For reactor trips, the POST-TRIP REVIEW TEAM (Event Review Team) consists of the following: Team Leader: Management or Supervision, (D) l Member: ISEG Supervisor or Alternate (D) l Member An I&C Supervisor or Superintendent (D) i1 Member: An Engineering Supervisor (D) l Member: Operations Supervisor or Shift Supervisor (D) 9 OI 4

PROCEDURE No. Revision PAGE No, VECP 00057-C 4 6 of 37 4 Member: Maintenance Supervisor or Superintendent (D) l Member: Other members as requested by the Team Leader (e.g., HPES, Outage & Planning, Technical Support or SAER) (D) = designated 3.8.3 For other events the Event Review Team composition will 'be designated by the Event Review Team Leader as 1 appropriate. An Engineering representative will j-participate in all event investigations. A Maintenance representative will normally participate in event l investigations when abnormal component operation was a cause of the event. I 3.8.4 For other events identified by site management, the department manager responsible in the event or for the procedure involved, will be designated the ERTL, unless otherwise specified by site management. 3.8.5 Event Review team members should be someone who will be I available for the duration of the Event Review. 3.8.6 Team members are responsible for action plan items assigned to their department, as well as other duties assigned by ERTL. 3.8.7 Outage & Planning is responsible for checking the mode t l deferred binder to ensure required surveillances have not been missed. 3.9 MANAGER PLANT TRAINING AND SMERGENCY PREPAREDNESS l I The Manager Plant Training and Emergency Preparedness reviews the event report to determine what aspects of the even may impact training programs. 3.10 PLANT PERSONNEL Plant Personnel are responsible for the following 3.10.1 Completing an Event Personal Statecent when j involved / associated with an event, prior to leaving the site. 3.10.2 Providing information to the Event Review Team during the Data Collection. 3.10.3 Participating in any critique or post event review as requested. 1 NN

1 r i e PRocEQURE No. REylsioN PAGE NO. VECP 00057-C 4 7 of 37 s 3.11 ISEC 3.11.1 Maintain an Event Report Log to include the event number, event date, ERTL name and description of the event. 3.11.2 Support a thorough review of events by providing personnel to participate in Event Investigations. 4.0 INSTRUCTIONS 4.1 GENERAL 4.1.1 The event investigation process is a six-step process. I Step Responsibility Initial Data Collection OSOS Event Investigation & Report Event Review Team Leader Restart Decision GMNP/AGM-OPS Event Investigation Review AGM-OPS /PRB Identification of Corrective Event Review Team Leader 4 Actions Follow-up Technical Support l Duty Manager for reactor trips as stated in step 4.1.5 4.1.2 The initial objective of an investigation is to determine the acceptabil'ty of performing a reactor restart or operational work resumption. An investigation should determine root cause(s), and recommend corrective actions (s). I 4.1.3 The OSOS informs the Vogtle Duty Manager of events. i 4 4.1.4 For unplanned reactor trips where the direct cause is known, plant conditions have stabilized and emergency systems have appropriately operated, a restart decision may be made in accordance with Procedure 00300-C " Authority To dtartup And Shutdown Reactors",by theprior to the event investigation and report performed ERTL. The initial data collection step and procedure 10006-C, " Reactor Trip Review" will be followed prior to determining a reactor restart. j t 4.1.5 The Vogtle Duty Manager determines if an Event warrants callout of an Event Review Team. ) 4 l mw. 1

_yo j \\ PROCEDURE NO. REVI5loN PAGE NO. VEGP 00057-C 4 8 of 37 4.1.6-The Vogtle Duty Manager assigns an ERTL for events i j requiring futther evaluation. 4.1.7 The Event Investigation and evaluation will be initiated by the Event Review Team after plant j conditions have stabilized. 4 4.1.8 The Event Investigation must not distract the OSOS or operating personnel from their primary responsibility of monitoring plant parameters and maintainin4 the plant in a safe condition. t 4.1.9 If deemed necessary by the Vogtle Duty Manager or l respective department management, additional personnel will relieve shift personnel to allow the investigation to occur while the information is fresh. 4.1.10 The Vogtle Duty Manager /ERTL can modify the team size t j or scope of effort when revealed facts show that the 1 Event Investigation can be modified. l 4.2 DATA COLLECTION ) 4.2.1 The purpose of the data collection-phase of the event review is to gather sufficient data to reconstruct the i event from a point prior to the initiating event until plant parameters have stabilized after the event NOTE Procedure 10006-C, " Reactor Trip l Review" will $e used to l supplement Data Sheet i for reactor trips. 4.2.2 The OSOS, or OSOS designate, is responsible for I 4 determining information and records to be collected. l The OSOS designates the individual to conduct data j j collection of appropriate hard copy information listed in Data Sheet 1. Strip chart recordings must I accurately reflect real time to have meaningful in formation. If this is not the case, the OSOS designate will ensure that the chart paper is annotated with a time mark, chart speed (chart speed may change i during transient), and time scale. Appropriate computer tapes should be retained until released by the ERE. Prior to resetting annunciators and flags not on the alarm printer, they should be recorded (i.e., generator LEDS or common alarm lockouts). 4 ,n-,- --w -e y

PROCEDURs NO. MEYl6 ION PAGE NO. VEGP 00057-C 4 9 of 37 4.2.3 After the plant is in a safe, stable condition, the ERTL will ensure appropriate individuals involved in the event (e.g., plant operator, mechanic, technician, shift supervision etc.) have provided a statement concerning his/her involvement in the event prior to leaving the site. These statements may be obtained in I any one or combination of-the following ways. a. Written personal statements b. Event Review Team interviews with personnel involved in the event c. Critique with all involved personnel 4.2.4 If either of the last two techniques is used, the information should be recorded to ensure future availability of the information. The event personal statements will be restricted to facts personally observed concerning the event, and the facts should be stated chronologically, if possible. Conjecture and i opinions stated should be annotated as such. The statement will include the following a. Plant ennditions prior to the event (for maintenance personnel, this will include the status of maintenance or testing). h. First indication that a problem existed (e.g., #2 S/G decreasing level at 301 or radiation monitor RE-006 increasing), Individual's specific actions as a result of the c. indications (e.g., opened B/P FRV or started a leak rate determination). d. Subsequent indications and plant response, including manual actions. Noted equipment malfunctions or inadequacies. e. f. Procedure deficiencies identified during the situation. g. Recommendations to prevent recurrence. The written statements or tape recordings will be l included in the Event Report to assist in event reconstruction. j mue m____.____

/ PR$;EDURE NO. REVilloN PAGE NO. VEGP 00057-C 4 10 of 37 j 4.2.5 As part of the investigation the Investigation Questions, listed in Data Sheet 1, as appropriate, will I be answered by the Event Review Team at the completion of interviews. 4.2.6 The OSOS designate assembles the initial hard copy information and personal statements for the Event Report. This information will be submitted to the Manager Operationa to be used during the event I investigation. 4.2.7 The Mannger Operations ensures the event report data is in provided to the ERTL 4.3 EVENT INVESTIGATION e 4.3.1 The Event Review Team, under the direction of the ERTL, is responsible for the investigation and analysis. The Event Review Team will complete the requirements of, and answer the questions on. Data Sheet 1, as t i l appropriate. 4.3.2 The Event Review Team will chronologically reconstruct the transient in the event investigation, using the collected data. A chronologient description of the i event will be developed using all available data. Pertinent alarms, trips, actuations, and isolations will be listed, or marked on, the sequence-of-events or alarm-type printout. Pertinent plant parameters should be incoroorated into the chronological list of events during the reconstruction. j 4.3.2.1 For pinnt transients, a comparison of the i reconstruction with past experience should be made by i the Event Review Team based on their training and experiences. A review will be conducted of the in-house Operating 1 Experience Report (GER) to identify similar industry OERs and similar previous in-house Event Review Reports available on the Operating Experience Program data base. This review may be conducted by Technical Support or ISEG and should be orovide'd to the Event Review Team for evaluation. T11s will assist in i identifying indications of abnormal or degraded conditions, identify trends and indicate whether past corrective actions have been effective. 4 i e

PRQcEDURE NO. REylStoN PAGE NO. VECP 00057-C 4 11 of 37 The event reconstruction will also be com')ared with the required procedure actions to determine the effect of those actions on the plant res)onse. In some cases it may be worthwhile to compare tie transient with a similar transient described in the Final Safety Analysis Report (FSAR). However, it should be noted that FSAR transients are " Worst case" or limiting conditions and it should not be assumed that, because a transient did not result in peak parameters exceeding the FSAR values, the plant response was acceptable. j A review will also be conducted, as necessary, to evaluate susceptibility of other systems or components to a similar occurrence. 4.3.2.2 The Event Review Team will analyze and evaluate the i event reconstruction and event comparison. They will determine the cause(s) of the event and will provide operational recommendations to the Assistant General Manager-Plant Operations. The Event Review Team will look beyond the obvious indications to diagnose the root and contributory causes of the event and evaluate the plant response. They will review the available information thoroughly, looking for (1) abnormal indications or degraded trends performance, (2) events occurring out of the normal or anticipated sequence, (3) failed or degraded response i of equipment to control signals (4) unusual chemistry results or radiation readings, and (5) unanticipated alarms. The actual or suspected cause of the event and any abnormal or degraded indication identified during the transient will be documented in the Event Report. 4.3.3 A preliminary safety assessment of the event and subsequent plant response will be performed by the Event Review Team. ne maximum and minimum values of selected parameters will be compared with their established specifications. The Event Report will document this safety assessment. 4.3.4 A root cause determination is to be conducted per Procedure 00058-C, " Root Cause Determination". The root cause worksheet and the recommended corrective i actions with actions to prevent recurrence are attached l to the Event Review and presented to management for approval. I i f R e

PROCEDURE NO. REYllioN PAGE No. VEGP 00057-C 4 12 of 37 4.3.5 Corrective actions assigned by the Event Review Team must have the receiving departments concurrence. This may be achieved by having the Event Team members contact their department manager directly or having the i ERTL obtaining concurrence at the daily status meeting. If concurrence is not obtained the affected department manager (s) will attend the presentation to management. i Their concerns will be resolved by management at this i meeting. 4.3.6 The Event classification guidelines in section 4.10 should be used for event classification. 'Ihe statements following the identified classification (s) should be addressed in the Event Report. 4 Once the event is classified, the Event Review Team Leader (ERTL) will inform the GMNP/ACH-OPS /ACM-SPT. If I the event is classified as being of unknown cause or safety-related equisment did not function proserly during the event, t1e ERTL will also inform t1e OSOS, Manager Operations and the Manager Engineering Support. I 4.4 RESTARTING WORX/0PERATIONS 4.4.1 The OSOS and ERTL may recommend a restart of the reactor or work, whenever the cause of the event is known, corrected, and all associated safety-related equipment operated satisfactorily during the event. 4.4.2 The ERTL will inform the CMNP/AGM-OPS /AGM-SPT when an l l event cause is unknown. At the request of the ERTL, appropriate management or personnel will report to the plant site to assist in further investigation of the I event and to determine necessary corrective action 3 f before restart. In some cases restarting work or the reactet is a apropriate without the investigation being cottplete. be restarted as allowed by T1e reactor may only' Reactor Trip Review" and Procedure Procedure 10006-C, 00300-C, " Authority To Startup And Shutdown Reactors". Operations and Engineering management will analyze the event reconstruction, emphasizing t:te root cause(s) of the event and the resolution of abnormal or degraded indications. They will use available expertise to resolve questions concerning the cause and plant response. Sources of expertise that should be considered include nuclear steam supply vendors, vendor engineers, on-site engineering staff, corporate I engineering staff, and other experienced operations and l maintenance personnel. The following information will i be presented to management ~..

z-l'ROCEDURENO. REV151oM PAGE NO. VEGP 00057-C 4 13 of 37 a. The actual or most probable cause of the event i b. The maintenance and testing necessary before restert including additional measures to verify this most probable cause c. Arditional monitoring or trending required during ar.d/or af ter reactor restart d. Necessary briefings to Operations and/or Haintenance personnel concerning specific equipment indications or possible malfunctions e. The conditions necessary for resumption of work or for a reactor restart l 4.5 REPORT NUMBERING Each Event Report will be assigned a sequential number with the unit number and last two digits of the current year preceding the assigned number (e.g. 1-89-XXX). The sequence will begin at X-XX-001 (e.g. 1-89-001) at the beginning of each year. An Event Report log will be kept by ISEG and updated an each event occurs. 4.6 EVENT REPORT l l The following basic information should be included by the ERTL in an Event Report. The ERTL may delete non-applicable sections. 4.6.1 Unit (s) Status at Time of Event List the plant operating conditions prior to the event for each unit involved. These include:

1) megawatts thermal, 2) percent of rated thermal power, and 3) mode.

The information may be augmented by reactor reactor coolant temperature, or other i pressure applicableinformation. This section should also include any inoperable equipment, structures or components that contributed to the event. The status of these systems must be stated. l l This section will have two major subheadings: i 1. Power Level / Mode and 2. Inoperable Equipment.

DRoCEDURE No. REYisioN PAGE NO. VEGP 00057-C 4 14 of 37 I The sections should be in the form 1. Power Level /Hode l Unit 1 was in steady state operation at an approximate power of 3411 HWe (100 percent of rated thermal power). The reactor was in mode 1. 2. Inoperable Equipment The TD AFW system was tagged out of service l for maintenance. 4.6.2 Description of Event This section has 6 subsections. These are:

1) Event,

2) Dates / Times, 3) Other Systems Affected, 4) Method of Discovery, 5) Operator Actions, and 6) Auto / Manual Fafety System Response.

This section of the report may be written in a narrative fashion where possible. l 4.6.2.1 Event The description of the event shall be written in l sufficient depth so that knowledgeable readers conversant with the design of commercial nuclear power plants, but not familiar with the details of a particular plant, can understand the complete event. Characteristics of a plant that are unique and that l influenced the event, favorable or unfavorable should l be described. Also, describe how system, component, and operating personnel performance affected the course of the event. The descriation of the event should also describe the event from t1e perspective of the operator, for exanple, what the operator saw, did, perceived, understood, or misunderstood during the event. 4.6.2.2 Dates / Times This section may be done in a serial (list) fashion. However, every attempt should be made to maintain each item in the list in a narrative form. t Include the dates and approximate time for all major , discoveries, immediate corrective occurrences (e.g/ components declared actions, sy/ operable, reactor trip, stable conditions stems inoperable achieved). Include an estimate of the time and date of failure of components, trains, and systems if different than the time and date of discovery. For failure that rendered a train of a safety system inoperable, provide an estimate of the elapsed time from the discovery of the failure until the train was returned to service.

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d 5 PMXEOURE No. QEVI6loN PAGE No. "VEGP 00057-C 4 15 of 37 4.6.2.3 Other Systems Affected Provide a list of other systems et secondary functions that were also affected by each component failure or fault, if the component had multiple functions (if none, so state). 4.6.2.4 Method of Discovery Describe the method of discovery of each component failure, system failure, personnel error or procedural deficiency (e.g., while reviewing surveillance procedures or results..., during a pre-startup valve lineup check..., while performing quarterly maintenance on. during a plant walkdown...). 4.6.2.5 Operator Actions Describe all major operator action that affected the course of the event (including immediate corrective actions, operator errors, etc.) and any procedural i deficiencies that contributed to the event (if none, so i state). 4.6.2.6 Auto / Manual Safety System Response List all automatic and manually initiated safety system responset that occurred including those necessary "to place the plant in a safe and stable condition. ( All systems responded as designed" is not sufficient. If none, so state.) i 4.6.3 Cause of Event This section has two subsections:

1) Direct Cause, and

2) Root Cause(s).

Both of these sections should be written in as close as possible to a narrative format. i Each subsection is more fully described below. l 4.6.3.1 Direct Cause l Describe the cause of the event per section 4.10 and include the failure mode, mechanism (direct cause), and effect (consequence) of each failed component (e.g. valve failed to open because the stem broke resulting in no flow to the reactor). 4.6.3.2 Root Cause (Perform per Procedure 00058-C, " Root Cause R Determination" and attach a copy of the root cause i dete rmination worksheets). l l

\\ i ,e..; m .-./:. p PROCEDURE No. MEVI5loM PAGE No. VECP 00057-C 4 16 of 37 If the event involved personnel error, the cause discussion must also includes j Information as to whether the personnel error was the result of a cognitiva error or the result of a procedural error. Also, information as to whether 1 the personnel error was a result of not adequately following an approved procedure, was a direct result of an error in an approved procedure, or was a result of the activicy or task not being covered by an approved procedure. l The type of personnel involved in the event (e.g., ' contractor maintenance personnel, utility-licensed operator, utility-nonlicensed operator, utility maintenance personnel). Any unusual characteristics of the work location (e.g., heat, noise, smoke, poor lighting) that directly contributed to the personnel error. If the cause of a failure cannot be readily determined and the investigation is to continue, states (a) the steps planned to continue the investigation, and (b) that a supplemental report will be rubmitted that discusses the results of the investigation and includes the cause and all planned corrective actions. 4.6.4 Analysis of Event An assessment of the safety consequences and implications of the event should be made. This assessment must include the availability of other systems or components that could have performed the same function as the systems or components that failed (or otherwise became inoperable) during the event. The assessment should also include the safety consequences and implications had it been possible for the event to have occurred under a more severe set of initial conditions (e.g., at power rather than shutdown, at 1001 power rather than 201). If it is concluded that no safety consequences resulted from the event, state how this conclusion was reached. i l I

~PRocEDUHENO. REVl61oN PAGE NO. VEGP 00057-C 4 17 of 37 As general guidance, when an event involves the loss of a system, ele analysis should focus on the other-systems available to mitigate the event. If the event involves a hardware breakdown or design deficiency / inadequacy the analysis can focus on the administrative controls (procedural guidance that are in effect and which can mitigate the event). Where the event involves an administrative problem, the analysis can focus on the hardware and design that mitigate the consequences of the event. 4.6.5 Corrective Actions A description of any corrective action planned or taken i as a result of the event should be provided. This i should include a discuasion of repair or replacement l actions as well as those actions that will reduce the 1 l prohnbility of a similar event occurring in the future involved in the event vore counseled " gersonnel (e.g., "the valve was replaced and the l the pump was l repaired and a discussion of the event was included in the craining lectures." "no modification to the l instrument was deemed necessary but a Caution Notice l was inserted into its calibration procedure just prior i to the step that initiated the event"). This section should address the four elements of the corrective action program:

1) correction of the deficiency, 2) investigation of similar conditions, 3) decennination of root cause of the event, and 4) l l

development of long term corrective accion to prevent I recurrence. 4 4.7 INVESTIGATION REVIEW 4.7.1 The Event Review Team Leader is to have completed the Event Report within 7 days of the event and present ic to appromriate management for approval. The ERTL will I cnsure t'1st a minority opinion is attached to the report whenever a team member does not agree with finding of the team and request his opinion be included. 4.7.2 Department managers who have not provided approval to I corrective actions assigned by the Event Review Team will be present at the presentation to management. Department managers will approve of corrective actions I or provide alternative corrective actions. Differences will be resolved by plant management. mun L____________

f~ _f-on 'o, PROChDURL No. REYlSloN PAGE No, VEGP 00057-C 4 18 of 37 i l 4.7.3 Events with known causes and proper system response will be revtewed by matiagement. If deemed appropriate by the, AGM-OPS, as a result of safety significance or l potential generic aspects, the AGM-OPS will forward the report to the PRB for review. 4.7.4 Events with unknown causes or with significant systems not responding properly during the event, if directed by the GMNP/AGM-OPS /ACH-SPT, will be reviewed by the i PRB before a reactor or work restart is commenced. In any case, the GMNT/AGM-OPS /ACM-SPT will forward the i Event report to the PRB for review. 4 4.8 FOLLOW-IfP 4.8.1 Complete and incomplete corrective actions vill be forwarded to the Technical Support Department as part of the original Event Report for input to the Open Item / Commitment Tracking Program. At this point I the Event Report Log should be marked with the Investigation report completion date. 1 4.8.2 When all corrective actions have been implemented and action items closed the Technical Support Deparen.ent l will transmit the completed report to Document Control for retention as a lifetime record. 4.9 EVENT CLASSIFICATION CUIDE Each Event Report will be classified according to the direct cause of the event. Root and contributcry causes are to be classified in the Root Cause Determination. This is to aid in finding problem indicating trends, clarifying administrative areas,ls, and improving the operational reliability of contro the plant. DIRECT CAUSE CODES Cause Code Meaning 4 4 A Personnel error B Design, Manufacturing, Construction / Installation C External Cause 1 D Defective Procedure

i: s 4 --= DMocEDV2EM8 REth51oM PAGE No. VEGP 00057-c 4 19 et 37 E llanagement/9uality Assurance Deficiency X Other The generni definitions of these classification are ao follows: l A. ' Personnel Error - This classification is assigned to tailutes attributed to human errors. When. errors were made as a result of following incorrnet written procedures, tSe occurrence should he entered under defective procedure (see i Paragraph D below). When errors were made because written procedures were not followed or because personnel did not perform in accordance uith accepted or approved practice, the occurrence l ) should be classified under personnel.trror. For examples failure to use an approved procedure, failure to pro erly identify equipment, failure to observeradiat!onprotectionrules,failureof qualified personnel to perform in accordance with accepted or approved practices. In addition, personnel errors may be due to lack of or insufficient training, experience, supervision, environmental conditions, proper tools, poor health, etc. An event classified as A. Personnel Error should include the following: A description of the personnel error as well I a. as a concise statement of the personnel error (i.e., Tech "A" did not follow procedure). b. A discussion of the procedural invo*vement as well as employee qualification to perform the indicated task. d e. An evaluation of the corrective action taken I pursuant to the personnel error. B. Design. Manufacturing. Construction / Installation - This classification in assigned to tailures reasonably attributed to design, manufacture, construction or installation of a system, component or structure. For example, failures that were traced to such things as defective 4 materials, significant breakdown in the quality assurance program or components otherwise unable to meet the specified functional requirements or performance specification should be included in this classification. j I MMM - -. - ~ - _.

PROClOV;.E NO. REVISloN PAGE NO. VECP 00057-C 4 20 of 37 1. Design Deficiency An event classified as B. Design Deficiency j should include the followings a. Describe in detail the deficiency and how it reisted to or contributed to tho event. Provide sketches as appropriate. b. Address the same or similar design deficiency an it may exist elsewhere at the station. c. Discuss how long the existence of the deficiency has been known and describe any action taken previously to correct it. 2. Manufacturing Deficiency - This classification is assigned to events attributed to a manufacturer's fabrication activities. Cencrally it will cover a component or system that fails to perform its intended function as specified in design or procurement documents, manufacturer's technical manuals, etc. For examples failures traced to defective material, incorrect materials, abnormal wear or ccher degradation under normally anticipated plant conditions. An event classified as B. Manufacturing, Deficiency should include the tollowings a. Describe in detail the deficiency and how it related to or contributed to the event. Provide sketches as appropriate. b. Provide manufacturer data such as make, model or part number, sufficient to uniquely identify the deficient item. c. Indicate whether or not the manufacturer has been notified, d. Review NPRDS for industry experience. e.s i 1

R PROCEDURE NO. nEVISION > ALE NO. VEGP 00057-C 4 21 of 37 3. Construction / Installation Deficiency - This

• lassification is assigned to events cattributed to field construction and/or installation errors.

For exarale location of components different from that shown on drawings: not following inspection or cleanliness specifications or installing valves backwards. An event classified as a B. Construction / Installation Deficiency should include the followings a. Describe in detail the deficiency and how it related to or contributed to the event. Provide sketches as appropriate. b. Does the same or similar deficiency exist elsewhere in the plant? Where? c. How did the deficiency occur? (if able to determine) d. If the deficiency was oreviously known, describe any action taien to correct the deficiency. 4. Component Failure / Malfunction - This classification is assigned to events whenever the cause of equipment failure cannot reasonably be attributed to inadequate design, manufacturing, construction, or installation. An event classified as B. Component Failure / Malfunction should include the following: a. Describe in detail the failure and how it occurred. b. Describe previous failure of a similar nature and previous corrective actions taken. c. Discuss how the failure relates to or contributed to the event. j d. Address potential generic concerns if applicable.

t PROCEDURE N3 r.EylSION PAGE NO. VEGP 00057-C 4 22 of 37 Discuss any relevant preventive e. maintenance or surveillance testing concerning the item. f. Review NPRDS for similar iters. C. External cause - This classification is assigned co failures actributed to natural phenomena. A typical example includes failure resulting from a lightning strike, tornado, or flood. This classification is also assigned to man-made externsi causes that originate off-site (e.g., an industrial accident at a near-by industrial facility). An event classified as C. External cause should include the followings a. Describe in detail the unusual service enndition and what created it, b. Describe how the condition related to or contributed to the event. Addreas the same or similar condition which c. has been identified during the investigation. d. Address how long the condition had existed and what arevious action (s) had been taken to correct tie condition. i Review industry experience for similar events e. and corrective action. l D. Defective Procedure - This classification is assigned co tailures caused by inadequate or incomplete written procedures (see Paragraph A I above) or instruction. The absence of good judgement or good engineering practice generally l should be classified as A. Personnel Error. All i l circumstance cannot be covered by procedures. I An event classified as D. Defective Procedure should include the followings Describe in detail the deficiency and how it a. related to or contributed to the event. Attach procedures, directives, etc., clearly I marked as to problem areas if appropriate. )

' PROCEDURE No. rem 5loN PAGE NO. VECP 00057-C 4 23 of 37 b. Address the same or similar deficiencies which have been identified during the investigation process, c. Discuss procedural involvement, if any, as well as personnel qualifications to perform the procedure. E. Management / Quality Annurance Deficiency - This classification is assigned to a failure of management or management systems (e.g., major breakdowns in the administrative controls, preventive maintenance program, surveillance program, or quality assurance controls). An event classified ad E. Management / Quality Ansurance Deficiency should include the followings a. Describe in detail the deficiency and how it related to or contributed to the event. Attach procedure or directives clearly marked as to problem areas if appropriate. b. Address the same or similar deficiencies which have been identified during the investigation process. c. Discuss procedural involvement, if any, as well as personnel qualifications to perform the procedure. X. Other - This classification will be assigned to TaITures for which the approximate cause cannot be identified or which cannot be assigned to one of the classifications noted above. An event classified as X. Other should include the followings a. Describe in detail the event and how it was discovered. b. Discuss previous occurrences of similar nature. c. Discuss what possible causes have been considered as well as any reasonable postulated cause. l

i. (l,:-l t,Q:;. - u; 4 p,..<. ..;:., :,p '/ '$ FRoCEDURE NO. REYl6 ION PAGE NO, , 24 of 37 .,v, VEGP 00057-C 4 ..t 'fa

5.0 REFERENCES

l.- 5.1 PROCEDURES C. 5.1.1 00007-C, "Vogtle Duty Manager / Response Team" l [$ l 5.1.2 00058-C, " Root Cause Determination" 5.1.3 00150-C, " Deficiency control" 5.1.4 00300-C, " Authority To Startup And Shutdown Reactors" 5.1.5 10006-C, " Reactor Trip Review" 5.1.6 90142-C, " Security Report Procedure" l END OF PROCEDURE TEXT 6

Pr.OCEDURE NO. REyl510N PAGE NO. VEGP 00057-C 4 25 of 37 EVENT INVESTICATION CUIDELINES 1. COLLECT DATA PACKAGE FROM MANAGER OPERATIONS OR OSOS, l OR DESIGNEE, AND REVIEW. 1 2. PREPARE AN INTERVIEW

SUMMARY

OF QUESTIONS AND ANSWERS FOR EACH INTERVIEW CONDUCTED. 3. REQUEST AND KEEP HARD COPIES OF ALL PERTINENT RECORDS (HWO'S, SECTIONS OF VENDOR MANUALS, PRINT, ETC.) 4 ANSWER QUESTIONS ON SHEF.TS 8, 9 AND 10. 5. DETERMINE THE SEQUENCE OF EVENTS AND LIST ON SHEET 7. 6. KEEP TRACK Or ACTIONS AND SOLUTIONS FOR USE IN THE EVENT REPORT. 7. WHEN ALL CONCERNS ARE ANSWERED, PERFORM A ROOT CAUSE DETERMINATION PER PROCEDURE 00058-C. 8. DETERMINE THE EVENT CLASSIFICATION AS DESCRIBED IN THE CLASSIFICATION CUIDE, SECTION 4.9. 9. DETER"TNE AND DOCUMENT ANY ADDITIONAL RECOMMENDED CORRECTIVE ACTION ON ROOT CAUSE DETERMINATION SHEETS. 10. COMPLETE AN EVENT REVIEW REPORT BASED IfPON THE REQUIREMENTS OF SECTION 4.6. 11. PERFORM A SAFETY ASSESSMENT PER 4.3.3 and 4.6.4. i 12. DEPARTMENT MANAGER REVIEW AND APPROVAL OF RECOMMENDED l l CORRECTIVE ACTION AND EXPECTED COMTLETION DATES GIVEN ON THE ROOT CAUSE DETERMINATION SHEETS. 13. PRESENT INVESTICATION RESULTS TO RESPONSIBLE DEPARTMENT MANAGERS AND SITE MANAGFK:,NT WITHIN 7 DAYS OF THE l EVENT. 14. PROVIDE TRAINING A COPY OF EVENT REPORT FOR REVIEW AND USE IN CONTINUING TRAINING. j 15. FORWARD THE EVENT REVIEW PACKAGE TO TECHNICAL SUPPORT DEPARTHENT FOR INPUT TO OPEN ITEM /COMMIIMENT TRACKING. 16. TECHNICAL SUPPORT FORWARDS THE EVENT REVIEW PACKAGE TO I DOCUMENT CONTROL OR RETAINS AS A HISTORICAL DOCUMENT PER OTHER INSTRUCTIONS. FIGURE 1 EXAMPLE

PROCEDURE NO. REYlSION PAGE NO. VECP 00057-C 4 26 ef 37 Event Report No. Report: Page _ of EVENT PERSONAL STATEMENT

• 1.

FOR THE PERIOD PRIOR T0, DURING, AND AFTER THE EVENT, SUMMARIZE THE SEQUENCE OF EVENTS THAT YOU OBSERVED, AND YOUR SPECIFIC ACTIONS TAKEN BASED ON INDICATIONS. l 2. DID ANY AUTOMATIC SYSTEMS OR EQUIPMENT MALFUNCTION REQUIRE ANY OPERATOR INTERVENTION? (Describe) ) 1 3. DID THIS EVENT REVEAL ANY PROCEDURAL INADEQUACIES? (Describe) FIGURE 2 EXAMPLE i

PfAoCEDURE NO. REYlSION PAGE NO. VECP 00057-C 4 27 of 37 Event Report No. Report Page _ or 4. IF THIS EVENT OCCURRED AGAIN, WHAT WOULD YOU DIFFERENTLY 7 5. ARE THERE ANY LESSONS LEARNED FROM THIS EVENT THAT YOU BELIEVE SHOULD BE INCLUDED IN TRAINING 7 (Describe) 6. COMMENTS: a r SIGNATURE TITLE DATE For reactor trips the personnel statement form in Procedure 10006-C may be used in lieu of this form. FIGURE 2 (CONT'D) EXAMPLE I x I l'-

I.. .,. c w.g PROCEDURE NO. REVi8lON PAGE NO. VEGP 00057-C 4 28 of 37 Sheet 1 of 10 DATA SHEET 1 Report: Page of l l l EVENT REPORT EVENT TITLE: REPORT NUMBER: DATE(S) 0F EVENT: EVENT CLASSIFICATION: Name: of EVENT REVIEW TEAM MDmERS i l Signature of l EVENT REVIEW TEAM LEADER 1 DATE COMPLETED MANACDENT REVIEW AND APPROVAL PRB Review Required YES [] NO (l 4 1 i f PRB Chairman Meeting NO./ Date i J M 1446

PROCEDURE NO. REVl810N PAGE NQ. j VEGP 00057-C 4 29 of 37 Sheet 2 of 10 DATA SHEET 1 Report: Page _ of i TABLE OF CONTENTS FOR EVENT REPORT NO. -

• PAGE 1.

REPORT NARRATIVE (PER SECTION 4.6) 2. EVENT DATA COLLECTION. l 3. CHRONOLOGY,..................... 4.** PERSONAL STATEMENTS...(Figure 2) 5. ROOT CAUSE DETERMINATION (PER 00058-C). 4 6. ADDITIONAL SUPPORTING ITEMS............. i i ERTL TO NUMBER EACH PAGE OF THE REPORT AND ENTER APPROPRIATE i PAGE NUMBERS. ADDITIONALLY, THE ERTL WILL ENSURE THE EVENT REPORT NUMBER APPEARS ON EACH PACE OF THE REPORT. l l \\ l l INFORMATION WILL BE PRESENTED ON THE INDICATED FICURE. ] 4 t b 1 l l i wm

• s t a ge

PROCEDURE NO. REYlSiON PAGE NO. VEGP 00057-C 4 30 of 37 Sheet 3 of 10 DATA SHEET 1 Event Report No. EVENT DATA COLLECTION Report: Page of _ l. EVENT DESCRIPTION EVENT DATE UNIT EVENT TIMK DEFICIENCY CARD NLHBER l (!F REQUIRF.D) 2. TYPE OF EVENT A. REACTOR TRIP ( ) F. RADIOACTIVE SPILL / B. FORCED RF. DUCTION ( ) UNCONTROLLED RELEASE ( ) C. PLANT TRANSIENT ( ) C. LIQUID INVENTORT LOSS ( ) D. ESTAS ( ) N. OTHER SIGNIFICANT EVTNT ( ) E. PERSONNEL CONTAMIN ( ) 3. EVF.NT REVIEV TEAM CAtt.ED 007: TIME SAER INFORMED: T!HE CORPORATE DUTT HANAGER INTORMEDI TIME 4. DATA COLLECTION ASSICNMENT 5. DATA: TOR REACTOR TRIPS COMPLETE 10006-C, AND CIVE A COPY TO THE EVENT REVIEW TEAM. FOR ALL OTHER EVENTS, COMPLETE THE SECTION $ THROUGH 16 AND PERSONAL STATEMENTS. STATD(ENT ACTIVITT PERFORMED ATTACHED SHITT TERSONNT.L AT THE TIME OF THE EVE?ff YES OR NA CSOS SS S S'- g Rf STA OT1tERS INVOLVED _ 6. DATA TO BE Cott.ECTED (0 SOS TO CHECK 1TEMS) NOTER REMOVE THE DISK PACK ATTER A TRIP /St. PLANT COMPUTER At. ARM PRINT 0tTT ( ) PtANT COMPUTER EVENT LOCS ( ) ATS! PRINTOUT ( ) ERT COMPUTER EVENT 1.0CS ( ) TAULT RECORDER PRtHTOUT ( ) ERP COMPUTT.R TREND PRINTS ( ) CHART RECORDERS (LIST) COPLES oft NRC-OC HOTIFICATION h'ORKSHEET ( ) SS LOCS ( ) AUX BLDG OPERATOR IDC ( ) TURRINE BLDC LOC ( ) RWO LOC ( ) I CONTROL BLDC OPERATOR LOC ( ) ELECTRICAL LOC ( ) OtTTSIDE OPERATOR LOC ( ) UNIT CONTR01. ( ) CHEMISTRT l HP NWO'S i

l h- ~~ PROCEDUMENO. AEvlS10N PAGE No. VECP 00057-C 4 31 of 'T Sheet 4 of 10 DATA $NEET 1 Event Report No. Report: Page of 7. PLANT CONDITION WHEN AFFROPRIATE MAXIMUM /MININUM PRE-EVElff VALUE POST F7FNT l l NODE / XEACTOR F0VER / I l BORON CONCEtrTRATION / STEAM CENERATOR LEVEL 1* /

• Use NR or WR, 24

/ l i-whichever is 3a / i indicating 4* / CENERATOR OUTPUT / MWE PRESSURIZER LEVEL / i ) f 8. PfANT CONFICURATION 8.1 0FF NORMA 1. STATUS OF FLANT SYSTEMS 8.2 TESTS AND SURVIILLANCES IN FR0 CESS .-~ 8.3 OTHER OPERATIONS IN FROGRESS AT THE TIME OF THE EVENT 9. FOR ESFAS ACTUATION OR FAILURE AUTOMATIC ( ) MANUAL ( ) N/A ( ) 9.1 LIST CRANNEL ACTUATED / FAILED EXPLAIN SYSTEM RESPONSI 9.2 DID TNE ESTAS COMPONENTS OPERAtt CORRECYtTt YES ( ) NO ( ) WITHOUT UNDUE DEIAYf TIS ( ) NO ( ) 9.3 EEFtAIM ANT ABNORMAL ST8T1M ESFAS RESPONSES. WNTt em

PROCEDURE NO. REVISION PAGE NO. { VECT 00057-C 4 32 of 37 Sheet 5 of 10 DATA SHEET 1 Event Report No. ~ 9.4 DESCRIBE ANT OTHER HALPUNCTIONS NOTICED: 9.5 APPARENT EVENT CAUSE WAS l 10. CORRECTIVE ACTIONS 10.1 WAT IMMEDIATE CORRECTIVE ACTIONS WERE TAKEN AS A REstit OF THE EVD(T7 10.2 WAT SUBSEQUENT CORRECTIVE ACTIONS ARE IN PROGRESS AS A RESULT OF THE EVENT 7 10.3 WAT TURTHER CORRECTIVE ACTIONS ARE RECONKENDED? K LIST CORRECTIVE ACTION TAREN FOR EACH ABNORMAL OCCURRENCE OR EQUIPMENT MALTUNCTION THAT ACCOMPANIED THE EVENT (STATE WETHER COMPLETED, IN PROGRESS, OR PROPOSED). I 12. WERE PROCEDURES USED ADEQUATE? TES ( ) NO ( ) VHT NOT7 i I i 13. DID THE OPERATOR $ AND OTHER PERSONNEL NANDLE THE EVENT CORREC11Tt l EXPLAIN. DISCUSS CORRECTIVE ACTION 10 DATE. 1

l PMOCEDURENO. HEYlSIOd PAOL NO. VEGP 00057-C 4 33 of 37 Sheet 6 of 10 DATA SHEET 1 Event Report No. Report Page _ of 1 14. WAS AN EMERGENCY PLAN EAL REACHED? DESCRIBE LEVEL Ilt?OLVED (NOUE, ALERT, $1TE AREA, CENERAL). i 15. LIST LC0'S ENTERED 1 LCO No. DF.SCRIPTION INITIALS \\ 1 i l k 16. LIST ANT SAFETY LIMITS EXCEEDED. TECH SPEC AND DESCRIPTION j. j 4 ,1 j i l I COMPLETED BYt DATA COLLECTOR j 9 1449

PROCEDURENO. Rivi$ ION PAGENO. l VEGP 00057-C 4 34 of 37 l Sheet 7 of 10 DATA SHEET 1 Event Report No. I Report: Page _ of l SEQUENCE OF EVENTS CHRONOLOGY l DATE/ TIME EVENT i 4 m A M 18 4%

d PROCEDURE NO. REYlSION PAGE NO. VEGP 00057-C 4 35 of 37 Sheet 8 of 10 DATA SHEET 1 Event Report No. Report: Page of INVESTIGATION QUESTIONS A. GENERAL 1. DOES THE EVENT REPRESENT A PREVIOUSLY UNFORESEEN ACCIDENT SEQUENCE 7 YES/NO 2. DOES THE FAILURE DIRECTLY OR THROUCH INTERACTION WITH OTHER SYSTEMS DEGRADE THE PERFORMANCE OF ANY SAFETY-RELATED EQUIPMENT? YES/NO 3. DOES THE FAILURE DIRECTLY OR THROUGH INTERACTION WITH OTHER SYSTEMS INCREASE THE PROBABILITY OF AN ACCIDENT 7 YES/NO l 4. DOES THIS FAILURE CRALLENCE OR ACTIVATE SAFETY SYSTEMS? YES/NO 5. DOES THE EVENT INCREASE THE PROBABILITY OF TRANSIENT-OCCURRENCES AND/OR REACTOR TRIPS? YES/NO 6. DURING THE EVENT, DID THE OPERATIONS STAFF RESPOND CORRECTLY? YES/NO 7. ARE TRAINING KNOWLEDGE OBJECTIVES, PERFORMANCE TASRS AND CONTROLS ADEQUATE TO PROMOTE THE PROPER PERFORMANCE i 0F THE OPERATIONS STAFF UNLER SIMIIAR CIRCUMSTANCES? YES/NO 8. BASED ON A COMPARISON OF THIS EVENT WITH PREVIOUS EVENT REPORTS AND/OR FSAR ANALYSES, VERE THERE ANY ABNORMAL OR DEGRADED INDICATIONS? YES/NO 9. BASED ON COMPARISON OF RELATED SIMILAR INDUSTRY AND IN-HOUSE EVENTS, IS THIS EVENT A REOCCURRENCE OF A i PREVIOUS EVENT: YES/NO 10. DURING THIS EVENT, DID ALL AFFECTED SYSTEMS RESPOND AS EXPECTED? YES/NO 11. DID THE INITIAL EVENT PRODUCE UNANTICIPATED SECONDARY EFFECTS WHICH COMPLICATED OR INCREASED THE CONSEQUENCES i j OF THE EVENT? YES/NO i j

PROCEDURE NO. REYlSION PAGE NO. VEGP 00057-C 4 36 of 37 [ Sheet 9 of 10 l l. DATA SHEET 1 Event Report No. Report: Page ot INVESTIGATION QUESTIONS (CONT'D) 12. BASED ON COMPARISON OF SIMIIAR INDUSTRY AND IN-HOUSE EVENTS WERE PREVIOUS CORRECTIVE ACTIONS / IMPLEMENTATION EFFECTIVE 7 YES/NO 13. IF QUESTIONS 1, 2, 3, 4, 5, 8, 9, OR 11 ARE ANSWERXD YES, DESCRIBE THE REASON IN DETAIL IN THE EVENT REPORT. 4 14. IF QUESTION 6, 7, 10, or 12 ARE ANSWERED NO, DESCRIBE THE REASON IN DETAIL IN THE CVENT REPORT. i B. PERSONNEL ERRORS 1. WERE JOB ENVIRONMENT CONDITIONS SUCH AS LICHTING, VENTILATION, EXTREME TEMPERATURE OF PHYSICAL ACCESS TO THE TASK CONTRIBUTING FACTORS? YES/NO 2. WERE PROPER TOOLS AVAIIABLE AND USED7 YES/NO 4 3. WERE WRITTEN APPROVED PROCEDURE AVAILABLE AND PROPERLY FOLLOWED7 YES/NO 4 IF THE PROCEDURE WERE FOLLOWED, WAS PROCEDURE COMPLIANCE A CONTRIBUTORY CAUSE? YES/NO 5. WERE ADEQUATE INSTRUCTIONS CIVEN AND COMPREHENSION VERIFIED? YES/NO 6. WERE THE PERSONNEL INVOLVED IN THE PROPER PHYSICAL CONDITION 7 YES/NO 7. DID THE PERSONNEL INVOLVED HAVE ERR 0NEOUS IDEAS AND/OR CONCEPTS ABOUT THE SYSTEM INVOLVED? YES/NO 8. DID THE PERSONNEL INVOLVED HAVE PREVIOUS EXPERIENCE AND/OR TRAINING ON THE SYSTEM INVOLVED? YES/NO 9. DID THE PERSONNEL RECEIVE A BRIEFING OF THE EVOLUTION PRIOR TO STARTING? YES/NO 10. WERE COMMUNICATIONS ADEQUATE FOR THE EVOLUTION? YES/NO 11. WERE COMMUNICATIONS TESTED PRIOR TO STARTINC? YES/NO i )

g -3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 4 OPERATING LIMITINGCONDITIONFoiCPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: Two physically independent circuits between the offsite transmission a. network and the onsite Class IE Olstribution System, and b. Two separate and independent diesel generators, each with: 1) A day tank containing a sinimum volume of 650 gallons of fuel (52% of instrument span) (LI-9018 LI-9019), 2) A separate Fuel Storage System containing a minimum volume of 68,000 gallons of fuel (76% of instrument span) (LI-9024, L1-9025),and 3) A separate fuel transfer pump, 3 APPtlCABILITY: H00ES 1, 2, 3, and 4. ACTION: j With one offsite circuit of the above-required A.C. electrical power a. sources inoperable, demonstrate the OPERA 8ILITY of the remainino A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within I hour and at least once per 8 hours thereafter. If either dieset j generator has not been successfully tested within the past 24 hours, demonstrate its OPERA 8ILITY by performing Surveillance Requirements i 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 for each such diesel generator, separately, within 24 hours unless the diesel generator is already 4 I-operating. Restore the offsite circuit to OPERA 8LE status within i 72 hours o-be in at least HOT STAND 8Y within the next 6 hours and j in COLD SHU1DOWN within the following 30 hours. b. With either diesel generator inoperable, demonstrate the OPERA 81LITY I of the above required A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour and at least once per 8 hours thereafter. If the diesel generator became inoperable due to any cause 1 other than preplanned preventive maintenance or testing, demonstrate i the OPERABILITY of the remaining 0PERA8LE diesel generator by perform-ing Surtelliance Requiremen s 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 within 24 hours 4. Restore the inoperable diesel generator to 0PERA8LE status within 72 hours or be in at least HOT .Ah08Y within the next 6 hours l-and in COLD SHUTDOWN within the following 30 hours.

• This test is required to be completed regardless of when the inoperable olesel generator is restored to OPERA 81LITY.

1. The diesel shall not be rendered inoperable by activities performed to suppoit testing pursuant to the ACTMN Statement (e.g., an air roll).

l VOCTLE UNITS - 1 & 2 3/4 8 1

Q 1 1 1 ELECTRICAL POWER SYSTEMS i LIMITING CON 0lil0N FOR OPERATION ACTION (Continued) c. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. of fsite source by performing Surveillance Re-quirement 4.8.1.1.1.a within I hour and at least once per 8 hours thereafter, and, if the diesel generator became inoperable due to any cause other than preplanned preventative maintenance or testing, demon-strate the OPERA 8ILITY of the remaining DPERABLE diesel generator by performing Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 within 8 gours*, unless the OPERA 8LE diesel generator is already operating. Restore at least one of th inoperable sources to OPERABLE status within 12 hours or be in at least HOT STAND 8) within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore the other A.C. power source (offsite circuit or diesel generator) to OPERABLE status in accordance with the provisions of 3.8.1.1, ACTION Statement a or b, as appropriate, with the time requirement of that ACTION Statement based on the time of initial loss of the remaining inoperable A.C. power source. A successful test of diesel generator OPERA 81LITY per Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 performed under the ACTION Statement for an OPERABLE diesel generator or a restored to OPERABLE diesel generator satisfies the diesel generator test requirement of ACTION Statement a or b. d. With one diesel generator inoperable in addition to ACTION b. or c. above, verify that: 1. All required systems, subsystems, trains, components, and devices that depend on the remaining OPERABLE diesel generator as a j source of emergency power are also OPERA 8LE, and i 2. When in MODE 1, 2, or 3. the steam-driven auxiliary feedwater pump is OPERABLE. If these conditions are not satisfied within 2 hours be in at least HOT STAND 8Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours, With two of the above required offsite A.C. circuits inoperable, demon-e. strate the OPERABILITY of two diesel generators separately by perform-Ing the requirpents of Specification 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 within 8 hours, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours or be in at least H0T STAND 8Y within the next 6 hours. Following restoration of one offsite source, follow ACTION Statement a with the time requirement of that ACTION Statement based

• This test i required to be completed regardless of when the inoperable EDG is restored to OPERABILITY.

t

1. The diesel shall not be rendered inoperable by activities performed to support testing pursuant to the ACTION Statement (e.g., an air roll).

V0GTLE UNITS - 1 & 2 3/4 8-2 ~

ELECTRICAL POWER SYSTEM 5 1 LIMITING CONDITION F08 OPERATION ACil0N (Continued) on the time of the initial loss of the remaining inoperable offsite a.c. circuit. A successful test (s) of diesel DPERASILITY per Surveil-lance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 performed under this ACTION Statement for the OPERA 8LE diesels satisfies the diesel generator test requirement for ACTION $tatement a. f. With two of the above required diesel. generators inoperable, demonstrate the OPERA 8ILITY of two offsite A.C. circuits by performing the require-ments of Specification 4.8.1.1.1.a. within I hour and at least once per 8 hours thereafter; restore at least one of the inoperable diesel generators to OPERA 8LE status within 2 hours or be in et least HOT STAN08Y within the next 6 hours and in COLD SHUTOOWN within the following 30 hours. Following restoration of one diesel generator unit, follow ACTION Statement b with the time requirement of that ACTION Statement based on the time of initial loss of the remain'ng inoperable diesel generator. A successful test of diesel OPERA 81LITY per Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 performed-under this ACTION Statement for a restored to 0PERABLE diesel satisfies-the diesel generator test requirements of ACTION Statement b. SURVE!LLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite-Class IE Distribution System shall be: Determined OPERABLE at least once per 7 days by verifying correct a. breaker alignments, and indicated power availability. t 4.8.1.1.2 Each diesel generator shall be demonstrated OPERA 8LE: a. In accordance with the frequency specified in Table 4.8-1 on a STAGGERED 1EST BASIS by: 1) Verifying the fuel level in the day tank (LI-9018. LI-9019), 2) Verifying the fuel level in the fuel storage tank (L1-9024, L1-9025), 3) Verifying the fuel transfer pump starts and transfers fuel from i-the storage system to the day tank, 4) Verifying the diesel starts and that the generator voltage and frequency are 4160 + 170, -135 volts and 60 + 1.2 Hz within 11.4 seconds" af ter the start signal. The dTesel generator shall j be started for this test by using one of the following signals:

• All diesel generator starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as i

recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized. 1 V0GTLE UNITS 1 & 2 3/4 8 3 4. ---n --e~- ~=*e---A = + a

l ELECTRICAL POWER SYSTEMS SURVL.LLANCE REQUIREMENTS (Continued) a) Manual, or b) Simulated loss-of-of fsite power by itself, or c) Simulated loss-of-of fsite power in conjunction with an ESF Actuation test signal, or d) An ESF Actuation test signal by itself. 5) Verifying the, generator is synchronized. Ioaded to an indicated 6800-7000 kW, and operates at this loaded condition for at least 60 minutes, and 6) Verifying the diesel generator is aligned to provide standby power to the associated emergency busses. 7) Verifying the p essu-o in at least one diesel generator airstart receiver (P!-9060, P!-9061, PI-9064, P!-9065) to be greater than or equal to 210 psig. b. At least once per 31 days and after each operation of the diesel where-the period of operation was greater than or equal to I hour by_ checking for and removing accumulated water from the day fuel tank; j c. At least once per 31 days by checking for and removing accumulated j water from the fuel oil storage tanks; } d. By sampling new-fuel oil in accordance with ASTM 04057 prior to l addition to storage tanks and: 1) By verifying in accordance with the tests specified in ASTM-0975 81 prior to addition to the storage tanks that the j sample has: a) An API Gravity of within 0.3 degrees at 60*F, or a specific gravity of within 0.0016 at 60/60'F when compared to the supplier's certificate or an absolute specific gravity at 60/60'F of greater than or equal to 0.83 but less than or l equal to 0.89, or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees:

• This band is meant as guidance to avoid routine overloading of the diesel generator.

Loads in excess of the band or momentary variations due to chang-ing bus loads shall not invalidate the test.

1. All diesel generator starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as recommended by the manuf acturer so that the mechanical stress and wear on the 4

diesel engine is minimized. V0GTLE UNITS - 1 & 2 3/4 8-4 l

1 f -ELECTRICAL POWER SYSTEMS SURVEILLANCC REQUIREM[NTS (Continued)- b) A' kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with supplier's certifica.fon; c) A flash point equal to or greater than 125'F; and d) A clear and bright appearance with proper color when i tested in accordance with ASTM-D4176-82. l 2) By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM-0975-81 are met when tested in accordance with ASTN-0975-81 except that the analysis for sulfur may be performed in accordance with ASTM 01552-79 or ASTM-02622-82. At least once every 31 days by obtaining a sample of fuel oil in e. i accordance with ASTM-02276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM-D2276-78, Method A; f. At least once per 92 days and from new fuel prior to addition to the l' storage tank obtain a sample and verify that the neutralizatio number is less than 0.2 and the mercaptan content is less than 0.01% g. At least once per 184 days by: i '1) Verifying the diesel starts

• from ambient conditions and the-generator voltage and frequency are 4160 + 170. -135 volts and 6011.2 Hz within 11.4 seconds af ter the start signal. The diesei generator shall be started for this test by using one of the signals listed in Surveillance Reqvfrement 4.8.1.1.2.a.4.

This test, if it is performed so it concides with the testing 3-required by Surveillance Requirement 4.8.1.1.2.a.4, may also serve to concurrently meet those requirements as well. 4 i "All engine starts for the purpose of surve111ance testing as required by i Specification 4.8.1.1.2 may be preceded by 'an engine prelube period as recommended by the manufacturer to minimize mechanical stress en the diesel s engine. U

1. Mercaptan content shall not be required to be verified within specification for new fuel prior to its addition, for up to 15.000 gallons of fuel added

'? to the tank, if the last tank sample had a mercaptan content of less than a 0.007%. All subsequent new fuel addition will require mercaptan content veri-fication prior to its addition until the tank contents are verified to be less than 0.007%. V0GTLE UNITS - 1 & 2 3/4 8-5

~ Mm mm... 4 i ELECTRICAL power SYSTEMS i SURVill, LANCE' REQUIREMENTS (Continued) 1 2) Verifying the generator is synchronized, loaded to an indicated i valua of 6100 - 7000 kW*** in less than or equal to 60 seconds, and on. rates with a load of 6800-7000 kW*** for at least 60 minutes This te;*., if it is performed so it coincides with the testing required oy Survell',ance Requirement 4.8.1.1.2.a.5, may also serve to concurrently meet those requirements as well. l - h. At least once per 18 months,** during shutdown, by: 1) Subjecting the diesel to an inspection in accordance with proce-dures preparert in conjunction with its manufacturers' recommenda-tions for thl. class of standby service; 1 2) I Verifying the diesel generator capability to reject a load of greater than or equal to 671 kW (motor-driven auxiliary feedwater pump) while maintaining voltage at 4160 + 240. -410 volts and speed of less than 484 rpe (less than nominal speed plus 75% of the dif ference between nominal speed and the Overspeed Trip setpoint); and recovering voltage to within 4160 + 170, -410 volts within 3 seconds. i i 3) Verifying the diesel generator capability to reject a load of 7000 kW without tripping. The generator voltage shall not exceed 5000 volts during and following the load rejection; 4) Simulating a loss-of-of fsite power by itself, and: 4 a) Verifying deenergization of the emergency busses and load shedding from the emergency busses, and b) Verifying the diesel starts on the auto start signal, energizes the emergency busses with permanently connected loads within 11.5 seconds," energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. Af ter energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 +170, -410 volts and 60 f, 1.2 Hz during this test. 5) Verifying that on an ESF Actuation test signal, without loss of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal' to 5 minutes. The generator voltage and frequency shall be 4160 +170, -135 volts and 6011.2 Hz within 11.4 seconds after the

• All engine starts for the purpose of surveillance testing as required by l

Specification 4.8.1.1.2 may be preceded by an engine prelube period as recom-i mended by the manufacturer to alnimize mechanical stress and wear on the diesel engine.

• • For any start of a diesel, the diesel must be operated with a load in accor-dance with the manufacturer's recommendations.

I

• • • This band is' meant as guidance to avoid routine overloading of the engine.

toads in excess of this band or momentary variations due to changing bus l loads shall not invalidate this test. V0GTLE UNITS - 1 & 2 3/4 8 6 t- ,-r-

C SURVE!LLANCE REQUIREMENTS auto-start signal; the steady-state generator voltage and frequency shall be maintained within these limits during this . test; 6) Simulating a loss-of-offsite power (- conjunctionwithanESF Actuation test signal, aid; a) verifying deenergization of the emergency basses and load shedding from the emergency busses; b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11.5 seconds," energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 +170 -410 volts and 60,+ 1.2 H2 during this test; and c) Verifying that all automatic diesel generator trips, except engine overspeed, low lube oil pressure, high jacket water temperatures and generator differential, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety injection Actuation signal. 7) Verifying the diesel generator operates for at least 24 hours. During the first 2 hours of this test, the diesel generator shall be loaded to an indicated 7600 to 7700 kW,*' and during the remaining 22 hours of this test, the diesel generator shall be Ioaded to an indicated 6800 7000 kW.** The {,r.ierator voltage i and frequency shall be 4160 + 170, - 135 volts and 60 1 1.2 Hz 1 within 11.4 seconds after the start signal; the steady-state i i generatorvoltageandfrequencysgallbe 4160 + 170, -410 volts l and 60 1 1.2 H2 during this te t. Within 5 minutes after com-pleting this 24-hour test, perf orm Specification 4.8.1.1.2h.6)b);,, 8) Verify.ag that the auto-connected loads to each diesel generator do not exceed the continuous rating of 7000 kW; 9) Verifying the diesel generator's capability to: n

• All engines starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as recommended by the manufacturer to minimize mechanical stress and wear on the diesel engine.
  • This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band or momentary variations due to changing bus loads shall not invalidate the test.

1. Failure to maintain voltage and frequency requirements due to grid disturbances does not render a 24-hour test as a failure.
   1. !f Specification 4.8.1.1.2h.6)b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test.

Instead, the diesel generator may be operated at the load required by Surveillance Requirement 4.8.1.1.2.a5 kW for 1 hour or until operating temperature has stabilized. V0GTLE UNITS - 1 & 2 3/4 8-7

ELECTRICAL POWER SYSTEMS l SURVEILLANCE REQUIREMENTS (Continued) a) Synchronize with the offsite power source while the generator is loaded with its emerger,cy loads upon a simu-lated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Se restored to its standby status,

10) Verifying that with the diesel generator operating in a test mode, connected to its bus, a simulated Safety injection signal overrides the test mode by: (1) returning the diesel generator to standby operation, and (2) automatically energizing the emergency loads with offsite power;

11) Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross-connection Ifnes;

12) Verifying that the automatic load sequence timer is OPERA 8LE with the interval between each load block within + 10% of its design interval; 1.

At least once per 10 years or af ter any modifications which could affeet diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate.to at least 440 rpm in less than or equal to 11.4 seconds; and J. At least once per 10 years by: 1) Draining each fuvi oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution, or equivalent, and 2) Performing a pressure test of those portions of the diesel fuel oil system designed to Section 111 subsection ND of the ASME Code at a test pressure equal to 110% of the system design 3 pressure. 4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall be reported to the Commission in a Special Report pursuant to Specification 6.8.2 within 30 days. Reports of diesel generator failures shall include the informa-tion recommended in Regulatory Position C.3.b of Regulatory Guide 1.108 Revi-sion 1. August 1977. If the number of failures in the last 100 valid tests on a per nuclear unit basis is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in' Regulatory, Position C ' h of Regulatory Guide 1.108, Revision 1, August 1977. jf.-% V0GTLE UNITS - 1 & 2 3/4 8-8

TABLE 4.8-1 O!ESEL GENERATOR TEST SCHEDULE Number of Failures Number of Failures in in Last 100 Valid tast 20 Valid Tests

• Tests
• Test Frequency 4

$1 14 Once per 31 days > 2** >5 Once per 7 days

• Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, but determined on a per diesel generator basis.

For the purposes of determining the required test frequency, the previous test f ailure count may be reduced to zero if a complete diesel overhaul to like-new condition is completed, provided that the overhaul, including appro-priate post-maintenance operation and testing, is specifically approved by the manufacturer and if acceptable reliability has been demonstreted. The reliability criterion shall be the successful completion of 14 consecutive tests in a single series. Ten of these tests shall be in accordance with the routine Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 and four tests in accordance with the 184-day testing requirement of Surveillance Requirement 4.8.1.1.2.f. If this criterion is not satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.

• • The associated test frequency shall be maintained until seven consecutive f ailure free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one.

v0GTLE UNITS - 1 & 2 3/4 8-9

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• l NUCt. EAR OPERATIONS y

80-1 7 3 Revt480n No. 18 c unit 1 forg PbWer - ], p. g e. a.. ~ Egg.f 1 of 31 l ! Q ) OIO DIESEL GENERATOR OPERABILITY TEST; .y x 1.0 PURPOSE E l.1 This surveillance.pr re se o' demonstrate the operability?of the.Eme'rgencylD s alt. Generators. This procedure sficuld notLbeaused;for maintenance troubleshooting or testing, ~ ~.g,, 1.2 This surveillance 'sa ff.'es these. Technical Specification Requirementsi 4.8.1.1.2.a J i '. 4.8.1.1.2.b p* 8 4.8.1.1.2.g, r 5;,y.~ %o 1.3 The frequency of t esti-a given by Technical Specification Tablef4 8-1 , y r :..c J. W., 4,;i: g 2.0 APPLICABILITY p -H t l 2.1 This surveillance pp Modes' 1, 2, 3 and 4 g@,QMqlgidies u. 1 2.2 Portions of, this,surve .,ance.are applicable in Modes 5 j and 6. ( ,) ?- 3.0 PRECAUTIONS!ANDLIMITTIONS< j. I ,a,, - - -- J O 3.1 Th-Unit Sh:ift Supervisdr7.(~USSh be notified imediatirly' if a subsystem or component malfunctions or test data i'ndicate a tantiallproblem during a surveillance test. -{gg. 3.2 The ratad espacity'of. DieseljCenerator is 7000 kW. Load should not be permitted to exceed this limit during testing. The Diesel Generator should not be operated at 1ssa than 301. load (2100 kW) for prolonged periods ofltimo. l pAi

M y

.,, 5 i ,[ 3.3 During Diesel Genera dD:esti, , oads in excess of 7000 kW or momentarf" variations' us to changing bus loads shall not invalidite.then, test?.'.-.. 4 e g 6 h w, ' p *.php )L,:,t) e. . f ? ' : l I ~

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-hjper. f,h 2 of 31 GP 14980-1 .' t ' 5 m '. 1.;t.. l r i-3.4 If during a Diese,Eng comes in but the' engine,n.s art,the; Fail'To Start alarm theeps; running 7r,the support systems will operate li athe' engine was shut down. To reset the'se system

h START ptishbutton must. be This willys t elKesp. Warm Pumss, turn off Warm Heaters 3)]ic pressed.

the Kee) stopithe(Crankcase fans and ' erv E are bypassed when shut place cae alarms down. 8 p,,:, 3.5 Once initiated, ese. enerator; shutdown signals f,, remain in effect1 or 9,01sedondsygDuring this period, the DLesel Generator will' onlyJrespond.co an emergency start signal. Torpre dnt heh.d6pletionofstartingad stopping' lig air, wait uriti14thagoTil (approximately 90tsec6Eds Jafte normal stop before attempting to start h diesel y

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3.6 All start attempt ose from bona fide start signals, shall og ed;ln' the USS and/or the Control Room logbook e f' entry shall include the following informati l g a. Start tiime,5 /c . 4. J. b. Reason for' start f. I c. Succesd or failure e..' start attempt. i TJ gWW shali'.o.not be used for 3.7 The Emergency Diese nerators peaking service.. i. 4 4 .t 3.8 Diesel Generator'surve ance at all be initiated i only from the Control com e. 3.9 During surveillance; ngime' ' the.o. Diesel Generator one shall be parallele,d . ff-site power source.

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i g; i fbrstandbyper 3.10 The Diesel Generator , enn:a gne 13145-1, " Diesel Genitrators" and a 11145-1,"DieselGeneratorAlighmen:currentcopyof t",and 11146-1, " Diesel Gensrator Fuel iliTransfer. System Alignment" dh j h. i 3.11 If any unusual grid sturbances.'. occur,while the Diesel Generator is operating start.the' Fault Recorder in the Control Room and notif th Sys' tem Engineer for an evaluation of the prob Testing of a Dies;g; roulh' shooting ~ i 3.12 e. enerator first engine'l runt ollow;in (i.e., f should be performed.'usingf.g major maintenance, etc.) 13143-li." Diesel Generators") If necessary n testing.for operability shouldfollowusing,Mbhh$$$W( this procedure. l { g.f,';.7,A, '*i' @ k.h. [; pa t. jU j,,.,. .s S. i ~ l

t i q. VEGP 14980-1 ,3 of 31 j .r INITIALS 3.13 A cylinder moisture performed if in an action statemen a hnich pacification 3.8.1.1 or 3.8.l.2. 4.0 PREREQUISITES ORJINITI ONDITIONS i 4.1 The USS shall en urve ne test does not affect' thi itsstf presently in progresi separdj plant operation prio tantin approval to perform tirveil anc 'jf est. USS AFFROVAL 4.2 OBTAIN the foll ' nt a. Two stop wate 'f L j No. I serial'num No. 2 serial ) i b. A clear'conta ne er zero Iarger. f,,. l 4.3 NOTIFY the System, per e Unit 2 Control Room ' Die'sel Generator Test.,. A., 4.4 The NSCW System provide cooling water H{ eat 6 theiDiese ,i Generator Jacket Wate xchan ers Al ,;[. x l

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(: .a 3 '4,5 - ) TEST STARTED . d. X,/ >>d.NO DATr. .,,,. J,. W;,.. MODE

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d '.E,Q Diesel Generator Be n E S once begun ppropr:,at e portions procedure v: should.b' c'~l adji possible d MQsyst. subsystem;o onent i returnedito erv ceT ? ~ comitted ~ "'a i required ../ $.1 DIESEL CENERATOR' STAR p; No "".i s .e w j Prior to, perform ngit

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s i month surveillanceifthe diesel should remain't.in 1'. ' i standby.for3several hours to 'i. I allow temperature stabilize 3 l 5.1.1 If this test is beLng, orme T.. l the six-month;(184> day urveillase .c ) per TechnicaliSpecif.ic ion 4.8.1.1.2.g VERIFt.the'Diese$ i l Generator has been'shu down~for,m' ore u., than 4 hours.' .5 i .hNOTE [. i Whilethd'D$se enerator d!- is in operation 3 check for rubbing or; excessive 1%Q f.' i vibration ofismallrdiameter "f,. j-tubing supporting: Diesel. 3 Cendrator'operationite' t itis trument in fuel line's,%',nstruman f/ cubing, or tubing. } ~ N }gl ~- 5.1.2 STATION an operator. ese.. Generator Building to. monitor 2the. J: Diesel Generator operationfand~mainta y 3 headset or radio communication'with .c. i the Control Room.throughoutfthe$p i. [ duration of the test! 3' ' .9 I . x - - h,m ' k.,, 4 m,. j ?.... : ;. J,. c.,. ; - ; 4..... -- s.,... )

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, {., '5 of 31 i 3 P I 7 jj d',2 INITIA1.S I UTIO f i The ey' sture 7 shall;not b~ pe'rforme ti this test i iirformed's l aceion itstii e'chnic'il l Specificat 3.8.1.2 v. i 5.1.3 If Le has not been the preceding 4' hour RTORM ./' Cylinder Moisture,Ch ?! " Diesel Cenerator 5.1. l. RECORD the Diesel, one tartu i " Diesel Generator.0 e$ijjil8 59 Ii readings on Section;A s rstin 1 RECORD the Engin's % M Tour Data aat 5.1.5 ?.Q':. 29 5.1.6 TEST the annunc ator its I 1 .ilarm panel at PDG2 4) and RIF W t.hnt all annunciator ht are l operabic. If this test 15 5.1.7 regulnr monthly,por orm surveill e LI ~ starting air systeni ollows S.I.7.1 If the month i anuar or October. UNLOCKtand OSEt ,8 Ai f. Start Receiver 1?Dischar ' Is - tion t..- - I-2403-U4-765(722

M

,. s 5. t. 7. If the month is February Aagust' N or November, UNLOCK and., CLOS.the Air -lA ' Start Receiver 2 Discharge Isol ion 1-2403-U4-769(729) 1 5.1.7.3 RECORD the valys w e s t ', "i. Datu Sheet l '. If both alves;were; left open. RECORD Bo lve on Data Sheet 1..

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n s EP 14 i; l INITIALS i l i The Tur .P j Byp'a s s ',Valv i ul ibe'j.open (Step *5?1 minutes orio g, to dissel-nd Muld1 s ,y l prompt 1 Fad te ,1712) aftera. htii t ?*i throurh 5 t 1 t 1 performed R itious l Excess result rgti umul c the ex aust gYiti exhaust fi 5.l.8 OPEN the Turbo L

• 1 Ilypasa valve 1-2403 1

~ 5.1.9 PLACE the DSL CE il Switch to'A-B. t. 5.l.10 When aenttin t era 'g;. TIME the fol win t 5.1.10.1 The timo from dtIpre Generator START Pushbutt til voltage reaches,40 gy 5.1.10..' The time from dipress o Generator START Pushbet til in frequency reaches J l 4 : i n. Whilo -, neartinsichetoperator tri 4; j the Diese11 Room should] lis tan :for: thd scape from the.84 art ng! Air L Manifold Vent erif. manifold vent an unobstrudte i b. When t raue i.- nearted.'. nYt ext step cenerator~ rou larA arm may 4s annunciat due tafspurious 'e cenorator Fiel roundirela netuation Thi is orma startup al m andsr. W g. p 5.1.11 At Panel QEAR'. OEPRES DIESE GENERATOR START Pushbu ton I d.S 4 i g

d' i nav VEGP 14980-1 7 of 31 7. . INITIALS 5.1.12 CLOSE the Turbs Bypass Valve le240 ' 30 131 j i 5.1.13 RECORD the ti frequency on D ' h j. 4 1 5.1.14 RECORD the Diese { and frequency on'Da i .M f 5.1.15 If the Generator 4 i flag is visiblef ',the ERFORN lie following at Genora r a O PDG1 (PDG3) :'; 'i-I a. RESET the DC1 entrator Field Ground re afjf13'iby T placing the Ground Relay, Generator;Fiel i Jes witch to t RESET cosition' '5 - l I b. DEPRESS t:h ese N j Pushbu ton! 1 5.1.16 LOCK OPEN the ve i Discharge Isolati os W-i in Step 5.1.7 l.(. _ ir - 5.1.17 If the Diesel Gener b paralleled to that4160 ( lROCEED to Subsectio l 5.1.18 If the Diesel Genera shut down, immediate1/ ROCEED y. Subanction 5.3. > 3. g,; \\ %;} ,; h 'y.'% 4 [,, - i , f.. c ..y . tpip 2... a n.6, c 4 F. 4.',- y y,N.':'9. ,, "b$ / { ~.~[. ,f. , (, ;. l ...u ,t. ~ '6 T *e. b V<l,L' *, e [' ,,,,-..f-[, i t l

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..n, -.. t.s i V P 14980-1 g og 31 L f JINITIALS e 5.2 DIESEL CENERATOR: LOA ], f AUTI h. If th enera or being.'operat rgt og 3: Parallellmo' var trans J the LOCAL REM S i:ch i 1-HS-451 1' ntPDG .i to LOCAL h1 1 7 } governo 1 (. i regulat P' l^ mode. j,*- l ^l w i IfthI per orm F the 6 month rye lancer e l then the Diesel 3Generat.o chould not?.be 11 owed;t l idle priory rallel .,l and loading .-f., c> w i 5.2.! If this test is not per rme i* six month surveillance 1 ~ hen DL diesel for 5-10 minute nti temperatures stabilis !V ~ 5.2.2 ENSURE the Diesel' ener J l SYNC MODE SELECTOR Swit S-DG1A 1-(DCIB) is in AUT i .i.el i. 10 'h Never p see. . syne-sw to the ON.- sit:.onj,atsthe woe.. 'r = same time' lown ' fuse -r" may result V U:6 i. l 5.2.3 PLACE the breaker 1:, BA0319' Sychronir.ation Fwitch l f':f x-MomentarilyPbCE' 5.2.4 GEN UNIT / PARALLEL Switich11H 4148 .5-(HS-4452B) to PARALLE !0BSERVE V.? rhe red DSL GEN 1A(15 ROOP DE . ) light is on. t .. ~-

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• INITIALS r1 5.2.5 OBSERVE 4160V'Bu 03)

'. ^. voltage on the QEAB;RUNNINGJoltmeter via BUS 1AA02 NORMi1NCH E SW((BUpilBA0 -[. NORM INCH VM SW) land iTHlTCenerat v 1A(IB) voltage on th EABUNCOMIN t? t Voltmeter via DSL N CEN 18 MV SW).' c' I 5.2.6 VERIFY that the S rotating and thattt ron Lights are brightTd Vtiliilock ? position and darkTa ffofcid'c ,t' i position and that?t PERMISSIVE F red light comds o' c' loc g.', i l position. p. i 5.2.7 ADJUST generat'or vo necessar to slightly 1 dad'the b olta (Generator voItagell han 4., above the lowest h'

s "s

5.2.8 While observirig" p C ADJUST the generato n E i Syne Scope needlesi EM's1 '7 l in the clockwiseE(FAST) iiact c f (8 to 10 seconds rota 5.2.9 If this surveillance performed as thejrigu ly mon !,7 or as an actiongitiemr]ofp:. / test. Technical Specificatio 318fl. ?,7 l i PERFORM Step 5.2.1 and MARK Ste 'a" 5.2.12 as N/A.i.. 5.2.10 If this surveillance performed as the six4ionth1( ib : .P test per Technical Spucificat -Q 4.8.1.1.2.g. PERFORM.St 211 c MARK Step 5.2!11*as:N .i. g-5.2.11 PARALLF.L the Diese bus. 5.2.11.1 When the Syne Scope ee rea e the 11 o' clock posi io EPRESS"1 . ~ - HOLD the Diesel Generato A(18).AUT SYNC PERMISSIVE Pushbu ' -DG1 A'. ? (PB-DC1B). .-1 J.' ; m k 5.2.11.2 When the DGIA (DC1B UTPUT BRX i.i Auto Sync Permissive Pu'h(button 1AA0219 (1BA0319)tcloses1 RELEASE 1 }.;'.. s .x 1

• .e m rye w p f. <.

Aot no. VEGP 14980-1 10 of 31 s t .i ~ INITIALS 1 ..j j l1 Il. j To per x-mc'nt load m,th selgen0rator tes t et i fiised b greiI^e'us60 : s'eWo)nd 6100lk t t. ? '/ l r t Elo71 i ensrat6 Diesel Bre u, ~.? 5.2.12 Parallel the~ l bus. p 5.2.12.1 When paralleli enerator TIME che interval'lff l'o'si5g the . '2 Diesel Generator'Out enke nei F ] load exceeds,6100kW jy, 5.2.12.2 When the Sy'ne: cop reac 4 l the 11 o'c1'ock*pos i DEFRESSja 2' l' HOLD the DieselsGen'irito A(15); AUTO E. g. SYNC PERMISSIV PushbUtt DC1 l (PB-DG1B).i .b' l I. n-l. 5.2.12.3 When the DGIA. DG BRKR J' i 1AA0219 (1AB03197 's1 RELEASE i j Auto Sync Permisi hb'uttos l I'. 5.2.12.4 RAISE generato ?, i 5.2.12.5 RECORD the ti rq ra: se E. i Diesel Generator oad ove Ok 9 Data Sheet 1.

4..

S i i., v., c. Whe orm i six-mont ist th Generator t. should b fe' .'o.ad d(in 4 increm;en f proximat i l 1000.kWfd kVAR ithl \\. 3 ' A'imin ' ~ onc chan 3 b. As t' gen age adjusted,? [th's VARishoul be maintil.iisd cisiti s'fand Y ". no moraiths if theE / load ,{;. 5.2.13 Pl. ACE che brea 319 Synchroni:ation ite j r s'.1 ,3.- e a l -Q, g .g .g ,e* i j s. .~. . ~. ~..

.. - ~ - -. 4 J M Mi Otvis#C ~~ pagg gg, I VECP 16980 1-(Q 11 og 31 j - ~ 1 4 'I -:i. .. hg 1~ _ INITIALS 2 ADJUST genera or dLGit)(IR$M' Mp a. e.. 5.2.14 e.. i $.2.15 ADJUST genera ~ {!*? r ~ generator kVARS Itw eo f .! -.h 3 OUT. ," r - c c,[} l 5.2.16 RF. CORD the t m i, ~ a t ' E'.2 WP i Cenerator load ic de'd 800kW Qy-l'f['f l Data Sheet 1.

q..

3'M - ~ v: 4 - 5.2.17 When the Die'se n or asa.'een dT Loaded for.30pii niit' It{ITIATE D 11885-C, " Diesel GeWrator 0 erat ng 7, o.j[$ M* Log." s(' b. ) l p,- gl.$ - ~.' d i r. wi; an. L M[thi i 1. Subsee S-i0 Transfa eiti a 'S. 5 RAi ' r iTo~rhnea ti. :s d.O- 'l i maylbf 1 td 'during't'1 DieseltCen atbir loaded run. '$ ?- i if.desidad. .- e 1 1 t. 1 5.2.18 While the dies '. a e. EXAMINE.- che following. and NOT any;'. problems :/.'.JC t i

T s

- ', =& 5.2.18.1 Cenerator Si pr n t.[ f, Brush s'. J - ~f $. i 4 c.. S'.,;'..M ',y ? , y:.. 5.2.18.2 Cenerator hear:n . r~:ng, i s. o G. v..M } }. ,.. +. 1- \\ 4 5.2.18.3 Jacket Wator' ya em, . J '. ' i I.f.I=. . a.o > 0? 5.2.18.4 Lube oil S,0 stem, ~. . WY; .- k.- 5.2.18.5 Fuel Oil Sys i ..0 S. t - 4N 5.2.18.6 Diesel engf.no ($1d2) dih@

• d;4 74 l

ii P P ng, .,1 b i y.. a* 5.2.t8.7 Combustion Air 's - u one valve < s,, -

2. w, 0 j

[ f F .g I I.,1 . 44 ,.,... r s.. [ 4.a- '. ' O ~,) ..,9 r.s 9 .,:I ;:.l; vt} j

l,

. n p , l 5) r .~ J l -l4_' t.' .,,,.; g:. -- _3,,'. '. 1

~- - - ~ ~ ~ ~ ~ ~ ~~ } 6 *utuut<L %Q VEGP 14980-1 7 g5f-12 of 31 t j t-INITIALS h 4 i I. s. os i.' L ' adjusted erstor a 'shouldLb tiis ted ' ?concurren ^ tol, ai m 'kVAR BW si is 4 i and~n 'm al j .o h f i b. I un1 dd creme i approxi i 5002kVAR .nutes b betwee ,. r- .o 5.2.19 m n che Didse een e Loaded to great h'an 80 .I- ~ ac least 1 hour y I 'n'e 5.2.19.1 RECORD the t uce { Icas chan 6800k ta' Shoe 1 p. -: ;jd,.; .ibi ,,' a 4S' ^ <sy' i 5.2.19.2 REDUCE Diesel, one o

l. ' 'g< 5 100-200 kW and'5041

VARI

'g

] 5.2.19.3 TRIP the DG:, 1GL Q . c k$ ~

• e l

1AA0219 (1BA0319). + .4~ ?' i 5.2.19.4 IDLE cho Die o +Q$jgg) L for 4-5 minutes < } SHUTDOWNtNe34 t'f qT4 5.2.20 a I '. ' i Subsection 5. r. ..hrN-x i". j

l.' $. _

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P 14980-1 y' ,7,. 7'- INITIALS l 5.3 DIESKI.GENERATORJS l UTIO 1.0 i. If an.SI gna race i 4 i during ens n coastdown monitorglub it',presabre 1 F and trip h. La'se Canarato fj ressur below t it l. l 30 psi 5.3.1 At Panel QEAB, DEPRES DIESE ~- GENERATOR 1A(IB):ST tton 1-HS-4571B (45725) ?.. - 5.3.2 RECORD the time t entrator was shut down on Data Sheet g 5.3.3 At 480V AC MCC 1NBI, INBO),, VERI W 9-the Generator Space'Heate isi % I; energized. Pump starts. .Y 5.3.4 VERIFY the Jicket to arm 1. 5.3.5 VERIFY the LAbe"0 rm um .L starts. i e? s 5.3.6 Atter ap)roximate VERIFY the red sto pin 11 ht.a Panel PDG2 (PDC 4) f 2 c. y 5 { r e. l. .e

• 'y
• e

"\\ 4 h.$i' Y hh

wh-,.. - '"r-navisio n... pag g,,o, VEGP 14980-1 2 .) t,{J, [,fi g., 14 of 31 i-) l l 9 -~ $.Wp i h INITIALS w n inutes!3.w'/d. ..-the 5.3.7 if after approximate red STOPPING light is.N07 off;Oh3:n6~% RESET @ ' as follows: 'thn est.g?., 01 m. Handswitc oun *on,the s.t' front of the ' ngineJauxiliary skid. ~'" e a. PLACE'the push ut HS-88 fJ (4689)..DG1A.(DG153RUN/STOPiti ~ approximately,10. position.for:gMg l the PUSH-TO-STOP: Sf.h

se d

. $. con s, u,.e e.r,wm b. Pl. ACE che pushbutton 1,-HS-4688 5.! (4689), DGIA (DG15))RUN/STO?, in' the PULL-TO-2UN position,- s 4Wypeg. 9,*/ ... i.- VERIFY the red' STOPPING'lig st is. c. off, and the blue UNIT AVAILABLE J. light is ON, 5.3.8 RECORD the engine our n' Da ta. [,'J!j.,- Sheet 1. -w M$6@,;...pi' 4 AI.IGN the D16sel Genera or. Build.ing L:;i:'. 5.3.9 per 13325-1, "AuxiliaryiFeedwater c'k.:. HVAC System for automatic [cperat%on i 47 Pumphouse And Diesel! Generator 2 %.$:.;1M f.,,Q~. flui1 ding HVAC Syatems" -"ypy n..

n.,

.t .. 5. W.-C - <f

p. ;

c. Q t'd uN M4 g. w y;.1 a m <..- r

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• y.4.44'&,..eZ,.~', -

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I I -t 't : "t *. R(WISloN .s-p PAgg Ng, VECP 14080-1 2,. y .D,16 15 of 31

y. ;.

l Mbl.Yk l INITIALS I NOTE {; d?/in %;.g.- ,i .t.... Accumulated water must be drained from the Fuel 0 1 Day Tank per Technical.. Specification 4 8.1.1.2.b.- t .4 * ' f. ~~- 5.3.10 If this test was performcd..as. a r regular monthly surveillance test p.t W. c. or, if the Diesel Generator WAs M M.N-h operated for a period of fone hour T.M.'. I or greater, SAMPLE the Diesel .t.- noneratorDieselFuelOil'.(DFO)j '- Day Tank for water: 4 jgg.,;.,. 5.3.10.1 OBTAIN a clear container'ont liter si:e or larr.er. a i yr 5.3.10.2 DP.A Ih asmallamountof.fueloilk into the container from the Da Tank Drain 1-2403-U4-035(036).y 5.3.10.3 EXAM'NE the sainple for water on the hot tom of the container. - I' 5.1.10.4 If water detected REPEAT the ! sample uttil no water is found.. l.. 1 5.3.10.5 C!.0S E, I.0CKandCAPtheDayTankj Drain Valve 1-2403-U4-035(036). '. [ DIEGE! GENERATOR FUEL OIL TRANSFER l SYSTEM TEST i l NOTE I This section of the procedurn i will verify the operability of the Diesel Generator ' Fuel l Oil Transfer Pumps. 5.4.1 START the DF0 STOR TANK Pt.HP-1 (-3), 1-HS-9044(9045). 5.4.? VERIFY the pu starts and transfers fuel oil to the DF0 Day Tank. e 5.4.3 STOP the DF0 STOR TANK PLHP-1 (-3), 1-HS-9044(9045). i 5.4.4 START the DF0 ST0k TANX PUMP-2 (-4), 1-HS-9046(9047). r I c l t .......i.. , p,f&v O. *'

• lv.,. !

n

7 i -t oc.os v4ogs2 VEGP 14980-1 '} ,}hf 16 of 31 ~* g f' * '.y '.,

• s; i

',' i, - INITIALS 5.4.5 VERIFY the pump starts.and~ transfers fuel oil to the DF0 Day., Tank..,; 5.4.6 STOP the DF0 STOR TANK PUMP-2 (-4), 1-HS-9046(9047). .f - M.n. 1 -9 f9:7,"1 5.5 DIESEL GENERATOR AIR START COMPRESSOR TEST gg ..r. CAUTIONS'i f < Only one Air Com.R!I.NIpressed "v.~. VIAip a. s.ould be tested at a time. .v: b. At least one' air start receiver must be pressurized to greater 1 than 210 psig at all times. q l'OTE g; r.a These instructions are written for the Train A Air Compressors. The Train B components are indicated by parentheses.,.,- 5.5.1 NOTIFY the Coptrol Room that QEAB annunciator ALB35F02 DGIA LOW PRESS STARTING AIR TALB38F02 DG1B LOW PRESS STAP. TING AIR) will energize in the following step. l I 3. 5.. CRACK-OPEN the Air Sr.nrt Receiver 1 Drain. 1-2403-X4-762(723), and slowly REDUCE air receiver pressure to 145-155 psig.' j CAUTIOll. If the Air Compressor feils to start automatically do not redyce air receiver pressure below 210 psig. ~ 5.5.3 VERIFY the Air Starc Compressor, 1-2403-G4-001 COL (002-C01) starts

• uma*.ically when the air receiver is between 215 and 235 psig.

ssure

-gamme

o. 4 }%s s I

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. l

- r I . +.ustuse&s.saem ;.. 4,.. cuvision. ca no. ..e .y. '. INITIALS .:*. t.*Ui [- 5.5.4 If the Air Compressor fa'ils to start '. au tema eiur.lly: qQiuc t.GF. in i. i, W' - V ..:1jlg'.h,. 3 L - ~- CLOSE the Air Receiver ~ ;.; .!., a. Drain 1-2403-X4-762(723),;.'..J.+ ' +15g,..,1.! ,, '6 ' t b. INITIATE maintenance on the compressor to correct.they p:I ' I problem- ~ ' y b,g., ia? -:. * :.. 5.5.5 NOTIFY che control. Roots hat QEAS ar nunciator ALB35F06 DGlA SWITCH. NOT It' AUTO ( ALB38F06 DGl3 SWITCH NOT IN AUTC) will energize in the foligwing step. 2,.,. j 5.5.6 PLACE the Control Switch for tho' Ai-Comprennor 1, e 03-C4-001-C01(002-C01) in OFF. p +' 5.5.' When the Air Start Receiver Pressure has been reduced to 145-155 psig, Cl.OSE 1-2403-X4-762(723). ".S.A "TAdT the All Compressor by placing the Control Switch in AUTO. .. n. s 5.5.9 RECORD the Air Compressor start time on Data Sheet 1. t '.5.10 VERIFY the Air Compressor stopst automatiently when air receiver', pressure is between 245 and 255 psig. 5.5.lI RECORD the time the Air Compressor s tops on Data Sheet 1.- 5.5.12 NOTIFY the Control Room that QEAB annunciator ALB35F02 DGlA LOW PRESS STARTING AIR (ALB38F02 DGlB LOW, PRESS STARTING AIR) will energife tu the following step. j s.s.1) CRACK-OPEN the Air Start Receiver ? Driin 1-2403-X4-772(728) and sinvly REDUCE air receiver pressure to 45-155 psig. i t

1. b.2....4;

P,..><......e... a Evisio N paos so, ~ VEGP 14980-1 1, 18 C. M: 18 of 31 3 k

Y[Q..

• .

L- . h.sSr.f - ?;.c INITIALS ik.. 4;-{ :. tbC I CAUTIONJU W l4.&~

p p n *. Q ':. J.

• IftheAirCompressor{ ails to start automatically;do. -

not reduce air.3.receiverpressure below 210 psia.~ T .g. - 5.5.14. VERIFY tlie Air Start Co ressor.. 1-2403-c4-001-C02(002-CO ) acarts automatically when thetair receiver '., pressure is between 21 and@35.psig.;:{* .cew..s.. - /, ';.5.Ii I( the Air Com la~to start'e automatically: pressor f W. ..,%.p.} 9a a. CLOSE the Air Rece ver + > - Drain 1-2403-X4-772(728),

• L%.

b. INITIATE maintenance on the' compressor to correct the problem. g, ( 5.5.I6 NOTIFY the Control Room,that QEAB .innunetntor ALB35F06 DG1A SWITC}l NOT IN AUTO (ALD38F06 DG1B SWITCH NOT ) IN At!TO) willi energize'in the foiicuing st4p. { :. e.,j b. 5.5.1/ Pl. ACE the control Switch for the. Air Compressor 2 4WF >+' l-2403-c4-001-C02(002-C02) in 0FF. . c.. 5.5.18 When the Air ' Start Receiver Pressure has be.en reduced to 145-155 psig, Cl.0St 1-2403-X4-772(728). 'a. $.19 START the AiriCompressor 2 by placingtheC;ontrolSwitchinAUTO.

6. r

'. 5..' 0 RECORD the Air Compressor start, timeonDatafheet1.,,. 5. 5..' l VEk1FY the A1.r Compressor stops * - automatien11y;whenairreceiver! pressure is Uetween 245 and 255 psig. i 5 'i..' 2 RECORD the time the Air Compressor s t op s or. Da ta shee t 1..;.:.., dl, I.'e,-) ',tr 2

e hNY, e n. ("a *. r. .4.e. d: t71SioN p4gg g - .. g VL:Gp 14980-1 }, 3 . l.G., 39 of 3; g g '. " INITJA1.S s. i 5.6 SY:. TEM RESTORATION cB

w S'

i

- Q.6 5.6.1 PERFORM Checklist 1, Diese Generator. % ?

'E. Standby Mode Status check fosi. the. Dtesc1 Cenerator which.wa ested. h. 5.6.? RFCORD DF0 Storage TanM ave l 'V 1-1.I-9024(9025) on Da hee .5

5. f. T RECORD DF0 Day Tank,leve y

~ 1-l.I 9018(9019) on Data ~ es 8 .-e j s.h.c RECORD Air Start Receive

pres sure 'l Ti-

. I*i-9060(4061) on Data e s t : 1'e~p~ ;..

• T 5 fi. 'i RECORD Air Start Receiver; pressure i

t l't-9064(4065) on Data Sheet 1. .c s.7

DMPhNDENTVERIFICATIb

f......

.s ;..

. ~_ v. s't Indepentlently VERIFY LOCKED OPEN the Air St. art Receiver Discharge Isolation 4 whir 5 was n'ened in Step.5.1.16 l .c ' sy- ~.s.. S. 7..' Independe. .'ERITY CI0 SED 39'Idd.~i.?: I :' 4 01 - U4 - 1 i 11) which was. clocad ".M ',gp!. '. [" in Step 5.1.12. s/ i I

.idependently VERIFY LOCXED CLOSED.

ihe DF0 Day Tank Drain Valve :*9; t 1 .'4 0.'1 - tf 4 - 0 3 5 ( 03 6 ) which wasIclosed t r. Step 5.3.10.5. i e. e:.s.,. 8 s. 4 Independently VERITY CLOSED the Ai'r i St a rt Receiver 1 Drain I -:'4 03 -x 4 - 762 ( 723 ) which was closed in Step 5.5.7. ~;W s. ; ', !ndepenvlent;y VERITY CLOSED the Aitr start Reectver 2 Drain o l 401.x4-772(728) which was closed / t o St er S. S.18. y. r

7. #

Ii.' pendentiv VERITY OPEN the i Keep-Wa'rmi Pump 1-PI.19145 (19152) I. 0. no.it 1-2403-X4 798(797) which was. .perated in Step 5.1.4.',.'. t.. i f I )

- g.

.i ..k 'Me.

c

. a

I ~ ~ esam. m 4. i nEv$QN - pagg go, ,P 20 of 31 'rts:P 14980-1 3 V.- c;glM "%... 3pst: U i T INITI.\\t.S j c. 4.n.., g 5./., inilependently VERIFY CLOSED thei t..o. Keep-Warm Pump 1-PI-19145(E9152) doot 1-2403-X4-796(795) which was opernted in Step 5.1.4 9j;'.dh$L n? 5.7.x Inilependently VERITY OPEN'the t \\ .'.W. Keep-Warm Pump 1-PI-19124(19134) Root 1-2403-X4-812(811).which was operated in Otep 5 f. '>. /. 's Int epently VERITY CLOSED.the DM'N .I. k. Keep-Warm Pump 1 PI-19124(19134) Ro.r 1-2403-X4-810(809) operated in Step 5.1.4,which was

g.. ;',. l

, 4... 6.o Af:f:EPTM'CE CRITERIA * .T '1 .p. i

v.. I The Dienel Generator staren andt voltage and frequency are between 4025 to 4330 volts and 58.8 to 61.2 h..rtz within 11.4 seconds.

~ 4. 6.. The Diesel Generator operatos vs.th a lo.nl of 680d to 7000 kW for at least 60 n.Inutes. Modes le.2, 3 or 4 only. -s.,.. 6.t If this cent was performed as the rer.ularly scheduled 6 month r.u rve t 11ance, the Diesel Generator tonded to greater than 6100 kW was wiibfn (>0 seconds. 6. '. At t e n n t. one DF0 Day Tank Transfer i Pump stnrted and transferred fuel to the DF0 Day Tank. 4 6. ', The DF0 Day Tank contains greater ihan 650 gallons of fuel 52I on 1-1.1-9018 (9019). t. 6 The DF0 Storage Tank contains g cater than 68.000 Iga 11ons of fuel. 761 on 1 -I.I. 9024 (9025). I 6.' The pronours in at least one air .a a r t rec.eiver is at least 210 psig. (..a ti the Diesel was operated for "60 minutes or more, the DF0 Day Tank was snmpted for water, and all water i removed. i L

,,da..;-,2M L..

i

i I ntesson w, fm 1 paci, so VEGP 14080-1 ..;[ 18.% ?,. 21 of 3 3

e..

1 I 7.O EVALUAT10?! AND REVIEW r l .a 7.1 TFST l'kOCEDURE 'E i 1.. I 1 Surveillance: [,1 Monthly [ ] Semi-annual [ ] liot h Other,(explain);r g ; I I 2 ., yn.

ese, 7.?

Results obtained through performance of this procedure me'er. Acceptance Criteria of Section 6.0 3 [ ] QNn&!- i. I 1 Yes No.c # " ' >; gg.. ..; j i.1 ?;0TIFY the.USS of the: test resbitu. REFER to Technic,il 8; ice i ficae fon 3.8.1.1 or 3.8.11,2. n. s .J If no was checked and the failure was due to a Diesel ci'nera tor fault, EVALUATE the reason for the fatture per Table 1. .~ \\

W l.

.1 NOTIFY rhe Diesel Generator System Engineer of the 7 1)Lesel Generator start. Provide the following 4 i n fo rma t i on s .z' A copy of Completion Sheet 1, 1 a. . g...,, b. A copy of the completed 11885-C, "Dicael Generater Operating tog". g.. j If any parameter recorded on 11885-C was out of ranr.e. / i I TNITTATC maintenance to invest.igate and repnir as necessary. l etther Air Compressor fails l' 7.4 1( tot

tart automatically at the correct pressure, or

.i. b. Fails to raise air receiver pressure from 150 to 250 piiig in % hour or les:s INITIATE mnintenance to repair the Air Compressor. t f i I e 1 i >e.- e* ee ammum 't; ?;. 2. ,y.j@Q

V.,.

e

i i-4eHWegs%t.v.a.M.... t aa vision

4...,

MQg No, ..N : 22 of 31 l VEGP !4980-1 .s i h. l.5 Comments (include any abnorntal conditions and I corrective actions taken): 3, s l. . a.Q .,..\\ 3-%.:& : :;.. - . w.. USS not i f t 2d of Tes t Completion and Results.' -'-

,j

.}??$%!l$ $ p j 3

,l,.Ini cials Dace Time 7,

t i.., (.'..np i. t.. I R y, / / j signature Date T I ne

ope. rv i so r v Review.

I 4 M,3 / / Signature Date ~ T i ene.

8.0 REFERENCES

I.

• h t

8.1 FSAR , j.}.. l .20:.. F. 1.1 Technical SpeEification;3/4.8.1.1} S.I.2 Technical Specification 3/4.8.1.2 g. H.1.3 FSAR 8.3.1.3 'PZ; W. 8.!.4 FSAR 9.5.4.4 ~ 8.l.5 FSAh 9.5.5.3 8.1.6 FSAR 9.5.5.4 1 8.1.7 FSAR 9.5.6.4 I 8.1.8 FSAR 9.5.8.4 ~ 8.1.9 FSAR 1.9.108 Reg Guide 1.108 i 6. '.' PROCEDURES 8..>. 1 13145-1, " Diesel Generators" 8.2 ? 00404-c, l"SurveillanceTestTrackingProgram" 8.?.J l1885-C, " Diesel Generator' Operating Log" 8.2.4 13375-1, " Auxiliary Feedwater Pumphouse And Diesel Generator Building liVAC Systems" i 8.2.5 54169-1, " Diesel Generator Miscellaneous Trending And Evaluation" 2.... s.uTV,.G i_ '; ' i.... i

..,;, s -,, ,, nog m....-- VEGP 14980-1 (. 4.j { g.'. 23 of 31 l j ' $( j i]f['.T',' l 8.3 P&ID's "i ?hf'.Y'I'N I"<3 t - eg7.J.. : -. ' l 8.3.1 IX4DM170-1 Diesel denaratoi': Train A %:.-. :e y. 8.3.2 IX4DB170-2 Diesel Cenerator - Train 5 8.4 ELECTRICAL DIAGRAMS 'M..N<M. I i Diesel Ce$fer.'>Qh.1 T:- 3 8.4.] IX3D-AA-K01A nerator Relay And Metering Swgr1AA02?/'"y:l Diagrams..$. hh:? s ;. .A 8. r. 2 IX3D-AA-D02A ~., $:H.- ". ' n ~ 8.4.3 IX3D-AA-002B Swgr 1AA02 37,.K*M.. i 8. 4. t. Ik3D-AA-003A . m;..., Swgr 1BA03..'U':Ok ' Swgr 1BA03 '.: O3 'g:. Y!'y.,J.? wW. 8.4.5 LX30-AA-D03B y l 8. '; El,EMENTARY DIAGRAMS 5..,".,. .. -t s :.; ;., i 8.5.1 IX3D-HA-D02G Breaker:1AA02-19 4 8.5.2 IX3D-BA-D03D Breaker 1BA03-19

w.

I 8.6 1.0CIC JIAGRAMS

• N ' '.'

i 8.6.1 lx5DN107-1 Diesel Fuel 011 System " y., 8.6.2 IX5DN107-2 Diesel Cenerator Engine 8.6.3 IX5DN10/-3 Diesel Generator Excitation

as.m...

8.6.4 IX5DN107-4 Diesel Generator Engine Auxiliaries 8.6.5 IX5DN107-5 Diesel Generator Engine Auxiliaries 8.7 TECilNICAL MANUALS H7 1 AX4AK01-509 Diesel Engine Techn!. cal Manual i 8. /..' AX4AK01-563 DieselCeneratorAsnociatedPublications Manual Vol 1 8.7.J AX4AK01-564 Diesel Generator Associated Publicationn Manual Vol 2 ' Ci END OF PROCEDURE TEXT ... t 1D i = l l i .Sih%.LY. *..- J

^*~~~~ e susuon c., vaanno EGi-1 :. w o - 1 / 18 g.,.,f,# ' 24 of 31 i TABLE"1 ' M : 4 D:ESEl. GEMEI'ATOR VALID TEST AND FAILURE EVALUATION CRITERIA '.U'; .,p....c l '*atid tests and failures (per Regulatory Guide 1.108. Section c.7.e and Technical Specification 4.8.1.1.3) shall be based on the follovinr, criteria: Jp-l ,s i 1. Ai; start attempts (automatic,' including those from bona ~ide signals, or manual) that result in a failure to start. except as noted in (2) below hould tie considered valid tests and failures, w ? fr ... ??.4 n. I!nsucces s ful start and load attempts that can definitely be .ittributed to operating error; to spurious operation of a trip that is bypassed in the emergency operating mode, to mal funct ton of equipment that is not operative in the energency operating mode (e.g., synchronizing circuitry) or is not part of the defined Diesel Generator unit design .hould not be considered valid tests or failures. 1. %.cesstul.i t a r t s. including those initiated by bona fide s i r. n a l.. fellowed by successful loading (sequential or manual) to ar least 50% of continuous rating and continued creratton for ut least one hour should be considered valid -ucevu,ful teser. (Failures occurring after one hour are a..t censidered valid failures.) f 4 Successful starts that are terminated intentionally without 'nading, an defined in (3) above,.should not be considered valid teset. or failures. g.- ) 't. Sucee:.aful starts followed by an unsuccessful loading atrenpt should be considered valid tests and failures.

m. pr as noted in (2) above.

6. T4.u s that are terminated intentionally before completion au defined in (3) above because of an alarmed abnormal condt t ion that wot.1d ultimately have resulted in Diesel Generator damage or failure should be considered valid tests atul f a l[urett. Tests performed in the process of troubleshooting should not N. considered valid tests. Tests that are performed to /ertfv correction of the problem should be considered valid tests'and successes of failures, as appropriate. o. Cranking and venting procedures that lead to the discovery or ceinti t ion. (e.g., excessive water or oil in a cylinder) that would have resulted in the failure of the Diesel Generarnr unit during test or during response to a bona fide - i r.o.. I should be considered a valid test and failure. ..:;4;..

l M =oN.g!. D.M.M, : g;. ' f..

• • G E ' o l

l YEGP I4980-1 ,;;18 - 25 of 31 Sheet 1 of 2 y'-- l DATA SHEET 1 .p.. DIE 5EL GENRATOR. SITRVEILLANCE DATA i - C.'[7'E,i)G%.'.

9.. :

p. '$

a ? ' nc un.t.r test: Date -e-

4. Hode s -

l

v... s fY Elh y'*

o Generator StartupascM06:$.~ ' 5.I Diesei Engine llours at Startups.$$$h'4.g. ht l' - 'Mt ,2. 1. ), ... M9,4..., 5.1 7.1 Air Start Receiver Valve Closed:..I .m av .M. 4-5 d.L.!I Time to voltage: i ime to frequency: 5.1.14 Volrage: A-B 'k-B-C C-A

'requency:

Hz l

• r.

t;.

5..' Diesel Generator Loading'. Diesel Generator Leading::i 5. ?. t ~'. 5 Time seconds (6 month surveillance only) i. d.2.16 Time load exceeded 6800kW: .G 5.2.19.1 Time Inait reduced to less than 6800kW: 5.1 DieselCeneratorShutdoN s \\ 5.3.2 Diesel Shutdown Time: l 1 5.1. 8 Diesel Engine Hours at Shutdown l 5.5.9 Alr Compressor 1 start time 5.5.II Air Compressor 1 stop time 5.5. 10 Air Compressor 2 start time i 5. 5..' ? Air Compressor 2 stop time .p. .w. 4 ..$Rc..* a wk s u. s -, 1 e9 p

u - & % ^ h*c.,. n. VE P 14 80-1 26 of 31 l dM..A.W.... DATA SHEET.-1Wh.... ;.ji4.W Sheet 2 of 2 [ c > '- ivysupindi.'MIM%i*- I DIESE!. GENERATOR SURVEILLANCE DATA '.2-hY!!$$k{$?'* - iQ '..w[.n.: n - v I N,d E'.-[,'. 5,6 System Restoration s - p..#,.... I 5.6.2 DF0 Storage Tank Levels,. .2 +~ v' l-1,I-9024(9025) ,s r s. 5.6.3 DF0 Day Tank Level 'l sogn'<nQ;; @u, % ' i. a..?.' l-!.1-9018(9019) ; a c M. a p w.. W.: ... c. 5.6.4 Air Start Receiver 1 Pressure:r_ w psig 1-PI-9060(9061) *%p... . y. e 5.6.5 Ai r Start Receiver 2 Pressures.g..g. p psig 1-PI-9064(9065) e -g..... t .j - j b g Q:.- g.

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.s..,.- 4 .t 3 2,y ' .} - p.-- f..-.7'. r '. p: a. +.. s.t P... J. .. li.p.y. a... ). j,. W \\ e-i pp. p - M,M.-. i + (.M:

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a6 2 'EGP 14980-1 28 of 31 n. n :... 'r :,. 1 of 4 CHECKLIST 1..:....s{:;';v".'L:... Sheet . >. ~

-v a

e -. w M r.;.:r. W e '.. ,~ DIESEL GENERATOR STANDBY' MODE STATUS CHECK INITIALS ENGINE CONTROL PANEL - PDC 2(PDC 4) ? / ', ' STATUS 1. All annunciator windows ~, ' -. ((fh': alarms.pected ~ o unex "i ..g 2. Control Air Pressure j;*M'58-62psig W. 1-PI-19174 (19175) y ad. .i a \\ 3. l'MIT AVAILABLE Lighe N$,.%.. ..s ,4 t %m. s.- 4 Thermocouple Selector: i i-6.s i Lubricating 011 In '( gag.142-170*F a. l A u' s 142-170*F l b. Lubricating 011 Out i c. .facket Water In 142-170*F j d. .facket Water Out 142-170*F 5. POWER AVAILABLE Lir. hts: c. A ' ".s 1 ON i i b. R i I.i." ' ) ON ,4 5:. ',e, c. C ~ -

c-O,N '

..;,OFF a 6. STOPPING light 0 0 .. '~ .g 2

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3 1

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MEWiboN ',f..l-j' 29 of 31 ~" iPAGE No' VEGP I4980-1 ' .M.. iNYT.h. Sheet 2 of 4 { i } CHECKLIST l,',G, _,. + '.... :. ;.. ~.. .. W$Nf C-INITIALS IV OENERATOR CONTROL PANEL - PDG1(PDG3) D [i'..". STATUS ..-ygin 1 ;;,.. 1. Unic/ Parallel Switch 1-HS-4413A(4452A): Center 'r4 After Unit . 'i w%%. ,2. I.ccal/RemoteSwitch1-HS-4516(517)@fREMOTE .:,, :. y : 3. I.ockout Relays: t,;.S.fg..k;4. ?# ..p. tr. a. 186A Ag'gRESET umf i,' u. i b. 186R

.G.4 pf~~. RESET

. i y.... 1'~~ RESET e. !86C .t . 44 ,a 4 o l t a ge Regulator l.N -. AUTO Automatic Voltage Regula &;^ a tor Light ;0N 1e,.,. 3 b. Manual Witage Regulator, Light, !OFF . '. -. t 'j.4 e.. L.a,.,,M.. 5:',7* i '*oTOR CONTROL CENTER INBI(1NBO) 4 1. Air After Cooler Fan No. 1 ^; 3 ' AUTO 4

ni

a.-l AUTO

-t T7 2. Air Compressor fio. 1 .,l AUTO 3. Air After Cooler Fan No. 2.' 4 4 Air Compressor No. 2 -[ AUTO .9 5. Jacket Water Circulating Pump AUTO 6. Jacket Water Heater . AUTO i 7 Lube Oil Circulatir.g Pump , AUTO 8. Lube Oil Heater

. AUTO

r..

.n. ' AUTO 9. Generator Space Heater ) 1 Y. P. v d.i ] -s'.- 1 * . s{, l ,.4 j

ik...

2&l'.,l b

.o.. savissa 4'. ' g. _ noa no - g [f,';t.h. VECP 14980-1 f,.. 30 of 31 s

• Ek$$lh CHECKLIST 19[".

Sheet 3 of 4 i: 2.E ',., ;

g. f.,

INITIALS IV i DIESEL GENERATOR SKID n.:... STATUS (;MhM.- r. .7 1. Governor Settings i .4:.d.e w5 ib/4 W- -a 4 Speed Droop

1. )A v.. - 2. 6 na

f B: 4'2.6 J.. ;, ;,.,.. lead Limie MAX FUEL t, g. A: ;...14.34 Speed 'B:1 12.2 -s t-otl Level t 4b W Above- ?J centerline .i'. of q (.; " sishe glass 2. Overrpeed Trip Air Press W. n; "l ' '.58-62 psig (located under rf;;ht bank turbocharger)' ,,y,g. ;,,..,. s '.,., i' 3. Lube 011 Level - Dipstick . MAX STATIC *1" 4 Jacket Water Keep-Wa P re s s u.....,.... <15-35 psig re o 2..,u,.dy.j 1-PI-19124 (19134) + S. Lube Oil Keep ' arm Pressure '+ 6; 25-5bpsig .. N [:I$4~,.. .,103 ~ I"ITNTROL ROOli $h.v.; ',.3 5,..-

p )

et-1. DSL CEN 1A(1B) UNIT /PARALLEC'S tchi'['*:j NORMAL 1-HS-4414H(44528) p-T~.*,c":.,.AFTER IINIT .I.n.,., u. ?. SYNC MODE SELECTOR Switch 1-TS-DG1A'.;Wg,, it (DCin) p. 0, 1. Dt;!A(11 Gill) O!!TPUT BRKR l-llSalAA0219 ~..'NJ ~~ ~ t liiAn 1191 AUTO

e..

4 if. s 4160V AC F.WCR lAA02(IBA03) - CONTROL BLDC LVL A t. I)IESEI. CENERATOR BRKR CONT SELICT.

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CONT RM SWITCil 1-HS-1 AA0219B(1BA0319B);gfG' * ' . J. g

rA c.s x -

. W.':X, '. "4 WG.M..c. -',M.4.)' 4:. ,..e: f:Y : A lm-i.y).4.'b.:. i ..f*s w y - ......\\ JE.. W '

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{ ._ A < f g. y. s' _~g" * - i...- a , s.v ' ', ' ~ =.. ';?.k.

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..g / l i REVIEWED BY . D ATli, (OSOS, SS, or STA) ..g;;*/. r. ~~ - .h.f';'., :,. \\ 4:a-

= - we-u1 %.3 " sus-r I,,0.e in egg ISM 4' PAGS NJ. 's,.... ~ 8 j, g 2 ,p,C 27 of 31 "EdP 14980-1 t COMPI.ETION ' SHEET *{.%jd.'."j.$ Jgh! 2'.y 1id e.' ? g &.m.?: ?- %. - TO: DIESEt, CENERATOR SYSTEM:ENGINEERT.WT' !- .1-XsiiL%: %'. )*; FROM: UNIT SHIFT SUPERVISOR '(UNIT ~1).shv;. - i .,g:.,s !r., bDC14[5.. fif[~ ] DClB Diesel Generator Testedi f[ 5 .?g se 1. Start Date: / / . 1 Shutdown Dater / / t:u. 4,:,O. Start Time: Shutdown ~ Time: 'g enH.:e Start Engine Hours: -2,'Sh. own'.. Engine Hours: .w. j m. t **j * ; t o. '

• i 3

Start preceded by turbocharger. pre ubrications i[ ] Yes [ JNo

• d
• :+n;$.':

Reason for scart: ,"*;(';

7,,,

.. 'r. :

( ) Surveillance Test ( ) Other: Wi.*, '- t;: a wc. Reason for trip or failure to start .d-t- 9, :.g..iii [ } Mcnual l ) Equipment failure ( ], Trip sflgnall ] Alarm Response. ..,.g .a- - M. a r ] Other: e< . g,*s.t:.... t 3 . A 4., w DRf (if known) .;.T WRT l.(If Known) ',.. g. 3 3.. s.. !. i s t any conificions that would have' resulted in Diesel Generator failure'to st.arr: 1.5. Comments: Completed By: t Date. Time u.. Reviewed By: Date Time Diesel Generator Start Evaluation.e e,-.:J m.. .t. j '. * ( ) Successful Start [ ] Valid Test ..;;b.E m..'~. ;. [ ] Valid Fail'Jre [ ] Non-Valid Test .w.. g ( ) Non-Valid Failure e}Unitshiftsupervisor -l v. Cnpe sent to ~ l- / Diesel General System Engineer snuc uern uste ...(gjrp :1,.... .. c... -u-

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• w am... gr mm l'

N / Vogtfe Bectris Gener 6ng Plant 10000.C 3 C2 ht#JA N ON** n. i oss 15 g,g,h unn N Georglah wD of 27 yold CONDifCT OP OPERATIONS 1.0 PURPOSE This procedure establishes the responsibilities of Operations Department personnel and provides administrative instructions for conduct of plant operations. 2.0 ORGAN!!ATION AND REMPONS18tLITIES e Figure 1 gives a baste organisation chart for the operations Department. Npeciffe responsibilities, dutien and reporting relationships are as in11ows. 2.1 MANAGER OPERATIONS ) The ManaAer Oparations is rea sonsible for the overall j management of the Operations hpartment to ensure safe and effietent operatton of Plant Vogtle. Specifte dutten and reporting relationships are descri'oed in i Plant Administrative Procedure 00001-C " plant organisation ManagerialStaffResponslbilitiesAnd Authnrity". l l l ^-

< a: .m uppyg Pa0C40ua8 880. naveseoes PAG 4 8eo. .)l [ VECF 10000.C 15 2 of 27

• y --g j

1 2.2 ON.8HIFT OPEP.ATIONS SUPERVIson The On 8hift Operations Suservisor (0808) r e rts to the Manager operations. Tie 0808 is the senior management representative on each shif t and is - responsible for the safe and efficient operation of the plant lie has the following duties and responsibilities. 4 a. Functions as senior management representative for plant operations on shift. b. Han authority and responsibility to declare emergeretes in accordance with the 7ECF Emergency ple". Also, the 0508 functions as site F.pergency Dirvetor untti relieved by a higher ranking j

manager, i

c. Ensures that plant operations are ennducted in accordance with the Technical Specifications and approved procedures. i d. Reviews operations narrative logs and round sheets in accordance with 10001 C, "Logheeping", e. Ensures shif t relief is conducted in accordance l with 10004.C. " Shift Relief". f. Ensures standing orders and ntaht orders are entried out. { g. Ensures that the shift is properiv manned,ipated the i Fire Team constituted and team captain des l in accordance with 10003.C. " Manning The thift". l h. Ensures cppropriate notifications of reportable eccurrences are performed, i. Maintains a broad perspective of opetational conditions affecting the safety of the plant as a matter nf highest priority at all times, J. Does not heecme involved in any single operation l that distracts him when multi required in the Control Ruom.ple operations are Durlng plant transients nr an emergency he should not become totally invnived in any single operation that distracte him from the rest of the operations required in the Control Ream, k. Ensures that shift activities are conducted in a manner that keeps personnel ras'.iatten exposures as low as reasonable achievable. l t

"* w ...n:,,w, : NM# atvresoes em a ,g p,. c YECF 10000 C 15 + 3 of 27 + 1. Ensures temporary procedure changes are properly administered on shlft in accordance with 00052, " Temporary Changas To Procedurea", il i m. Tours plant areas on a routine basis, noting condition of the plant and equi monitoring rounds performance. pment, and 2.3 SHIFT SUPT.RVISOR One Unit Shift Supervisor (USS) is assigned to esch operating unit en each shift. He is responsible for the safe and efficient operations of the assigned unit. The US5(s) reports en the Osos and has the following specific duties and responsibilitiest i ~ a. Ensures that unit operations are conducted in accordance with Tecinical Specifications and approved procedures, b. Directa reactor to be shut down whens (1) Safety of the reactor is in jeopardy, or (2) Operating parameters exceed any of the reactor protection system trip setpoints and i autoentic reactor trlp does not occur. or j 1 (3) Personnel or equipment safety require it, or (4) Unusual circumstances warrant it. c. Direcen operational activities of the assigned unit from the Control Room unless relieved by a qualified licensed SRO. d. Authorises maintenance and/or testing activities to be performed on the assiped unit, and ensures 1 plant conditions are suitab..e for performing such activities. Maintains status of equipment, and determines operability of equipment upon return to

service, e.

Issues equipment clearances and ensures proper control of tage in accordance with Plant Administrative 00304 C. " Equipment l Clearance And Tagging". f. Ensures proper control of temporary jumpers, l lifted wires and pulled annunciator cards l in accordance with 00306-C. " Tem Jumper And t.ifted Wire Control",poraryand 10018 C. " Annunciator Status Control". - -~ ,-r-- e

i

r.

m ; gggy 4- { PROCEDURE No. pgyis ON PAGE No. '1 VEGP 10000-C 15 a 4 of 27 ,N, l g. Explains plans, procedures, and safety precautions y to shift operating personnel prior to infrequent e or unusual activities, h. Ensures shift relief is conducted in accordance with 10004-C, " Shift Relief", 1. Maintains the Shift Supervisor narrative log and administers logkeeping in accordance with 10001-C, "Logkeeping", j. Supervises operators assigned to specific shift positions on the unit, k. Maintains operating work spaces in a clean and orderly condition, and ensures good housekeeping practices by operators assigned to the unit, 1. Conducts periodic safety meetings for operators on-shift, enforces safe practices, ensures appropriate protective equipment is used, prepares accident reports, and obtains medical attention. when needed, m. Limits access to the Control Room in accordance with Procedure 00301-C, " Main Control Room Access And Personnel Conduct", n. Tours plant areas on a routine basis, noting condition of the plant and equi and monitoring rounds performance. pment, t i 2.4 SUPPORT SHIFT SUPERVISOR The Support Shift Supervisor (SSS) reports to the OSOS. He provides technical and administrative sssistance to the USS. Specific duties and responsibilities include but are not limited to: Coordinates clearance and tagging review for the l a.

USS, b.

Coordinates control of keys required for plant operation per Procedure 00008-C, " Plant Lock And Key Control", c. Performs maintenance work order and deficiency card reviews for the USS, { d. Supervises shift operators who are not assigned a 2 f., specific shift position. ? c.

l ,w . < q..a g PROCEDURE No. pgyssioN PAG E No...m.>. "5 'of 27 '4. k)kh' VEGP 10000-C 15 s,t ,5 Y e. Assists the OSOS in implementing work scheduled per the Plan-of-the-Day, and provides input to the 's POD work process, f. MayserveasFireTeamLeaderifdesignatedbythe-[

OSOS, g.

Tours plant areas on a routine basis, noting condition of the plant and equipment and monitoring rounds performance. 2.5 REACTOR OPERATOR The Reactor Operator (RO) reports to the USS. He is the licensed operator assigned to operate the reactor and related controls from the Control Room. The RO normally operates the Primary Plant Systems (located on Control Room Panels A2 and C). Specific duties and responsibilities include: a. Maintains the unit in a safe condition, including shutting down the recctor when (1) Safety of the reactor is in jeopardy, or (2) Operating parameters exceed any of the reactor protection circuit set points and automatic shutdown does not occur, or (3) Required to protect personnel and equipment, or (4) Unusual circumstances warrant it. b. Initiates immediate actions necessary to maintain the unit in a safe condition during abnormal and emergency operations, c. Performs shift operations and surveillance testing in accordance with approved procedures, standing orders, and the Technical Specifications, d. Exercises continuous surveillance of unit y Tt conditions and sy' stem parameters. Remains in the f "at the controls area unless properly relieved. "At the controls" is defined in 10003-C, " Manning

1. 3-

) t The Shift", e .c e. Instructs the Balance of Plant Operator and the plant equipment operators to perform prescribed 9' plant operations, p 16 gyv f. Manipulates the controls and equipment to start h)ij up, operate, and shut down the unit as required byg i-y operating schedules and load demand,3;,n,. q$, f 4;. 3,, F .Y4545Gf7.WJ. I

Dhii,

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C PROCEDURE No. REVISION PAGE No. ,,y,,y VEGP 10000-C 15 6' of 27h-;ll /  ; s . p. .'\\ g. MaintainstheUnitControlLogandcompletesroundin t:. 3 sheets for his position. Maintains recorder 16 gyji[Ty charts for his work station, e 4)1 : yyjfl g h. Promptly notifies the USS of unusual' conditions *,CMt/ ~ Remains alert and knowledgeable of all utiithn.%.d;p'."J a.. m n u f 1. n operations in progress that involve the functioning of equipment controlled from the Main A Control Room, ,jn j. Functions as a team member during initiation of ) the Site Emergency Plan, k. Coordinates startup and shutdown operations of the P nuclear reactor, turbine generator and auxiliary equipment, .g. f, 1. Responds to the system operator requests at the t,, direction of the USS. yy ) e ~ 2.6 BALANCE OF PLANT OPERATOR l The Balance of Plant Operator (BOP) is a second + licensed operator assigned to each unit. He reports to { the USS. He normally operates primary support and balance of plant systems and controls (located on Control Room Panels A1, B1, B2 and those panels not d' located in the at-the-controls area). Specific duties 3 and responsibilities include: i a. Maintains the unit in a safe condition, including shutting down the reactor when: 4 (1) Safety of the reactor is in jeopardy, or (2) Operating paraneters exceed any of the reactor protection circuit set points and automatic shutdown does not occur, or j 4 (3) Required to protect personnel and equipment, h or y t- '[g/4 [ (4) Unusual circumstan:es warrant it, }p b. Initiates the immediate actions necessary to

• b

s-maintain the unit in a safe condition during abnormal or emergency operations,

,y Performs shift operations and surveillance testing

s c.

in accordance with approved procedures standing .+ 1 orders, and Technical Specifications, ' w:/ e g.... ~ ,w.. a h.@. f i d. Exercises continuous surveillance of un " 'h-conditions and system parameters, g. ,6 v.o x.: q C mu,

i t' i O ret. pgygstorg $f d'?!&gg ..fy]' {t Receives instruction from the Reactor O e e. Completes check lists for hi 'positio%n,"perato .;t

amiC+.16' f.

m'aintains c-1 recorder charts for his work station tand assists the Reactor Operator in maintaining the Unit - Control Log, jg, .g g. Promptly notifies the USS of unusual' conditions,., i- /. -a r:,...m$'. h. Remains alert to and knowledgeable of all unit "~ 'W k;, i operations in progress that involve the o functioning of equipment under his control, i' h 1. Functions as a team member during initiation of 2 7,*; the Site Emergency Plan, r j. MainOains the Control Room in a clean and orderly i:p condition, T. k. Directs activities of Plant Equipment Operators as

required,

,I ( T, 1. Relieves the RO when authorized by the USS, ? m. Normally remains in the Control Room unless J performing necessary duties elsewhere in the l plant. 2 2.7 PLANT EQUIPMENT OPERATORS There will normally be four Plant Equipment Operators (PEO) on shift for each unit: A Turbine Building Operator (TO), an Auxiliary Building Operator (AO), an Outside Area Operator (OAO) and a Control Building 4 Operator (CBO). 74 4 The PEOs report to the USS, but may also receive ]1 T~ direction from the RO or BOP. Specific duties and 4 ..a responsibilities include: i l Performs rounds to ensure proper operation of a. equipment in assigned work area, b. Executes routine shift duties as directed by the ..g

USS,

.M) $,D Removesequipmentfromservice$sdD;o.< f ,f* hp .u. l c. restores equipmen.! executes and W .G% E clearance orders: tsto service' '. he USS, 4s, ).( (/ and removes clearances as directed b" 1 A.s.?.v.x

n

.t. 'M d. Maintains clean and orderly work ar y, Acts as Fire Team member when designated by~the..y 4 >. .~ e. k ^ x-f ,g j 1

i ,tjit.sy w 3. #yfgga; ..yj.,gi - 9 e.. PROCEDU81E No. AEVISloN PAGE No 3 VEGP 10000-C 15 M g d.8 of j27 j .~;.; 2.8 RADWASTE OPERATOR ~ ;.,.?4 :[ y], The Radvaste Operator reports functionally to the USS - 2 and administratively to a Radwaste Foreman. Specific - duties and responsibilities includes .c pwtg 9.,; - l, cc;, . v ; 7 a. Operates Radwaste Systems in.accordance with M t pg approved procedures and Standing Orders, g:; .n .g~; t g, b. Maintains round sheets and logs for his position, p,; ? 6 p.: c. Executes routfne shift duties as directed by the Radwaste Foreman or USS, L d. Maintains clean and orderly work area. 2.9 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor (STA) provides engineering 2 ); expertise during operational emergencies to assess .d' plant status and assist in implementing E0Ps. An STA is not required on shift if the OSOS or a USS i holds a bachelors degree in engineering or a related science. The SSS may also be designated to perform the STA function, if qualified. If an STA is assigned on shift, he or she will report to the OSOS. 2.10 OPERATIONS SUPERINTENDENT (UNIT 1) The Operations Superintendent (Unit 1) reports to the Manager Operations. He has the following duties and responsibilities: i a. Provides direction to OSOS for routine scheduling i of Operations shift activities for Unit 1, i including interfacing with other plant departments, when necessary, b. Provides input to the Work Planning'and Outage Planning Groups for Unit 1, apg. 2 .U 1 6.71 i"'s hi' c. Keviews and approves operating procedures, as M';

c designated by the Manager Operations,h,p.

y,; ~ l ,., < h. 3., d. Provides technical and schedular direction to the o g, g OSOS for safe and efficient plant operation; ...g ha designated. j.g;;i, p ~ ..x. w ~ t.

.lM l

e. May function as Manager Operations when t i ~ } Gh? .a s:w a .M b1ll

3, :m*x. 4r.~.mm,ay.. PROCEDURE No. agygsgoN PAGE No. VEGP 10000-C 15 '6 qi,. mos . 1,9 2.11 OPERATIONS SUPERINTENDENT (UNIT 2) e*Qm.., g i q.,;,,.g. The Operations Superintendent (Unit 2) reports to:the, Manager Operations. He has the following duties and responsibilities: +: h.....,o 3: .c i M n a. Provides direction to OSOS for routine ^schidtili t f of Operations shif t activities for Unit 2, i + including interfacing with other plant ?.Et i departments, when necessary, 'e 3.,4 b. Provides input to the Work Planning and Outage Planning Groups for Unit 2, ', ~t. Reviews and approves operating procedures as c. l designated by the Manager Operations, ? i i d. Provides technical and schedular direction to the ,yg OSOS for safe and efficient plant operation, f.9 w. e I Y-f;.$.f c. May function as Manager Operations when designated. ? 2.12 OPERATIONS SUPERINTENDENT (SUPPORT) E .} - The Operations Superintendent (Support) reports to the Manager Ocerations. He has the following duties and re s pons ib'ilitie s : ,.y., Supervises the preparation and review of plant a. operating procedures, +.c". b. Provides input to the Training Department for F development and conduct of training and V:6 qualification of Operations Department personnel, ,'l4.:g c. Develops and maintains personnel records such as shift schedules, vacation schedules, and seniority 4,

lists, Ju; M.-..'r.

.v d. Provides interface between Operations and other

• c....

departments on all administrative matterait c... Y - - pgfs.s.C , fiQ$ v e. Serves on the Plant Review Board when' designated ' ~. *19.U2 Wi May function as Manager O f. sp'ecifically designated. perations when's 4 9..l M 1 ? ig 1 Sr j >;.,

• )

Y.- h., W44%

F j j i .7 M@dMN CR.bN Qs-j.Q g ::y PAOCEDURE No. pgvlSloN PAGE No. ) 4. 10of27f,. i VECP 10000-C 15 , p nn ~; - f }; ~ 'r 1 .. >( h3 W ' u ,4 -. ;A: 2.13 OPERATIONS SUPERVISOR (ENGINEERING) ) f% R The Operations Supervisor (Engineering) reports to the 3 Operations Superintendent (Support) and has the ^N following duties and responsibilities: .) e CoordinatesOperatier.alExperience'Issessment n a. G-Program activities pertaining to plant operation '/d.,' g{ w (with Nuclear Safety and Compliance Section), b. Maintains plant operating procedures' current and 'U $-l

accurate, l

c. Reviews plant design changes to ensure timely 7[ l, revisions to operating procedures when necessary, f', ? e d. Provides technical and administrative support to the Operations Superintendents and Manager Operations, ? t l e. Supervises administration of the Operations ~ u Reading Book p'er Procedure 10017-C, " Operations 7 Reading Books, y-f. Coordinates operations responses to plant open j ;lg l items. L .g. P. f 2.14 OPERATIONS SUPERVISOR (TRAINING COORDINATOR) Operations Supervisor (Training Coordinator) reports to the Operations Superintendent (Support) and has the 1 j following duties and responsibilities i a. Assures that each applicant has the knowledge and + i skills to competently perform the assigned

position, b.

Monitors on-the-job-training (0JT) performance and Operations Department training needs, c. Primarily and routinely interfaces with the

b

}?.f,, S-Training Department, wqqs:. -y d. Maintains Training Qualification Checklist and OJT.5 J d b"+ documents, af,f / ^. 3 d $;- )Y I; C< w ?; Q e. Obtains and distributes training material, W x? W.0%s;;

4?

^ M.i:2 f. Attends training course IN-001, " Instructor "X $1 Development Program" within one year of being Q '~ R appointed to the position, x.y f... g. Establishes and maintains a list of approved k t Operations Department OJT Trainers / Evaluators, w t

.w.gw.,

'C ig Serves on the Operations Trainingj e s.momittee M18.;d.; c M h. ..a.se,c... 4J

r. PRoCEDURENo.,..

~ , 3.. - i pcw90f4 PAGE No. g diVECP 10000-C Y 15

gup, i

I 1l ~. M k' e;; , jM'_. $gp, h 2.15 SHIFT SUPEF.VI5CR (TRADING COORDINATOR) ,q,... s.

,5..p. -. - >.

iC-The Shift Supervisor (T. raining Coordinator) reports to' _ p ri ' the Operations Supervisor (Training Coordinator) and,." has the folleving duties:

• 'C:g;i "57~.:

gj,lJ-l a -:W.. Coordinates and schedules evaluations ~an"d;'"' ;.- lv ?- a.

training, 3jy '

.p'r. I b. Performs evaluations and trai ng;,.; g+.m l \\

g-n c.

Attends training course IN-001, " Instructor, 3 %' l Development Program" within one year of being ri l appointed to the position, q d. Identifies area of candidate's deficiencies and

3.,

provides icedback to Training and operations '.3 m management. s.g, 2.16 RADWASTE SUPERVISOR 1 l 2 The Radwaste Supervisor reports to the Operations d Superintendent Support. He has the following duties and responsibilities: a. Plans, directs, and supervises Operations Department liquid and gaseous radioactive wastes 4. processing, and coordinates :.hese activities with < 'z da 4 other plant departments as necessary, }; #}. 3 b. Conducts routine administration and scheduling for -2 E ' w.: ,' ') radwaste personnel, ~ b$W& c. Advises the Training Department on requirements ~. 2l 2 ?,4 personnel, ping and conducting training-of radwaste for develo 't d. EnsuresliquidandgaseousradwasteoperhElonsare conducted in accordance with state and federal regulations, and approved procedures, r p: 4 .n

x+4 i

e. Tracks and trends water usage in tie'plar' 1WV coordinates water management activities plans wide L.. to ensura efficient safety operati6ns. g.AttP ;- ( oa I 1

t i , MYM%%'$fS?**P8 PROCEDURE No, ,3 agVISloN PAGE No.,,3 gf,. ?.g p'127ef 27 % ) % VEGP 10000-C # 15 4.. w*t - %,j. 9

a m s

L ,rc,. s.. 2.17 RADWASTE FOREMAN W.; i, ':..) ... ~ c The Radwaste Foreman reports to the Radwaste 9 R 2 >1 "9 Supervisor. He has the following duties and ' i responsibilities:.g.g , g. ' o g'= s.* -s t. . '- ~ ' - S rpyy cer% y *.,,q; a. Directs the activities of the Radwaste Operators; L ' % k;p#th V m g b. Coordinates and schedules radwaste activities,'.pp:c m,r M...~ ~. (- ^ C$iG: .v.X l c. Reviews Radwaste Operator logs, S d. Initiates corrective actions for'ou,t-of-limit'1i.. :4. - r%q A &bk m A conditions and notifies the Radwaste Supervisor i j3 and the USS, 4,.. c. Coordinates and schedulec Chemistry, Health' .$j Q,! 4 Physics and Maintenance support, ..g y.; $l .,} .< t p, f. Conducts the Radwaste Operator Qualification Program. 3.0 SHIFT OPERATIOP' 1 i tl 3.1 SHIFT COMPLEM M ' #' d re l [ The OSOS shall ensure that the operating shift is {%., p' Manning The Shif t". g. -6 roperly manned. in accordance with Procedure 10003-C, { 3.2 SHIFT WORK HOURS i 3.2.1 Shift Hours The shifts will be conducted on a 24-hour clock system, using Central Standard Time (or Central Daylight Savings Time). Specific shift schedules will be posted by the Operations Superintendent (Support). - 'a .p 3.2.2 Overtime ,.r n. s Overtime should not be routinely scheduled to' meet the shift crew staffing requirements. In the event that J., ). overtime must be used, the overtime restrictions of Procedure 00005-C, " Overtime Authorization",,'~will be 6 ';/. folloved. . j;g, ..;f.. j ~ ., 4 s

,....

4 u i

Tll; ~!k,'$ U' Y ((.' ~ }.f. $ ..; i j 'r c. . w a. - .if b gi k aihu,d

• /$vi4WyN, *

}.

;,'&ll. ', ;'a ' ye,sQt ; ;,.,

_a, I PROCEDURE No. ngyssioN P .I$ ' AGE NC b VEGP 10000-C 15 ] ,s 1

f. 2 n

i t t .e 3.2.3 Notification of Absences f-p..y r. .01 l Anyone expecting to be late or unable to; report for' shift duty at the scheduled time shall, at.the earliest? l j possible time, inform the OSOS or USS._g e 3.2.4 Call Out Authority '1 p-l.7 # i s l

.nr; s The OSOS is authori

:ed to call out anyone required for _

y' '1 ' '.'c Procedure 00006-C, " Recall Of Off-Duty Personnel". f sh, the safe plant operation, per Plant Administrative D - L q 3.3 GENERAL WORK PRACTICES e a l Y l6' All personnel assigned to shift operations-shall: j'j l a. Be aware that the primary responsibility of the 4 operating shift is to assure the safe operation of l the plant under all conditions, l b. Protect plant personnel, the health and safety of i l the public and plant equipment, ,t. J c. Conduct plant operations in accordance with - approved written procedures, 4 -!, d. Be attentive to the condition of the plant at all

• 1 times.

They must be alert to ensure that the plant is operating safely and take action to prevent any progress toward a condition that might be unsafe, e. Believe and respond to instrument indications until they are proven to be incorrect, f. Not bypass, roset bypasses, defeat safety systems or interlocks or remove Category 1, 2 or 3 instrument channels from service, unless allowed a to do so by an approved procedure. 9. .i&?. ~ k._. lM - n '.yj w f,,' ... J.' l { I. 4 o g.s ~h k-...,~,.. _.,, %...... j ~ L-

a 1 ! . W.? $ N l Q L.'. $ {'l UQ a 10000-C vl 15 d.I f GP c, ' ? 'p y. "Qy 3.3.1 Shift Conduct ~ 'i. ) '. w.m.... s c : 3.3.1.1 Each member of the shift crew shall perform in,nai professional manner. Potentially distracting l' activitics shall not be conducted in the Control Room' area. Activities prohibited include loitering, & 1 listening to music, hobbies, non job-related read ng i e material, and horseplay. The full focus of the shif t j o f, complement's attention shall be the safe and efficient l n 1 nc A operation of the plant. . ik-rki+.. -Q - - M. -,lI \\ , \\ p i 3.3.1.2 Operations personnel on shift must be aware'of'and ",1 1G responsible for the plant status at all times. This j' i p-.

• includes supervisors being responsible for the j

d. performance of personnel assigned to their shift who 4,. Tl l 9 could affect plant safety. u 3.3.1.3 All Operations personnel on shift must be alert and . f. i remain within their work areas until properly relieved.

,g Q

-.74 ^M Operators are responsible for monitoring the l instrumentation and controls located within their work areas. They are responsible for taking timely and 3:% .b proper actions to ensure safe operation of the

.g facility.

1 3.3.1.4 Controls that directly affect the reactivity or power Y level of a reactor shall only be manipulated by licensed operators, except for training purposes. 3.3.1.5 Mechanisms and apparatus, other than controlsF that may K 5 c indirectly affect the power level or reactivity of a' ftl 2 reactor shall only be operated with the knowledge and prior consent of a licensed operator.

• 1 8',.

~ N, 3.3.2 Abnormal Indications l the OSOS, USS, and RO, and BOP have the authority and l responsibility to perform the tasks necessary to limit plant operations or to shutdown the unit when such action is warranted by unit conditions or unusual ' C.'j, ciret ms tances. When analyzing such situations, shift i operating personnel shall consider instrumentgreadings < im and control' indications to be true unless'they*are A.~ proven to be incorrect., When abnormal 3 indications occur, operations personnel shall determine (the cause p of the abno*; mal indication and initiate'ap priat 1,g, corrective action. .? ,s.. 7, '

• h 1,h y;4,

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b

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• a y ~.

.% +S. qi: gL,*p, :.. p ~.u

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i p e a n ummeo w n.:t 0b00-C $f \\QL.j$ k}; Cp ' 'l. m; g ) 3.3.3 j Instrument Setpoints !.ig W..,. .:p

r....

Shift operating personnel shall.not mani instrument, control or alarm setpcints, other)i: those available on the control console or.thos,o- ) normally required during routine operation.+Setpo 2 4!. changes shall be entered in the Unit Control' Log or th t r,). Shife Supervisor's Log. v.y..,,., =. u.s, 2.g .14 - Anyone performing a function that may affect a unit's M.. ; Jif operation or a Control Room indication shall notify the H p+ 3 Control Room operators before initiating the function. M.;- r 3.3.4 Control Room Access .# ".f " M;~,. s .i : Control Room access shall be limited to offici t y business only in accordance with Plant Administrative..w, S l 4 Procedure 00301-C, " Main Control Room Access And =; Personnel Conduct". .j; f 3.3.5 Generator Load Changes j i i Normally generator load changes will be made as -l requested by the System Operator. If approved by the OSOS, and if plant operating conditions and operational f orders permit, the Reactor Operator will comply with 4 I the request. The RO shall. inform the USS when the . 4.I ~ requested load change is completed. Whenever plant gj conditions require a load change, the System Operator .5 shall be notified as soon as possible of the proposed load and rate of change. y. Scheduled outage requests shall be initiated by the IS Operations Manager and approved by the General Manager .A, and System Operator prior to scheduled plant shutdown. 7 u 3.3.6 Control Room Housekeeping -?j v[/ y. TheControlRoomwillbemaintainedin$ clean'and 1 orderly condition in the interest of safe and efficient operations.4 Dusting and cleaning of controlicensolesi instrument panels, and computer consoles willibe S,C performed by shift operating personnel. .i a.A;fwQj %M. R f l . fy. l c .u "}}yl.;?. a s f $+19%% s .a -g ? :.- l ..A ..p?? i$Q.:. u* l 1 v v : w.,; w.- .c

M.y._

3 9 rA e 5 $ k.. '. 4 smn L

1 O. Xc"p'"2MGR'dQ "y f y My**'";, g y l ~. f., ' '"?.y' ,; 3.3.7 Manual Operation Of Motor Operated Valves q~ Avoid overtravel. Some MOV's are adjusted to stop' v. traveling open for less than 100% stroke due to pump system flow restriction requirements. ~,-7 W - i. NOTE , n.t., SJ f- .w. MJV >j Excessive closing or opening':M y , j ~ ~. 9 7 can damage the limitorque W. z2 %. 9,,Qa,;7. Q force during manual operation-h@', iC . e, i ~ 'r I operator.

• • -)). ; ;,:.:L';% '.gg:

.j ....w If manual seating or backscating is required,the'^ds gT,I, i t'- 6 6 associated handswitch shall be caution tagged to indicate that the valve has been manually operated. M.P $y h. p r -,.c ,(. yo r,. w. l or are required to be repositioned to fulfill a safety @[.s 7 i Safety related MOV's which receive an actuation signal @ related function shall be considered inoperable. l The valve shall be manually unseated and then stroked using the motor operator prior to returning the MOV to ,f remote service or for the case of safety related MOV's, v. I g declaring the MOV operable. ~, " I g:. d4 [ l V g, ..s C .,Q M', .s + n, - Q l. &.,%.; t, 4 .o n. .g.,. ,,- y ,. y }g UW ' G'. m ',{ 3 's h,A-4,- (~ o 1 ..r j - _f, s. ?s ? d q, A .s.- s a >.r s,

*k;,

,x . w. .s

• y

.S'.~. s 3 b s.. 4., r O Y 4 O$ G. mum M L

~ ~" PROCEDURE Ho. f.,,p2' REVISloH e , ee - . mg PAG E No. S I'E ,. kfi

h..

['$ ~VECP 10000-r y 6 l'f . gjgit '.@ Wtr"," - I j u 3.4 'd,NOTIFICATIONREQUIREMENTS ~ ,,,,j. The OSOS is responsible for the notification f' l. NRC, plant management and staff in special situattons W s i 5, Notifications required during day shift, Monday thru gN4 Friday, should be to the Manager Operationsst <a.e j 'M Requirements occurring at other times should be' first "5 to the Duty Manager, who may direct the OSOS.to call a i department superintendent or the Manager.0perationst \\ 'l'I. - ~ p*'c Q son g '.Y3.4.1'- Notification Of Duty Manager i s-g The OSOS shall notify the Manager Operations'or Duty-j ..e - t C. Manager if the following occur: gg Reportablo Occurrences requiring URC red phon U p# fi[,* a. notification per Plant Administrative Procedure , $,-l};., Requirenents",

.h C

00152-C, " Federal And State Reporting } d Conditiens that require the use of Abnormalh3 y,d >. b.

1. N:R.,. _

Operating Procedures, c. Unscheduled entry into an LCO action statement !g 1 . '...i with less than 72 hours restoration time, g.. g ) i , 5.6 d. Equipment failures that could necessitate a 6

derate, e..

l e. A major failure resulting in structura mage'to l company property,g..., ,c eu ) i f. Any serious personnel injury, Ankcallfor.offsiteassistaNce i l g. ...a

h..

A fire with activation of the plan re tieam 1

s 1.

Serious environmental problems,%' sue tox i chemical, oil, or hazardous waste < spills; i . g IDt' $ w p 4 9 & 4 e -

j.. Tec mical assistance or managemen rec e

needed for. issues'ofireportability operability technical; specification compliance procedura adequacy y - s,, e. i n .c q,,. e y. l..),) s ls;',' f,t * ^ .c y a

,y

. f (f}y 'l,; m.. --~.,.. -.

~ ~ ~ ~ ~ ~ ~~ .,,,.Q f ~~ ~ g. ,,y 1 PhocEDURE NO.. .4 REVISloN PAGE No.m =% k VECP h.'10000-C. %M!( >,9i. 15

-4 3.g18]f

~ l l k, ' '. ~,(.,\\ ^

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'3.4.2 '.. NRC Immediate Notification Events,./y v,9. ~ hs w f s,. o.. A " f',, .. the OSOS is responsible for notification of the NRC' i . Operations Center for prompt reportable occurrences i ..0. % ? accordance with Plant Administrative Procedure 00152-C, t, (( ' " " Federal And State Reporting Requirements". 'g; ^- .,n.n "?f@M> 3.5 .l.' SHIFT RELIEF AND EVOLUTION BRIEFINGS .,, B tj .ys, t.. f..,,. s + m

3. 5.1. " ' s Eachshift'reliefshallbeconductedinanorderly,.p?

^- $rofessional ennner in accordance with Procedure PA .g c 0004-C, " Shift Relief". The OSOS may add to these T p? [c: yj ,2 ) S minimum requirements as he sees fit. - igjj T l ]W'Q d < r. .x. 3 lK352 Briefings shall be conducted for individuals involved ; M $j 'd l k.k. in complex or unusual evolutions. The detail of the a P F 4 V f'6 briefingisdependentonthedegreeofcomplexity,.?A.f.og routineness, logistics, or number of people involved.' p y ,, Y'TheindividualwhoistoperformanactivityisUbbbd'k.N 3.5.3 1 responsible to adequately review its procedure, to ' M M fully understand what he is doing, and to be cognizant of all the linitations and precautions and M. [/ requirements.

.t. >.

~. ,.. + ..e : 1 4 3.5.4 Evolutions involving many individuals, especially froml$f'S .-4 fy two or more departments or disciplines, may require WEB 2 % j<.N. large formal briefings or pre-planning sessions. If the $ g ';' * ;{;' evolution is complex and involves close coordination, 'i h L i the briefing session should includet j t y.N.~a ~; m... m - + v u.; l i j-

P a.

A review of the appropriate sections'of he j

g procedure by key, parties,

.j og MedW Strp b M A ,4 -.' b. An examination of each f.ndividual s spec fi 'f d- .. 24gget.;.g cneve. p.involvementandresponsibilityh, 1 t' 1 i

1.,

. ~. 4pw... w a. m e g.pected results er performnnee n i. c. A discussion of ex e - gg , u. 7 'P. .? $ d. "" review of limitations, hold points dingrergs%esennmameru..,c.m

v. m t4 A.rev: ew;of emergency. action to e.t en Y.*j contingencies, Wwce$r) r.:MWfi,$

, (.. w,, M Melt,M 4 w .,OChecks to ensure that everyone un ers an ~L:W; f. interface and communications required W ..%W.NEMTffAMW.' 'W64-fA2 h ;p .4AtIdentification'p'f.individu 4 o ar a 1 tevolution. ~ 1 4 9.d 1 i ,0941* ...m... -,..n,-

,, ~ "f. M J.. l4 v644) PRoCEOGRE No.,, REVISloN

s..

.e PAGE No. .s . p,.. $VEGPf.N,.I'dOOO-C :M . ' f 3,' l'5 llj f s .g..* g. ' ' cd il,@iW-4M*A *

. q,:

NR. 3.6

• d'W Q SHIFT RECORDS i

i *p.o. %.,. .,,,,g.. 3.. i r,3 M.., 'i ' V. ' Shift records include logs, round sheets ch e c sts

• !; eg recorder charts, computer printouts and other data

. 45 f generated during operations. qg.g 'I / T#2 . Y3'.6.1 Logs l N.vA

1. >G.

w:s., .: % i Operations narrative logs, round she%'y'

c.

l TF h{y.. ets, recorder i a. charts and computer printouts shall be kept.in;y/ accordancewiththeprovisionsof10001-C,q.9%y ( l'* p "Logkeeping", f, l

g.

J',, j 3p b. Where instrument numbers are provided in Rounds

• W i

/ ,3 Sheets and Technical Specification Surveillance. JA i Logs, it is not intended to limit recording of the N i ?. specified parameter from only the instrument -r,y M. i ? '. number spe ified if an equivalent instrument is available s 'ch measures the same parameter /. Y l } ..L.);.,.,?.A 95 7, .Ir .. q:..

5.,

l

1. 3.6.2 Night Ordefs and Standing Orders Night Orders and Standing" Orders are issued inhM' fl0 W

S. 1 ,r 4-accordance with 10002-C, Plant Operating Orders'.. l j ..s. ~- .. < ?' 4 3.6.3 Reactor Trip Review..n.,._yJ.bgh>' y ..n..:g{ The OSOS shall initiate review of reactor trip's - accordance with 10006-C, " Reactor Trip Review. h 3.7 KEY CONTROL.. 8 2 .v % m, .w.w i 4.' Keys required for plant op'eration are ' controlled '.p. accordance with 00008-C, Flant Lock And Key. Control /4 i 4 e., r ..s :. - + RADIOLOGICAL CONTROLS L -i 9 3.8 m Q u'v. m W $' % G.;- 'i ~ 3 3.8.1 Each person on the plant staff is responsiil. o use proper radiological practices and procedures.g Everyon s must be continuously aware of the radiologica17. aspects ~ .of the work he is involved in and.take appropria . actions to. minimize exposure and to controltthe 'r. EP c'c' generation 4and spread of. radioactive contamination 3:.. & mnpy y >:. y, q; :- 9 . ?.. 3.8.2 Refer.to 43007-C,4" Issuance,.Use An i.: Radiation Work Permit", for control.of work radiation and high radiation areas; Oran m v .9' SAFETY CLEARANCE AND ACGING Clea e agg personne pme safety is'.' conducted;1 accordance with 00304-C / ' Equipment learance And Tagging" .e. -l N

~ Edd$ffifUc'$ EdifilW%$ g2gg s , ifhhhhN3'$h'$;QY 3.I'0 7 3 EQUIPMENT RETURN TO SERVICE ~ w.?: ..i6 5 A<.-4 % dg m 4.@ Msg 4Wf 7 tty ed Following maintenance on or modificat}.o$.to ystem component, operations shall verify the operable l

• ;gl'o

^ .ff. 'n. ';'

"' condition of that system or component.'p, Verification

?? may be by functionally testing or by surveillance i s? h,E testing. If the component or system is not covere l 6. a surveillance procedure and a special functional test ' l. is not performed, a return to service functional W - f inspection should be performed. The inspection shou 5 Lg address items such as the following: 4,j,jg-e "c. :

e.. _.

.,v-- e ,b, w'f 'p... a. Mechanical coupling, W i ' %.y i.' s 1 ff- .w 4~ ' r 1 2 y'- W. b. Blind f1anges instalied/ removed, V &gg,..f y m-3 g ', e c. Electrical connections, 1.M g r;b .;z } l g j~, 1 A. .n . c.':. " i3 p d. Area c1ean1iness,>l J. 3(, 3.,,.

• ~-

M ".c t

.; c..

3 T'

e. Valve' alignment,f .N.. . p'N ^ '.kn.:,, J. - Propei+ lubrication,-(f.'--.. ) t -- Mzw->b?

t f.

',y r.w seg. m '. s ;,iJ. J J. g. System integrity. ~ r w ,9@, ' h. Function of remotely operated va ves . my,xc t .r a3.11 TECHNICAL SPECIFICATION INTERPRETATIONS = l d' Y h .v. .x n#. y w ..m <'

j 3.11.1 Technical Specification interpretations may~ e ma

= . c.w 4 using Figure 2 as follows:.. , v.-a. - i +4 4%

^. n.

. 'y y -l

-Q g".

'.,., j a. Immediate Nee i , w&.n.ad

M;L:: w%g a

'1he re uestor will contact one of the ow list J indivi uals:

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f27. i ..q.,, ' (1) On-Shift Operations Supervisorf .gx., s,my.,y.,..m m. y. (2T Manager. Operations _ ;S - 1 ' i; nW y i (3) perations uperintendent. ~' Th neerpretat:. 1 .ven er an ay be followed,up.b the interpreter.with written request form. M

i .I l. l P"OGt utMF *so p r..yo., ,g,.g l VEGP 10000-C 15 21 of 27 e 1 b. Normal Need The requestor fills in the first two portions of the request form and forwards it to the Manager Operations. After interpretation is made and I approved by Operatiens Management, copies are l dir.tributed and the original is placed in the Technical Specification Interpretation Book. This book will be maintained in the Control Room area. I 4.0 PLANT OPERATING PROCEDURES 4.l PRO NDURE COMPLIANCE { 4.1.I Operating personnel will follow approved plant procedures as directed by 00054-C, " Rules For l Performing Procedures". i i, 4.1.2 In emergencies. Operations personnel are directed to j take such action as is necessary to minimize personnel i I injury and damage to the plants to return the plant to p a stable, safeconditionsandtoprotectthehealthand'}'- ) safety of the general public and personnel on site. yd

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- Wm4nea% 6 4.1.3 In emergencies, personnel may take reasonable act on. 4 l 6 that departs from a license condition or a Technical.. 4 i } Specification when this action is immediately needed to 4 y protect the public health and safety and no action t 4 consistent with license conditions and Technical. j: k.{. Specifications that can provide adequate or equiva ent' t L't protectionisimmedatelyapparent.;5k+k...r-v g

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. a a.m. a. p' 4.1.4 Personnel action pernitted by Paragraph 4.1' 3 shall,be' 3 i approved, as a minimun, by a licensed Senior Reactor Operator prior to taking the action. s ....; y cr n n v. u.,, x + .. N4 y 4.2 PROCEDURE IMPLEMENTATION'> ;', ;..; g, .c.... r g .,..y v .2.1 Procedures for oth,er than simplef. requently aerformed1 ~ operations shall be followed step-by-step with the ..e sE,..;. procedure present.gMany procedures..will. require - ) ,[. A signoffs.<gRoutine.proceduraliactions3thatFare l - frequently performed may not necessitat thetpresenc ei

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'd.of a procedureM.If..the operator is}not completely familiar with the pr.oceduraliactioncto a the procedure must.be3prescntMeImmedi) ate!performe. i.1 < - t +. 4" actions of emergency procedures 7'shall be-c. opera or y'W ommitted o memory.l g r ~ Q&%g.,W.bc, 2.2 h ? Independent Verif cat ons' require - 3 roce ure c i do not have?signoffc' spaces:shall be7documentedgsing 11879-C..," Independent Verification. Documentation Los 'She et. ' r r il i I

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• n000-C 15 22 of 27 I

4.2.3 If an evolution is suspended for an extended period of time, reverification of the initial conditions is required. 4.3 SYSTEM LINElfPS AND SYSTEM STATUS FILE l l Systsm lineups establish and confirm the status of i equipment and systems. The current lineup for each sustem is maintained in a system status file. The file contains the most recent complete lineup and those i partin' lineups performed subsequently which collec tively reflect the current status of the entire j system. t.3.1 Complete system lineups are p.>rformed as directed in unit operating procedures. Partial lineups are i pe-tormed on pertions of systems it. side clearance I bo.ndaries, after clearances are released, when direc*ed by the Shift Supervisor. Partial lineups are l alno performed on portions of systems affected by l procedure revisions when directed by the Operations Superintendent. Complete or partial lineups may be perforr.md when directed by the USS. 4.3.2 Each svstem lineup will be performed at least every 30 months. The Operations Manager or his designee will druignate system lineups that will be performed prior to unit startup following cold shutdown. Any l exceptions to this policy will be approved by the Assistant General Manager - Operations. I 4.3.3 Lineups should he performed in sequence identified in Lineup procedure unless otherwise directed by the USS. 4.3.4 The operator shall compare the position of the component with the condition required on the alignnent, and initial in the spaces provided. Report components found not to be in the required position to the USS for evaluation prior to repositioning to the condition required. Control valve position is verified by ensuring that power or air, as oppropriate, is available to the valve operator and that no physical obstructionn that could prevent operation are apparent. 4.3.5 All components left in other than the condition required shall be noted on *he comments section of each j alignment procedure and the reason for the cyception rhall be entered. 4.3.6 While performing lineups, the operator should compare the component ran 'eich the alir.nnent precedure component I.D. and description. Discrepancies should he noted on the comnents section of the alignment procedure.

1 l l l paoccount no mvision notNo VEGP [0000-C 15 23 of 27 = 4.3.7 Independent position verification shall be performed in accordance with 00308-C, " Independent Verification Policy" and Sub-subsection 4.2.2. 4.3.8 The USS or SSS shall review the completed system lineup for completenens and to ensure exceptions do not warrant further corrective action. The original lineup is placed in the nystem status file. Superceded lineups are forwarded to Document Cont ol. Care must I taken when removing lineups from the file to ensure be that the file reflects the current status of the i svstems (e.g., partial lineups can supercede only partial Itneups on the same compenents: partial lineurs can only supercede complete lineups if, collectively. l they constitute a complete lineup.) 4.4 SURVEILLANCE TESTING 4.4.1 Operation Surveillance Tests 4.4.1.1 The Operations Department shall perform, document and review operations surveillance tests. 4.4.1.2 The approval of the USS shall be ootained before starting each surveillance tes. The operator performing the test shall record information as required by the test procedure and initial each step as it is completed. He shall sign and date the procedure upon completion of the test. If a step is not completed the explanation shall be recorded on the procedure. If a test does not meet the specified acceptance criteria, the USS shall be notified and corrective action initiated. 4.4.1.3 The OSOS or USS shall review all operations surveillance tests performed on his shift for completeness and accuracy. He shall indicate his review by signing and dating the procedure in the appropriate space. 4.4.1.4 Refer to 00404-C, " Surveillance Test Program" for methnd of tracking Tech. Spee. surveillance tests during normal conditions. 4.4.2 Special Condition or Off-Normal Surveillance Requirements The I!SS shall ensure 14915-1/2, "Special Condition Surveillance Logs" is or has been initiated as required to comply with Technical Specifications in conditional or off-normal situations. 4.4.3 The USS shall ensure 14000-l/2 " Operations Shift & Daily Surveillance Logs" surveillances are started within 2 hours of shirt turnover and worked to completion, provided circumstances warrant.

h ) ) i ~~ rooci noot no in m,m >.ac,, so ~ vgcp in000 C 15 24 of 27 ~. _... _. 5.0 REFE8tENCES 5.1 'FSAR - Chapter 13 l 5.. VECP Technical Specifications j l 5.3 PROCEDilRES i l 5.3.1 00001-C. " Plant Organization: Managerial Staff Responsibilitier. And Authority" 5. 1. 00005-C, " Overtime Authertzation" l 5.1.3 00006-C, " Recall Of Off-Duty Personnel" 5.3.4 00008-C, " Plant Lock And Key Control" 5.3.5 00052-C, " Temporary Changes To Procedures" 5.3.6 00054-C, " Rules for Performing Procedures" 5.3.7 00152-C, " Federal And State Report.ing Requirements" 5.3.8 00301-C, " Main Control Room Accesr And Personnel l Conduct" 5.3.9 00304-C, " Equipment Clearance And Tagging" 5.3.10 00306-C, "Temporarv Jumper And Lifted Wire Control" 5-.3.11 00308-C, " Independent Verification Policy" 5.3.12 00404-C. " Surveillance Test Program" 5.3.13 10001-C, "Logkeeping" 5.3.14 10002-C. " Plant. Operating Orders" 5.3.15 10003-C, " Manning The Shift" 5.3.16 10004-C, " Shift Relief" 5.3.17. 10006-C, " Reactor Trip Review" 5.3.18 10017-C, " Operations Readinc Book" 5.3.19 100lS-C, " Annunciator Control" 5.1. :'O f1879-C, " Independent Verification Documen*ation Log Sheet" t

PROCE004E NO AEviOIGN PAGENO VEGP 10000-C 15 25 of 27 5.3.21 14000-1/2, " Operations Shift And Daily Surveillance Logs 5.3.22 14915-1/2, "Special Conditions Surveillance Logs" 5.3.23 43007-C, " Issuance, Use And Control Of Radiation Work Permits" END OF PROCEDURE TEXT E I h 1 l i l

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MOCE DUf4 N'> r.EvlSION PAGE t<Q VEGP 10000-c 15 27 of 27 PLANT V0GTLE UNITS 1 & 2 TECH SPEC INTERPRETATION TECli SPEC # : i QUESTION OR AREA NEEDING CLARIFICATION: INTERPRETATION: Approved By: !4anager Operations Date xc: Manager Operations Nuclear Safety & Compliance Manager Engineering Support Manager Plant Training & Emergency Prepardness Manager Required Reading Bcok l FIGURE 2 1

^ *l* ' Vogtle Electric Generating Plant Procedure No. 10008-C NUCLEAR OPERATIONS ne,,,,on no. one 9 ,7 g p Unit COMMON Georgia Power am ag,y 11 JGlD . RECORDING LIMITING CONDITIONS FOR OPERATION 1.0 PURPOSE This procedure prescribes the method to record the failure to meet the Limiting Conditioni. for Operation (LCO), the associated ACTION requirements any change in status effecting the ACTION, and the return to compliance with LCO. 2.0 DEFINITIONS 2.1 LIMITING CONDITION FOR OPERATION A condition specified in the plant Technical l l Specifications which limits unit operations. An LCO may be entered by equipment malfunction or a change in a unit parameter. If an LCO is not met, the associated ACTION requirements shall be met. 2.2 ONE Il0UR ACTIONS One hour actions are actions that must be performed within one hour or less. 2.3 INFORMATION ONLY LIMITING CONDITION FOR OPERATION (Info LCO) A method of tracking an equipment malfunction or change in plant parameter which would restrict unit operation in any other mode or prevent a mode chenge, or may become an LCO for the present mode should other Technical Specification related equipment or redundant safety related equipment become inoperable, i

PRocEDUAE No AEvi5 son PAGE No VEGP 10008-C 9 2 of 11 3.0 PROCEDURE 3.1 LCO STATUS SHEET PREPARATIO!! When a unit fails to meet an applicable LCO and requires initiation of an ACTION statement or equipment malfunction requires an Info LCO, the Unit Shif t Supervisor (USS) shall complete Figure 1 "LCO Status Sheet" Section I, inform the On-Shife Operations Supervisor (OSOS), and log the status sheet on Figure

2. "LCO Status Log" prior to completing his shift.

The LCO Status Sheet shall be placed in the LCO Status Binder. Completion of an LCO Status Sheet is not required for the performance of surveillances or short term entry into an LCO that does not continue past a shift turnover if the USS logs the following itema in the USS Log: a. Entry and exit timeu of an LCO, i b. Reason for entry, Completion of all required Technical c. Specification Action Statements due to entry into the LCO if it in not documented in the surveillance procedure. 3.1.1 Initiation of I.C0 Status Sheet For An LCO complete Section I of the LCO Status Sheet in accordance with the following subsections: 3.1.1.1 Applicable Modes Record most limiting applicable modes from Technical Specification References. 3.1.1.2 LCO Number The LCO Number is assigned by unit-year-sequence. e.g.: 1 1-85-002 l The 2nd LCO for the year 1985 Unit 1 3.1.1.3 One Hour Actions Circle YES or NO. 7.-.. c

i 1 PRoctOURE No REvasioN PAGE NO VEGP 10008-C 9 3 of 11 3.1.1.4 Technical Specification 3.0.4 Applicable Circle YES or NO. 3.1.1.5 LCO initiated The date and time the LCO was not met. If a time cannut be determined for the initiating event, the time of discovery should be used. Record the date as mm-dd-yy. 3 where mm - month (01-12) 1 dd - day (01-31) ( yy year (84-99) l \\ Record the time using a 24 hour clock as hh-mm. l where hh - hours (00-23) m - minute (00-59) 3.1.1.6 Technical Specification References List the paragraph number (s) of the LC0(n) stated in the Technical Specifications. List the most restrictive paragraph first. 3.1.1.7 condition Initiating LCO The initiating event, equipment failure, or parameter deviation explained in a few words. 3.1.1.8 DC Number (s) List al! DC numbers which apply to the LCO. Additional DC numbers should be added to this section if the LCO is referenced on new DC cards. 3.1.1.9 MWO Number (s) List all MW0s which apply to the LCO. MWO numbers should he obtained from Work Planning prior to complorion of Section 1 of LCO Status Sheet. If other MW0s are worked under this LCO, the MWO numbets should be added when the MWO work authorization is given. 3.l.1.10 Required Actions List required actions from the Technical Specification reference (s). Use Figure 3 for guidance in listing actions. The USS will initial, date and time each action when complete. 2-__.m___-.._-._____.-_..-.___.__.____.m m.___ m_______.__._.-_

b PROCE DUR( ho R(VillCN PAGENQ VEGP 10008-C 9 4 of 11 3.1.1.11 Remarks 6 Include any additional information on the LCO in this ~ section. 3.1.1.12 USS/OSOS Signatures The USS and OSOS both sign indicating correctness of all.ntries. 3.1.1.13 Disposition The original LCO Status Sheet is placed in the LCO Status Binder. 3.1.2 Initiation of LCO Status Sheet For An Info LCO Complete Section I of the LCO Status Sheet per Sub-subsection 3.1.1 except as modified by the following subsections. 3.1.2.1 Information Only LCO Number The LCO Number is assigned by unit-year-sequence and information only identifier. e.g.: 1-85-002-1 1 Information LCO (only) The 2nd LCO for the year 1985 Unit 1 The LCO numbers and Info LCO numbers share the same sequence numbers. 3.1.2.2 LCO Initiated Enter date and time of equipment malfunction. 3.1.2.3 Required Actions State any mode restraints or restraints on equipment j operation. The completion section will be N/A. i l \\

... _ - _ _ ~ PROCEDURE No HE VIStoN PAGE NO VEGP 10008-C 9 'i of 11 3.1.3 Restoration Of LCOs And Info LCOs 3.1.3.1 When the LCO restoration is complete, the USS shall the LCO Status Sheet from the LCO Leatus Binder, removu I complete Section II, and forward the sheet to the OSOS. Specific entries are: j Corrective Measures Taken: Include a statement on i n. the corrective actions taken. h. Operability determined: The SS shall, on LCO restoration, make a determination of operability status of all plant components effected, anc! shall verify their functional acceptability. This is documented by listing the items verified and the procedures used to verify operability. The SS's signature indicates that this has been satisfactorily performed. Chemistry llP person notified (for Rad Monitors c. i only): Enter date, time and person contacted. Necessary to ensure required Chemistry /HP surveillances are completed prior to returning i Rad Monitors to operable status. d. LCO No Longer Active: Enter date and time that limiting condition no longer exists. 3.1.3.2 The OSOS shall verify the correctness of all entries und the completion of all required action prior to signing the form. The completed fom is then forwarded to the Operations Superintendent (Shift Operations). 3.1.3.3 When the Operations Superintendent has indicated his approval of the cumpleted action by signing and dating, j the original form is sent to Document Control for permanent file. Copies should be forwarded to the i Nuclear Safety & Compliance Department and placed in the completed portion of the LCO Status Binder. { 3.1.3.4 LCOs and Info LCOs are restored in exactiv the same way. l I l i t l i t l

u u mm I l PAoCEDURE NO RivtStoM PAGE No VEGP 10008-C 9 6 of 11 3.2 CONVERSION OF LCOS TO INTO LCOS When the unit enters a mode where a given Technical Specification is no longer applicable LCOs against that npecification should be converted to Info LCOs. To convert to Info LCOs perform the following Add an "I" to LCO Status Sheet and LCO Status Log, n. b. N/A required actions and add note to remarks section stating " Conversion to Info LCO on (date and time) upon entry into mode (number)", i Add necessary statements to Required Action c. Section per Step 3.1.2.3. 4 3.3 CONVERSION OF INFO LCOS TO LCOS An Info LCO should be closed out and a new LCO status sheet generated. 3.4 LCO STATUS BINDER An LCO Status Binder shall be maintained for each unit by the SS. The binder is a looncleaf notebook containing 3 sections: 3.4.1 Part I. LCO Status Log. The first part shall list, on Figure 2. "LCO Status Log", all LCO's in their order of initiation. New log pages should be placed in the front, so that opening the front cover will expose the most recent entries. The LCO Status Log Sheets will be retained in the binder until all listed LCO Status Sheets have been retired, then the log sheet should be removed and sent to Document Control. A copy of the complete status log sheet should be placed in Part III. 3.4.2 Part II. Active LCO Status Sheets, j Part II contains the original of Figure 1. "LCO Status Sheet" forms for all LCO s that are in effect. New entries are placed in the front. LCO and Info LCO forns may be kept separately in Part-II if desired. 3.4.3 Part III. Completed LCO Status Sheets. Part III contains copies of LCO Status Sheets for LCO's that have been restored. Sheets are filed in order of their LCO number. Copies of completed sheets should be retained in the binder for at least 30 days after they have been closed out. i

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4.0 REFERENCES

4.1 PROCEDURES i 4.1.1 10000-C, " Conduct Of Operations" i 4.1.2 00150-c. " Deficit.cy Reports" 4.1.3 00152-C, " Federal And State Reporting Requirements" END OF PROCEDURE TEXT 1 l l I i j l! l 1 1 1 l l i I l l I i t l l l l

i l-i l PROCEDUAE NO. REVISION VEGP 10008-C 9 8 of 11 PAGE NO. ' CO STATUS SHEET SECTION I: IllITIATION Applicable Modes LCO Number One Hour Actions. YES NO Tech. Spec. 3.0.4 Applicable YES NO (circle one) (circle one) LCO Initiated: Date Time Tech. Spec. References Condition Initiating LCO Action DC Number (s) FN'O flumbe r ( o ) i REQUIRED ACTIONS Completion SS Init/Date/ Time J "I Figure 1

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l a PROCEDgNo. REVISloN p PAGE NO. Completion REQUIRED ACTIONS CONT' D. SS Init/Date/ Time l l Remarks i USS osos SECTION II: RESTORATION Corrective Measures Taken: Operability Determined: l l t j. Chemistry /Hp Person Notified (for Rad Monitors only): Date Time LCO No longer Active Date Time USS OSOS s Operations Superintendent Review l (Date) Figure 1 (Cont'd.)

PROCEDURE NO REvi$:ON VEGP 10008-C 9 10 Of 11 PAGE NO. 19 _ _, LCO STATUS LOG UNIT TERMINATED !!O. DATE T.S. PARA. & CONDITION INITIATING LOG DATE / SS 1 t 4 1 i l I i i i 1 l Figure 2 I l 1

PROCEDURE NO REVIStoN PAGE No. VECP 10008-C 9 11 of 11 l GUIDELINES FOR WRITING REQUIRED ACTIONS l ON LCO STATUS SHEET I 1. Break action statements into single actions. Exampler Restore to operable within 72 hours -or-h Be in HOT STANDBY within following 6 hours -and-Be in COLD SHUTDOWN within i following 30 hours { s 2. Use the following statement for actions to be performed i periodically. / " Initiate (the required action) every (required interval) and log completion in USS Log." This action can be signed complete when performed the first 5

time, i

{ 3. Use the following statement for actions that are taken by other departments. " Notified (Department Supervision) (Printed Name) to initiate (required action) / / Department Supervision Date Time or Unit Shift Supervisor (USS) The above statement should be made next to the applicable " Required Action" statement. In the case of a short term entry as defined in Subsection 3.1 paragraph 2, the above information should be entered in the USS Log, if applicable. 4 Paraphrase action statements where it would result in a clear, concise action. Example: "With one AFW pump inoperable, restore the required AFW pump to operable status within 72 hours or" can be paraphrased "WiP_h one AFW pump inoperable, restore within 72 3 hours -or " Figure 3 m -}}