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Rev 0 to Procedure 12 PMP 4021.TRP.001, Reactor Trip Review.
	ML17326B119
Person / Time
Site:	Cook
Issue date:	03/20/1984
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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	12-PMP-4021.TRP, NUDOCS 8404060371
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~C 12 PMP 4021.TRP.001 LIST OF EFFECTIVE PAGES

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12 PMP 4021.TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE SIGNOFF SHEET 5.1 Con't Page 8 of 11 Revision 0, 3/20/84 Page 9 of ll . Revision 0, 3/20/84 Page 10 of 11 Revision 0, 3/20/84 Page ll of 11 Revision 0, 3/20/84 SIGNOFF SHEET 5.2 Page 1 of 2 Revision 0, 3/20/84 Page 2 of 2 Revision 0, 3/20/84 SIGNOFF SHEET 5.3 Page 1 of 4 Revision 0, 3/20/84 Page 2 of 4 Revision 0, 3/20/84:

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12 PMP 4021.TRP.001 LIST OF EFFECTIVE PAGES (g PAGE NUMBER REV1SION NUMBER AND DATE SIGNOFF SHEET 5.5 Page 1 of 2 Revision 0, 3/20/84 Page 2 of 2 Revision 0, 3/20/84 SIGNOFF SHEET 6.1 Page 1 of 9 Revision 0, 3/20/84 Page 2 of 9 Revision 0, 3/20/84 Page 3 of 9 Revision 0, 3/20/84 Page 4 of 9 Revision 0, 3/20/84 Page 5 of 9 Revision 0, 3/20/84 Page 6 of 9 Revision 0, 3/20/84

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12. PMP 4021.TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE APPENDIX A Page 1 of 40 Revision 0, 3/20/84 Page 2 of 40 Revision 0, 3/20/84 Page 3 of 40 Revision 0, 3/20/84 Page 4 of 40 Revision 0, 3/20/84 Page 5 of 40 Revision 0, 3/20/84 Page 6 of 40 Revision 0, 3/20/84 Page 7 of 40 Revision 0, 3/20/84 Page 8 of 40. Revision 0, 3/20/84 Page 9 of 40 Revision 0, 3/20/84 Page, 10 of 40 Revision 0, 3/20/84 Page ll of 40 Revision 0, 3/20/84

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12 PMP 4021.TRP.001 INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT REACTOR TRIP REVIEW

1. 0 OB JECTIVES 1.1 To provide for the collection and retention of data required to implement objectives 1.2 and 1'.3.

1.2 To ensure that all required automatic responses associated with a reactor trip have functioned.

1.3 To determine the. cause of the reactor trip.

1.4 To establish requirements for reactor restart.

1.5 To establish criteria for. requesting independent assessment of the event.

1.6 To provide a written compilation of event circumstances.

1.7 To provide operating instructions for equipment which provide data useful for event analysis.

0)"

2.0 REFERENCES

2.1 References on which the procedure is based.

2.1.1 The ATWS Events of February 22 and 25, 1983 at Salem Nuclear Generating Station have demonstrated the need for a procedure for comprehensive data collection and review following a reactor trip. The Salem events are'described in NUREG 0977 and NUREG 1000, Vol. 1.

2.1.2 This procedure has been written with consideration of items listed in the NRC "Salem Restart Status Report", March 28, 1983 which includes items appropriate for such a procedure.

2.1.3 Generic Letter 83-28, "Required Actions based on Generic Implications of Salem ATWAS Events", July 8, 1983.

2.1.4 AFPSC response to Generic Letter 83-28, file AEP: NRC: 0838A Page 1 of 15 Rev. 0

12 PMP 4021.TRP.001 INPO Good Practice OP-211, "Post Trip 2.1.5'.1.6 Reviews"," 9/83 10 CFR 50. 73 (IV) 2.1.7 OSO .052, 6/3/82 issue, and OS0.056, 10/27/82 issue 2.1.8 1-OHP 4021.001.002 Rev. 11 and 2-OHP 4021.001.002 Rev. 5 2.1.9 Oconee Nuclear Station directive, Xnvestigation of Unit Trips, Revision of 10/23/75 2.1.10 Oconee Nuclear Station Performance Manual, Section 4.7, Support of Reactor Trips, Revision of 2/16/83

2. 1. 11 Memo, V. VanderBurg to W.G. Smith, 6/30/83 2.2 References, to assist in procedure implementation.

2.2.1 Elementary Diagrams 2.2.1.1 98501 98515, Reactor Protection and Safeguards Logic'Diagrams.

2.2.1.2 98361 98377, Elementary Diagrams for Protection System and Safeguards, Train A.

2.2.1.3 98381 98397, Elementary Diagrams for Protection System and Safeguards, Train B.

2.2.1.4 1-98101, 2-98101, 2-98102, Turbine Control.

2.2. 1.5 98211, Steam Generator Feedwater Turbine E. 98212, Steam Generator Feedwater Turbine W.

2.2.1. 6 9 802 1 I Generator and Transf ormer Differential.

2.2.1.7 98120, Turbine Events Monitor and Miscellaneous Recorders..

2.2.1.8 98655, 98656, 98657, Operations Sequence Monitor.

2.2.1.9 98665, 98666, 98667, Oscillograph.

Page 2 of 15 Rev. 0

12 PMP 4021.TRP.001 2.2.1.10 '200-A,B,C,G, one Line Electrical Diagrams.

2.2. 2 Recorder Chart Index, 4/21/81 Revision

. 2.2.3 Hathaway H634 .Manual, Issue 55, May,1975 2.2. 4 Hathaway H-559 Manual, Issue $ 1, April 1970 2.2.5 Westinghouse DIll P250 manual, 1/68 Revision 2.2.6 Westinghouse P250 Continuous Monitoring System Manual S2G-08A, issued 11/68 2.2.7 S2G-09B Westinghouse Post Trip Review Program Description, original issue.

2.2.8 D. C. Cook Plant operating records.

3.0 PREREQUISITES The purpose of this procedure is to collect and provide for the retention of reactor trip data which will be used to verify that required automatic responses occurred and to

. determine the cause of the trip. This procedure is intended fg to be'mplemented after the reactor has been placed in a safe condition. Therefore, the following prerequisites apply:

3.1 A reactor trip has occurred.

3.2 The immediate and subsequent actions of the "reactor trip" operating procedure have been completed.

3.3 Any other abnormal or emergency operating procedures which may be required in conjunction with the "reactor trip". operating procedure or which may supercede been completed.

it have 3.4 The affected unit has been placed in a safe condition.

3.5 This procedure is not applicable to intentional complete or partial trips initiated as directed by an approved surveillance test procedure.

4.0 CONDITION I EVENT REVIEWS Using the description below, the SS and STA shall determine event. Ifif the trip is to be reviewed as a Condition I the SS and STA do not concur on whether the trip meets Condition I criteria, the matter will be referred to the Operations Superintendent for resolution.

Page 3 of 15 Rev. 0

12 PMP 4021.TRP.001 CONDITION I: The cause of the trip is positively known.

and has been corrected;. all safety-related equipment functioned properly during the trip.

Examples of events in this. category are lo-lo steam generator level trips during startup and human error during Reactor Protection System Surveillance procedures.

Since the cause, of the event is clearly understood, data collection can be limited to that which cannot be recove ed later, is required to prepare the LER, or is needed to verify proper automatic response. The only data analysis required is verification that automatic protective responses took place and occurred in an acceptable time frame.

The judgement that a trip is a Condition I event shall be documented on Signoff Sheet 4.1. For these trips, only procedure sections 5.0, DATA COLLECTION, and 6.1, VERIFICATION OF AUTOMATIC RESPONSES need be completed.

If during RESPONSES performance a malfunction is of VERIFICATION OF AUTOMATIC discovered, the trip no longer satisfies the criteria of a Condition I event. In this case, as well as for trips which cannot initially be classified as Condition I events, completion of the comprehensive review (i.e. performance of all review procedure sections) is required.

5.0 DATA COLLECTION

5. 1 Checkof f sheets are provided for data collection. These are:

a) Relay Target Data b) Unit 1 EHC First Hit Annunciator Data c) Recorder chart and Trip Monitor Data d) System status and Response Form e) Personnel Interview Form NOTE: The extent of data collection required will depend on circumstances of the trip. These include trip classification, plant configuration (turbine rolled, exciter breaker closed, etc.) and involvement of certain plant equipment (main feedpumps, etc.)

NOTE: If space alotted inadequate for a on any signoff sheet is complete answer, use additional pages. Label these pages with the appropriate signoff sheet and step numbers and attach to the back of the associated signoff sheet.

Page 4 of 15 Rev. 0

12 PMP 4021.TRP.001 5.2 When the affected unit has been placed in a safe condition, the S.S. shall assign personnel to complete sign off sheets 5.1 and 5.2. These will be required. as follows: I Si n Off Sheet Re uired When 5.1 Generator exciter field breaker was closed when reactor tripped 5.2 turbine reset, Unit 1 only NOTE: Steps 5.3 and 5.4 may be performed simultaneously.

5.3 Marking of Recorder Charts The SS shall assign personnel to mark recorder charts as specified below.

5.3.1 Condition I event reviews: Mark Turbine Events Monitors and any chart directly related to the trip. Example: For a trip initiated by a lo-lo level on steam generator 52, mark the level and flow chart for that steam generator.

5.3.2 Reviews other than Condition I: Refer to.

Signoff Sheet 5.3 and mark those charts which are required to be copied or collected for the particular circumstances of the trip being reviewed.

Mark the time on each applicable chart and indicate with arrows the pen positions at this time. The arrow shall be drawn to the tip of the pen when the mark is made and the time shall be legible. For recorders where selection of recorded channels is possible, indicate on the chart which channels are selected.

5.4 Collection of Chart and Printout Data The SS shall assign personnel to obtain copies or originals of charts and printouts as specified below.

5.4. 1 Condition I event reviews: Obtain originals of the Turbine Events Monitor,- P-250 Sequence of Events printout, P-250 Post-Trip Review printout, Operation Sequence Monitor printout, and Oscillograph. Obtain copies of the control room log and any charts marked in Step 5.3.1 as directly related to the trip.

Page 5 of 15 Rev. 0

12 PMP 4021.TRP.001 Follow the methods outlined on Signoff Sheet 5.3, Steps 5.3.3, 5.3.4, and 5.3.6 for obtaining these items.

5..4.2 Reviews other than Condition I: Perform Signoff Sheet. 5.3. This will include collection, of items marked in Step 5.3.2 above.

Make a list of all originals retained. Include name, list that dates, and times for each item. Note on .the these items were obtained for a reactor trip review report. Specify date and unit. Forward this list to

the Performance Section.

5.5 If S.S.

RMS alarms occurred in conjunction with the trip, the shall assign personnel to obtain RMS 10 minute averages from the RMS control terminal when the plant has been placed in a safe condition. The alarming and related channels shall be obtained. For example', if ERS-1305 alarms on unit I, obtain VPS 1101, 1201, ERS 1301, 1303, 1305, 1401, 1403, 1405, 1307 (if indicating) and 1407 (if indicating). If more than 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months have elapsed since the trip obtain 1 hour averages.

5.6 After the affected unit has been placed in a safe e> condition,'he STA shall complete signoff sheet'.4 which requests information on system status and response, consulting with operations personnel as required.

5.7 The STA shall conduct personal interviews using signoff sheet. 5.5 with each of the following personnel:

Both control room RO's (affected unit)

Unit Supervisor (affected unit)

Other operators or technical personne'1 who may provide additional insight into the situation or who played a major role during the transient.

6.0 DATA ANALYSIS NOTE: There are two distinct aspects to the analysis of reactor trip data. These are:

a) Verify that required automatic responses took place and occurred within an acceptable time.

b) Determine the cause of the trip.

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12 PMP 4021.TRP.001 6.1 VERIFICATION OF AUTOMATIC RESPONSES NOTE: Signoff sheets 6.1Rx, 6.1TUR, 6.1GEN, for Unit I or Unit II, provide a format for verifying and documenting expected plant response. The signoff sheets include the expected response, an indication of whether the response time is to be measured or only be observed to occur, an indication of plant configuration for which each event is expected, and acceptance

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criteria. Data collected during performance of section 5 provide the information needed to complete signof f sheets 6. 1Rx, 6. 1TUR, 6. 1GEN.

The SS and STA are responsible for the review of signoff sheets 6.1Rx, 6.1TUR, and 6.1GEN.

If 'S.S. cannot participate in this review, he shall designate someone to work-with the STA.

They shall look for failed or degraded response of equipment to control signals.

For those items of Signoff. Sheet 6.1 where acceptance criteria have yet to be developed, compare performance to that of previous trips (from STA "Rx Trip Writeups" file). Check for major variations in system performance which appear to indicate degradation or failure of protective functions and which cannot be attributed to variations of trip circumstances (such as origin of trip signal). Any such indications must be examined by appropriate support personnel to determine has occurred.

if a failure 6.1.1 Examine recorder charts and monitor printouts to verify that the SSPS functioned as expected:

6.1.1.1 As closely as can be determined, the signal which initiated the reactor trip'as actuated at the proper value of the deviant parameter.

6.1.1.2 While the events leading to the trip took place, no trip setpoint was exceeded without trip signal actuation.

Document on signoff sheet 6.1 step 6.1.2.

Page 7 of 15 Rev. 0

12 PMP 4021.TRPB 001 The initial event on signoff sheet 6.1Rx is the initiating event for the reactor trip.

This could be steam generator lo-lo level or turbine trip above P-7, for example. This signoff sheet shall be completed for every reactor trip.

The initial event on signoff sheet 6.1TUR is the initiating event for the turbine trip.

This could be steam generator hi-hi level or turbine trip from reactor trip. This signoff sheet shall be completed fo every reactor trip which occurs with the turbine reset.

The initial. event on signoff 6.1GEN is the initiating event for the generator trip. This could be turbine stop valves closed and generator motoring cause overall differential trip. This signoff shall be completed for every reactor trip which occurs with the generator exciter field breaker closed.

If expected responses were not obtained or were outside the acceptable time frame, and the trip had initially, been deemed a Condition I event, then the trip no longer satisfies the criteria for a Condition I event and the

.full-length performance of this procedure is required.

NOTE: Reactor restart may not take place until the the failure is corrected failure is safety related.

if Signoff sheet 6.1 includes a signoff (signoff sheet step 6.1.3) to document SS and STA concurrence for acceptability of restart for those trips which are classified as Condition I events in section 4.0 of this procedure.

Completion of this signoff is sufficient to recommend restart of the affected unit to the Plant Manager for Condition I events.

NOTE: The Plant Manager's decision to restart is documented in OHP 4021.001.002.

Page 8 of 15 Rev. 0

12 PMP 4021.TRP.001 6.1. 7 Ifevent, I

the event is being reviewed as a Condition complete signoff sheet 6.3, Review Report cover sheet, and attach to signoff sheets completed in the it all Condition I

'event review. See Step 6.2.10 for distribution of this review package. I This concludes the Condition I trip review.

6.2 INVESTIGATION INTO THE CAUSE OF THE TRIP NOTE: Trouble shooting and diagnosis are activities which cannot be readily described in a procedure. The following steps include objectives,, authorization to obtain additional assistance, direction for putting the data in .

a form which may lead to understanding, and instructions to verify certain automatic responses not addressed in section 6.1.

Judgement is permitted in the implementation of this section. The procedural steps are to be used as a- guide. Alternate techniques may be employed to analyze the event as long as the end result is an understanding of the cause of the event, verification that required automatic responses took place, and identification of any, detrimental effects on the plant or equipment.

6.2.1 If the trip has not been classified a Condition I event, a full investigation of the situation is called for. To release the SS to fulfill his other obligations, this function will normally be carried out by the Operations Superintendent, or his designee. After addressing performance of the data gathering and "verification of response" portions of this procedure, the SS shall contact the Operations Superintendent and request that he assume responsibility for completion of the investigation. The SS may at his tion,~o perform the functions of the Operations Superintendent listed below, relinquishing the responsibility if the investigation becomes too involved or his attentions are required for other functions.

6.2.2 The purpose of the investigation is to determine the cause of the trip and assess the plant's readiness to return to power. If at any point in the investigation, the Operations Superintendent concludes that he is unable to achieve the purpose of the investigation Page 9 of 15 Rev. 0

12 PMP 4021.TRP.001 without additional technical support, he shall immediately call the department superintendent(s) who can best supply needed expertise. If he cannot reach the department superintendents, he shall call the Staff Duty Week End Supervisor. They shall ensure that appropriate support is supplied.

The Operations Superintendent, the STA, and other investigating personnel shall look beyond the obvious indications to diagnose the cause of the trip and evaluate the plant response. They shall review the available information thoroughly, looking for (1) abnormal indications or degraded trends in equipment performance, (2) events occurring out of the normal or anticipated sequence, (3) failed or degraded response of equipment to control signals, (4) unusual radiation read-ings, and (5) unanticipated alarms. The actual or suspected cause of the trip and any abnormal or degraded indication identified during the transient shall be documented in the Reactor Trip Summary, Signoff sheet 6.2 and the Reactor Trip Review Report.

The Operations Superintendent or his designee, and the STA will reconstruct the transient using the collected data. A chronological description of the event should be developed, using the Operations Sequence Monitor data as a base. Pertinent alarms, trips, actuations, and isolations will be listed. Selected plant pazameters should be incorporated into the chronological list of events in the reconstruction. Information from the Turbine Events Monitor, Unit I EHC First Hit Annunciator, Oscillograph, and the P250 Sequence of Events Record shall be used to confirm and augment the Operations Sequence Monitor information.

If the Operations Sequence Monitor is out of service, the event shall be reconstructed using other available data.

NOTE: The preparation of signoff sheets 6.1Rx, 6.1TUR, and 6.1GEN will provide much of the input for this step.

Page 10 of 15 Rev. 0

12 PMP 4021.TRP.001 Plot data from the P250 post-trip review as appropriate to evaluate the behavior of any logged parameter which initiated the trip or which was observed to exhibit unusual response.

Review signoff sheet 5.4, System Status and Response, and signoff sheets 5.5, Personnel Interview Form, for clues to the nature of the event and information that should be included in the chronological description of the event prepared in step 6.2.4.

Examine recorder charts, monitor printout, and signoff sheets 5.4 and 5.5 to verify that setpoints for the following protective features were not exceeded or that expected automatic responses occurred:

6. 2. 7. 1 Safety Injection (any automatic initiation).

6.2.7.2 Phase B containment isolation and containment spray.

,6.2.7;3 Pressurizer PORV or Safety'Valve actuat'ion.

6;2.7.4 Steam'enerator. PORV or Safety Valve actuation.

6. 2. 7. 5 Steam dump block below 541'F.

Verify that RCS temperature changes were within the cooldown limits of Tech. Specs.

3.4.9.1 and 3.4.9.2.

Document the analysis of the event by completing signof f sheet 6. 2. Completion of all signoffs for step 6.2.10.1 OR 6.2.10.2 OR 6.2.10.3 of signoff sheet 6.2 is sufficient to recommend restart of the affected unit to the plant manager.

Complete Signoff Sheet 6.3, Review Report Cover Sheet, and attach to sheets, it all signoff operator interviews, and chart and printout copies. Copies of this trip review package shall be supplied to the following:

Operations Department Technical-Engineering Department Page Rev.

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15

12 PMP 4021.TRP.001 Technical-Chemical/RP Department Managerial Department STA's PNSRC AEPSC Plant Master File (original)

AEPSC Onsite QA The original shall be maintained for the life of the plant.

NOTE: The Plant Manager's decision to restart is documented in OHP 4021.001.002.

7.0 ACCEPTANCE CRITERIA AND AUTHORITY FOR UNIT RESTART 7.1 Acceptance criteria for specific responses are included on the signoff sheets.

7.2 Event Classification and Authority for Plant Restart.

NOTE: The following classification scheme differentiates between. "minor" and "major" safety.-related equipment. The classification. is relative and no implication is intended that "minor" equipment is unimportant.

Failure of major equipment could have a substantial adverse impact on a normal plant shutdown or an accident situation. Such failures merit examination by the PNSRC prior to plant start-up. Examples: failure of an auxiliary feedpump to start when required, failure of a reactor trip breaker to open, failure of a turbine trip system to depressurize. Examples of minor equipment failures: failure of a single reactor

.trip instrumentation channel, feedwater isolation actuation slightly below spec. 553's 554'.

Whether a failure has serious safety significance shall be determined by those classifying the event.

7.2.1 Condition I The cause ofrthe trip is positively known and has been corrected; all safety-related equipment functioned properly during the trip.

If the SS satisfies and STA concur the that an event criteria for condition I, the S.S. shall have the authority to recommend restart of the affected unit to the Plant Manager.

Page 12 of 15 Rev. 0

12 PMP 4021.TRP.001 Condition II The cause of the trip is positively known and has. been corrected; some minor safety-related equipment did not function properly; however,

'the malfunction has been corrected and no Tech. Spec.

constraint prohibits start-up.

If the Operations Superintendent and STA concur that an event satisfies the criteria for Condition II, the Operations Super-intendent shall have authority to recommend restart of the affected unit to the Plant Manager.

Condition III The cause of the trip is not positively known, or some minor safety-related equipment malfunctioned and has not been repaired; or some major safety-related equipment malfunctioned during the event (whether or not, repairs have been made).

If the concur Operations'uperintendent and STA that an event. satisfies the criteria for Condition III, the affected unit shall not be restarted until the PNSRC reviews the event.

If the do not Operations Superintendent and the STA concur on event classification, the Assistant Plant Manager for Operations shall classify the event.

The PNSRC will review all reactor trips.

Condition III events shall be reviewed prior to restart of the affected unit.

The PNSRC will analyze the event reconstruction, emphasizing the determination of the cause of the trip and the resolution of abnormal or degraded indications. The PNSRC shall use available expertise to resolve auestions concerning the cause and plant response. Sources of expertise that should be considered by the PNSRC include nuclear steam supply vendors, vendor engineers, on-site engineering staff, corporate engineering staff, and other experienced operations and Page 13 of 15 Rev. 0

12 PMP 4021.TRP.001 maintenance personnel. The PNSRC shall supply the following information to the plant manager:

a) the actual or most probable cause of the trip or b) the maintenance and testing necessary before reactor restart including additional measures to verify the most probable cause c) additional monitoring or trending required during and/or after reactor restart d) .necessary briefings to operations and/or maintenance personnel concerning specific equipment indications or possible malfunctions e) the conditions necessary for a reactor restart The plant manager shall evaluate the recommendation made by the persdnnel performing the trip investigation and, if the PNSRC review. His decision to 'ecessary, restart the reactor shall include th8 following considerations:

a) . The cause of the trip is known and

, corrected.

b) Major safety-related and other important equipment functioned properly during the transient, or corrective maintenance and satisfactory test'ng has been performed or will be completed when plant conditions permit.

c) The plant response during the event has been analyzed and the plant responded as anticipated, or all abnormalities are understood and corrected as required by Technical Specifications.

If the cause of. the trip has not been positively identified, the plant manager shall determine if the cause and the circumstances surrounding the cause have been analyzed Page 14 of 15 Rev. 0

12 PMP 4021.TRP.001 adequately. He shall ensure adequate measures are taken to prevent repetitive challenges to

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safety systems during future power operations.

Page 15 of 15 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 4.1 ABBREVIATED 'II1PZEI%2ITATION OF PROCEDURE CONCURRENCE on The reactor

't trip on Unit, which occurred is classified as a Condition I event for which only data collection and verification of automatic response is required.,

S.S.

STA

(;

Page 1 of 1 Rev. 0

12 PMP 4021.TRP.001

--REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.1 RELAY TARGETS Check the relay targets on the G panel and panels A-1 through A-14 in the control room, and the relay targets in the switch gear complex. Use the attached data sheets. Place an x in the appropriate square on the data sheets to indicate actuated status.

Completed by Page 1 Rev 0 of ll

A t,' "=;;..

PAI/EL G rARGETS UNIT 1 (HAA) (HAA)

Tl T2 T3 Tl 1 T12 T13 Turbine Generator Excitation Turbine Hyd Stator Trans. 1 Valves Relays Relays Trip Cooling Sudden Soleniod Trip Pressure-T12 T15 T16 T4 T5 T6 Turbine Transformer Emerg. P.B. Trans. 1AB Trans. 1CD Trans 1 Mech. Trip Relays Trip Gen.

Sudden Sudden Tap Chgr Soleniod Panel Pressure Pressure hndl in UNIT DIFFERENTIAL (HEA) OVERALL DIFFERENTIAL'HEA) 87X-Ul 87X1-Ul 87X2-Ul 87X-OA1 87X1-OA1 87X2-OA1 UNIT 2 (HAA) (HAA)

(HAA)

T17 T18 T19 Tl T2 Tll Hain TransfHain Transf Hain Transl T12 Turbine Generator Excitation Turbine Stator Sudden Sudden Sudden - Valves Relays Relays Press. tj Press. Press, Tripping Cooling 1 9 2 9 3 (Right Sys) Trip T20 T21 T4 T5 T6 Trans. 2AB Trans 2CD Turbine fV Transformers Emerg, P.B. O R

Sudden Sudden Trippping Relays Press. Press. Trip ~(W Sj~

(Left Syst) Gen. Panel f

~O CA M

~- 8 UNIT DIFFERENTIAL (HEA) OVERALL DIFFERENTIAL- (HEA) CQ Mo 0 Q 87X-U2 87X1-U2 87X2-U2 D 87 X-OA2 87X 1 -OA2 87X2-OA2 C/l ~

O CD O CD (D et CL Ul

~ S Page 2 of 11 Rev 0

j ~ 12 PNP 4021.TRP.001 REACTOR TRIP REVIEW PRtY~WURE SIGNOFF SHEET 5.1 PANEL A RELAY TARGETS UNIT 1 A-2 A-3 A-4 52-KX 52-K1K ~

52-KlX 25P, 25TX 63X-SPl

-AUX 15 87X UOA 87Xl VOA 25 87-OA 87-OA 87-OA AUX AUX .PH. 1 PH.2 PH.3 87-Al 87-Al 87-Al 83G 839 PH.l PH.2 PH.3 25Z 25A 64-GF 64-AF 87-T 87-T 87-T PH.1 PH.2 PH.3 151X-Gls 96-GlS 151X1- 59 N 87-G 87-G 87-G I

Gls PH.1 PH.2 PH.3 151-GlS 159N Page 3 of 11 Rev. 0

t' i', 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PRESSURE SIGNOFF SHEET 5.1

'PANEL A RELAY TARGETS UNIT 1 A-8 A-7 A-6 63X- 63X- ~

SPlCD SPlAB 125A 87T-1CD 87T-1CD 87T-1CD 87T-lAB 87T-lAB 87T-lAB PH.l PH.2 PH.3 PH.1 PH.2 PH.3 51TN- 251TN- 51TN- 251TN- 27-4EPl 27-4EP3 1CD 1CD lAB lAB Page 4. o f 11 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PR~~

SIGNOFF SHEET 5.1 PANEL A RELAY TARGETS UNIT 1 A-ll A-9 51X-B7 51X-B5 27X-TllD1 63X- 27KTllD2 27XTllAl 63X- 27XT11A2 SP101CD SP101AB 51T-llA 51N- 51T-llB 51 12CD 25-TCD 27XT11D3 51 12AB 25 TAB 27XTllA3 PH.1 TllB PH.1 51T-llA-'H.3 51T-1lB PH.3 87-TCDLD PH.l PH.

2'7-TCLD 87-TCDLD PH.3 87-TABLD PH.l 87-TABLD PH.2 87-TABLD PH.3 87-DGAB 87-DGAB 87-DGAB 87T-101CD 87T-101CD 87T-101CD 87T-101AB 87T-101AB 87T-10'1AB PH.1 PH.2 PH.3 PH.1 PH.2 PH.3 PH.1 PH.2 PH.3 87T-llA 87T-11A 87T-llA PH.1 PH.2 PH.3 87T-11B 87T-llB 87T-llB 51TN- 25 ITN- 51TN- 251TN-PH.l PH.2 PH.3 101CD 101CD 101AB 101AB 51-DGAB 51N-DGAB 51-DGAB 27TllD-1 27T11D-2 27TllD-3 27TllA-1 27TllA-2 27TlkA-3 PH.1 PH.3 TR llA TR llB Page 5 of 11 Rev. 0

12 PNP 4021.TRP.001 (~.

REACTOR TRIP REVIEW PR. ri. URE SIGNOFF SHEET 5.1 PANEL A RELAY TARGETS UNIT 1 A-13 A-12 51X-C6 51X-C4 51T-11C 51N-T11C 51T-11D 87 RCP1 87 RCP1 87 RCP1 PH.1 PH.l PH.1 PH.2 PH.3 51T-11C 51T-11D 87 RCP2 87 RCP2 87 RCP2 PH.3 PH.3 PH.1 PH.2 PH.3 87-DGCD 87-DGCD 87-DGCD 87-TBMC 87-TBMC 87-TBMC PH.1 PH.2 PH.3 PH.l PH.2 PH.3 87T-11C 87T-11C 87T-11C 87-TCMC 87-TCMC 87-TCMC PH.l PH.2 PH.3 PH.l PH.2 PH.3 87T-11D 87T-llD 87T-11D 87-RCP3 '87-RCP3 87-RCP3 PH. 'I PH.2 PH.3 PH.1 PH.2 PH.3 51DGCD 51N- 51DGCD 87-RCP4 87-RCP4 87-RCP-4 PH.l DGCD PH.3 PH.1 PH.2 PH.3 TR11C TRllD Page 6 of 11 Rev. 0

jo 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PR ""-MURE SIGNOFF SHEET 5.1 PANEL A RELAY TARGETS

.UNIT 2 A-2 A-3 A-4 52-A2X 52-AlA2 52-AlX 25P 25TX 63X-SPM1 63X-SPM2 63X-SPM3

-Aux 15 r

n 25 87-OA 87-OA 87-OA PH.1 PH.2 PH.3 87-A 87-A 87-A 83 G 83B PH.1 PH.2 PH.3 25 Z 25A 64-GF 64-AF 87-T 87-T 87-T PH.l PH.2 PH.3 151X-GlS 96-Gls 151X1-Gls 59N 87-G 87-G 87-G PH.l PH.2 PH.3 151-Gl s 159N .

Identification ll

="

No Page 7 of Rev. 0

12 PNP 4021.TRP.001 REACTOR TRIP REVIEM PRt'-"MURE SIGNOFF SHEET 5.1 PANEL A RELAY TARGETS UNIT 2 A-7 A-8 A-9 63X-SPAB '63X-SPCD 63X SP201AB 125A 125A 25 TAB 87T-AB 87T-AB 87T-AB 87T-CD 87T-CD 87T-CD 87T-201AB 87T-201AB 87T-201AB PH.1 PH.2 PH.3 PH.1 PH.2 PH.3 PH.1 PH.2 PH.3 51TN-AB 251TN 51TN-CD 251TN 51TN- 251TN

-AB CD 201AB 201AB 27-T21A 27-T21A 27-T21A PH.1 PH.2 PH.3 Page 8 Rev. 0 of ll

~r.w>

j 0 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PRM>>=

SIGNOFF SHEET 5.1 PANEL A BELAY TARGETS UNIT 2 A-10 A-ll A-12 63X- 51X-87 51X-85 SP201CD

/

25-TCD 51T-21A 51N-T218 51T-218 87-RCPl 87-RCPl 87"RCP1 PH.1 PH.1 PH.l PH.2 PH.2 51T-21A 51T-218 87-RCP2 87-RCP2 87-RCP2 PII. 3 PH.3 P1I; 1 PH.2 PH.3 87,-9GAB 87-DGAB 87-DGAB 87-TBMC 87-TBMC 87-TBMC PH.l PH.2 PH.3 PH.1 PH.2 PH.3 87T-201CD 87T-201CD 87T-201CD 87T-21A 87T-21A . 87T-21A 87-TCMC 87-TCMC '7-TCMC PII. 1 PH.2 PH.3 PH.l PH.2 PH.3 PH.1 PH.2 PH.3 51TN- 251TN- 87T218 87T218 87T218 87-RCP3 87-RCP3 87-RCP3 201CD 201CD PH.1 PH.2 PH.3 PH.l PH.2 PH.3 27-T219 27-T21D 27-T21D 51DGAB 51NDGAB 51DGAB 87-RCP4 87-RCP4 87-RCP4 PII. 1 PII. 2 PH.3 PH.1 PH.3 PH.1 PH.2 PH.3 TR-21A TR-218 Page 9 of 11 Rev. 0

i 12 PMP 4021.TRP.001 TRIP REVIEN SIGNOFF SHEET 5.1 PR~

f'+'EACTOR ORE PANEL A RELAY TARGETS UNIT 2 A-13 51X-C6 51T-21C 51NT-21C 51T-219 PH.l PH.1 51T-21C 51T-21D PH.3 PH.3 87-DGCD 87-DGCD 87-DGCD PH.l PH.2 PH.3 87T-21C 87T-21C 87T-21C PH.1 PH.2 PH.3 87T-219 87T-21D 87T-21D PH.1 PH.2 PH.3 51-DGCD 51-DGCD 51-DGCD PH.l PH.2 PH.3 TR-21C TR-219 Page 10 o Rev. 0 f 11

12 PMP 4021. TRP.001 REACTOR TRIP REVIEW P ~~URE SIGNOFF SHEET 5.1 SWITCIIGEAR COHPLEX RELAY TARGETS UNIT.

TlkfE DATE PERFOBKD BY:

RC Pum Bus and T-bus 4KV Switch ear:

I,ist all relay targets actuated.

(llGPll IIOTll etc )

Specify "1", "3", or "N". where applicable. Note alarm lights lit Reset Breaker Instrument No. Name Attempted Successful "

600 V Safet Bus Switch ear List all relay targets actuated. Include relays on back of'breaker panels (feeder relays).

Reset Instrument No. Name Attempted. Successful Page Rev.

ll of ll 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGN OFF SHEET 5.2 Ul EHC FIRST, HIT MNUNCIATOR For a Unit I reactor trip which occurred with the turbine reset, check the first hit annunciator in the EHC control cabinet. Use the attached data sheet.

Place x in the appropriate square on the data sheet to indicate actuated status.

Page 1 of 2 Rev. 0

12;PHP 4021. TRP.+~

REACTOR TRIP REVT~ROCEDURE SIGN OFF SHEET 5.2 UNIT I EHC I'IRST HIT ANNUNCIATOR I I I

ERST HIT PS 100 CUST. NO EHC DC FIRST P ONER/LOAD -22VDC !

I ARB TRIP INPUT HIT .UNBALANCE 'I.OST i

POWER I SPD SIG HA TRIP BACKUP PAST CLST +30VDC S RESET LOST BUS OVERSPEFD RESET IV'S I,OST ENERGIZER TRIP Page 2 of 2 Rev. 0

12 PMP 4021.TRPB 001 REACTOR TRIP REVIEW'ROCEDURE SIGNOFF SHEET 5.3 RECORDER CHART AND MONITOR PRINTOUT DATA NOTE: Except as a general guide to chart and printout retrieval methods this signoff sheet is not applicable to abbreviated reviews of Condition I events.

5.'3. 1 Step 5.3.5 of this signoff sheet is a list of plant recorder chart data which must be copied and retained in conjunction with a reactor trip analysis. The list includes a column labeled "Requirement". The codes in this column indicate the circumstances which require obtaining the indicated data. These codes are:

All all reactor trips Reset turbine reset Rolled turbine rolled off turning gear Turbine turbine initiated events except. steam generator hi-hi level during startup Exciter exciter field breaker closed Generator generator initiated event Vacuum vacuum initiated event FPT feed pump turbine initiated events SI events associated with SI Judge based on SS or STA judgement 5.5 when required by procedure step 5.5 5.3.2 The list below also includes a column labeled "Copy". A C in this column indicates the recorder chart is to be copied. An 0 in this column indicates the original data is to be attached to the trip review package. An 0 will be found next to data from equipment which is dedicated to monitoring reactor trips.

5.3.3 Cut out and remove portions of the listed charts and printouts extending from before the initiation of the transient until after conditions have stabilized.

Judgement must be utilized to ensure that all data which may lead to an understanding of the cause of the event is included. Two to four hours of data before the event shall be included for slow moving (~l"/hour) control room charts. For the OSM, P250 TREND (Post Trip Review), and P250 Alarms (Sequence of Events) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of data prior to the event shall be included.

When a strip chart is cut for copying, label with Page 1 of 4 Rev. 0

12 PMP,4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.3 recorder number and function for ease of replacement and later analysis. For multipen recorders each trace must be clearly labeled. Be certain to include the time labels and marks made in accordance with procedure step 5.3. After copying, restore these chart and printout segments to their original positions by taping. Ensure proper functioning of the recorders.

5.3.4 For those recorders whose input channels can be selected, ensure that channel selection is identified on the chart. If selection was changed during the transient, identify this on the chart.

5.3 ' Chart Recorder Data to be copied/collected'ecorder Chart Sicinof f Pressurizer pressure chart All Pressurizer level chart All NI recorder NR045 chart All bT chart All Tref-Tavg chart All Steam generator 1'evel/flow All charts (4)

Main Steam/First Stage All Pressure Chart P250 sequence of events printout All (Alarm typewriter)

P250 Post-trip review printout All (Trend typewriter)

Operation sequence monitor All printout Turbine events monitor chart Reset BBC turbine events monitor chart Reset (U2 only)

Oscillograph chart Exciter Generator Voltage and Exciter I

reactance chart

~

j Page 2 of 4 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.3 Valve position and turbine Rolled speed chart (Ul)

Vibration and turbine Rolled speed chart (U2)

Generator frequency chart Exciter (if selected to generator)

Main Vacuum Chart Vacuum FPT Steam/Backpressure Chart Vacuum Supervisory Charts I'urbine Turbine Ul: bearing temperature vibration .

metal temperature shell, rotor expansion U2: bearing temperature vibration, eccentricity, speed metal temperatures FPT Vibration Chart FPT FPT Bearing Temperature Chart FPT Feedpump Suction and Discharge Pressure Chart FPT Wide Range Thot and SI Tcold charts (4)

Wide Range RCS Pressure Chart, SI Containment Pressure Chart SI Computer Analog Trend Charts (2) Judge Computer Alarm Printout Judge RMS 10 minute averages 5.5 5.3. 6 Obtain a copy of control room log to include one full shift of entries prior to the event.

Page 3 of 4 Rev. 0

{'l'kdJC~LL44 'A~ah' ~4 k% ~~4J4Ak4 c 'k4JLaG'JL4LMI '~~Wdw DA 'w "IIVX'~blQl4<<S M lg'~ <<'Aa/'4 ~AHAtrw V a aA AV/pl L l

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE, SIGNOFF SHEET 5.3 In addition to those listed above, obtain copies of any recorder charts which are known to apply to the specific transient Include with any additional charts all information necessary for interpretation of these charts, such as chart speed (if variable), channel selected, bank number, etc.

Additional charts copied: Comments:

(u PERFORMED BY e

Page 4 of 4 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 SYSTEM STATUS AND RESPONSE Nuclear Instrumentation 5.4.1.1 List all NI drawer "negative rate" trip status lights which are energized.

5.4.1.2 Source Range instrument power restored automatically as designed (both channels) 5.4.1.3 Major equipment out of service:

5.4.1.4 Describe any abnormal conditions (such as

'loss of detector voltage'r 'channel on test') or behavior noticed during the transient.

5.4.2 Reactor Coolant Pum s 5.4.2.1 Describe circumstances, including place in sequence of events, of any RCP trips (manual or automatic) which occurred during the transient.

5.4.2.2 Describe effect of reactor transient on leakoff flows.

5.4.2.3 Describe any behavioral abnormalities noticed during the transient.

Page 1 of 10 Rev. 0

0 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 RCS Pressure Control 5.4.3.1 Control status prior to trip (man/auto) 5.4.3.2 Backup heaters "on" banks "auto" banks 5.4.3.3 Pressure channels selected (control/bistables) 5.4.3.4 Pressurizer PORV's blocked prior to transient:

5.4.3.5 ~

Spray valves in "auto" 5.4.3.6 Did pressurizer PORV's or safeties during transient? Describe circumstances.

lift 5.4.3.7 Major equipment; out of service:

5.4.3.8 Describe any behavioral 'abnormalities noticed during the transient Pressurizer Level Control 5.4.4.1 Control Status prior to trip (man/auto) 5.4.4.2 Charging pump in service 5.4.4.3 Charging flow controller (QRV-251 or Recip speed controller) status prior to trip'man/auto) 5.4.4.4 Level channels selected (control/bistables) 5.4.4.5 Describe any behavioral abnormalities noticed during the transient.

Page 2 of 10 Rev. 0

y~~Q+t~I'i~A> ~e. wg~iiK~gMi'~+'++~++6~i)i "+C6fg+~~~~~~~piwg jg Q+ a~ypg <<r>g~ici4>g>> '<~J5g~g~-,f~ j ..~ '~ypgj~~s/~@. ~Ks 0AOAiM~

i 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 5.4.5 CVCS Makeu 5.4.5.1 Prior to transient, blender line contained (acid, pri. water, blend) 5.4.5.2 Makeup in auto with 'start'ignal?

(yes/no) 5.4.6 Control and Shutdown Rods 5.4.6.1 Pull insertion of all control and shutdown rods verified.

Rods thai: did not insert:

5.4.6.2 Rod control status prior to trip (auto/man) 5.4.6.3 Was the rod contzol statuq changed during the transient?

events?

If so, when in the sequence of 5.4.6.4 Major equipment out of'service:

5.4.6,5 Describe any behavioral abnormalities noticed during the transient.

5.4.7 Main Feedwater Steam Generator Ievel 5.4.7.1 Operating main feed pumps tripped on reactor trip (yes/no/OOS)

EMPP Page 3 of 10 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE'IGNOFF SHEET isolation received 5.4'.4.7.2 Feed water when Tavg

<554'F. Valves closed (yes/no)

FRV210 FRV220 FRV230 FRV240 FM0201 FM0202 FNO203 FMO204 5.4:7.'3 Feedpump control status prior to trip (auto/man)

East feedpump speed control West feedpump speed control DP controller 5.4.7.4 Feedpump steam supply prior to trip East feedpump (reheat/main/aux)

.West feedpump (reheat/main/aux) 5.4.7.5 Feedwater regulating valve status prior to trip (auto/man)

FRV210 FRV220 FRV230 FRV240 5.4.7.6 Condensate bypass valve status prior to trip (auto/man)

CRV224 5.4.7.7 Feedwater Heater level controls in manual prior to trip:

5.4.7.8 Major equipment out of service:

Page 4 of 10 Rev. 0

0 12 PMP 4021.TRP.001 REACTOR TRIP REVIE

W. PROCEDURE

SIGNOFF SHEET 5.4 5.4.7..9 Describe any behavioral abnormalities noticed during the transient.

Auziliary Feedwater 5.4.8.1 MDAFP's started automatically on trip of main feedpumps EMDAFP WMDAFP 5.4.8.2 TDAFP operated? Describe circumstances and approzimate duration of operation.

5.4.8.3 Did operator intervene in the response

'(manually adjust or trip)?

the sequence of events?

IfTDAFP so, when in 5.4.8.4 Major equipment, out of service:

5.4.8.5 Describe any behavioral abnormalities noticed during the transient.

Steam Dum Steam Generator Pressure Relief 5.4.9.1 Control status prior to trip (Tavg/Steam Pressure/Off) 5.4.9.2 If in Tavg to maintain mode, steam dump valves modulated

~547.

Tavg (yes/no) 5.4.9.3 If Tavg dropped below 541'F, steam dump blocked (yes/no)

Page 5 of 10 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 5.4.9.4 'Did steam open prior to trip (yes/no)? If yesvalvedescribe.

dump II 5.4.9.5 If vacuum trip, closed (yes/no)?

did steam dump valves stay 5.4.9.6 Control status of atmospheric steam dumps prior to trip (auto/manual)

MRV213 MRV223 MRV233 MRV243 5.4.9.7 Did atmospheric steam dumps operate during transient (yes/no)? If yes, describe (automatically, manually, circumstances).

5.4.9.8 Was the control status of atmospheric steam dumps changed during the course of the transient?

events?

If so, when in the sequence of 5.4.9.9 Did steam generator safeties transient (yes/no)? If lift yes describe.

during 5.4.9.10 Major equipment out of service.

5.4.9.11 Describe any other behavioral abnormalities noticed during transient.

Page 6 of 10 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 5.4.10 Main Turbine SR 5.4.10.1 Was there a turbine runback (yes/no),?

5.4.10.2 If yes, provide best estimate of power change and the time in sequence of events when it occurred.

5.4.10.3 Did the operator intervene in the turbine runback?

events?

If so, when in the sequence of 5.4.10.4 Turbine trip: Main turbine stop, reheat stop, control, and intercept valves closed e, 5.4.10.5 Controlling device prior to trip (load, limit'er/operating'evice/load changer/turbomat)

'L 5.4.10.6 Set rates loading unloading 5.4.10.7 Were valve or misc turbine tests in progress when the trip occurred?

Which one?

5.4.10.8 Did exhaust hood sprays actuate (yes/no)?

5.4.10.9 Vacuum breakers opened following trip?

(yes/no) 5.4.10.10 'Hogging'JAE's in service following trip?

(yes/no)

Page 7 of 10 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEN PROCEDURE SIGNOFF SHEET 5.4 5.4.10.11 MSR in service prior to trip?

(no/partial/full) 5.4.10.12 Did any MSR safety valves transient (yes/no/identify)?

lift during the 5.4.10.13 Major equipment out of service:

5.4.10.14 Describe any behavioral abnormalities noticed during the transient.

Generator/Electrical 5.4.11.1 Generator trip. This will occur seconds after the reactor trip unless a generator event.

it 30results from output breakers open (yes/no)

K or Al Kl or A2 Exciter breaker open (yes/no) 5.4.11.2 If auxiliaries were were suppled by auxiliaries automatically the generator, transferred to normal reserve (yes/no/NA)? Describe any failures.

5.4.11.3 Diesel generators operated?

Describe curcumstances.

Page 8 of 10 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 5.4.11.4 Any GRID or CRP bus switched to alternate supply? Describe circumstances.

\

5.4.11.5 Major equipment out of service:

5.4.11.6 Describe any behavioral abnormalities noticed

.during transient.

5.4.12 Safet In'ection 5.4.12.1 Was the event associated with an SI (yes/no)?

5.4.12.2 If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?

5.4.12.3 If yes, if list actuations not received, reason known, and whether the response was successfully initiated manually.

5.4.12.4 List major equipment out of service.

5.4.12.5 Describe any abnormalities noticed 'in the response of the safety injection system.

Page 9 of 10 Rev. 0

12 PMP 4021.TRP.001'EACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.4 5.4.13 Phase B 5.4.13.1 Was there a phase B/CTS actuation (yes/no)?

5.4.13.2 If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?

5.4.13.3 If yes, if list actuations not received, reason known, and whether the response was successfully initiated manually.

5.4.13.4 List major equipment out of service.

5.4.13.5 Describe any abnormalities noticed in the response of the CTS System.

5.4.14 Miscellaneous 5.4.14.1 List any major plant equipment. not covered above which is out of service and could have had an effect on the progression of the transient.

5.4.14.2 Describe any behavioral abnormalities of systems not covered above which may affect plant safety.

COMPLETED BY Page 10 of 10 Rev. 0

12 PNP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.5 PERSONNEL INTERVIEW FORMi 5.5.1 Person interviewed 5.5.2 Role in event 5'. 5.3 Interview by 5.5.4 Description of the event:

Include the plant conditions prior to the trip, your indications that a problem existed, your action as a result of those indications, noted equipment malfunctions or inadequacies, and any identified procedure deficiencies.

5.5.5 .Sequence of events and actions taken:

Page 1 of 2 Rev. 0

12 PNP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5.5 Apparent cause of the event:

Include description of any related activity in progress when the event occurred and any underlying or contributory factors.

Additional comments including any unexpected aspect of transient behavior:

Page 2 of 2 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1 VERIFICATION OF AUTOMATIC RESPONSE 6.1.1 This signoff sheet. uses forms 6.1RX, 6.1TUR, 6.1GEN for reactor trip, turbine trip, and generator trip, respectively. Column 1 lists the expected response starting with the initiating event. Column 2 will either indicate obsv. or meas. The former means the response is to be assessed as yes or no based on operator observation. Meas means the time from the initiating event to that expected response is to be

,measured on a monitoring device such as the OSM, TEM, Oscillograph, or P250 Sequence of Events Recorder. The OSM will be considered the primary device and the quantit'ative acceptance criteria is based on OSM data.

Column 3 will indicate whether the expe'cted response should always be present or whether it may only be present under certain circumstances. For example, an Auxiliary Feed pump start will not be present if the steam generators are being fed from Auxiliary Feed pumps prior to the trip. Column 4 will be used to indicate the time from the initiating event, to the expected event or a yes no entryyfor an operator observation. Column 5 will contain acceptance criteria.

The procedure specifies when each signoff'sheet must be used.

6.1.2 Procedure step 6.1.1 has been completed.

p Page 1 of 9 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1 6.1.2.1 As closely as can be determined, the reactor trip initiating signal occurred at the proper value of the deviant parameter.

6.1.2.2 While the events leading to the trip took place, no trip setpoint was exceeded without trip signal actuation.

Page 2 of 9 Rev. 0

PMP 4021.TRP.001 ACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1RX REACTOR TRIP EXPECTED RESPONSE (Ul)

Acceptance Ex ected Res onse Data T e Re irement Time Criteria Initial Event. Neas All 0 0 Reactor Tri Breaker A Meas- All Reactor Tri Breaker B 'eas All Reactor Tri Breaker Undervolta e coil A Meas All Reactor Tri Breaker Undervolta e coil B Neas All Control Rods Bottom Obsv All Yes Mechnical Tri 0 crated Turb Obsv All WNFPT Vacuum Tri Obsv MMFPT Vac Tri Reset EMFPT Vacuum Tri Obsv EMFPT Vac Tri Reset MNFPT H dr Pr Low WMFPT Reset Gbsv'bsv EMFPT H dr Pr Low ENFPT Reset.

Feedwater Isolation Obsv On Main Feed Yes MNDAFP Start Obsv. On Main Feed, Aux feed on standb Yes ENDAFP Start Obsv On Maxn Feed, Aux feed on standb Yes TDAFP Start Obsv On Maxn Feed, Aux Yes feed on standby Ifsignal start re ired

~To Be Prepared Page 3 of 9 Rev. 0.

(.0 .;:;"'~ PMP 4021. TRP.001

'-'"",.-.KACTOR TRIP REVIEN PROCEDURE SIGNOPF SHEET 6.1TUR TURBINE TRIP EXPECTED RESPONSE (Ul)

Acceptance Ex ected Res onse Dakota T e Re irement. Time Criteria Initial Event 0 0 RT-Turbine Tri + P7 Meas. Turbine Reset 8 above P-7 Mech Tri 0 er Meas Turbine Reset Emer Gov OVSP Tri Seas. Turb Reset.

MT Reheat VA CL Neas Turb Reset MT Sto VA CL Meas Turb Reset Overall Diff 0 er Meas Turb Reset EHC Tri S s Tri Neas Turb Reset DC BRG Oil PP Run Neas Turb Reset TRB Oil Bu Run Meas Turb Reset STM Seal PR Low Neas Turb Reset STM Dum Actuation Obsv Tav Mode Yes "To Be Prepared Page 4 of 9 Rev. 0

(.0 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1GEN GENERATOR TRIP EXPECTED RESPONSE (Ul)

Acceptance Ex ected Res onse Data T e . Re uirement Time Criteria Initial Event Neas Generator Exciter o Nech Tri 0 er Generator Exciter Overall Diff 0 er Neas Generator Exciter Alterx Diff er Meas Generator Exciter Generat Notorin Neas Generator =Exciter Unit S s Fre Hi Lo Nhas Generator Exciter Gen Cool Flow Lo Meas Generator Exciter Gen Cool Tri 0 er Meas Generator Exciter Trans To Normal Reserve Obsv Gen Su lies Auxiliaries Yes Generator Field Brk. 0 en Obsv Field Brk Closed Yes Generator Out ut Brk 0 en Obsv Paralleled. Yes Diesel Generator AB Start Meas Blackout SI Diesel Generator CD Start Meas Blackout SI

" To Be Prepared Page 5 of 9 Rev. 0

( (;0 12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1RX REACTOR TRIP EXPECTED RESPONSE (U2)

L Ex ected Res onse Data T e Re irement Time Criteria Initial Event Meas All 0 0 Reactor Tri Breaker A 'Meas All Reactor Tri Breaker B Meas All Reactor Tri Breaker Undervolta e coil A Meas All Reactor Tri Breaker Undervolta e coil B Meas All Control Rods Bottom Obsv Main Turbine Left S stem Tri Neas All Main Turbine Ri ht. S stem Tri Meas All WMFPT Vacuum Tri Neas WMFPT Vac Tri Reset EMFPT Vacuum Tri Neas EMFPT Vac Tri Reset.

WNFPT Emer enc S stem Tri Neas WNFPT Reset EMFPT Emer enc S stem Tri Meas ENFPT Reset Feedwater Isolation <554'F Obsv On Main Feed WbH)AFP Start Gbsv On Main Feed, Aux EMDAFP Start Obsy On Mazn Feed,standby'es feed on standb feed on standb Aux Yes TDAFP Start Obsv On Nazn Feed, Aux Yes feed on Ifsignal start re ired

To Be Prepared Page 6 of 9 Rev. 0

j ~ 12 PNP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1TUR TURBINE TRIP EXPECTED RESPONSE (U2)

Acceptance-Ex ected Res onse Data T e Re irement. Time Criteria Initial Event Neas Turb Reset. 0 0 Main Turbine Left S stem Tri Neas Turb Reset Main Turbine Ri ht S stem Tri Neas Turb Reset Left Emer enc Circuit Tri <8.5 si Meas Turb Reset Ri ht Emer enc Circuit Tri <8.5 si . Meas Turb Reset.

Control Fluid Safet, Circuit Tri Neas Turb Reset Auxilliar Lube Oil Pum Meas Turb Reset Nest Emer enc Lube Oil Pum Meas Turb Reset East Emer enc Lube Oil Pum Neas Turb Reset Main Turbine Sto Valves Closed Neas Turb Reset, Main Turbine Interce t Valves Closed Neas Turb Reset Reactor Tri from Turbine Tri 'eas Above P-7 Overall Differential Generator Trip from Turbine Sto Valves Closed Meas Turb Reset Steam Dum Actuation Obs Tav Mode Yes

To Be Prepared Page 7 of 9 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1GEN GENERATOR TRIP EXPECTED RESPONSE (U2)

. Acceptance Ex ected Res onse Data T e Re irement, Time Criteria Initial Event Meas Generator Exciter 0 0 Nain Turbine Left S stem Tri Meas Generator Exciter Nain Tubine Ri ht S stem Tri Meas Generator Exciter Transfer to Normal Reserve Obs Gen Su lies Auxiliaries Yes Generator Field Breakers 0 en Obs Field Breaker Closed Yes Generator Out ut Breakers 0 en Obs Paralleled Yes Diesel Generator AB Start Neas Blackout SI Diesel Generator CD Start Meas Blackout SI

To Be Prepared Page 8 of 9 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.1 This signoff is to be used only for events classified as Condition I in section 4.0. This classification is documented in signoff sheet 4.1.

Automatic responses to the reactor trip on Unit which occurred on at have been 'reviewed. This review determined that reactor restart is. acceptable.

SS STA Page 9 of 9 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.2 REACTOR TRIP

SUMMARY

6.2.1 Trip: time date Unit 6.2.2 Plant status prior to trip (power level, load changes in progress, startup, etc).

6.2.3 Shift .crew (affected unit)

S.S.

Asst. S.S.

U.F.

Control room R.O.

S.T.A.

6.2.4 Data collected as required by the plant configuration.

Signoff Sheet 5.1 Signoff Sheet 5.2 Signoff Sheet 5.3 Signoff Sheet 5.4 Signoff Sheet 5.5 6.2.5 Verification of expected responses using signoff sheet 6.1 complete.

Expected response occurred OR Failure of expected response.

Describe the nature of the failure and corrective action taken.

NOTE: Reactor restart may not take place until the failure .is corrected if the failure is safety

..related. Reactor restart may not take place without the approval of the Operations Superintendent and the Plant Manager failure is non-safety related.

if the

Description:

) Failure corrected Page 1 of 4 Rev. 0

12 PMP 4021.TRPB 001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.2 Approval to restart with non-safety related failure Operations Superintendent P ant Manager 6.2.6 , Verification of protective features (procedure step

6. 2. 7. ) complete Expected response occurred OR Failure of expected response Describe the nature of the failure and corrective action taken.

NOTE: Reactor restart may not take place until. the failure is corrected

Description:

Failure corrected 6.2. 8 Verification of cooldown limits (procedure step 6.2.8) complete.

6.2. 9 Analysis of reactor trip.

6. 2. 9. 1 Describe the immediate (trip signal) and the root causes of the event.

6.2.9.2 Describe factors contributing to the trip or the initiation of the transient which resulted

,i in the trip.

Page 2 of 4 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 6.2 6.2.9.3 Describe events subsequent to the trip until the plant was placed in a safe condition.

6.2.9.4 Describe any damage to the plant that resulted from the trip.

6.2.9.5 Describe any abnormalities associated with the trip or the unit response to the trip that have not been previously addressed.

(g 6.2.10 Event Classification 6.2.10.1 The event is reclassified a condition I event OPS SUP STA OR 6.2.10.2.a The event is classified a condition II event OPS SUP STA AND Page 3 of 4 Rev. 0

12 PMP 4021.TRP.001 REACTOR TRIP REVIEN PROCEZfURE SIGNOFF SHEET 6.2 6.2.10.2.b All condition Reports associated with the event are closed.

PNSRC 6.2.10.2.c The Operations Superintendent concurs that a recommendation to restart the affected unit be made to the Plant Manager.

OPS SUP OR 6.2.10.3.a The event is classified a condition III event.

OPS SUP STA 6.2.10.3.b All Condition Reports associated with the event are closed.

PNSRC 6.2.10.3.c The PNSRC concurs that a recommendation to restart the affected unit be made to the Plant Manager PNSRC 6.2.10.4 Comple'tion of all signoffs for step 6.2.10.1 or

6. 2. 10. 2 or 6.2. 10. 3 is suf ficient to recommend restart of the affected unit to the Plant Manager.

NOTE: The Plant Manager's decision to restart is documented in OHP 4021.001.002 Page 4 of 4 Rev. 0

12 PMP 4021;TRP.001 REACTOR TRIP REVIEW PROCEDURE REVIEW REPORT COVER SHEET 6.3 D. C. COOK PLANT Q REACTOR TRIP REVIEW REPORT AFFECTED UNIT EVENT DATE EVENT TINE

,0)'

f TRIP REVIEW PERFORMED BY Page 1 of 1 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A I

APPENDIX A: Miscellaneous Information Relatin to the 0 eration of Tri Monitorin Devices.

Page 1 of 40 Rev. 0

,12 PMP 4021.TRP.001 APPENDIX A I. HATHANAY OPERATIONS SEQUENCE MONITOR The sequence monitor provides a printed record of the operation of certain selected events. It has the capacity to monitor 192 on-off points and produces a line item output on a printer located in the control room when any one of the monitored points indicates an abnormal condition. Forty five points are used to monitor events related to reactor trip initiation or reactor trip circuit breaker position, 6 points monitor condensate or hotwell pumps, 13 points monitor feedwater heater extreme high level events, 6 points monitor onsite power diesel generators, 22 points monitor the main feedwater pumps, 40 points monitor the main turbine-generator, and 8 points monitor the step-up and auziliary transformers and miscellaneous items.

The operations sequence monitor permits discrimination for contact closures which occur more than 2 milliseconds apart.

A contact closure will result in a line item printout, on a dedicated printer located in the control room. The line item contains a 3 digit number for the day of the year, a 4 digit number for the hours a minute, a 2 digit number for the second, a 3 digit number for the milliseconds, an "A" indicating an off normal condition, a 3 digit number to identify the event to the operator. A sample output is attached to the end of this section.

The following information elaborates on the meaning of particular alarms that commonly appear as a result of reactor trips.

Page 2 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A A.

UNIT I QO:

019 Reactor Trip, S.G. Lo Lo Mater Level, Loop 4.

This alarm is a typical example of a signal from the RPS initiating a trip.

044 Reactor Trip Breaker Tripped, Train A.

This alarm originates from breaker position limit switches. It indicates the breaker is actually open.

046 Reactor Breaker Undervoltage, Train A.

This alarm indicates the undervoltage trip attachments have operated. They report, late in spite of the fact UVTA's actuate the trip breakers for reactor trips other than manual trips. This situation results from the fact that the auxiliary relay the reports the event is part of an RL circuit. The delay is -200 msec.

U 112 NNFP Vaccuum Trip As indicated on elementary, Dia 1-98212-5 coordinate H-3, this alarm indicates a vacuum trip has occurred.

1118 WMFP HYDR. Press Low.

This alarm results when the MFP Hydr. Oil pressure reaches 130 psi dec.

140 Mechanical Trip Operated.

This alarm indicates a turbine trip has been initiated. As indicated on elementary diagram 1-98101, the following trip signals will initiate this alarm:

1) Overall differential

2) Unit differential Page 3 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A

3) Thrust, bearing wear & low bearing oil trip

4) MSR level

5) Turbine high vibration trip

6) Turbine solenoid trip

7) Loss of stator cooling turbine trip

8) Turbine low vacuum trip

9) EHC low hydraulic press trip

10) EHC trip system press trip ll) Turbine shaft P.P. low oil press trip

12) EHC master trip

13) Rx trip train A + SG HI HI or S.I.

156 Generator Motoring As indicated on elementary Dia 1-98021-2 coordinates C1, this alarm results from: (All valves closed or control valves at no load position) and (generator output breakers closed).

UNIT II 019 Reactor Trip, S.G. Lo Lo Water Level, Loop 4 This alarm is a typical example of a signal from the RPS initiating a trip.

044 Reactor Trip Breaker Tripped, Train A This alarm originates from breaker position limit switches. It indicates the breaker is actually open.

(verbal comment by T. King) 046 Reactor Breaker Undervoltage, Train A Page 4 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A This alarm indicates the undervoltage trip attachments (UVTA's) have operated. They report late in spite of the fact UVTA's actuate the trip breakers for reactor trips other than manual trips. This situation E

results from the fact that the auxiliary relay that reports the event is part of an RL circuit. The delay is typically -200 msec. 131 Main Turbine Left System Trip This alarm indicates a turbine trip h'as been initiated. As indicated on Elementary Diagram 2-98101, coordinate D-2, the following trip signals will initiate this alarm:

1) Turbine solenoid trip. control switch

2) Unit overall differential

3) Transformer and generator unit differential

4) Thrust bearing position trip

5) Moisture separator reheater high level trip

6) Turbine vibration

7) Lube oil pressure low

8) Loss of stator cooling

9) Reactor trip, SI, or steam generator hi-hi

10) Turbine low vacuum trip ll) High exhaust hood temperature Page 5 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A 137 Main Turbine Control Fluid Safety Circuit Tripp'ed As. indicated on Elementary Diagram 2-98101, i

coordinate Hl, this signal results from pressure switch 63X TSP indicating low pressure in the safety fluid circuit. It is operated by pressure switch 2515 on the Turbine Control Diagram, Figure PGS-4B-11 in the training manuals.

151 Left Emergency Circuit Tripped As indicated on Elementary Diagram 2-98102, coordinate D-7, this alarm results from pressure switch 63 ECL indicating that emergency circuit pressure dropped below 8.5 psig. It is operated by pressure switch 4591 on the Turbine Control Diagram, Figure

~

PGS-4B-ll in the training manual.

NOTE: 63 indicates a pressure switch on an elementary diagram.

158 Generator Motoring As indicated on Elementary Diagram 2-98021-2, coordinates D2, this alarm results from: (all valves closed OR control valves at no load position) AND (generator output breakers closed.)

165 Turbine valve Trip overall Differential As indicated on Elementary Diagram 2-98021-2, this signal results from a trip of the unit overall differ-ential by turbine valves closed and required delays.

ill FPTW Vacuum Trip Page 6 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A

's indicated on Elementary, Diagram 98217-3, coordinate D-4, this alarm indicates a vacuum trip has occurred. It is operated by limit switch 33X BVTW on a mechanical linkage. This mechanical linkage is operated by all trips (verbal coment by T. King) and is expected for FPT trips initiated with the vacuum trip reset.

114 FPTW Emergency System Trip As indicated on Elementary Diagram 2-98217, coordinate H-3, this signal results from pressure switch 63X BESTW indicating low pressure in the emergency circuit.'OTE:

33 indicates a limit switch on an elementary diagram.

NOTE: 63 indi.cates a pressure switch on an elementary diagram.

Page 7 of 40 Rev. 0

~ ~

12 PMP 4021.TRP.001 APPENDIX A SAMPLE OSM OUTPUT Page 8 of 40 Rev. 0

826 1639 99 481 7 898 DCCOOK 2 T'ST PT 8'26 1738 98 488 T 988 DCCOO)C 2 TEST PT 826 1638 98 498 7 888 DCCOOK 2 TEST 1 7 826 1938 88 481 7 888 DCCOOK 2 TEST PT 826 2838 98'81 T 888 DCCOO)< 2 TEST PT 826 2138 88 481 7 988 DCCOOK 2 TEST PT 826 2215 86 218 A 856 DG2AB.HEA OPEP.

826 2226 83 828 A 868 DG 2AB START 826 2238 88 481 T 889 DCCOO)< 2 TEST PT 826 2339 98 488 T 898 DCCOOK 2 T ST PT 827 8839 88 488 T 888 DCCOOK 2 TEST PT 827 8139 98 481 T 888 DCCOOK,2 TEST PT 827 8239 88 481 827 8338 88 481 T 889 DCCOOK 2 TEST PT T 898 DCCOOK 2 TEST PT ~q P 8 27 8358 53 185 827 8424 56 962 A 875 HTF. I.C LEVEL HI A 149 MT VAC TFI P BLOCKED zg 827 8424 59 819 A 149 MT VAC TRIP BLOCKED 827 8425 23 387 A 15S GENERAT MOTOPING 827 8425 25 126 A 819 RT LP3FDVT FL LO 827 8425 25 217 A- 845 REACT B)<P. TP.I P B 827 8425 25 237 A 844 FEACT BKR TRI P A 827 8425 25 261 A 131 MT L SYSTEM TRI P 827 8425 25 262 A 132 MT R SYSTEM TF.IP 827 9425 25 436 A 886 RT LP I FDi).'7 FL LO 827 8425 25 461 A 151 LEFT Et~ERG CKT TP.I P 827 9425 25 463 A 986 PT TURB TP.I P 6 P7 827 8425 25 469 827 9425 25 535 A lll A 999 FPT(1 VACUUM TRIP VACUUM TR I P 'PTE 827 8425 25 618 A 829 F.T PI'1F.G PNRATE TR 827 8425 25 635 A 946 REACT BKR UV A 827 8425 25 639 A 847 FEACT BKR U'J B 827 8425 25 654 A 818 RT LP3FDir'7 FL LO 827 9425 25 656 A 137 MT CONFL. SAFC)<T TR, 827, 8425 26 224 A 182 FPTE Ei~:ERG SYS TR 827 8425 26 242 A 875 HTR I C LE'1EL HI 827 8425 26 296 A 182 FPTE EiMERG SYS TR 827 9425 26 669 A 114 FPTV EMERG SYS TR 827 9425 27 468 A 816 RT SG I LEV EX LO 927 8425 27 756 A 816 RT SG I LE'J E)< LO 927 8425 27 694 A 8IS RT SG 3 LE'J EX LO 827 8425 26 869 A 917 PT SG 2 LEV EX LG 927 9425 26 595 A 899 PT LP2FDVT FL LO 827 9425 26 644 A 816 RT SG 3 LEV EX LO 827 9425 26 695 A 919 FT Lo3FDr>r 7 FL LP 827 8425 26 924 A 889 RT LP2FDIiT FL LO 927 8425 29 978 A 8'17 RT SG 2 LEV EX LO 827 8425 29 174 A 996 RT LP I FDVT FL LO 827 8425 29 446 A 911 RT LP4FDR'7 FL LO 827 8425 29 656 A 811 PT LP4FDkr T FL LO 927 8425 38 228 A 819 FT SG4 LEV EX LO 827 8425 34 467 A 113 FPT'r.'ONT G I L PR LO 827 9425 34 645 A 191 FPTE CONTOIL PR LO 827 8425 35 271 A 181 FPTE CONTOIL PR LO 827 9425 36 217 A 9)1 FT LP4FDVT FL LO 827 8425 36 369 A 113 FPTV CONTOIL PR LO 827 8425 36 661 A 899 FT LP2FDVT FL LO

e. 827 8425 36 666 927 8425 36 287 A 191 FPTE COiVTOIL PR LO A 8)1 RT LP4FD'>'T FL LO 827 8425 36 622 A 889 RT LP2FDlriT FL LO 827 8425 36 763 A 9)8 FT LP31 DVT FL LO 827 8425 36 799 A Sll RT LP4FDVT FL LO 927 8425 38 8)6 A 986 RT LP I FD'a'7 FL LO 927 8425 39 246 A 811 RT LP4FDVT FL LO Page 9 of 40 827 8425 39 264 A 888 RT LPIFDVT FL LO Rev. 0

12 PMP 4021.TRP.001 APPENDIX A II.. ESTERLINE ANGUS TURBINE .EVENT MONITOR.

The turbine event monitor is a dual unit strip chart recorder. Each of the 2 charts has 20 on-off points. The speed of the continuously moving charts is changed after a trip initiation so that 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of chart are advanced through the recorder in 24 seconds. Fast speed on Unit I is 3 inches/sec.

Fast speed on Unit II is 1.5 inch'es/sec. The chart speed then returns to normal and a trip initiation event recurs. Two points, one on each chart, are used to monitor the Train A and Train B reactor trip circuit breakers, 2 points monitor electrical lockout relays which indicate an electrical system level trip, 16 points monitor the position of turbine emergency and pre-emergency valves

.(stop and interceptor. valves). The remaining Jooints monitor

,e>

various turbine. trip initiating events.

The time discrimination between events is approximately 20 milliseconds when the chart is in high speed operation.

The data is displayed. on 2 strip charts. Each point operates a heat pen which leaves a continuous trace on the thermally sensitized chart. The pens trace a printed line on the chart to indicate a normal condition. The pen moves off the printed line to a position approximately midway between the printed lines for 2 adjacent points to indicate an off normal condition. A sample

\

strip chart is attached to the end of this section.

Page 10 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A UNIT I PEN IDENTIFICATIONS Equipment or Device Being St lus number Chart. Monitored

1. Unit differential

2. Overall differential

3. Reactor trip TR-A 4 ~ Reactor trip TR-B

5. Mechanical trip

6. AEP to master trip

7. EHC master trip

8. Back-up overspeed trip

9. Loss of speed

10. Loss of station battery

11. Trip system pressure EHC

12. Mechanical overspeed trip operated

13. Mechanical trip operated

14. Power load unbalance

15. AEP EHC trip system

16. Stop valves closed

17. Reheat and Intercept valves closed

18. Vibration trip operated

19. Trip system pressure HFA

20. T1me St lus Number, Chart 2 i ment or Device

21. Stop valve No. 1 closed

22. Stop valve No. 2 closed

23. Stop valve No. 3 closed

24. Stop valve No. 4 closed

25. Reheat, valve No. 1 closed

26. Reheat. valve No. 2 closed

27. Reheat valve No. 3 closed

28. Reheat. valve No. 4 closed

29. Reheat valve No. 5 closed

30. Reheat valve No. 6 closed

31. Intercept valve No. 1 closed

32. Intercept valve No. 2 closed

33. Intercept valve No. 3 closed

34. Intercept valve No. 4'losed

35. Intercept valve No. 5 closed

36. Intercept valve No. 6 closed

37.

Thrust bearing wear or low bearing oil trip operated 38., Low vacuum trip operated

39. Moisture separator trip operated

40. Time

Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.

Page Rev.

ll of 40 0

12 PMP 4021.TRP.001 APPENDIX A UNIT II PEN IDENTIFICATIONS Equipment or Device Being St lus number Monitored

1. Unit differential

2. Overall differential

3. Reactor bkr tripped TR-A

4. Reactor bkr tripped TR-B

5. Turbine trip left system

6. Loc Vacuum trip operated

7. Condenser A low Vacuum trip

8. Condenser B low Vacuum trip

9. Condenser C low Vacuum trip

10. Spare

11. Spare 12'. Left emergency ckt tripped

13. Right emergency ckt tripped

14. Fhed pump turbine "E" & "W" emergency trip

15. Turbine trip right system

16. Stop valves closed

17. Reheat stop and intercept valves closed

18. Vibration trip operated

.19. Cont. fluid safety circ.

tripped (0) 20. Time Recorder Points 21-40 St lus Number E i ment or Device

21. No. 1 stop valve closed

22. No. 2 stop valve closed

23. No. 3 stop valve closed

24. No. 4 stop valve closed

25. No. 1 reheat stop valve closed

26. No. 4 reheat stop valve closed

27. No. 2 reheat stop valve closed

28. No. 5 reheat stop valve closed

29. No. 3 reheat stop valve closed

30. No. 6 reheat stop valve closed

31. No. 1 intercept valve closed

32. No. 4 intercept valve closed

Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.

Page 12 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A Recorder Points 21-40 (cont.)

St lus Number E i ment or Device

33. No. 2 intercept valve closed

34. No. 5 intercept 'valve closed

35. No. 3 intercept valve closed

36. No. 6 intercept valve closed

37. Feed pump turbine "E" emergency tr3.p

38. Feed pump turbine "N" emergency trap 39., *'oisture separator Hi level trip

40. Time

.,)

Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.

Page 13 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A SAMPLE TEM STRIP CHARTS Page 14 of 40 Rev. 0

,;,0"'-:

0 C,'

. -0 -,

~ ~ r 0

...C 0, C

'GA 0 " C' 0

C-

"'f 0

! C g4A I

'C cl I

fag

))Y)(

gH~

~

C, sw o Pa e15of 40 Rev. 0

-0 C

~ p 0

'0

'4A C"

W C

C I

y n

-0 CSA ge.J,6. of 40 C Rev. 0 C

12 PMP 4021.TRP.001 APPENDIX A III. UNIT I EHC FIRST HIT MONITOR PANEL PS 100 A Sc B Are the Emergency Trip Pressure Switches which signal the electrical trip system logic that, the Emergency Trip System has depressurized.

SPD SIG LOST Activated by concurrent loss of primary and secondary speed signals with turbine speed greater than 200 RPM.

CUST. TRIP Customer trips are the following:

Thrust bearing wear S low bearing oil trip Steam Generator High Level Overall differential Unit differential MSR high level Reactor trip (P-7)

Turbine high vibration (1 right plus 1 left)

Solenoid trip (Control Switch)

Loss of stator cooling Low condensor vacuum EHC hydraulic pressure low: 1100 PSIG

'EHC system pressure trip: 800 PSIG Shaft pump oil pressure low > 1300 RPM Safety injection MA TRIP BUS Indicates that a turbine trip has occured, 'and ENERGIZER the master trip bus. has been energized. Also indicates trip is sealed in.

NO EHC DC INPUT POWER Loss of 24 V DC 61800 RPM or 250 V DC RPM.

if < 1800 Verify "No Station Battery" Annunciator in Miscellaneous Turbine Test Cabinet.

BACKUP OVER- Activated by excessive turbine speed.

SPEED TRIP POWER LOAD Initiates rapid control and intercept valve UNBALANCE closure on. greater than 40% power/load mismatch.

FAST CLST Rapid closure of intercept valves demanded by IV~S turbine supervisory instruments.

-22 VDC LOST DC supply for electrical control lost. Verify OR indication on lambda power supplies to the left of

+30 VDC LOST the First Hit Panel.

Page 17 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A IV. HATHANAY OSCILLOGRAPH t...,. 4 The unit oscillograph has 32 galvanometers. Each galvanometer will record one analog channel or, if properly modified, 4 on-off functions. Eight galvanometers have been converted to on-off functions and the remaining galvanometers are reserved for electrical analog quantities. The unit has a prefault recording feature where all input quantities are continuously recorded on a magnetic disc. Under normal conditions, the data are erased and current recordings written over the old space after approximately 100 milliseconds. If one of a specific set of events occurs, the data are recorded on ultra-violet sensitive photographic paper such that the information recorded prior to the event is recorded followed by additional data resulting from the event. The recording is.

continued for a fixed time period following the everrt. Recording chart speed may be selected to be either 12" or 3" per second, the usual practice being to record the initial portion of the event at the higher chart speed followed by additional recording at. the slower chart speed.

Six points are used, to monitor the,A and B train reactor trip circuit breaker posit'ions, undervoltage trip initiation, and safety injection actuation, 2 points monitor the start of onsite power diesel generators, 1 point monitors the trip of the feedwater pumps, 10 points monitor turbine initiated events, 7 points monitor generator and excitation events, and 4 traces are 7

used for references to assist in identification of trace Page 18 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A locations. The. analog traces record generator phase currents, j"

phase and ground voltages, and field'current.

~

<<pA.

The display provided by the developed photographic paper is a reproduction of the amplitude and wave shapes of the analog electrical quantities. The on-off events are indicated by a continuous straight line trace for a normal condition or the absence of the trace at that location signifying an off normal event. The photographic paper is developed by exposure to ultra-violet light (fluorescent lights are adequate sources) and no wet chemical processes are required. A sample strip chart is included..at the end of this section.

The time descrimination between events during higher -chart speed is better than 5 milliseconds between events and better

\

than 10 milliseconds during slower chart speed.

.g Page 19 of 40 Rev. 0

Pt71P 4021. TRP.001 APPENDIX A DONALD C. COOK NUCLEAR PLAVI'2 1/84 UNIT Pl OSCILLOGRAPH TRACE NO. TRACE ASSIGi%ENT Generator Current 51 7000/1 37,960 A/in.

4 2 S are Generator Current g3 7000/1 37,960 A/in.

4 Spare 4

5 Spare 4 S are 7 Gen. Groundin Trans. Volta e 41.5/1 220 V/in.

9 Gen. Field Current Zero Mirror t

~~.9 4

9

. 9 Gen. Field Current (Shunt-6000 A/100 M.V.) 160 M.V./In. 9,466 A/in.

.'AI- Gen. Metering Pot. Voltage 220/1 227 V/in.

12 S are I

7'.

13 345 1P Pot. Timing Trace '800/1 213 V/in.

4 14 Spare (Current)

"9 15 Spare 9 ~,

16 ~gare (Current Traces: 1-Reference; 2-Reactor Breaker Tripped 'A',

OM4 3-Reactor Breaker Tripped 'B'; 4-Reactor Breaker Under-17 ' On/Off OM4 Traces: 1-Safety Injection 'A'; 2-Safety Injection

'8 'B'; 3-Diesel Gen. 'AB'Start; 4-Diesel Gen. 'CD'tart. On/Off OM4 Traces: 1-Reference; 2-Feed PP. Turb. 'E89 3-Spare; 4-Spare. 'W'rip; 19 On/Off

~

OM4 Traces: 1-Main Stop Valves Closed; 2-Main Turb. Mech 20 .3-Emerg. Gov. Overspeed Trip; 4-Back-up Overspeed On/Off

$ rf ;

2 OM4 Traces: 1-Reference; 2-FHC System Trip; 3-Reactor 21 Bkr. Undervolt Trip 'B'; 4-Thrust Bearing Trip. On/Off 2

OM4 Traces: 1-Moisture Separator Hi. Level Trip; 2-22 Vacuum Trip Operating; 3-Main Turb. High Vib. Trip; On/Off 4-Lube Oil Press. Low Trip.

OM4 Traces: 1-Reference; 2-Stator Outlet Cooling Water 9 23 Temp. High; 3-Stator Cool Turb. Trip; 4-Stator Cool Gen. On/Off Tri I 24 OM4 Traces: 1-Generator Motoring; 2-Unit HEA Operated; 'n/Off 3-Overall HEA operaced; 4-Alterrex & Excitation Trip ~

OSCILLOGRAPH STARTING SENSOR CALIBRATION 1.-38 Undervoltage --- 109. VAC Note: Overcurrent - (Noc Used) 2.-39 Overvoltage --- 130 VAC 3 '18 Overvoltage --- 50 VAC Rage. 20 of 40

" -Any on/off operation will start oscillograph '

Rev. 0

12 PMP 4021. TRP. 001 APPENDIX A

,H ~H DONALD C. COOK NUCLEAR PLANT 1/84 H

2 UNIT NO. 2 OSCILLOGRAPH TRACE NO. TRACE ASSIGNMENT RATIO ON Generator Potential E51-2 Volts 220/1 130 V/in.

Generator. Potential E52-3 Volts 220/1 128 V/in.

3 ~ . Generator Potential E53-1 Volts 220/1 124 V/in.

4 Generator Current Ill 7,000/1 36,119 A/in.

Spare Genera r N a V 2 'Vi Generator Current 152 7,000/1 36,119 A/in.

Generator Current 153 7,000/1 43,914 A/in.

10 Spare 11 S are S are Spare 14 765 KV Timing Trace 128 V/in.

OM4 Traces: 1-Reference; 2-Reactor Breaker Tripped "A";

15 3-Reactor Breaker Trinpad,",B,",; 4-Reactor On/Off Breaker Undervolta e Tri "A" OM4 Traces: 1-Safety In)ection A ; 2-Safety In)ection B; 16 3-Diesel Generator AB Start; 4-Diesel Gener- On/Off OM4 Traces: 1-Reference; 2-Feed Pump Turbine "E" and "W" On/Off Pump Turbine "E" and "W" Trip Trip; 3-Feed 4-S Emer ancv are OM4 Traces: (IVacgum3T@ip Oparg[ed;L2pn)n ItopTVglye On/Off 18 vM4 Traces:,1-Reference; 2-Control Fluid Safety Circ.

19 Tripped; 3-Reactor Breaker Undervoltaga On/Of f Trip "B"; 4-Thrust Bearing Trip OM4 Traces: 1-Moisture Separator Hi-Level Trip; 2-Air-Oil, H2 Diff. Press. Low Trip; 3-22ain Tur- On/Off 20 bine High Vib. Trip; 4-Lube Oil press. Low Trip.

OM4 Traces: 1-Reference; 2-Stator Outlet Cooling Water Temp High; 3-Stator Cooling Turbine Trip; 4- On/Off 21 n races: - enarator tor ng; ' nit ea perate 3-Overall Hea Operated: 4-Altarrex and On/Off

'2 Excitation Trip OSCILLOGRAPH STARTING SENSOR CALIBRATION

1. 3Itj'Undarvoltage E51-2 102 VAC 2~ 30 Overvoltage E81-2 128 VAC 105 129 E02-3 E03-I VAC 107 VAC 2'53-I E52-3 125 VAC VAC

3. 10 Overvoltage 52 VAC 4. Any on/o operat on w start osc ograph.

21 of AA. Rev. 0

12 PMP 4021.TRP.001 APPENDIX A SAMPLE OSCILLOGRAPH STRIP CHART Page 22 of 40 Rev. 0

I

V t

1 a l'

~ VV re+

A

12 PMP 4021.TRP.001 APPENDIX A V. P250 SEQUENCE OF EVENTS RECORDING PROGRAM The Sequence of Events Recording program records the sequence of operation of a number of monitored contacts to a high time resolution. When one of the monitored contacts changes state, an interrupt is initiated which causes the P250 to scan each monitored contact for any change from its previous state.

The program stores such changes and the cycle count since the first event. A cycle is approximately 20 milliseconds in length. Due to a dead time of 2 milliseconds in the interrupt process, an automatic rebid of the program is programmed for the cycle following each interrupt bid. This is done to avoid loss of contact changes during the dead time. The Sequence of Events a

Recording program is terminated when either the cycle count II reaches'3600 or 25 contact changes have been recorded.

When the program is terminated, an output routine is called. All collected data are first moved to the output program buffers to free the Sequence of. Events Recording program buffers for continued monitoring. The output routine prints the time of the first event in hours, minutes, and seconds. Following this message, the alpha-numeric address, a 36 character contact description, and cycle count from the first event are printed for each contact change. The first event will always have a cycle count of zero. A sample output is included at the end of this section.

Page 24 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A I

SEQUENCE 'OF EVENT ADDRESSES (Reference P250 Manual TPS129)

F0403D RCZ LO F ABOVE P-8 CAUS RE

,F0423D RCL LO F ABOVE P-7 CAUS REF F0493D STM LINE HI F SI CAUS RE L0406D STM GEN A ZO ZO Z CAUS RE L0426D STM GEN B LO LO L CAUS RE L0446D STM GEN C ZO ZO L CAUS RE Z0466D STM GEN D LO LO L CAUS RE L0483D PRESSURIZER HI 1 CAUS RE N0005D PWR RNG CHAN HI Q CAUS RE N0010D PWR RNG CHAN ZO Q CAUS RE N0024D INTERM RNG HI Q CAUS RE N0029D PWR RNG CHAN HI Q RATE CAUS RE N0036D SOURCE RNG HI Q CAUSE RE P0407D STM LINE A HI DP SI CAUS RE P0427D STM LINE B HI DP SI CAUS RE P0447D STM LINE C HI DP SI CAUS RE P0467D STM LINE D HI DP SI CAUS RE P0483D PRESSURIZER HI P CAUS RE P0488D PRESSURIZER LO P CAUS RE P1003D CONTAINM HI P SI CAUS RE T0498D RCL OVERTEMP DI CAUS RE T0499D RCL OVERPWR DT CAUS RE V0324D RCP BUS UNDER VOZT GP7 CAUSE RE Y0004D REAC MANUAL TR 1 CAUS RE Y0005D REAC MANUAL TR 2 CAUS RE Oj Y0006D Y0007D REAC MAIN TR'KR A REAC MAIN TR BKR B Y0026D REAC AUX TR BKR A Y0027D REAC AUX TR BKR B Y0320D RCP BUS UNDER FREQ PART RE Y0321D RCP, BUS UNDER FREQ PART RE Y0322D RCP BUS UNDER FREQ PART RE Y0323D RCP BUS,UNDER FREQ PART RE Y0324D RCP BUS UNDER FREQ CAUS RE Y0335D UNIT ON LINE TIE OCB A1 BKR Y0335D UNIT ON LINE TIE OCB A2 BKR Y0337D UNIT ON LINE TIE OCB Bl BKR Y0390D TB TRIP CAUSE RE .

Y0391D TB STOP VLV A CI PART RE Y0392D TB STOP VLV B CI PART RE Y0393D TB STOP VLV C CI PART RE Y0394D TB STOP VLV D CI PART RE Y0400D RCPA BKR OP CAUS RE Y0401D STM GEN A ZO L S( FW F CAUS RE Y0420D RCPB BKR OP CAUS RE Y0421D STM GEN B LO L & FW F CAUS RE Y0440D RCPC BKR OP CAUS RE Y0441D STM GEN C LO L Sc FW F CAUS RE Y0460D RCPD BKR OP CAUS RE Y0461D STM GEN D LO L 6 FW F CAUS RE Y0480D PRESUZER LO P&L SI CAUS RE Y0920D SFTY INJ SET i~AL 1 CAUS RE Y0921D SFTY INJ SET MANUAL 2 CAUS RE Page 25 o f 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A SHE'LE SEQUENCE OF EVENTS OUTPUT Page 26 of 40 Rev. 0

j~

0257 ALARtl III T04iUA AI RCLA OVEICTEIIP DT I SP 178 5 H i52 0 DEGF 0257 RETRH OR 10430A AI RI'.LB OVERTENP DT 1 SP 159 ' DEGF 0257 kf1ktt OR 104boA Al RCLC OVLRILIIP DT 1 SP 164.i. DEGF 0257 RErRH OR T0470A AI RCLO OVERTEIIP Ol' SP 160.3 OEGF 0257 ALARtl LO T0400A Al RCLA I TAVG 546 7 L 552 0 DEGF 0257 SEGUEHCE OF EVENTS RECORD. FIRST EVENT Ar H 2 tl56 S40 D25/ ALARtl LO T0420A AI RCLB i TAVG b47 5 L 553 0 DEGF Y03900 18 TRIP CAUSE PE TR C 0

-2.0 02bB 0258 RE1RH LO 80340A ALARtl HI Y00070 Al UHI1 GEHEkA10k GROSS flit 10450A tlAlN 1R BKR 8 AI RCLC OVERTEtlP DT 1R.

i 3.08P L NM ib2 4 H i52 0 DEGF 02b8 02bB REAC ALAT<tt LO ALARtl HI TU44UA UU400 Al CV RCLC i 1 A C 4 RCLA OVERPWR SP DEV FR COPIPUTED 5 6 i04 2 L

H 552 0 6 0 DEGF PC Y0006D REAC flAIH 1R Btlk A 1R C 5 0258 ALARM LO TU460A AI RCLD 1 TAVG 5 2 L 552 0 DEGF H00290 PIIR RHG CNAH NI 0 RATE CAUS Rf 21 i04 7' TR C 02b8 ALAI(tt tll U0448 CV RCLC OVFRI WR SP DEV FR COtIPUTED 6 0 PC 0258 ALARtt tII U0468 CV RCLD OVERPWR SP DEV FR COtIPUTED i04~ H 6 0 PC Y03'920 18 S1OP VLV B CL PART kE TR 28 02bB 0258 ALARM ALARtl LO tll T04/OA P0142A Al AI RCLD OVERTEtIP DT C

CHARG PtlP DISCH HDR P i SP ibU i 2i65 0 H i5D 0 L 2200 0 DEGF PSIG Y0394D 1B S1OP VLV 0 CL f'AkT RE 1R C 28 0258 DELTA FLUX PROGRAfl IH LOM POllER CU'TOFF IIOOE Y0393D 18 S1OP VLV C CI. PART RE 1R C 30 Y03910 TB STOP VLV A CL PARr RE Y0441D Sift GEN C LO L 6 lit f CAUS RE 1R C 226 L0426D STII GEH 8 LO LO L CAUS RE TR C 257 f'0488D f'RESSURIZER LO P CAUS RE TR C 266 0259 ALARtl tlI UU428 CV RCLB OVERPWR SP DEV FR COPIPUTED i06 0 H 6 0 PC L04060 STII GEH A LO LO L CAUS RE TR C 271 10466D S1tl GEH D LO LO L CAUS RE Tk C 272 0259 INCR L0446D Srtl HI T0470A GEH C LO LO L CAUS RE Al ICCLD OVERTEtIP DT TR C 278 i SP ib2 2 I 'ib2 0 DEGF T042ID Sltl GLH 8 LO L 6 fM F CAUS kf 1R C 278 Y04010 Slfl GEN A LO L 6 FM F CAUS RE I'R C 307 YD461D S1tl GEk 0 LO L 6 fM f CAUS RE 1R, C 307 o3oo 2/18/1984 Dc cOOK Uklr 2 Y0461D Sltl GEH 0 LO L 6 fM f CAUS kf NT 1R C 317 Y04610 Sln GEH O t.o L 6 FN F CAUS RE ~ TR C 323 Y0421D Sltl GEH 8 LO L 6 FN f CAUS RE HT 1k C 660 Y04010 srtt Lo L 6 Flt F cAUs Rf Hl'R 666 0300 ALARtt HI Y0461D Srft GEH A 1'0430A GEH 0 LO AI L 6 FM F CAUS RE RCLB OVERTEtlP DT Nr TR C

C 679 i SP i50 6 H i50 0 DEGF

'104410 S1tl BEN C LO L 6 fit F CAUS kE kl 1R C 746 Po/IBBD 1082 0301 INCR PRESSURIZER LO P CAUS RE Hl T0430A Y0336D UNIT OH LIHE TIE OCB A2 BKR Al HT TR RCLB OVERTEPIP DT OP C

C 1476 i SP i52 0 I i52 0 DEGF 1033bD UNIT OH LIHE 'llf OCB A1 BKR OP C 1476 03ol fuo sfGUEHcE oF EVEHrs RfcORo 0301 SLOULNCL OF f VENTS kfcoko. flkST EVEHT AT N 2 IIN S31 Y03900 TB rRIP CAUSE RE NT TR C 0 104410 Sift Gl.k C LO L 6 fM f CAUS Rf 1R C 1811 Y0441D Srft GEH C LO L 6 Flf F CAUS RE Hr TR C 2250 0301 LHD SLOUI.HCE OF EVEIITS kfcokD 0303 AHALOG TREHO-OE'Vlcf 2 8'TOPPEO Page 27 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A VI. POST TRIP REVIEW PROGRAM.

je The Post Trip Review program periodically records a number of pre-selected inputs. These inputs are stored on a disc in a circular buffer, with newer sets of data replacing the older sets. When a trip occurs, either automatically (Post Trip) or manually (Test Trip), the pre trip data being entered into the circular buffer are frozen and the data are thereafter stored in a post, trip buffer. When this buffer is filled, both sets of data (pre and post) are printed out on the typewriter..

The parameters monitored are analog in nature. At the present time, they include selected RPI indication (for unit 2 only), steam generator feed water flow and steam flow, steam generator narrow range and wide range level, pressurizer level, pressure'izer livel setpoint, source range detector output, (Og intermediate range detector output, power range detector output, first stage turbine pressure, steam generator pressure, pressurizer pressure, containment pressure, unit gross electrical output, Taverage, delta T power, overtemperature delta T setpoint, overpower delta T setpoint, wide range cold leg temperatures, pressurizer steam temperatures, T-reference, auctioneered delta T, and auctioneered Tavg. These parameters remain as selected by the computor vendor, Westinghouse Electric Corporation, except for certain RPI indications on. Unit 2. The RPI indications were substituted'or the four channels of total power range NIS power in order to obtain data on the anomalous response of RPI H-8 upon trip. The individual power range upper

,g Page 28 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A and lower detector outputs remain in the Post Trip Review output for both units to monitor NIS power range indications.

Eight of the parameters in the previous paragraph are sampled at 2 'second intervals 6 seconds before and after the trip. These are total NIS power range power on unit 1 and RPI indications on unit 2, turbine first stage pressure, unit gross electrical output, and auctioneered Taverage. All parameters are sampled at 8 second intervals for 2 minutes before and 3 minutes after the trip. These sampling times remain as set by the computor vendor.

The Post Trip Print .program first outputs a start message on the appropriate typewriter. It then outputs a line of headings for the values which will be printed in columnar form. The headings consist of the six-character name of the point.'he I values are printed below their names starting with the oldest set of data on the first line, the next oldest on the next line and so on until the most, recent pre-trip data are printed. Included in each row of data is a column indicating the time. When all the pre-trip data for this set of points are printed, the message POST TRIP DATA TRIP TIME KXXX is printed. All the post-trip data for these points are printed in the same ormat,'as described above.

After all the post-trip data for these points are finished, the program starts over with another set, of data in the same format: 6 character names, pre-trip values, trip message, and I

post-trip values. When all the points have been printed, the program outputs a finished message, unblocks the collection Page 29 of 40 Rev. 0

12 PNP 4021.TRP.001

', APPENDIX A programs, and exits. A sample output is included at the end of this section.

)

4 Page 30 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A POST TRIP REVIEW ADDRESSES C0010A Cont. Rod Bank B Group 1 Pos N08 (Unit 2 Only)

C0027A Cont. Rod Bank D Group 2 Pos P10 (Unit 2 Only)

C0029A Cont,. Rod Bank D Group 2 Pos H08 (Unit 2 Only)

C0075A SD Rod Bank D Group 1 Pos F10 (Unit 2 Only)

F0403A Stm Gen A Feed Wtr in 1 F F0404A Stm Gen A Feed Wtr in 2 F F0405A Stm Gen A Stm Out 1 F F0406A Stm Gen A Stm Out 2 F F0423A Stm Gen.B Feed Wtr in 1 F F0424A Stm Gen- B Feed Wtr in 2 F F0425A Stm Gen B Stm Out 1 F F0426A Stm Gen B Stm Out 2 F F0443A Stm Gen C Feed Wtr in 1 F F0444A Stm Gen C Feed Wtr in 2 F F0445A Stm Gen C Stm Out 1 F F0446A Stm Gen C Stm Out 2 F F0463A Stm Gen D Feed Wtr in 1 F F0464A Stm Gen D Feed Wtr in 2 F F0465A Stm Gen D Stm Out 1 F F0466A Stm Gen D Stm Out 2 F L0400A Stm Gen A Nar Rng 1 L L0401A Stm Gen A Nar Rng 2 Z Z0402A Stm Gen A Nar Rng 3 L L0403A Stm Gen A Wide Rng L L0420A Stm Gen B Nar Rng 1 L Z0421A Stm Gen B Nar.Rng 2 L L0422A Stm Gen B Nar Rng 3 L (g L0423A Stm Gen B Ride Rng L L0440A Stm Gen C Nar.Rag.l L L0441A Stm Gen C Nar Rng 2 L Z 0442A Stm Gen C Nar Rng 3 L L0443A Stm Gen C Wide Rng L L0460A Stm Gen D Nar Rng 1 L L0461A Stm Gen D Nar gag 2 L L0462A Stm Gen D Nar Rng 3 L Z0463A Stm Gen D Wide Rng L L0480A Pressurizer 1 L Z0481A Pressurizer 2 L Z0482A Pressurizer 3 L L0483A Pressurizer Lvl Control S.P.

'N0031A Source Rng Detector 1 Log Q N0032A Source Rng Detector 2 Log Q N0035A Source Rng Detector 1 Log Q N0036A Interm Rng Detector 2 Log Q N0041A PWR Rng 1 Top Detector Q N0042A PWR Rng 1 Bottom Detector Q N0043A PWR Rng 2 Top Detector Q N0044A PWR Rng 2 Bottom Detector Q N0045A PWR Rng 3 Top Detector Q N0046A PWR Rng 3 Bottom Detector Q N0047A PWR Rng 4 Top Detector Q N0048A PWR Rng 4 Bottom Detector Q Page 31 of 40 Rev. 0

12 PMP 4021.TRP.001 APPENDIX A POST TRIP REVIEW ADDRESSES N0049A PWR Rng Channel 1 Q (Unzt 1 Only)

NOOSOA PWR Rng Channel 2 Q (Unit 1 Only)

N0051A PWR Rng Channel 3 Q (Unit 1 Only)

N0052A PWR Rng Channel 4 Q (Unit 1 Only)

.P0398A Tb First Stage 1 P P0399A Tb First Stage 2 P P0400A Stm Gen A Stm Out 1 P P0401A Stm Gen A Stm Out 2 P P0402A Stm Gen A Stm Out, 3 P P0420A Stm Gen B Stm Out 1 P P0421A Stm Gen B Stm Out 2 P P0422A Stm Gen B Stm Out. 3 P P0440A Stm Gen C Stm Out 1 P P 0441'A Stm Gen C Stm Out, 2 P P0442A Stm Gen C Stm Out 3 P P0460A Stm Gen D Stm Out 1 P P0461A Stm Gen D Stm Out 2 P P0462A Stm Gen D Stm Out 3 P P0480A Pressurizer 1 P P0481A Pressurizer 2 P P0482A Pressurizer 3 P P0483A Pressurizer 4 P P1000A Containment 1 P P1001A Containment 2 P P1002A Containment. 3 P P1003A Containment 4' Q0340A Unit Generator Gross T0400A RCL A 1 T-Avg.

T0403A RCL A 1 DT T0406A RCL A 1 Cold T T0407A RCL Overpwr DT 1 SP T0410A RCL A Overtemperature hT Setpoint T0420A RCL B 1 T-Avg.

T0423A RCL B 1 DT T0426A RCL B Cold T T0427A RCL B Overpwr DT 1 SP T0430A RCL B Overtemp DT 1 SP T0440A RCL C 1 T-Avg.

T0443A RCL C 1 DT T0446A RCL C Cold T T0447A RCL C Overpwr DT 1 SP T0450A RCL C Overtemp DT 1 SP T0460A RCL D 1 T-Avg.

T0463A RCL D 1 DT T0466A RCL D Cold T T0467A RCL D Overpwr DT 1 SP T0470A RCL D Overpwr DT 1 SP T0481A Pressurizer Stm T T0496A RC T-Ref.

T0497A RCL Auct. DT T0499A RCI Auct. T-Avg.

Page 32 of 40 Rev. 0

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~

I 12 PMP 4021.TRP,.001 APPENDIX A SAMPLE POST TRIP REVIEW OUTPUT

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Page 33 of 40 Rev. 0

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'A i 1

12 PMP 4021.TRP.001 APPENDIX B PROTECTION AND SAFEGUARDS SETPOINTS TRIP UNIT 1 UNIT 2 DESCRIPTION SETPOINTS SETPOINTS Actual Tech. Spec. Actual Tech. Spec.

1) Hanual N/A N/A N/A N/A

2) Pwr. Ran e Neutron Flux a) I,ow 25'/ =25/ ~

25'/ $ 25/

b) High 109/ <109$ 109/ <109/

3) Pwr. Ran e Flux Rate a) Positive 5/ In 2 sec <5'/ In R 2 sec 5/ In 2 sec $ 5/ 'In 8 2 sec b) Negative 5/ In 2 sec $ 5/ In R 2 sec 5/ In 2 sec <5/ In R 2 sec

4) Intermediate Ran e 25'X <250/ 25'X <25/

Neutron Flux (Current E~uival.) (Current Equival.) (Current E~uival. ) (Current Eq'nival.)

(9.6 x 10- amps) (8.1 x 10- amps) 9 x 104cps <105cps 9 x 104cps <105cps Neutron Flux

6) OTAT As Per Tech Spec As Per Tech Spec

7) OPbT As Per Tech Spec As Per Tech Spec

8) Low PZR. Press 1872 psig R1865 psig 1966 psig R1950 psig lM 2378 psig <2385 psig 2378 psig <2385 psig 10)Hi h PZR Lvl. 91'/ <92/ 91$ $ 92/

ll)Loss of Flow 90/ R90/ 93% >90%

Page 1 of 2 Rev. 0

VA 12 PMP 4021.TRP.001 APPENDIX 8 PROTECTION AND SAFEGUARDS SETPOINTS TRIP UNIT I UNIT 2 DESCRIPTION SETPOINTS SETPOINTS Actual Tech. Spec. Actual Tech. Spec.

12) S/G Wtr. Ivl.Low-Low 17/(N.R.) ~17/(N.Q.) 21/(N.R.) >21/o(N.R.)

13) Stm./Feed Flow 0.6 x 10spph <0.71 x 10 pph 0.6 x 10pph $ 1.47 x 10spph Hismatch W/I,ow Coincident with Coincident with Coincident with Coincident with S/G 'Wtr Ivl 26/ (N.R.) R25$ (N.R.) 26/ (N.R.) R25/ (N.R.)

14) RCP Undervolta e 3150 Volts R2750 Volts 3150 Volts >2905 Volts

15) RCP Underfre uenc 58.2 HZ R57.5 HZ 58.2 HZ >57.5 HZ

16) RCP Bkr. Position 1/4 Open Bkrs Above P-8 NA 1/4 Open Bkrs. Above NA 2/4 Open Bkrs Between P-8, 2/4 Open Bkrs.

P-7 6 P-8 between P-7 6 P-8

17) Turbine Tri a I.ow Sys. Press. 800 psig >800 psig 62 psig R58 psig b) Stop Vlv. Position 1/ open >1/ open 1'j, open >1/ open

18) Safet In'ection a) Hanual NA NA NA NA b) High Containment Press 1.1 psig <l.l. psig 1.1 psig <1.1 psig c) Low PZR Press. 1837 psig >1815 psig 1908 psig >1900 psig d) High Stm. Line 100 psid Q,00 psid 100 psid <100 psid Diff. Press.

e) High Stm. Line 1.42 x 10s pph for <1.42'x 10 pph for NA NA Flow Coincident with 0+20/ Pwr. Ramped 0+20/ Pwr. Ramped to 3.88 x 10 pph at to 3.88 x 106 pph at 100/ 100/

Lo-Lo Tavg or 541 oF R541oF NA NA Low Stm. Line Press. 600 psig 2600 psig 600 psig R600 psig Page 2 of 2 Rev. 0

tHFQPEAATI(QM 6>¹ ~i' ATTACHMENT II 2.2 Equipment Classification and Vendor Interface (Programs for All Safety-Related Coaponents) 2.2.1 E ui ment Classification 2.2.1.1 Criteria The criteria for classifying -the components of the D.C. Cook Plant were described in Section 2.1, attachment to letter AEP:NRC:0830A, M. P. Alexich to Darrel G. Eisenhut, dated'November 4, 1983. These criteria were used to classify all coayonents, not just the Reactor Trip System components.

2.2.1.2 Information Handling System P

Safety-related components (with known exceptions) are entered in a computerized list known as the N-List.

Structural items and piping are entered as a single line item. Electrical items such as relays, switchesp conduit, fittings, and trays also are covered by single line items.

Since the N-List is not all inclusive and does not individually list such items as pipe spool pi.eces, switches and relays, other documents such as the PSAR, technical specifications, related communications to the NRC, flow diagrams, electrical elementary and one-line diagrams and purchase specifications are also consulted . For example, the boundaries of each pipe specification are shown on the flow diagrams.

The control of the N-List, including updating and maintenance, is set forth in corporate level general procedures. If any one within AEPSC or the plant is unsure of the classification of a component, he is required by procedure to check with the responsible AEPSC cognizant engineer. Drawings are controlled by general procedures and design procedures of the cognizant engineering groups. The D.C. Cook Plant equipment specifications are the documents which were used in specifying the procurement, fabrication, installation and (in some cases) repair of systems or equipment. The specifications were prepared during the construction phase of the plant and supplemented as required. Control of the speci.fications, including updating and maintenance is set forth in corporate level general procedures. II Since this information system is cumbersome to use, we plan to transfer the required information to a new computerized component clas sif ication record. This will provide for uniform identification and description of plant components in a single docuaent.

Until the new information system is in place and operational, we will continue to review and update the existing system as required and conduct refresher training for appropriate plant staff.

The new system is described in Section 2.2.1.6.

2.2.1.3 Plant Use Under the present system of work control, a job order is prepared for all repair and modification work performed at the plant. During the job order preparation process, the safety classification of the equipment, as well as procedures required to perform the work, are entered on the job order form. The same reference documents are used to assure that properly certified replacement parts are used when required.

Plant procedures control the ordering of replacement parts.

Following completion of every repair and modification, the job orders undergo a review process by experienced and knowledgeable supervisory personnel. This review process provides verification that the information handling system is being used on a routine basis.

Particuiar attention is given to safety related job orders to verify that proper procedures were used and that properly certified replacement parts were installed where required.

2.2.1.4 Management Controls The activities described above for work control process are addressed in various plant instructions and procedures. The Quality Assurance Department performs audits of activities covered by the plant instructions and procedures and notifies appropriate plant management of any deficiencies noted. Thus, the audit program provides additional verification of the routine utilization of the information handling sys tern.

2.2.1.5 We are currently engaged in the completion of the qualification of components of safety related systems located in harsh enviroauents associated with IE Bulletin 79%1B. This program includes consideration of aging of these devices.

Rule 10 CFR 50.49 requires that replacement components for safety related systems meet the conditions of IEEE 323-1974 which includes aging requirements. Specif ic criteria for exemptions are provided by Rule 10 CFR 50.49.

Our current specifications used to procure new or replacement components identify normal and accident service conditions or reference applicable codes ~

Qualification testing and performance evaluation is required for harsh environments and test reports of this qualification testing are required to meet the conditions of the specifications.

Prior to future-use-for procurement, each specification subject to the requirements of 10 CPR 50.49 will be revised to include the'requirements'hat the vendor establish service life by test or performance evaluation=and require the vendor to supply documentation in support of the service life qualif ication.

New Classif ication Program We plan to implement a new. computerized component classification record which vill list all plant components, their safety classification and their procurement and QA requirements.

Crossmeferences to drawings and relevant plant and corporate procedures will ensure that the safety role of a component is kept in focus whenever a component is taken out of service, bought, maintained, replaced or returned to service. The job control classification will rely on the record.

We recognize the need to address the issue of "important to safety" and to tie it to specific components and their applications. This subject is being actively debated within the industry and is the subject of Mr. Darrel Eisenhut s Generic Letter 84&1 dated January 5, 1984. At the present time, however, the definition of the scope of the term "important to safety" has not been established; we do not have formal criteria to allow classification on a component by component basis.

We are planning our new component classification record to accommodate such classifications. As additional requirements are developed for the "important to safety" classified equipment these will be reviewed and, if appropriate, incorporated into the program.

We are starting work on our new data>>base projects We currently expect to have the new system in place before the end of 1986.

3.2 POST MAINTENANCE TESTING (ALL OTHER SAFETY-REIATED COMPONENTS) 3.2.1 We have reviewed our plant testing and maintenance procedures which cover safety related components and have determined that post maintenance testing is included. We are conducting reviews to verify that the testing specified is adequate to demonstrate that the equipment is capable of performing its safety function. This review is expected to be completed by March 31, 1985.

Plant tagout procedures require that operability is demonstrated prior to returning the component or system to service. Components within the tagouts boundary are reviewed for operability verification.

Plant procedures governing job orders require adequate testing upon completion of the job. The testing performed by the department completing the work has to be entered on the job order.

When a change is made to a plant structure, system, or component, the request for change (RFC) package is reviewed by the design change coordinator. RFC installations are normally required to be tested to verify operability. If such a test is not to be performed, the Lead Engineer has to document the justification for the exception.

Operability testing which is complex is performed by using an approved procedure.

The D.C. Cook Nuclear Plant technical specifications are the standardized format. However, they do not specifically require that post~aintenance testing be conducted before returning a system or component to service (i.e., declared operable). Specified surveillance test(s) (operability denenstration) are required prior to entry into an operational mode.

In addition, when the plant is in a condition that requires entry into a "Technical Specification Action Statement",

the relevant plant tagout, job order and change control procedures are activated. This ensures that the operability of all safety related components is verified before they are returned to service. The plant can then be considered to be out of the Action Statement condition.

3.2.2 We have canmenced a review of the plant maintenance procedures. The check for vendor and engineering recommendations to determine that appropriate test guidance is included will be included in the review. In addition, a separate review is being made of the technical bulletins for the Westinghouse supplied NSSS safety related equipment as defined by the Westinghouse bulletin. This same review will be made on other safetymelated device bulletins as they are'eceived

(including previously issued bulletins) under the program described by Section 2.2.2. In conjunction with our VDCS, we will give you a status report on the results of our review by December 31, 1985.

ATTAQRENT III 2.2.2 The following description expands our November 4, 1983 letter AEP:NRC:0838, Vendor Document Control System and provides an implements t ion schedule General Zn order to ensure that vendor information for safetymelated components is complete, current, and controlled throughout the life of the D.C. Cook Nuclear Plant, a "Vendor Document Control System" (VDCS) has been developed and is in the initial stages of implementation. The VDCS is comprised of a corporate level general procedure and associated review documentation forms, and is designed to track Vendor Technical Documents (VTD s) from their receipt to final disposition and filing, utilizing positive feedback at each stage to guarantee receipt and on-schedule review. To assure implementation of and adherence to the VDCS, the AEPSC Quality Assurance section has. been assigned the responsibility for monitoring and auditing the general procedure.

VDCS Ob 'ectives Prior to the detailed development of the VDCS, it was essential that program objectives be well defined. The resulting objectives were realistic, achievable, and addressed the intent of Generic Letter 83-28, Section 2.2.2. These objectives and the manner in which they were addressed are described as follows:

1. Centralization of Responsibility for VTD s Because the vendors use such diverse methods for trananitting VTD s to AEP, the assigning to one central group the responsibility for receiving, classifying, and determining distribution for all VTD s was a prime requirement. The Nuclear Operations Section (NOS) within the AEPSC Nuclear Engineering Division has been assigned this responsibility. All VTD s pertaining to D.C. Cook Plant, regardless of their points of arrival within the AEP System, will be forwarded to the NOS for initial processing.

2. Traceability of all VTD s The ability to trace and locate a VTD, not only during the initial review process but at any time during the life of the plant, will be achieved through the assignment of unique processing and filing numbers. Upon receipt, the NOS will assign to each VTD a unique processing number. This number will be retained from initial sorting through final disposition and filing. During the review of the VTD by the cognizant divisions, all VDCS forms will be identified with this unique processing number. During the review, determined to be "applicable", it if the VTD(s) is will be assigned a unique control number. A "Controlled Document" stamp will be affixed to the VTD, and the control number printed thereon.

Both the processing number and the control number along with all other pertinent data, will be recorded in the VDCS . This system-(detailed later) will enable the VTD to be located and its status determined.

System to Record and Track VTD Data Because of the large number of VTD s both existing and projected to be received in the future, a computerized tracking system is under development. This system will enable all VTD s to be tracked at each point of the review process from initial receipt through final disposition and filing. All data pertinent to the VTD and the component to which it is applicable will be included.

Complete Documentation for all VTD s The documentation required for the receipt, review, and dispositioning of each VTD is prescribed by the VDCS corporate level general procedure. Each step of the review 'process requires the use of a form specifically developed for that step. All forms contain a separate "receipt/acknowledgement" section which aust be completed, signed, and returned to the originator. The VTD, along with all disposition forms, will be microfilmed and filed at the completion of the review process.

Timely Review and Determination of Required Actions The time allotted to the cognizant divisions for review on a VTD is specified by the NOS on the transmittal form attached to the VTD. A annthly review of VDCS items will be conducted by the NOS. The NOS will initiate an "overdue notice" to a cognizant division and/or adjust completion dates when necessary.

All VTD s will be processed through the indicates that immediate action is required, VDCS. However, if a and the processing VTD delay through the VDCS could adversely affect either the health and welfare of the general public or Cook Plant operations, the general procedure permits the required action to be taken without immediate VDCS processing and review. After the actions are completed, the general procedure prescribes that the VTD nmst be processed through the VDCS in the normal manner ~

Ability to Retain and Retrieve all VTD s and Associated Material Upon completion 'of the review process, the VTD and all associated documentation will be microf ilmed for permanent storage and all pertinent information recorded in the VDCS tracking system. Whenever information is required concerning a VTD, a search of the computerized tracking system can be made.

Once the VTD is located, it may be viewed on microfilm and/or reproduced as required.

Ensure Receipt and Correct Processing of all VTD s To ensure that all VTD s transmitted to AEP by vendors are received, the VDCS contains provisions for a periodic contact with each safetymelated vendor. Over any given twelve (12) month period, each vendor will be sent a form letter, including a "receipt/acknowledgement" section, with an attachment listing the documents received from the vendor during the previous twelve (12) aonth period. If this listing is correct, the

vendor will be requested to sign and return the document. If documents are missing, the vendor will be requested to so inform AEP and provide copies of all missing documents. These VTD s, upon receipt, will be processed through the VDCS.

Processing of all VTD S includes an evaluation of "applicability" to D;C; Cook Plant. "Applicable" VTD s will be automatically processed through the VDCS . However, if a VTD is classified as "not applicable" by the'NOS, it will be automatically sent to a cognizant engineering group for a second evaluation of applicability. This step reduces the possibility of an "applicable" document being misclassified and not being reviewed and correctly dispositioned .

8. Incorporation of Existing VTD s into System The incorporation of existing VTD s into the new VDCS is underway. Each document will be reviewed and assigned a unique processing number. Each VTD applicable to D.C. Cook Plant will be classified and stamped as a "Controlled Document" and assigned a control number. All pertinent data will be recorded in the VDCS tracking system.

NUTAC AEP actively participated in the Nuclear Utility Task Action Canmittee (NUZAC) on NRC Generic Letter 83-28, Section 2.2.2 - Vendor Interface. While AEP is in general agreement with the NUXAC recommendations (transmitted to the NRC by E. Griffing, NUZAC Chairman),

we have modified the program slightly to meet our specific requirements.

VDCS Current Status and Im lementation Schedule Subsequent to the receipt of Generic Letter 83-28, an intense effort has been underway within AEP to develop and implement a program to address the document control concerns contained therein. AEP is canmitted to the successful and on-schedule implementation of the VDCS. The following schedule is contingent upon the objective previously defined remaining unchanged through the targeted completion dates. Additional regulatory requirements or unforeseeable difficulties arising from the full-scale implementation of the VDCS general procedure could cause delays. Because the implementation schedule is heavily dependent upon the performance of the vendors, the following are targets dates rather than commitment. dates.

1. VDCS General Procedure The corporate level general procedure and associated documents detailing the handling and review process for all VTD s has been completed and forwarded to AEP senior management for review and approval. Anticipating approval, implementation is proceeding and the VDCS is expected to be operational with the completion of the coayonent classification record described under 2.2.1.6.

2. Reactor Trip System (RTS) Component Vendors All RTS vendors have been contacted, and responses are being evaluated for determination of required actions. As the completion of this activity is almost totally dependent upon a vendor response it is not possible to project a completion date.

However, the timeliness of responses is being monitored, and those vendors who are late are being recontacted.

3 ~ Safety-Related Coaponent Vendors AEP is in the process of contacting all suppliers of safety-related components and requesting a list of technical documents (VTD s) pertaining to D.C. Cook Plant. Because of the depth of the information which must be gathered and supplied to the vendor for each component, this will be a lengthy undertaking. It is anticipated that all safetymelated vendors will be contacted and new documents reviewed and incorporated into the VDCS by the targeted date of December 31, 1985.

As the responses are received, they are evaluated for determination of required actions.

4. Incorporation of Existing VTD s into the VDCS The existing system for monitoring and tracking VTD s is much less sophisticated and incorporating these existing VTD s into the VDCS described herein requires a comprehensive inventory of the Cook Plant master files. This effort is underway and is anticipated to be completed by the targeted date of September 1984. Transfer of these VTD s into the VDCS will take approximately nine (9) months beyond this.

ATTACHMENT IV I

Amendments to pages 7, 23, and 24 of our submittal AEP:NRC:0838A dated November 4, 1983

The complement of programs for the P250 process computer includes two programs which are relevant to the analysis of reactor trips.

These two programs are the Post Trip Review Program and the Sequence of Events Recording Program The Sequence of Events Recording Program records the sequence of operation of a number of monitored contacts to a high time resolution. When one of the monitored contacts changes state, an interrupt is initiated which causes the P250 to scan each monitored contact for any change from its previous state. The program stores such changes and the cycle count since the first event. A cycle is nominally 20 milliseconds in length. Due to a dead time of 2 milliseconds in the interrupt process, an autanatic rebid of the program is programmed for the cycle following each interrupt bid. This is done to avoid loss of contact changes during the dead time. The Sequence of Events Recording Program is terminated when either the cycle count reaches 3600 or 25 contact changes have been recorded.

When the program is terminated, an output routine is called. All collected data are first moved to the output program buffers to free the Sequence of Events Recording Program buffers for continued monitoring. The output routine prints the time of the first event in hours, minutes, and seconds. Following this message, the alphanumeric address, a 36-character contact description, and cycle count from the first event are printed for "

each contact change. The first event will always have a cycle count of izero.

The P250 address list indicates that there is an input to the Sequence of Events Recording Program for each potential reactor trip. In the case of reactor coolant pump underfrequency, partial trips are also included. In addition, the reactor trip and reactor trip bypass circuit breakers, main generator output circuit breakers, and turbine stop valves are monitored'he time discrimination between events is one cycle or naninally 20 milliseconds. The format for data display is discussed above in the description of the program. The data is output on one of the P250 typewriters. The printer output sheets may be retained for future reference.

The primary power source for the P250 computer is an inverter supplied by the AB battery and 600 volt bus llB. If the inverter should fail, the P250 computer would be switched by an autanatic bus transfer to the control room power distribution circuit, CRP-3, which is supplied from the plant lighting transformer. The power source is balance of plant (non class IE).

4..5 S stem Functional Testing 4.5.1. STA and UVTA Testin The reactor trip breakers are currently tested on-line by operation of the undervoltage trip device ~

The present arrangement of four circuit breakers, two trip and two bypass, permits on-line testing of the breakers. We currently test the UVTA prior to every start-up and once every month during unit operation. The shunt trip is independently tested prior to each start-up. No failures have been encountered.

Once the modification to enable automatic actuation of the shunt trip attachment is made, we will test both the UVTA and the STA while the unit is in operation.

4.5.2. On-line Testin Since we perform on-line testing, this section does not apply to our plant.

4.5.3. Frequenc of On-line Testin Our position is as follows'.

The reactor trip circuit breakers at the D.C. Cock Plant are installed in a clean and dry location and are not subject to any deleterious environmental influences. The present maintenance program requires that the circuit breakers be serviced at every refueling outage. At this time the mechanical features of the circuit breakers are inspected and adjusted as necessary to maintain the critical clearances determined by the manufacturer to be necessary for reliable operation. The circuit breaker and its compartment are cleaned and lubrication is applied as recommended by the manufacturer. The main contact resistance is verified to be acceptable by test. The circuit breakers are then installed in the metal clad enclosures.

Prior to .returning the circuit breaker to service, an electrical functional test is performed which tests the electrical closing, electrical shunt trip and the undervoltage trip . In compliance with the Technical Specifications, the undervoltage trip of each circuit breaker has been tested on line at monthly intervals.

There have been no failures of the reactor trip circuit breakers to trip during tests or in actual operation. This history of excellent performance has been maintained for over 9 years for one unit and 6 years for the other. The present surveillance and maintenance program has been adequate, resulting in no failures.

The present maintenance schedule permits inspections and adjustments to the circuit breakers at intervals which are more frequent than necessary, considering the clean enviroanent and light electrical service required of the circuit breakers. The testing at one month intervals has provided the necessary exercise to ensure freedom of motion of the circuit breakers and its

attachments when they are called on to operate t'o perform their safety function. Assuming a maxiaam test interval of one hour for each on-line surveillance test for each circuit breaker, the reactor protection system is dependent on one safety train for 1 tripping for two hours every month. Increased on-line testing frequency will result in greater time dependency on one train for tripping without increasing the assurance that the reliability of the circuit breakers has been improved.

The Westinghouse Owner s Group is carrying out tests on these breakers. We expect to receive their results in February 1984.

If there are any changes we feel we need to make as a result of the tests, we will communicate to you by March 30, 1984.

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