ML20210A757

Fort St Vrain 1987 Power Ascension Plan

ML20210A757
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/30/1987
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20210A753	List: ML20210A748 ML20210A757
References
P-87038, PROC-870130, TAC-63576, NUDOCS 8702090007
Download: ML20210A757 (10)

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FORT ST. VRAIN 1987 POWER ASCENSION PLAN I

i Attachment to l

P-87038 i

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8702090007 870130 PDR ADOCK 05000267 PDR P

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l Attachment l

To P-87038 FORT ST. VRAIN 1987 POWER ASCENSION PLAN This Plan identifies the activities that Public Service Company of Colorado will perform during Fort St. Vrain's rise to power from its current shutdown condition to full power operation.

Key events, activity interrelationships, and plant condition prerequisites are identified.

The Fort St.

Vrain Overall Plant Operating Procedures (OPOP's) provide guidance for integrated operation of plant systems, for various operational conditions.

The OPOP's provide checklists for activities that must be complete prior to various milestone events, and these activities are summarized in this plan.

For specific details of the activities identified, the applicable OPOP's should be reviewed.

The following is a discussion of the activities shown on the attached schedule barchart.

The major milestones to be achieved in the 1987 Power Ascension Plan are: reactor criticality, operation up to 10%

power, operation up to 35% power, operation up to 82% power, and full power operation.

This Power Ascension Plan supplements the Fort St. Vrain Restart and Power Ascension Schedule (Startup Plan).

Activities addressed in this plan begin immediately prior to criticality and progress through the rise to full power operation.

1.

Commission Approval for Restart This activity represents that point in time when the NRC Commissioners grant approval for PSC to restart Fort St.

Vrain.

The regulatory, administrative and physical plant constraints to FSV restart are identified and scheduled on the Fort St.

Vrain Restart and Power Ascension Schedule (Startup Plan).

2.

NRC Approval for 35% Power Operations This activity represents that point in time when all regulatory constraints to 35% have been satisfied and the NRC grants permission for plant criticality and rise to power up to 35%, subject to a review of activities at 10% power by NRC Region IV.

The regulatory, administrative and physical plant constraints prohibiting plant criticality and plant operation up to 35% are identified and scheduled on the Fort St. Vrain Restart and Power Ascension Schedule (Startup Plan).

. 3.

OPOP I and OPOP III Pre-Criticality Testing This activity includes testing and other activities that will be performed prior to criticality, in accordance with OPOP's I and III.

These OPOP's ensure that the equipment status requirements and plant condition prerequisites are met in support of criticality.

Any administrative restrictions to criticality are also identified and satisfied.

OPOP I

includes checklists to ensure that applicable requirements are met.for various operating conditions such as PCRV pressurization above 100 psia, reactor startup, power increase above 2%, and power increase above 30%.

These checklists address such items as equipment clearances, Technical Specification surveillances, control room alarm

status, system valve lineups including independent verification, Operation Deviation

Reports, Temporary Configuration Reports, Station Service Requests, radiation monitors, PPS XCR's, electrical

relays, seismic snubbers, impaired fire protection notices, and Technical Specification equipment operability.

OPOP III contains FSV Startup Procedures.

It identifies the initial conditions, equipment operabilities, instrument checklists, and System Operating Procedures that apply to startup and the achievement of criticality.

In addition to satisfying the requirements of these OPOP's, PSC will provide an additional shift supervisor and management overview in the Control Room during the initial startup and during other major events.

4.

Control Rod Drive Operability Testing 4.1 Control Rod Drive Full Scram Test This activity includes the full stroke scram testing that is performed on all control rod pairs prior to restart.

This testing involves verifying a full stroke scram time less than or equal to 152 seconds, in accordance with Interim Technical Specification SR 4.1.1.0.

. 4.2 CRD Partial Scram Testing This activity includes the partial scram testing that is performed on Control Rod Drives for any control rod pair being withdrawn to achieve criticality.

This testing involves partially scramming a control rod pair at least 10 inches, and extrapolating the elapsed time to that for a scram from the fully withdrawn position.

Partial scram testing is also performed weekly for all withdrawn control rod pairs.

4.3 Back EMF Testing This activity involves Back EMF testing of the Control Rod Drive assemblies, to be performed in conjunction with the partial scram tests identified in Item 18.

Back EMF testing is being developed as a diagnostic tool to identify the presence and trend of any CRD degradation.

4.4 Control Rod Drive Temperatures This item represents the daily monitoring activity required to ensure compliance with Interim Technical Specification LCO 3.1.1 to veri fy Control Rod Drive motor temperatures remain below 250 F.

Note: If temperatures exceed 215 F then increased surveillance is required.

5.

Reactor physics Testing 5.1 T-216 Nuclear Detector Decalibration Testing, Cycle 4 This activity involves testing from precriticality through 100% power to confirm the nuclear detector decalibration curves provided by GAT for Cycle 4.

This testing involves reperformance of that rise to power testing performed in June 1984.

L

. 5.2 SR 5.1.3 Rx Temperature Coefficient of Reactivity Calibration This activity involves measurement of the reactivity change as a function of core temperature, from precriticality through 100%

power.

The testing performed in June 1984 will be repeated during this power ascension.

5.3 SR 5.1.5 Rx Control Rod Reactivity Worth Testing This activity involves measurement of the reactivity worth of the control rods which are withdrawn from low power to power operation.

This testing verifies the calculational criteria used in the rod withdrawal sequence and includes a reperformance of that testing performed in June 1984.

I 5.4 RT-500L Core Temperature Fluctuation and Redistribution This activity includes testing to be performed between approximately 40% power and 100% power.

This test activity will confirm PSC's resolution of the core temperature fluctuation problem.

6.

In Service Leak Testing This activity includes testing to verify the acceptable leak-tight integrity of the Fort St. Vrain systems that were worked on during the current outage. Much of this testing will be complete prior to criticality.

Portions of this testing require system pressures that will be reached at higher power levels, up to 50% power.

7.

SLRDIS Testing Operability of the Steam Line Rupture Detection / Isolation System will be demonstrated prior to reactor criticality. All applicable Technical Specification surveillance tests will be performed, including calibrations, functional tests, actuation logic tests, and response time tests.

, 8.

OPOP III.C Startup Activities and Testing This item includes activities and testing from startup to 2%

power. Written management approval is required and activities through criticality up to 2% power are conducted.

9.

OPOP I11.0 Training Starts Immediately following reactor criticality licensed reactor operators will perform training starts and shutdowns in accordance with OPOP III.D. Approximately 40 training starts are contemplated.

10. Nuclear Dryout Using nuclear heat, moisture in the PCRV is removed via the helium purification equipment.

Reactor flows and temperatures are varied in an attempt to accelerate this process, subject I

to the constraints of LC0 4.2.11 which includes a limitation on dew point as a function of average core outle'. temperature.

This activity includes dryout down to a total of 10 ppm for H 0, C0 and CO impurities, at which time average core outlet 2

2 temperatures can be raised above 1200 F, per LC0 4.2.10.

11. Vibration Test on A & C Boiler Feedwater Pumps This activity involves a series of vibration measurements that will be taken on the turbine driven boiler feedwater pumps.

These measurements will be taken prior to criticality and at other power levels indicated on the attached bar chart, and will confirm the acceptability of recent modifications for reducing pump vibrations.

12. OPOP III.E & F Rise to Power Activities and Testing OPOP III.E addresses the activities and testing that is performed in preparation for reactor operation above 2% power.

Above 2%,

the FSV reactor is considered to be "at power" and the majority of the Technical Specification requirements for system operability apply. This activity assures that system performance parameters are within limits so that the plant will be in compliance with the applicable Technical Specifications.

. OPOP III.F addresses power increase from 2% to 30%.

This includes placirg the Interlock Sequence Switch (ISS) in " Low Power", placing the turbine generator on-line, and placing the ISS in " Power" at 30% power.

13. Appendix R Fire Protection Shutdown Model Procedure and Training This activity includes revision of the Emergency Procedures to reflect the fire protection shutdown models identified in PSC's Appendix R submittals. Operator training in these fire protection shutdown models will be complete prior to exceeding 8% power.

14. NRC Region IV Approval for Operation Above 10%

Prior to exceeding 10% rated thermal power, the NRC Region IV will review the power ascension activities.

Region IV approval is required prior to entering boilout and resuming the rise to 35% power operations.

15. OPOP IV Rise to Power Activities and Testing (35% and 82%)

OPOP IV covers plant operation between 30% and 100% power, including safe and efficient operation at intermediate power levels such as 35% and 82%.

16. NRC Approval for 82% power Operation This activity represents that point in time when all regulatory constraints to 82% have been satisfied and the NRC grants permission for plant operation up to 82%.

The regulatory, administrative and physical plant constraints prohibiting plant operation up to 82% are identified and scheduled on the Fort St. Vrain Restart and Power Ascension Schedule (Startup Plan).

17. R.O. Candidate Training Starts This activity involves a reduction in power so that the current class of reactor operators can perform training starts. This is scheduled to occur in October 1987.

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. 18. Surveillance Shutdown This item represent a planned plant shutdown to perform a loss of off-site power Tech Spec surveillance test. This item may not require a plant shutdown if NRC concurrence is obtained for the PSC submittal that justifies a semi-annual simulated Loss of Off-Site Power test without plant shutdown in conjunction with a complete Loss of Off-Site Power surveillance test to be performed during the scheduled refueling outages.

19. B Series Testing 19.1 Full Load Rejection Test This activity is performed prior to long term, high power operation and confirms the ability of the plant to withstand a loss of full electrical load and the satisfactory performance of reactor systems.

19.2 Xenon Stability Testing This activity demonstrates the xenon stability characteristics of the reactor core, prior to long term, high power operation. Xenon oscillations are initiated by inserting an out of sequence control rod pair, and reactor performance parameters are compared with expected values.

20. NRC Approval for Rise to 100% Power Operation This activity represents that period of time wt." r all regulatory, administrative and physical plant constranats to 100% power operation have been satisfied and the NRC grants permission for plant operation up to 100%.

21. Refueling Outage (November 1988)

This item represents the planned plant outage for the 4th refueling. Any modifications required for release to 100%

power operation may be performed during this plant outage period.

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