ML20082U885

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Cycle 1 Startup Test Rept 4
ML20082U885
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 12/06/1983
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20082U884 List:
References
NUDOCS 8312190207
Download: ML20082U885 (51)
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Text

x 6x,-  ;, STARTUP TEST' PROCEDURE 1 CHEMICAL'AND RADI0 CHEMICAL MEASUREMENTS L

'1. PURPOSE "A.. The principal objectives.of.the Chemical and Radiochemical Tests are.to secure'information on the chemistry and radiochemistry of the reactor coolant, and to determine

..that the sampling equipment,_ procedures, and analytical'

. techniques.are . adequate to supply the data required to demonstrate that the chemistry of. all . parts of the entire reactor system meet specifications and process-requirements.

B.. Specific objectives of the test program include indirect observations of fuel clad integrity, evaluations of-demineralizer, operations by direct and indirect methods, measurement of filter performance, confirmation-of condenser integrity, measurement and calibration of the off-gas system, .and calibration of certain process -

. instrumentation. Data for these purposes lis secured for a variety of sources: plant operating records, regular routine coolant analysis, radiochemical measuremens of specific nuclides,;and special chemical test on fluids.

~2.  : CRITERIA Level 1 A.. Water quality must be' known at all times ad must remain within the guidelines of the water Quality Specifications. i

-B. The activities.of gaseous and ' liquid effluents must be 1knc,wn'and must conform to license limitations.

C. Chemical' factors defined in'the Technical Specifications and Fuel Warranty must be maintained within the limits specified.

~

3. RESULTS Test Condition 6

' Analysis of~radiolytic gas in steam and chemical / radiochemical tests of. reactor water, condensate demineralizer inlet and effluent, feedwater, off gas pre-treatment and plant vent were conducted. Measurements of. stored water (clean demineralized water storage tank,. cycled condensate-storage tank, suppression ,

pool, -. condenser hotwell, and heater drain tank) quality and condensate /feedwater systems. filterable iron concentrations were-taken. Reactor water quality was monitored during the no

' reactor water cleanup test.

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IAlthough'cIl--ttst rcsults were within the Technical Specific ticn licits, some paramet:rs wera cutsids the'GE

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specified values. GE has evaluated these criteria-exceptfons and has'found plant chemistry to be acceptable, f

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E_ 1 STARTUP TEST-PROCEDURE 2 RADIATION MEASUREMENTS-i

1. PURPOSE

-l The purposes of this test lare:

A. To determine the background radiation levels in the plant i environs prior to operation:for use as-base data on activity build-up.

.B. LTo monitor radiation at selected power levels to identify potential deficiencies .and assure the protection of personnel during plant operation.

To provide sufficient data _ (exposure rate and dose ,

C. . . equivalent rates) to' allow' comparison of the actual dose rates with the design dose equivalent rates outside selected plant shield structures and ' room entrances for

.potentially~ radioactive equipment.

2 .- CRITERIA LevelL1 A. The radiation doses-of plant origin and the occupance times of personnel- in radiation ' zones shall be . controlled.

. consistent with the guidelines of the standards fer

. protection against radiation as outlined in 10Cfd20, NRC General Design Criteria.

3. RESULTS This test was performed at test condition 6. The results of the radiation surveys showed that all radiation levels were within 1the respective criteria.

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  • :, . ,.. .STARTUP TEST PROCEDURE 5-CONTROL ROD DRIVE SYSTEM
1. PURPOSE' A. The purpose.of this test'is as follows:
1. To demonstrate that the Control Rod Drive (CRD) system operates properly over-the full range of primary.

coolant temperatues and pressures from ambient to operating.

2. To. determine the initial' operating characteristics of the entire CRD system.
3. To demonstrate the optimum settings'for the:CRD flow

. control loop by analysis of the transients induced in

- the CRD Hy d raulic System by means of CRD flow setpoint changes .

4.- To verify that the flow control' valve (FCV) closes to a minimum position within 10.to 30 seconds in response to the maximum error. signal (scran).

5. . To demonstrate that the FCV maintains a constant flow within 13 gpm as the reactor pressure changes from a shutdown condition to the normal operating pressure.
2. CRITERIA

. Level 1.

A. Each CRD must have a. normal _ withdrawal speed less than or L equal to 3.6.inchas per second indicated by a full 12 foot stroke in greater than or equal tto 40 seconds.

-B. The mean scram time of all operable CRDs with functioning.

accumulators must not exceed the following times: (Scram time is measured fra the time the pilot scram valve solenoids.are de-energized), i Position Inserted ,

From Fully. Scram Time Withdrawn (Seconds)

- 45 - 0.43 39 0.86 25 ' 1.93 05 ' 3.49

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+ , _.,7 C. The mean scram time of the three fcstsst CRDs in a two by

- two crrcy must not .exczed the following times: (Scrca time

- is; measured from the. time the pilot scram valve solenoids are' deenergized).

Position ~ Inserted-From Fully Scram: Time

{~ Withdrawn __

(Seconds) 45- -0.45

-39 0.92

25. 2.05 05' 3.70' D. The scram insertion time of each control rod from full out-

-to position l5, ~ based. on de-energization of the scram pilot

~

E - valve solenoids as time zero, shall not exceed 7.0 seconds. ,

Level.2.

o A. Each CRD must have a normal-insertion or withdrawal . speed

- of .3.0 ~ 0.6 inches' per second indicated by a full 12-foot stroke in 40 to 60- seconds.

B. - With_ respect tofthe CRD Friction tests, if the differential

- pressure . variation exceeds 15 psid for a continuous drive

- in, a settling test'must be performed, in.which case, the differential settling pressure should rx)t be -less than 30 psid' nor-should it vary more than 10 psid over a full stroke. Lower diffe'rential pressures are indicative of '

excessiveLfriction.

-3.- Results Test Condition 3

. CRD' scram timing (section 10.2.J) was performed in conjunction

with STP-25, MSIV Full. Isolation and.STP-27, Generator Load Rejection.

Scram times for ~25 drives were obtained in conjunction with STP-25 and their 90% times were within the . level 1 acceptance criteria (le's s than or equal- to 7.0 seconds). See Table 1.

Scram times.for' 23 drives were obtained in conjunction with

. STP-27 and their 90% times were within the level 1 acceptance

-criteria (less Lthan or:equalf to 7.0 seconds). See Table 1.

~

All CRD testing at~ tost condition 6 was satisfactorily completed.

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TABLE 1 TEST CONDITION 6' SCRAM TIMES i Slowe'st 905-scram time

~

in~ conjunction with STP-25: CRD 30-19, 2,564 seco'nd s

-Slowest 90% scram time' h

in conjunction _with  :

- STP-27: CRD 30-43, 2.556 seconds l 1

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STARTUP TEST PROCEDURE 9 WATER LEVEL' MEASUREMENT

'1; PURPOSE A. The purpose of.this' test.is as follows:

-1.

To check the calibration of the various narrow range

-and wide. range indicators

2. 'To measure the; reference leg temperature and recalibrate the narrow and wide range instruments if the measured temperature is different than the value assumed during the-initial calibration.

3.- ~ To collect plant data which can be used to investigate the effects of core flow velocity, carry-under, and subcooling on indicated wide- range level.

2. -CRITERIA.

Level 2

~ A.: -The narrow range level indicator readings on the

.~ instruments used for.feedwater level control (IC34-R606A-C)-

should agree within- 1.5 inches-of their average reading.

- B. The narrow range' level-indicator readings on the

-instruments not used.for feedwater level control-(1821-NO24A-D, 1821-NO38A-B, 1821-N100A-8, and-1821-N101A-B) should. agree within f3.0 inches of their average reading.

. C. ;The wide range' level system indicators (1821-NO26A-D, 1821-NO31A-D, 1821-NO36A-D,-IB21-NO37A-D, 1821-R604c- ,

-IC61-RO10, 1821-R623A-B should. agree'within'36 inches of.

the average reading.

. 3 .' Results .

A.- l Test Condition 6.

1. All narrow and wide range level instruments satisfied

-their respective level 2 criteria (see Table 1).

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WR. ACCEPTANCE ACTUAL DEVIATION

-INDICATOR- READING # AVEN (CRITERIA

  • FROM AVERAGE
  • 1821-NO3'6C . 23 21.1 ~ + 6.0' '+ 1.9

.1B21-N0268 23~ 21.1 i 6.0 +1.9 6.0 -1.1 1821-NO378 20 21.1

'1821-NO360 L22 '21.1 i 6.0 +0.9

-1821-NO37D- 22 21.1 -6.0 +0.9 1821-N026C 21 21.1  ; 6.0 -0.1 1821-NO318 20 21.1. 6.0 -1.1 1821-NO31D- 22 21.1 f 6.0 +0.9 l1821-NO36A 21- 21.1 6.0 -0.1 1821-NO37C- 17. '21.1 'i 6.0 -4.1

~1821-NO37A ~ 18 '21.1 -f.6.0 -3.1 e

1821-NO26D 20' 21.1 f;6.0 -1.1 i

IB21-NO36B 20 21.1 f 6.0 -1.1

~1821-N026A 22.5- 21.I f,6.0 +1.4 IB21-NO31A- 23 21'.1 i-6.0 +1.9 e .1821-NO31C .20 21.1 i 6.0 -1.1

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WR, ACCEPTANCE ACTUAL DEVIATION INDICATOR READING W AVEN CRITERIA

  • FROM AVERAGE *

-1821-R884A- 24. 21.1 i 6.0 +2.9 1821-R884B .22 21.1 f 6.0 +0.9 1821-R604 24- 21.1 f 6.0 +2.9 1C61-RO10 -18. 21.1 f 6.0 -3.1 1821-N0244 34.5- 34.3 f 3.0 +0.2 1821-N0248 -35 34.3 3.0 +0.7 IB21-N024C 35 34.3 f 3.0 +0.7 1821-NO24D :34 3'4.3 f 3.0 -0.3 -

1821-NO38A 34 34.3 i 3.0 -0.3

-1821-NO38B 33 34.3 f 3.0 -1.3 1821-N100A 35 34.3 3.0 40.7 1821-N1008 35 34.3 f 3.0 +0.7 L1821-N101A .33 34.3 f 3 30 -1.3 1821-N101B 34 34.3 f 3.0 -0.3 1C34-R606A 37 36.3 f 1.5 +0.7 1C34-R6068 ~ 36 36.3 f 1.5 -0.3 i

IC34-R606C 36 36.3 f 1.5 -0.3

  • All Data have units in-inches r

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... 'STARTUP TEST PROCEDURE 11 LPRM CALIBRATION

1. - PURPOSE A.. .To verify proper response of the-Local Power Range

' Monitoring (LPRM) System to. local changes in the reactor power level.

B. To calibrate the LPRM system.

2 .- CRITERIA Level 2~

A. Each LPRM reading will be within i 10% of its calculated value.

3...RESULTS-The .LPRM detectors;were successfully calibrated to read proportional:to the neutron ' flux at their locations. This was-accomplished by ~ using the Traversing Incore Probe (TIP) System. *

-The test was satisfactorily completed at test condition 6 and

all applicable-criteria were met.

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STARTUP TEST-PROCEDURE 12 APRM CALIBRATION

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1. PURPOSE A. ' The purpose of this test is to calibrate the Average. Power Range Monitor- (APRM) system.
2. . CRITEI R A' 1A. Level 1

' 1. The APRM channels ~ must W calibrated.to read gerater

.than'or equal to the actual core thermal power.

However,.recalibration'of the APRM system will not be necessary from safety considerations if at least two APRM channels'per RPS trip. circuit have readings greater than or equal to actual core thermal power.

I 4 .

The.APRM scram and rod. block setpoints shall be set no 2.

higher than the limits specified in the Technical Specifications and the fuel warranty document.

p 3. 'In the STARTUP mode, all APRM channels must produce a scram at-less:than or equal to 15% of rated ' core thermal power.

B. Level 2-

1. If the above level I criteria are satisfied, then the APRM channels will be considered to _ be reading

~

accurately'if they agree with the heat balance to within i 7%'of rated core thermal power.

3. RESULTS

~

Testing at test conditions' 6 and _ Warranty Run were successfully completed, and all applicable criteria were met. .The APRM's-

- were adjusted to the results of'an OD-3 heat balance, and alarm

- and' trip settings were _ demonstrated to be less than or equal to

' their~ respective limits.

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'STARTUP. TEST PROCEDURE 13 PROCESS COMPUTER'

l. 1 PURPOSE A. 'The purpose.of'this test is to verify the performance of the . process computer under plant operating conditions.
2. CRITERIA A. Level 2'
1. Programs 00-1, P1 and OD-6 will be considered operational when:

'A. The MCPR calculated by BUCLE and the process computer either:

)

1. Are in the same fuel assembly and do not

-differ in value by more than 2%, or

2. For the case in which the MCPR calculated by the process computer'is in a different assembly than the calculated by BUCLE, for each assembly, the MCPR calculated by the two methods shall~ agree within 2%.

B. The maximum LHGR calculated by BUCLE and the process computer either:

. ' 1. Are in the same fuel assembly and do not differ in value by more than 2%, or

2. -For the case in which the maximum LHGR.

calculated by the process computer is in different assembly than that calculated by BUCLE, for each assembly, the maximum LHGR's calculated:by the two methods shall agree within 2%.

C. The MAPLHGR calculated by BUCLE and the process computer either:

1. Are in the same fuel assembly and do not differ in value by more than 2%,.or h

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= 2. Fcr the crso in which the MAPLHGR calculsted by-the precess computcr.is in o diffcr:nt assembly : than that calculated .by BUCLE, for each assembly,.the MAPLHGR's calculated by

'the two methods shall agree within 2%.

D. -The LPRM calibration factor calculated by BUCLE and the process computer agree to within two

-percent (2%).

E. . The remaining programs will be considered -

operational upon successful completion of the static and dynamic testing.

3.- RESULTS

~ Test Condition 6

. Program testing at test condition 6 has been successfully completed. All applicable criteria were satisfied.

Thermal Limit data.at 98.6% power:

- A. MLHGR Comparison ,

Method MFLPD Location i P1 0.819 11-18-12~

BUCLE 0.818- 11-18-12 8.- MAPLHGR' Comparison Method .MAPLHGR zLocation-

'P1 9.93 11-18-12 BUCLE 9.92- 11-18-12 C. MCPR Comparison

-Method MCPR Location LP1 -1.525 13-16 6' BUCLE 1.527 13-16 h

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. STARTUP TEST-PROCEDURE 16

~ SELECTED PROCESS TEMPERATURES

1. PURPOSE A .= The~ purposes of.this test are as follows:
1. To assure that'the measured bottom head drain

~ temperature corresponds to bottom head coolant temperature during. normal operations.

2. To identify any reactor operating modes that could icauseLtemperature stratification.
3. To determine the proper setting of the low flow control valve limiter for the recirculation pumps to avoid coolant temperature stratification in the reactor pressure vessel bottom head region.
4. To familiarize plant personnel with the temperatue ,

differential limitations of the reactor system.

2. CRITERIA A. Level 1..

The reactor recirculation pumps shall not be started

~

1.

'nor. flow increased.unless the coolant temperatures

' between the steam dome' and bottom ' ?ad drain are 1

within 1450F (810C).

.2. The recirculation pump in an idle loop must not be started unless the: loop suction-temperature is within i 500F (280C) of the active loop suction temperature if orie pump is idle or the steam dome temperaturelif -

two pumpsLare idle.

B. ' Level 2.

( 1. During two pump operation at rated core flow, the bottom head coolant temperature, as measured' by the.

bottom drain line thermocouple, should be within 300F-(170 C) of the recirculation loop temperatures.

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-4 3 . -- RESUL.TS i

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LTest Condition'6'

' Analysis "of the .testidata showed no' evidence of thermal ~

- stratification'in the. event of-single recirculation-pump trips.

?The.following maximum delta' temperatures were observed during

.-.te s ti ng .

Steam Dome -Bottom Head .32.8 0F

-One Pump Trip:. ~ Idle Loop -: Active Loop70F

-TwoLPump Operation: Bottom Head - Recire Loop 5F0

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ISTARTUP TEST PROCEDUREL17'.

.. 1.

. SYSTEM. EXPANSION

7. .

.l.7; PURPOSE A. Verify that the reactor drywell piping 1 system is free and P unrestrained :with regard to thermal-- expansion.

4 B;; . Verify that. suspension components are1 functioning in the Jspecified manneri

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~.-2'. ' CRITERIA ~

i Level l'

1. ;There shall.be no evidence of blocking of the

, .displacementsiof any system component caused by thermal expansion of the; system.

.2. Electrical cables shall not be fully stretched.

L3. . Hangers'shall not be bottomed our or have the spring fully stretched.-

4. ' Snubbers shall.be in the operating range ~about the 1
midpoint of the total travel range at operating ~

temperature. 7

1. The measured ' steady state displacement of the -

recirculation and main steam systems shall not exceed the allowable values.

B .' Leve.1 2.

1.-- At a steady-state-condition, the' displacements of

-- ' instrumented . points'with displacement measuring Jdevices shall not vary.from the calculated values. If measured displacements do~ not meet these criteria, the. piping design engineer'must be contacted to

. analyze the data with ' regard ' to design stresses.

2. During the heatup. cycle, the trace of instrumented points on the main- steam. and recirculation systems shall fall within-a range of 150 percent of the calculated value from the initial cold position in the direction of the calculated value and 50 percent of the: calculated value from the initial position in the opposite direction of the calculated value.

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3. Hangers:will be in their operating range between the hot and cold settings.

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-: ' : 3. RESULTS'

.-Test' Condition 6

, Displacements of' instrumented points were recorded at steady state power. Displacements for. certain points exceeded Level 2 fl- icriteria but: analyses by General Electric and -Sargent and Lurufy-ha'e v shown these' exceptions to be acceptable with actual

. displacements yielding acceptable stress levels.

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STARTUP' TEST PROCEDURE 18

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CORE POWER DISTRIBUTION -

1. . PURPOSE.

' A .' The' purposes of-this t'est are:

1. To determine the core power distribution in three dimensions'.

c.To determine the reprvducibilit,y of 1.he Traversing

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In-Core Probe (TIP) system readings.

2. ACCEPTANCE CRITERIA

+-

A. Level ~2

~

- l'. The' total TIP uncertainty (including random noise,and-geometric uncertainties) obtained by averaging the uncertainties for. all data shets must be -less than -- '

6.0%.

- NOTE

'A minimum of two and a maximum of six data sets may be used

- to meet the above criterion.

3. RESULTS: i
Test Condition-6 LTip data taken at this test condition was evaluated along with

~-that~.taken at test condition 3. T he to at l TIP uncertainty for both data sets was' found to 'be 2.47%.

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STARTUP' TEST PROCEDURE'19.

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CORE PERFORMANCE '

l- 1. : PURPOSE A ~.- The purpose of this-test ~1s'to evaluate the following core-performance parameters:at Test Conditions 1 through 6:

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1.- Maximum' Linear Heat Generation Rate (MLHGR). .,

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.2; Minimum Critical Power Ration (l'iCPR).

~3. . Maximum Average Planar Linear Heat Generation Rate

? (MAPLHGR).

, i4. Core Thermal Power _(CTP).

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'2. ~ CRITERIA

-A. Level-1.

1. - The Maxinum Linear Heat Generation-Rate (MLHGR) of any rod during steady state conditions shall not exceed

- 13.4 Kw/ft.

12. The steady state-Minimum Critical Power Ratio (MCPR) shall not exceed the limits specified in the plant technical specifications.

.- 3. The Maximum Average Planar. Linear Heat Generation Rate

. (MAPLHGR)'shall not_ exceed the limits shown specified

- in the plant technical specifications.

1

-4. Steady' State' reactor power shall be limited to 3323 l

__IWt and values on or below Lthe analyzed flow l control . i

' line. 1

3. RESULTS

'The core performance parameters were demonstrated to be within Lthe range. required by the Technical Specifications for Test' Condition' 6 'and Warranty ,Run (Table 1) .

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ICore Perforgance Data.

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.' Core Value ~Value Level 1 .

Parameter- TC 6_ W.Run. ' Criteria Limit-

'CTP (PWt)- _ _3237- 3268

'3256 1 -3270 MLHGR-. 11 38 11.0 13.4-p, EL ~

MCPR 1.52 ..

-1.24-

1. 513 ..' 1.242

' MAPLHGR  :'10. 2 :

12.05 9.95-- 12.06--

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,o~ e STARTUP TEST PROCEDURE 20 STEAM PRODUCTION

1. PURPOSE A. To demonstrate that the nuclear steam supply system is

.providing. steam sufficient to satisfy all appropriate.

warranties as defined in the contract.

2. CRITERIA:

3 A '. tLevel 1.

The NSSS parameters as determined by using normal

~1.

operating procedures shall be within the appropriate license restrictions'.

3. RESULTS-The steam production verification initially scheduled.to be

-performed during 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> ~of-continuous operation at near rated power.was actually performed in two parts. The first two of three' scheduled data sets were taken during a 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> period of

-continuous operation at rated power. The plant was then forced to . reduce power due to a non-NSSS problem. By mutual agreement

.with GE, the third data set was taken after the plant was able to return to rated power.and stabilize.

All applicable criteria wers met during the test' period.

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. STARTUP TEST PROCEDURE 22 PRESSURE REGULATOR

1. PURPOSE A. To determine the optimum settings for the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of the pressure regulators.

B. To demonstrate the takeover capability of the backup j pressure regulator via simulated failure of the controlling pressure regulator and to set the regulator setpoint difference between the two regulators to an appropriate value.

C. To demonstrate smooth pressure control transition between the turbine control valvas and bypass valves when the reactor steam generation exceeds the steam flow used by the turbine.

2. CRITERIA A. Level 1.
1. The transient response of any EHC system-related variable to any test input must not diverge.

B. Level 2.

1. System-related variables may contain oscillatory modes of response. In these cases, the decay ratio for each control}ed mode of response must be less than or equal to 0.25.
2. The response time from pressure setpoint unput until the pressure peak of the pressure peak of the pressure regulator inlet pressure must be less than or equal to 10 seconds, with the Recirculation Flow Control System in the Position Command Mode only.
3. Pressure control system deadband, delay, etc. , shall be small enough that steady state limit cycles (if any) shall produce steam flow variations no larger than i 0.5 percent of rated steam flow.
4. The normal difference between regulator setpoints must be small enough that the peak neutron flux and peak

-vessel pressure remain below the scram settings by 7.5 percent and 10 psi respectively, for the Regulator Failure Test performed at Test Condition 6.

'4:

3. RESULTS A. .

Test Condition 6 Pressure regulator system testing was' performed with the turbine-generator load selector set so the pressure.

transients were controlled by 1) the turbine control valves, 2) turbine control valves and the turbine bypass

. valves, or 3) the turbine bypass valves. For each of these operating conditions, pressure setpoint step changes and simulated regulator failure-tests were performed.

b"O all applicable test result's were acceptable and applicable

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criteria were satisfied.

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Lc, STARTUP. TEST PROCEDURE 23A FEEDWATER CONTROL SYSTEM-

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, 1.- PURPOSE ~ '

. A.: The purpose of this' test is as-follows:

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1. To demonstrate satisfactory reactor water level and feedwater:. flow rate control. Measurements of 3 _ _

' feedwater system stability and performance are.

'~ <f J C analyzed for this determination.

? 2.- ACCEPTANCE CRITERIA A. ' Level 1 i '

'1. In the automatic mode,-the response of any. level'

system controlled _ variable-to any' test input change or

- disturbance' must not diverge. ,

-B.  : Level 2

1. Level control syst'em-related variables may contain

. Los~cillatory modes of response. In thes. cases, the decay ratio for each controlled mode of response. . In i these. cases,. the decay ratio for each controlled mode of response _must be less than or. equal to 0.25.

2. The average rate of response of theLfeedwater turbines to large (greater than 20%) step disturbance shall' be between 10 percent to 25 percent of pump rated

= flow /secondi This average response rate will be-assessed by determining the'~ time' required..to pass

-linearlysthrough the 10% and 90%. response points of the flow transient.

3. -The. dynamic flow response of each feedwater actuator

-(turbine or valve) to small (less than 10%) step

, distrubances.in the manual mode shall be:

a. -Dead Time 61.0 sec
b.  : Maximum time to 10%* 51.1 sec.
c. . Maximum time from 10%'to 90%*' $1.9 sec.
d. Settling time to within f5%* of the final:value 514.0 sec.
e. Peak overshoot * $15%

~

  • % of input step disturbance.

L '*f

~

' .:- :3.. RESULTS -; _

l At ' test condition 6,.: level setpoint steps with both turbine_

driven reactor. feed pumps ~-in 3-element were successfully completed. -All: applicable ~ criteria were satisfied.  ;

.j' a

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i STARTUP TEST PROCEDURE 23--B FEEDWATER SYSTEM', LOSSLOF FEEDWATER HEATER

1. PURPOSE- ,

.A. To-demonstrate adequate response to-feedwater heater loss.

2. 1 CRITERIA
A. Level 1-
  • ~

fi. The maximum feedwater temperature decrease due to a

- single failure case must be less- than or equal to

-1000 F. 'The resultant MCPR must be greater than the fuel. thermal ~ safety limit.

2 .' The increase in simulated heat flux cannot exceed the.

.preducted level 2 value by more than 2%. The predicted value will be based on the actual test

. values of feedwater temperature change and power level.

A. ' Level 2.
1. The increase in simulated heat flux cannot exceed the

~

preducted value referenced to the actual feedwater temperature change and power level- .

3. RESULTS Testing was satisfactorily-completed at test condition 6. The feedwater. temperature change and minimum MCPR observed when extraction steam to both high pressure heaters was isolated were '

56.90F and 1.727 respectively. The observed delta heat flux l of 7.9% was well within the preducted value of 8.73%. I l

l l

~

l 1

______.m________ _ _ . _ - _ _ -

+ _ - .

4 -STARTUP TEST PROCEDUREL23C A '

FEEDWATER SYSTEM, FEEDWATER PUMP TRIP

. PURPOSE

A. -To demonstrate the capability of the automatic core flow

' runback feature to prevent. low water level scram following

, the trip of one feedwater pump.

' B .- , To . demonstrate the ability of the standby motor driven feedwater pump'to maintain water level' if the turbine:

~ ^

driven _ system is totally lost.

-2. CRITERIA 1

~ Level'2-A. -A scram must not occur from low water' level following a trip of one of the operating feedwater pumps. There should be greater than 3 inch water level margin to scram for a feedwater pump trip initiated at 100% power. conditions.

3. -RESULTS

- Testing was successfully completed at test condition 6 and all applicable criteria were satisfied.

  • . Test results determined a 9.9" margin to a low level scram at

~100%' core thermal power.

Analysis of transient recorder data determined that the level

controller behaved as predicted in-the Control Systems Design Report (CSDR)Lin response to the reactor water . level drop induced by the feedwater pump trip.

l A 1 .STARTUP; TEST PROCEDURE 23D FEEDWATER SYSTEM, MAXIMUM FEEDWATER RUN00T CAPABILITY.

L1. ' PURPOSE-

The purpose of' this teste is to determine the maximum feedwater

~

runout capability.

2.. ' CRITERIA m,, . ..

. Level'1

-A. The feedwater flow runout capability must not exceed the

assumed valu~e.in the FSAR.

'3. RESULTS

, A. -Test Condition 6 Turbine driven feed pump performance data was taken during the power-ascension-to' Test Condition 6. Then, each turbine driven feed' pump was run up to -it's high speed stop to verify that it's capacity was less than that assumed in the FSAR for a runout condition. The test results are as follows:

Measured Runout Flow = 18.77 Mlb/hr FSAR Assumed Runout Flow = 19.22 Mlb/hr

. - ~

4 STARTUP TEST-PROCEDURE.24~

TURBINE VALVE SURVEILLANCE

1'., PURPOSE' iA. (The purpose of this_' test are'as follows

1.' To demonst'rsta acceptable procedures and maximum power levels- for' surveillance testing of the main turbine

m. - control, stop,.' and bypass valves withot producing a

", reactor scram.

~2. - To establish baseline ~ data for evaluating test.

condition acceptability'with respect to PCIOMR during future-startup tests.

2. ACCEPTANCE CRITERIA A. Level l'
1. _The decay ratio of an oscillatory response must be

-less than 1.0.

.B. Level 2.

.1. -

The peak neutron flux must'im at least 7.5 percent below the scram trip setting. .-The peak heat _ flux must

~

remain at least 5 percent below its scram trip.

.~

setting. . The peak vessel pressure must remain at least 10. psi below the high pressure scram setting.

2. The peak steam flow-~in each line must remain 10 percent below the high steam flow isolation trip 1 setting.:

3 .~ The decay ratio.of any oscillatory response must be less. than 0.25, when operating above -the minimum ~ core flow for the recirculation master manual' mode.-

3. 'RESULTS Testing was completed during the ascension ~ to test condition 6 ~

- at 70%:and 90% core thermal power (CTP) and again at test condition 6 with power at' 95% of- rated.

Testing yielded satisfactory results with the following margins to scram:

Neutron Flux 12%-

Heat Flux 14.4%

JVessel Pressure 54.5 psi v ~ , .p--,--y y g. n.,,. , , , - . , . , -

y . 4,,----,, , ,- ,, -,--,.n.w-- g ,

7;.

.- Some escillr,t:ry behavicr- was noted during the induced prsssura -

-.. ' tr:nsi;nt but specific'st:rtup tssts on the cpplicablo-systccs

'have shown~the control systems to be stable .

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  • ww m - v w

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4 iSTARTUP TEST-PROCEDURE.25: -

+ .

MAIN STEAM ISOLATION VALVES 1.r-POAPOSE-

= -A. .fhe-purpose of this' test is as follows:

- 1. xTo functionally check the main steam line isolation

. valves (MSIV's) for peroper operation at selected M"- ,powcr.Icval.

2. .To determine isolation valve closure times.
43. To determine the maximum power at which full closures of a single valve" can be performed without a scram.
4. To determine-the reactor transient behavior resulting

=from the' simultaneous full closure of all MSIV's.

I2. CRITERIA

'A.. llevel'1

~

1. MSIV closure time, excluding electrical delay shall be-O. -no faster thar. 3.0 seconds and-including electrical delay shall no slower than 5.0 seconds (each valve,

.not averaged).

2. The positive: change in vessel dome pressure occurring

.within.30. seconds after the full MSIV closure from greater than 95% of rated power must not exceed the Level 2 criteria, 6.2.Dj by more than'25 psi. The

- - positive' change in simulated heat flux shall not exceed the Level 2 criteria, 6.2.D,-by more than 2% of

-rated value.

'3. Feedwater-control systems settings must prevent' flooding of the steam lines.

-B. Level 2.

1.  : During full closure of individual valves:
a. Peak vessel pressure must be 10 psi (0.7

.Kg/cm )~below scram,

b. Peak neutron flux must.be 7.5% below scram.
c. Steam flow in ind'ividual lines must be 10% below the isolation trip-setting,
d. . Pea'k heat flux must be 5% less than its trip point.

U" 2. -Initiol ccticn of RCIC End HPCS shall~ be cutomatic if a J - ;the'Isval 2 sstpoint is r:cched, cnd systra i performance.shall be within specification.

s3. The. relief valves must reclose properly ~(without-leakage):following the pressure transient.

4. . For the full MSIV ' closure from greater than 95% power, predicted analytical resulst based on beginning of cycle design basis analysis, assuming no equipment failures and applying appropriate parametric Reca; -~

- corrections, will bc used ,- as the -basic to which the actual transient is compared. The following table

. specifies the upper limits of these criteria during the first:30: seconds following initiation of the indicated conditions:

-Initial Conditions Criteria Dome' Increse In Increase In Power Pressure Heat Flux- Dome Pressure

(%) (psia) -(%) (psi) 100 1020. 0 *

. To be determined based upon actual plant conditions at the time the test is performed.

13. .RESULTS The MSIV's were -functionally tested at this test condition.

Individual valve' closure was performed 'on the fastest MSIV and the? maximum power at which the full' closure.of a single valve can be performed was determined to be 90%. A simultaneous full closure of all MSIV's was initiated at 96% of rated power and reactor transient: behavior observed. Individual valve closure times were. determined. This test was successfully completed with allLapplicable acceptance. criteria being satisfied for test

~

, -condition 6.

-(<

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~

~~

. *c - !STARTUP TEST PROCEDURE:26 RELIEF VALVES-1.- PURPOSE:

.A.  :-The_ purpose of this test is as follows:

-1. To verify the_ proper operation of'the. primary system relief valves.

-a-. -

2. To. determine eachLrelief valve's' capacity.
3. .To verify that the discharge piping is _ not blocked.
4. .To verify that_each-relief valvecr essats following

.. operation.

5. To obtain a transient recorder _ signature of each

. relief valve operation for subsequent comparisons.

~

6. -To : confirm -proper overall _ functioning of the Low-Low-Set' Pressure Relief L'ogic.
7. DTo verify proper safety / relief valve discharge line backpressure.

2.- CRITERIA

Level-1.

^A.- .There should be ~ positive indication of steam discharge

,~ =during_the' manual actuation of each valve.

' ~ B; ~ The1 sum total-of the percentage corrected flow rates must.

be greater than 111.5% of the Nuclear Boiler warranted steam flow at 103% of the spring setpoint pressure'of 1165 psig.

C.' The Low-Low Set Prassure Relief logic shall function to

"' preclude subsequent simultaneous SRV actuations following the ~ f nit'ial SRV actuation due to the original - '

pressurization transient.

Level 2.

>A. No observable. leakage shall exists following closure. -

B. 1The pressure regulator must. satisfactorily . control the reactor transient and close the control'and/or bypass valves by an amount equivalent to the relief-valve' steam

. flow.'

s I

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~-t y , ,. g. , s-- , ,. --.-,,3 * .,e - - . . - , - -- -m,w, ,,,-me-+-- y+ ..v+-,,,-w , ,-c. .,--3-r,

m -

, .. . C. J The trrnsiint racdrd:r signaturss for cIch valvs must be o -analyzed _for:a relative-system response comparison. The dalay time (between trip and motion) shall be less than or

- equal. to 0.1. seconds, and _ the response time (main disk

' stroke time) shall be less than or equal to 0.15 seconds.

D. No individual relief valve may have a flow rate -(corrected

to theisetpoint pressure) thati.considering-measurement uncertainties, is less than 90%,- or greate than 122.5%, 'of

'its expected flow rate of 862,400 lbs/hr at 103% of the upr las Lavoputre pr vanur e us . Aaaeo psag E.. _ No more than 25% of the installed relief valves may have an individual corrected flow rate that is between 90% - 100%-

of their expected flow rates.

F. The: total flow capacity of the safety relief valves used in

' the Automatic Depressurization System must be equal _to or greater than 4.8. x <10 6 lbs/hr. at 1125 psig when the valve heaving the highest measured capacity is assumed-to be out ofl service.

~

G. The. selected MSRV with the highest: nominal safety' spring

, . setting must-indicate full open when manually actuated with'

'its accumulator air supply isoltsted and vented.

H. Discharge line backpressure shall be comparable with information presented on the ' Nuclear Boiler Process Diagram.

I. When the-Low-Low ~ Pressure Relief logic functions-, the open/close actions of the SRV's shall occur uithin i13 psi and 120 psi of their design points.respectively.

3. RESULTS:

Relief' valve testing was performed in conjunction with the NSIV Closure and Generator Load Reject Tests at greater than 95% of rated power. During both tests, the Low-Low Pressure Relief

' Logic performed'according to design. All other applicable criteria were also satisfied.

- 4 -STARTUP TEST PROCEDURE 27:

GENERATOR LOAD REJECTION:

l .' PURPOSE

~

A. -The~purpos0lof this test is to demonstrate the' response of the reactor land its control system to protective trip in the}turbineandthegenerator.'

2. : CRITERIA Level l'

-A. For Turbine and Generator trips there should be a delay of less than 0.'1' seconds following the beginning of control or stop valve closure before-the beginning of bypass valve

' opening. The bypas valves should be. opened to a point corresponding to approximately 80. percent of their. capacity

~

within an additional 0.2 seconds, or 0.3 seconds total, .

from the beginning'of control or stop valve closure motion.

.B. .Feedwater system settings must prevent flooding of the

-steam lines following these transients.

C. - The two recirculation pump' drive flow coastdown-transient

during the first three' seconds.must be equal.to or faster.

-than that'specified.'in this procedure.

D. .The. positive change!in vessel dome pressure occurring within: 30 -seconds after either generator or turbine trip

.must not exceed the L'evel'2 criteria by more than 25 psi.

~E. The' positive change-.in. simulated heat flux shall not exceed the Level 2 criteria-by more than 2% of rated value.

~

F. Turbine sped does not reach the point where a mechanical overspeed-turbine trip would occur.

Level 2-A. There'shall be no MSIV closure in'the first three minutes Lof the transient and operator action shall not be required in that period to avoid the MSIV trip.

B. <The positive change in vessel doem pressure and'in simulated heat flux.which occurs within the first 30

. seconds af ter thel initiation of either generator or turbine trip.must not exceed the predicted values.

r '

_____.____m______________

.- , ; . C. El:ctrical load trcnsfers occur cs' d: signed.

,D. The; reactor shall not. scram for initial thermal power at' less than or equal to 25% of rated.

E. 'If the Level I criterion (6.1.c of this procedure) for tho two~ recirculation pump orive flow coast down transient is passed, the data shall be analyzed within 3 weeks for compatibility with the safety analysis.

3. NtsutTS A generator load reject from 95.4% of. rated power was successfully performed at test condition 6. All applicable test criteria were satisfied.

E ~STARTUP TEST PROCEDURE 29-

' RECIRCULATION FLOW CONTROL SYSTEM

.1. PURPOSE

-The purposes o'f this test are:

A. -To. demonstrate the core flow system's control' capability over the entire flow control range, including valve

^

position, core flow, neutron flux, and load following modes of operation.

B. To determine that all electrical compensators and controllers are set for desired system performance and stability.

-2. CRITERIA Level'1' A. Position Loop Criteria

1. _The position loop response to test inputs shall not diverge.

{-

B. Flow' Loop' Criteria..

1. The-flow loop' response .to test inptits shall not.

diverge.

C ',' Flux-Loop. Criteria.

1. The flux loop response to-test inputs shall not diverge.

i-D. . Load'Following Loop Criteria.

1. The load following loop response to test inpouts shall not: diverge.

E. Scram Avoidance and General Criteria.

-1. None.

' F. Flow Control Valve Duty Test Criteria.

1. None.

~

~ , .

.- . . - - Lcv]l 2' A. l Position Loop Criteria.

Gains and limiters:shall-be set to obtain the following response:  ;

1. Maximum steady state reate of change of valve position lshall'be between 9 &-11%'per_second for a'100%

_. position demand : input. (Initial ~ valve velocity may

'~ ^

' exceed'this limit for a short time).

c2. Gains-shall be.' set to give as fast a response as possible for small position damand -input within the overshoot criterion and without additional valve duty *

. cycle. (See FCV duty criterion for valve duty cycle e requirement.)

3. The decay ratio of any oscillatory controlled variable must.be less than or equal to 0.25, when operating above the minimum core flow for Recirculation Master Manual mode! Below this minimum core flow, the decay ratio must be.less than or equal to 0.50 with the' recommendation that each control system be adjusted to meet less than: or equal to 0.25 unless there.is an

' identifiable perormance loss involved at higher power levels.

- B.. Flow Loop Criteria'.

>1. .The decay ratio of any oscillatory controlled vairable must-be less than or' equal-to 0.25, when operating above the minimum core ~ flow for Recirculation Master Manual mode. 'Below this minimum core flow, the decay ratio must be less than or euqal to 0.50,~with the-recommendation that each control system be adjusted to meet less than or equal to 0.25 unless there is.an identifiable operformance loss involved at higher power. levels.

.2. The flow loops provide equal flows in the two loops -

.during steady state operation. Flow loop gains should be' set to correct 90% of'a' flow imbalance in 20 1 5 sec.

7

  • -so, ,

. _ _ - _ _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - -A --- -

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.- - ~C.- l Flux Loop Criteria.

1. ,The docay' ratio oflany oscillatory controlled variable must,be.less than'or equal to.0.25,.when operating above the minimum' core flow for Recirculation Master Manual ~ mode (loops A and B receive command from~'a

. common point).. Below this minimum ~ core flow, the decay ratio must be.less:than or equal to 0.50, with the recommendation that each control system be ti.m ; .. _ .

, jadjusted to meet. : less than or equali to 0.25 unless -

~

=there is an identifiable performance loss. involved at 4

higher power levels.

.:2 . ~For.small flux command step changes of between 1%-5%,

at near rated power, the following apply:

'a. Deadband, percent. rated flux demand: less than or equal-to'0.5.

b. Delay time for flux demand steps, sec.: less than or equal to 0.8.
c. .Reponse time for flux' demand steps, sec.: less

-than'or. equal to 2.'5.

d. . Maximum ~ allowable flux overshoot, for step demand of-less than or equal,to.20% of rated is, in percent: -2.
e.

. Flux settling time, sec.: less than or equal to

.15.

i 3. Switching between estimated and actual- flow should not -

exceed 5 times /5 minutes'at steady state

'4. .During flux step transient there should be no

' switching to actual flux or if switching doesinot-occur,;it should switch back to estimated flux within

-20 seconds of the start of the transient.

' 5. JThe deadband of the. flux controller. for a flux demand

. step shall be less than or equal to .5% of rated flux

-demand.

T 4

y.

7

-1 .: . D. Load Following Loop Critsris.

1. - The decay. ratio of any. oscillatory controlled variable must be less than or equal to 0.25, when.oeprating above te minimum core flow for Recirculation Master a- Manual mode.. .Bloow this minimum core flow, the decay ratio ~must be less than or equal to 0.50,_with the recommendation ~that each control system be adjusted to t.
meet 11ess.than or equal to 0.2b unless there is an u -

. identifieble performance Linunivtd 'at higher power levels.

The response to a step input of-1ss than 10% in' load 2.~

demand'shall be iuch that the-load demand error is within 10% fo the magnitude of the step within 10 seconds.

3. When a load demand step of greatr than 10% is applied b (N%), the load demand error must be within 10% of the h magnitude of the step within N seconds.

,- 4 '. For_ large Auto Load following Recirculation sytem

. maneuvers along the 100 percent rod line, 90 percent'

- of the commanded step power change (P) must be completed within.(t) seconds:

a. For 10 percent change, 9 percent .within 10 seconds,
b. For 20 percent change,18 percent within 20

-seconds.

For 35 'percont change, 31.5 percent within 35

~

c..

seconds.

'5. . The Automatic Load. following range along the 100.

percent.(Flow Control) rod,line shall be at least 35 percent power (i.e., between'65 percent - 100 percent power).

E. Scram Avoidance and General Criter ia. For anyone of the

'above -loops' test maneuvers,- the trip avoidance margins must be at least the following:

L1. ' For APRM greater than or equal to 7.5%.

2. For. simulated heat flux gerater than or equal to 5.0%.

4 i

T

ae~

m

- .- . 3. .The system rssponss in cny mods rssponse shall produca

~

^s teady-steam flow limit cucle variations .no larger

- than 0.5% of. rated steam flow.

F. ~ Flow Control; Valve Duty-Test Criteria.
1. The-Ifow control. valve duty cycle in any operating

. mode.shall not exceed 0.2% -Hz. Flow control valve

. duty cycle'is defined as:

.m: - _ '

Total' valve travel (%) (% -~Hz)'

2x time span-in sec.

, !3. RESULTS-All applicable level:1 criteria were satisfied while testng at

' test! condition 6.

Level.l2 time response criteria were not met at this test condition. Testing determined.that relatively slow controller settings were> necessary in order to obtain minimum overshoot.

..These control system settings resulted in stable responses to the test inputs while maintaining acceptable response times.

STP229 was satisfactorily-completed'at. test conditon 6 and all applicable. criteria were satisfied except as stated above.

t f~- .j j :.

I r: +

L l:

L i

. ~

STARTUP TEST PROCEDURE-3d

.. . 1 RECIRCULATION SYSTEM 1..JPURPOSE,

!A. Obtain recirculation system'preformance data under different operational corditions, such as pump trip,- flow -

coastdown,L pump restarts and flow induced vibration.

" ,~ ..

_,To verify that no recirculation system cavitation will

-180 occur in the operating.rngion of the power-flow map.

C. To verify that during the; trip of one recirculation pump,

~

.the feedwater contrl system can satisfactorily control water: level without a resulting -turbine trip and/or scram.

D. To: record ard. verify acceptable performance of the

~ recirculation two pump circuit trip system.

2. CRITERIA

- Level-1 A. The two pump drive flow coastdown-transient during the first 3 seconds must be equal to or faster than that specified on Figure 14.2-7 of the FSAR.

Level'2-E A. .The water level, APRM hrd transients of simulated heat.

flux, pressure, drive and core flow for the one pump trip

shall not exceed the' predicted values.

- > 'B. :The reactor water level margin to avoid a high' level-trip

., shall be greate than or equal to 3.0. inches during the one pump-trip.

C. .The~ simulated heat -flux (TPM) margin-to aJoid a scram shall .

be greater than or. equal to. 5.0 percent during the one pump

trip.

'D. The recirculation system cavitation runback feature shall be/ adjusted such that a flow runback (transfer of recirc.

pump power supplies from 60 Hz to 15 Hz) occurs prior to any observable cavitation in the Recirculation System.

l

-,,,,-w. - ,v-, ., e, a-, n,- .u, n, ,,w,. -,c, ,, . , , - , , , - - - ,

f

-l

.7 v'

E. . Durinw recirculation rune restart (s) the scram trle  !

~~

avoidance marsins must be at least'the followinst i

1. For ' APRM, sreater than .or equal to 7.5%.

s

'2. ForJsimulated heat flux, sreater then or equal to 5.0%.

F. If the level 1 criteria for- the two Pune trip coastdown  !

transient is met, the data shall be analyzed within two

- weeks to ensure- compatibility with the safety analysis, l

3. RESULTS'

'A. The followins tests were successfully completed at test condit ion 6

- system performance > data acquisition,

- recirculation one eune trie and restart,

- sinste loor flow droe data acquisitlon, ,

- balanced flow data acquisition.'

. All test ins sat isfied the acceptance criteria. -

g.

k '

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T

..mv . *'

  • STARTUP TEST PROCEDURE 33 DRYWELL PIPING VIBRATION
1. PURPOSE A. 'The purpose of this test is to verify that the main steam, reactor recirculation, and feedwater piping have acceptable vibration.
2. CRITERIA Level 1..

A.. The mesured amplitude for vibration of the recirculation

- system during recirculation pump trips and subsequent coast down shall not exceed the allowable values.

2 8. The measured amplitude for vibration of the main steam lines during relief valve operation shall not exceed allowable values.

.C. The measured amplitude for. steady state vibration of the

' recirculation ~and main steam sysatems shall not exceed n allowable values.

l-t D. The measured amplitude for vibration of the main steam l lines due to: turbine stop valve trip and relief valve operation shall not exceed allowable values.-

l Level 2.

I

'A. The mesured amplitude of vibration of--the main steam system following relief valve operation and turbine stop valve

-trip should nt exceed the expected values.

B. . The' measured amplitude of vibration of the main team and recirculation systems during steady state operation should not exeed the expected values.

C. The measured vibrational stresses induced in the feedwater system following trip of one and both turbine driven feed pumps and during steady stat operations should not exceed the expected stresses.

~

i.

l r  !

l ,

[; 's :3. RESULTS At Test'Cohdition 6, steady state vibration measurcments were

made and found to be acceptable. Transient vibration measurements were also made at this test condition. Main steam line vibration due to a generator trip (STP-27) was found to be acceptable. Main Steam line vibration induced by a full MSIV isolation (STP-25) was within criteria limits. Recirculation system vibration induced by RHR shutdown cooling operation (STP-71) and by recirculation pump trip and restart (STP-30) were within criteria limits.

During the course of test it was determined by General Electric that four_(4) of the installed sensors were inoperative. The

' loss.of this instrumentation had,no impact on the test because the measurements from the functioning instrumentation indicated

, values.which were well within acceptance criteria limits.

STARTUP-TEST PROCEDURE 34 I

REACTOR INTERNAL 0 VIBRATION L~

1. ,PURPCSE-

[

A.. The purpose of this test is to obtan vibration measurements on the jet pumps to confirm the meet.anical integrity of the system with respect to flow induced vibration and to verify the accuracy of the analytical vibration model. .This test is in conformance with Regulatory Guide 1.20 requirements for Non-Prototype. Category II Plants (similar to-prototype but some component differences).

2. ' CRITERIA 3

' Level 1..

'A. lThe peak stress intensity may exceed 10,000 psi (single amplitude) when the component'is deformed in a manner corresponding to one of its normal or natural modes but the fatigue usage factor must not exceed 1.0..

Level'2..

-A. LThe peak stress-intensity shall not exceed 10,000 psi

'(single amplitude) when the component is deformed in a manner corresponding to one of its normal or natural modes. This is the low stress limit which is suitable for j sustained vibration 'in the reactor environment for the design' life'of the reactor components.

.3. RESULTS Vibration measurements were taken during the Recirculation Pump

. Trip and the Generator Load Reject Transient Tests and during steady state operation at various points on thv power vs flow l operating map' Although' the Level 2 vibration criteria at certain points.was exceeded during the high active loop flow operation which exists

-immediately. after a recirc ~ pump trip, this is a transient condition and is- therefore not expe::ted to cause any operational problems. -All criteria were met in the normal single loop and

.two loop operating regions-of the power vs flow map as well as

_the extended core flow operating region.

I 6 .. . . . . . . . . . . . . . _ . , . . - . . . .

r- ,

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~

5- STARTUP~ TEST PROCEDURE 35

~

RECIRCULATION SYSEM FLOW CALIBRATION

1. PURPOSE
A. The purpose of.this test is to perform a complete

-calibration of the installed recirculation system flow instrumentation.

2. M PTANCE CRITERIA A. -Level-2.

.1. Jet pump intrumentation shall be adjusted such that the jet pump total flow. recorder will provide a correct core flow indication at rated conditions.

The' APRM/RBM flow bias instrumentation shall be

~

2.

adjusted to function properly at rated conditions.

'3. RESULTS The. recirculation system flow calibration'was successfully performed at test condition 6. 'The core flow instrumentation

.was adjusted to provide accurate' flow indication based on: jet-pump flows.

No _ adjustments were performed on the loop drive flow instrumentation since these flows were.already conservatively adjusted per normal plant surveillance procedures.

All applicable criteria were satisfied at this condition.

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STARTUP TEST PROCEDURE 71

, _. -RESIDUAL HEAT REMOVAL SYSTEM 1, PURPOSE' j -A.

To demonstrate the ability of .the Residual Heat Removal (RHR) System to. remove residual and decay. heat from.the nuclear system so that refueling and nuclear servicing may H be performed. This will be demonstrated from both the -

control room and the remote. shutdown panel..

B; To. demonstrate the ability _of the RHR system, in l conjunction.with the. Reactor Core Isolation Cooling (RCIC) l' System, to condense steam.

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2. CRITERIA l Level 2 A. The RHR System shall be capable of operating in tahe steam I condensing (with.both 1 and 2_ heat exchangers), suppression I

~ pool, cooling,.and shutdown cooling moes (with either heat

~ exchanger operating) at the flow rates and temperature differentials indicated on the' process diagrams.

0 -B. In the ' steam condensing mode, for small disturbances, each

. -variable must have a decay ratio less than 0.25 throughout

'each controller *s: expected operating range.

C. The time to place the RHR heat exchangers in the steam condensing mode with the RCIC using the heat exchanger condensate flow Lfor suction 'shall be.one-half ' hour or less.

' D.: /gThe RHR System performance 'in the shutdown' cooling mode shall not be less than that. indicated on the process diagram.

'3. 'RESULTS

' Test Condition 6

'The ability of the shutdown cooling mode of RHR to establish a cooldown rate was demonstrated at Test Condition 6. The heat removal rate was large enough that bypass. flow around the RHR

. heat exchanger was required to avoid exceeding the Tech Spec cooldown< limit of 100 DF/ hour. W1th the-bypass open, it^was

not. possible to obtain a set of performance data which could be o compared ~ to the process diagram, though performance was estimated from-previous test conditions. The failure to make an exact comparison, though a Level 2 criteria violation, is not of major ~ concern because the estimated preformance was close to that expected and the demonstration of system performance greatly exceeded the cooldown required at the test condition.

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.4; STARTUP TEST' PROCEDURE'74 s

'0FF-GAS SYSTEM

!1. . PURPOSE A ._- .The purpose of this test is as follows:

1. . : To verify the proper operation of the Off-Gas System 4 over-its expected operating parameters.
2. To. determine the performance of the activated carbon absorber.
2. CRITERIA

'A. Level 1

1. The' release of radioactive gaseous and partaiculate effluents must not exceed the limits specified in the site Technical Specifications.

l'

! - 2. . There'shall be no . loss of flow of dilution. steam to

- the ~ non-condensing stage when the steam jet air ejectors are pumping.

.8. Level.2

1. The system flow, pressure temperatue, a'nd relative humidity shall comply with the design specifications.
2. The catalytic recombiner, the hydrogen analyzer, the activated carbon beds, and the filters shall be.

-oerating properly'during operation, i.e. , there ~ shall be no gross malfunction of these components.

3. 'RESULTS The release of" radioactive gaseous and particulate effluents was demonstrated to be within the. limits specified in the LTechnical

. Specifications during test-condition 6.

. There was no loss 'of dilution steam to the uncondensing stage

.when the SJAE's are pumping during test condition 6.

-The following level 2 design specification criteria were not satisfied during Test Condition 6:

a. :Off-Gas Flow to After Filter (Normal Mode)
b. Off-Gas Condenser Outlet Temperature (Normal Mode)

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c. Gas Reheater Outlet Deweoint (Normal Mode).
d. Adsorber = Vault Temperature (Normal Mode) e.- ' Adsorber vessel (1N62-0014) Temperature (Normal Mode).

'Thei0ff-Gas Condenser Outlet Temperature was indicat' ins uescale. <Tne level 2 criteria'is less than 154*F, and the desisn limit is 50* - 160'F. -The indicator only reads to 150'F.. This' fact, in conjunction with the fact that other system Parameters downstream of the condenser were within

.11mits, is sood. indication of no sross malfunctionins of equipment-(level 2).

The Gas Reheater .0utlet Deweoint instrumentat ion and the Adsorber Vault. Temperature instrumentat ion were not operable at

,the t ime 'or.the test. The Holsture Separator Outlet Temperature indicat ion assured the system dewpoint was not a sisnificant L

-Problem.~ : Local indication of the vault temeerature was within specifications. A station work request has been initiated to correct the instrumentation Problems.

The Off-Gas Flow to After Filters was 30 scfm above its criteria in test condition 3. A stat ion-work request addressed this Problem and a;1eak in the condenser boot was found and repaired. The flow .is. Presently 6-7 scfm above its level 2 cr iteria. This does not reeren: sit any sross malfunctionins of

^

the system (level 2).

- -The' temperature of the.Adsorber Vessel was slishtly below its level 2 criteria limit. All other vessel temperatures were 1 well- within specificat ions, thereby not represent ini an oeerat ins

. Problem nor malfunct ionins of equiement.

This' test was successfully completed for test condit ion 6.

'All applicable' Criteria were satl5 fled.eXCEPt as' stated above.

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. Design Specification Deviation (Test Condition 6) l l PARAMETER ACTUAL VALUE CRITERIA VALUE Off Gas' Condenser Upscale Less than 1540F Outlet Temp.

Gas Reheater' Not Operable 34-450F Outlet Dewpoint-Msorber Vault Not Operable 75-790F Temperature

-Off Gas Flow to 37 scfm 6-30 scfm After. filter Msorber Vessel 71.50F 75-790F IN62-D014 Temp.

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