ML20065E027

Suppl 2 to Seabrook Station Initial Startup Rept for June- Aug 1990

ML20065E027
Person / Time
Site:	Seabrook
Issue date:	09/13/1990
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90167, NUDOCS 9010010227
Download: ML20065E027 (11)

Text

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New Hampshire  :

, Senior Vice President and

Chief Operating Officer L

- NYN 90167 September 14,1990 2 < United States Nuclear Regulatory Commission ,

Washington, D.C. 20555

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Attention: Document Control Desk

References:

(a) Facility' Operating License No. NPF 86, Docket No. 50-443 .

k (b) NHY Letter NYN 90070, ' Initial Startup Report" cated March 9 F :1.

T. C. Feigenbaum to USNRC (c) NHY Letter NYN 90126, ' Supplement 1 to the Initial Startu' Le ra dated June 13, 1990, T. C. Felgenbaum to USNRC Supplement 2 to the initial Startup Report

Subject:

Gentlemen:

in accordance with. the requirements of Technical Specification 6.8.1.1 enOad is dupplernent 2 to the Initial Startup Report submitted via. Reference (b) and suppluranted -

via Reference (c). Supplement 2 to the initial Startup Report covers 1he pui.,d frov. en

• 1990-through August 1990, during which the' power Ascension Test Program was em d v on - August 18, 1990.

This supplemental report,provides a summary level description of the test .% T cach power level test plateau 'as test documentation is still being reviewed by the s tion Operation Review Committee. A final detailed supplementa' report (Supplement 3) AP k

. . submitted t y September!30,1990.

t Should you have any questions regarding this report please contact Mr. .la s, t Peschel, Regulatory Compliance Manager at (603) 474 9521 extension 3772.

Very tru 'yours, 66' (2 9 gW- -

c- Te C. Felgenb - /

Enclosure TCF:ALL/ss!

9010010227 900331 e jDR ADOCK 05000443 PDC e -

New Hompshire Yankee Division of Public Service Company of New Hampshire g-P,0 Box 300

• Seabrook, NH 03874

• Telephone (603) 474 9521 II.

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,, United States Nuclear Regulatory Commission September 13, 1990 Attention: Document Control Desk Pagt two 4.-

cc: Mr ' Thomas T. Martin Regional' Administrator

- United States Nuclear Regulatory Commission Region 1 2

475 Allendale Road King of Prussia, PA 19406

. f.. Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 .

Seabrook, NH 03874 w a ; .- ,

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. i NEW HAMPSHIRE YANKEE s i SEABROOK STATION ,

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SUPPLEMENT 7 -

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INITIAld TARTUP RIJ.QEI. I i

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c OPERATING LICENSE: NPF 86 NRC DOCKET NO. 50-443 l 1

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. For the Period j j June.'1990

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1.0 INTRODUCTION

ij r The Initial Startup Report was submitted to the Nuclear Regulatory Commission in March,1990 and. covered startup activities through completion of low power physics testing [t (June 1989). Supplement I reported testing which took place in the interval from July 1999 through May 1990c ,

Testing from June,1990 through August,1990 completed the Power Ascension Test .

Program. ST-40, NSSS Acceptance Test, was completed on August 17, 1990, and the Startup .

Test Program was officially completed at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, August 13, 1990.

i, g Supplemer 2 covers the three month period of startup activity (June through August,  !

1990) from the abmittal of Supplement 1. The remainder of the Power Ascension Test  ;

Program was ci mpleted la the three month interval, however, the large number of tests. '

conducted at the 30%, 50%, 75%, 90% and 100% power . level test plateaus, and the requirement to complete final test packages and submit them for Station Operating Review Committee (SORC) review and approval, has impacted preparation of the final startup report .

material.

• l This document will summarize the tests and results at each power level test plateau  :

. and any problems encountered during the test sequences.

1 Supplement 3, the Initial Startup Report final document, will contain detailed

^ descriptions and test data for each test.

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SUMMARY

OF TESTING AND RESULTS The summary will consider individually each of the power level test plateaus in the test se',pr~; ta5, M, 75%, 90% and 100%. The final testing reported in Supplement I was the revised torsional response test, ST 48.1, conducted with General Electric support .

personnel, which verified that the undesirable resonance frequency found during the original performanc;s of ST 48.1, had been corrected. On cotopletion of the turbine repair, preparations began to escalate to the 30% power level test plateau.

The tests to be reported are:

ST 13, Operational Alignment of Nuclear Instrumentation ST 14.1, Operational Alignment of the Process Temperature Instrumentation ST 15, _ Reactor Plant System Setpoint Verification ST.22, Natural Circulation Test ST 24, Automatic Reactor Control ST 25, Automatic Steam Generator Level Control ST 26 Thermal Power Measurement and Statepoint Data Collection ST.27, _ Startup Adjustments of Reactor Control System ST 28, - Calibration of Steam and Feedwater Flow Instrumentation ST 29 Core Performance Evaluation ST 30, Power Coefficient Measurement #

ST-33, Shutdown from Outside the Control Room ST 34, Load Swing Test ST 35, Large Load Reduction ST 36, Axial Flux Difference Instrumentation Calibration ST 37, Steam Generator Moisture Carryover Measurement ST 38. Unit Trip from 100% Power ST.39, Loss of Offsite Power Test ST 40, NSSS Acceptance Test ST 41, Radiation Survey ST-42, Water Chemistry Control .

, ST 43, Process Computer ST 44, .

Loose Parts Monitoring ST-45, Process Effluent Radiation Monitoring System ST 46, Ventilation System Operatliity Test ST 48, Turbine Generator Starten Test

• ST-49, Circulating Water Systn Wrmal Hydraulic Test ST 51 Power Ascension Dynamh, Vibration Test ST52, Thermal Expansion ST 56, Piping Vibration Testing

• Test Deferred. Testing will be performed prior to operation of the circulating water system in the heat treatment mode.

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, o l 2.1 Testina at the' 30% Power Level Test Pljgggg The test sequence at 30% included all, or portions of thirteen tests.

The PAT sequence required several tests in the 10% - 30% range of reactor power as part of the 30% power level test plateau. Turbine synchronir.ation and overspeed testing l

($f-48), and verification of automatic control by feedwater regulating valves (ST 25) were I performed. Rework of the turbine overspeed trip required several days. After completion  ;

of the turbine generator qualification, power ascension to 30% proceeded.  !

As was true at each plateau, certain tests to verify / align lustrumentation were carried out.  ;

The Nuclear Instrumentation System (ST 13), process temperature instrumentation (ST 14.1) and steam flow and feedwater flow instrumet.tation (ST 28) relied on the thermal power '

l measurement and statepoint, data collection peacedure (ST 26) to collect the data necessary  !

to perform any required adjustments. Setpoints, originally adjusted to initial . values specified by vendors, were changed whea actual values became available. Steam flow transmitter data, for both transmitters in the same loop, failed to meet the how difference limits in two cases. l A test exception was taken end Westinghouse concurred with escalation to the next plateau was satisfactory.. 3 ST 24, Automatic Reactor Control, was completed rat 30%; no further testing was required. The test was satisfactory and there were no test exceptions. >

Initial core pcrformance (ST 29) and power coefficient (ST 30) data were taken, and all results met acceptance criteria. Testing of the steam generator feedwater' pump automatic speed control (ST 25) yielded satisfactory results. Similarly, load swing tests (ST-34) were satisfactorv, although results met acceptance ' criteria, some exceeded the notification i requirement to Westinghouse. Level v3ristions in two instances, and one pressure swing were slightly outside the limits.  ;

Water chemistry (ST 42) at the 30% power level test plateau, found that cation conductivity and sulfates in the steam generators, and the specific cation conductlyity in the -

, main steam, feedvater and condensate systems, were above the limits in the Westinghouse  !

Secondary Water Chemistry anual. The source of these contaminates was identified as original system pre servatives. With Westinghouse and Chemistry Department approval, a test exception was pre rared. The mechanism for removal is continued operation.

In the initial ,cetion of testing of the Process Computer (ST 43), MPCS software of four '

systems was verified. Five test exceptions were necessary; two, related to the' method of-data collection, were resolved by procedure changes, the others, required instrument repair or l adjustment, i Additional data on thermal expansion (ST 52) of snubbers and spring hangers was taken; ,g

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p problem sheets were developed and resolved by review. ' No test exceptions were necessary.

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it 2.2 Testina at the 50% Power Level Test Plateau  ;

The test sequence at 50% included all, or portions of twenty oIse tests.

Turbine generator performance monitoring (ST-48), and a two shift hold for water [

chemistry preceded testing at the 50% plateau. The chemistry problem was attributed to flushing systems previously out of service. Cleanup of secondary systems throughout PAT was accelerated by the use of auxiliary, trailer mounted filter beds, which were frequently changed as needed.

The tes,ts to verify / align instrumentation, conducted at 30%, were again carried out at the start of 50% testing. Steam flow (ST 28) imbalance in three steam generators was noted; again a test exception was taken, and Westinghouse concurred with escalation to the next .

platenu.

i Loop temperatures, SO pressure, calorimetric reactor power and turbine impulse pressure were used for the first time at the 50% plateau in ST-27 to extrapolate to full }.ower values, i

< and make comparisons to design values. No adjustments at this level were. required.

, Core performance (ST 29) and pover coefficient (ST 30) results were acceptable for this .

plateau. The value of Fxy was higher than the full power limit, but lesothan that Allowed  !

at 50% Steam generator level control testing (ST 25) was again satisfactory. In the lord swing te',tt (ST 34) at 50%, two test exceptions were necessary; Tava and Trnnon did not -

return to Tnce within the toleratee specified. Other results required reporting to Westinghouse, as in the 30% case. i Shutdown from outside the control room, (ST 33), was performed at the. 50% plateau.

There were two minor prob! cms; three computer points were not recorded by the MPCS, and  !

a heat exchanger temperature control valve hand controller was reverse acting from what had '

been expected. Overall the system performed as expected and no test exceptions were .,

generated. j

, A preliminary lucore' excose cailbration (ST 36) was perforrned, and from the data, extrapolated fall power currents for NIS as a function of AFD, and the gain of the f(delta-

1) portion of the OTdelts T protection system were determined. With the plant at steady 4

, state conditions, the loose parts monitoring system (ST-44) operational test and quart.erly'  ;

surveillance was performed and no setpoint adjustments were required.

The initial radiation suvey (ST 41) was taken; no discrepancies were found which would L prevent esbalation to the next test plateau, Water chemistry (ST 42) again found problems with contamination due to system prese vatives. Westingl.c,use noted these were typical of plants n't this stage and approved continued operation. The process and effluent radiation i monitoring system (ST-45) was first tested at 50% power. Several monitors required test exceptions; these are summarized at the 100% test plateau, 6

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• - 2.2 Testina at the $0% Powet, level Test Plateau (Continuedl

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Process compater verification (ST 43) at this power level generated an additional five test exceptions. One identified a software ' problem, one a procedure change, another an instrurount adjustment and two were carryovers from the 30% testing, The heating, ventilation and air conditioning systems were monitored (ST 46) initially at

$0% power. Arcat were monitored in eleven structures. Areas which wm not within design limits are identified with the 100% test results. '

Turbine generator (ST-48) and thermal expansion (ST 52) tests were continued at this power level.

L3_Testine at,the 75% Power Level Test Plateau The test sequence at 75% included all, or portions of fifteen tests.

Two unplanned reactor trips occurred, the first during power escalation (30%) to the 75%

plateau, and the second at the 75% power level test plateau. The first trip interrupted resting for 4 days, due- to incorrect activation of generator protective relaying, and the hecond for 3 days, as a result of high vibration in EllC system pressure switches. Turbine i

.: setbacka were :esponsible for test delays of 12 shifts.

Fine tuning cf the secnndary plant, particularly the feed. vater train, was the primary activity at thin plateau outside the testing sequence itself. Feedwater heater level heater dsain tank level fluctuations required attention, along with bringing two heater drain pumps into service.

i Gains were adjusied on feedwater regulating valve controls to climinate feedwater flow oscillations.

Turbita generator performance monitoring (ST 48), and thr repetitive tests to verify / align intrumentation were the initial test activities at the 75% plateau. Steam flow (ST 28) unbalance in two generators was noted and again, no adjustments were made. Rescaling mi turbine impulse pretsure and the full power Taya program (ST-27) was necessary.

Steam generator level control (ST 25) was again satislactory. ,

The results for core performance (ST-29) and power coefficient (ST 30) were as expected; I% continued to remain above the full power limit, but again did not prevent operation at the next plateau. Flux mapping during a controlled nxial renon oscillation (ST 36), provided

[ !ncore excore dat*. for a multi point analysis; from which AFD calibrations were performed. ,

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Water' chemistry (ST-42) results continued to exhibit problems with system preservative con.tamination; with continued operation permitted. The process computer verification (ST-0), yielded three additional test exceptions; two were carryovers and one was closed by sdjasting a tolerance specification. Thermal expansion measurements (ST 52) continued.

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[3 Testina at the 75% Power Level Test Plateau (Continued)

The initial large load reduction (ST-35) was conducted at 75%. The test, a reduction from 77% to 31% (540 MWe), was completed without problems. Load swing tests (ST 34),

at this plateau, met acceptance criteria, but again, certain parameters exceeded Westinghouse reporting requirements.

IIcat ' treatment of the cliculating water intake tunnel by flow rever *1 (ST-49) was scheduled for the 75% test plateau. A chlorination system, installed after the procedure had been planned, appears to be effectively climinating the buildup of marine organisms in the funnel, so the test was deferred. Operation in this mode is not assumed in the safety analysis, therefore, the decision to defer the test will not affect a successful completion of PATP, or the overall Startup Test Program.

L4,_T,g;3 tina at the 90% Power Level Test Plateau The test sequence for 90% included process temperature instrumentation (ST-14.1),

thermal power measurements (ST.26), reactor control system adjustments (ST-27), and steam flow /feedwater flow (ST-28) adjustments. Steam flow (ST 28) mismatch was found in only one generator; respanning of flow transmitters was planned at 100%

Core performance measurements (ST 29) were continue,d, with results similar 16 those at the 75% plateau. Additional turbine generator data (ST-48) was collected. .

2.5 Testine at the 100% Power Level Test Plateau .

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The test sequence at 100% included all, or portions of twenty seven tests.

The moisture separator reheaters (MSR) were placed in service after the 90% testing in order to improve plant efficiency. This resulted in turbine impulse pressure and full power

. Tava program adjustments (ST 27). The tests to verify / align instrumentation were again repeated at this plateau. The eight steam flow transmitters (ST 28) were respanned, and the steam flow mismatch corrected.

At this plateau, the core performance evaluation (ST-29) yielded a value of Fx, which slightly exceeded the full power limit. Analysis deterrnined that there was sufficient margin between all possible opernting conditions and the technical specification limit on Ps. A test exception was taken. The power coefficient (ST 30) measurement' was satisfactory. The check of AFD (ST 36) at full power verified the calibrations performed at 75E Steam generator moisture carryover (ST 37) was measured using isotopic lithium, rather than radioactive sodium. Results analysis, performed by Combustion Engineerlog, showed that steam generator moisture carryover performance was very good with a carryover percentage far less than the maximum allowable moisture carryover.

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j 2.5 Testina at the 100% Power Level Test P.[ateau (Continued)

The full power load swire/ test IST 34) was coordinated to also provide data for the procer.1 computer (ST-43) an/ loose parts monitoring (ST-44). There were two deviations in the load swing test; manual intervention was required to control level oscillations on one steam gener s'.or, and Two which failed ta return to Tm, within t.pecifmation. GETARS showed that the generator oscillation was converging when manual control wr.s ta*4en, and the temperature problern occurred becausa control rods reached a fully withdrawn position before retu ning temperature to the dtsired value.

Tbc large load reduction (ST-35) nr full power was from 100% to 49%, (620 MWe).

During the load reduction, feedwater pomp saction pressure during the transient fell below ,

thc, feedwater pump trip setpoint, but no trip occurred. The trip circuit, which etilizes 2 out of 3 logic, was examined after the test, and the failure determined to have resulted frorn two problerns; the trip setpoint was adjusted to below the desired point, and an incorrect head prest.ure correction was used. N:cessary changes in the adjustment process have t,een made to prevent a reoccurrence and the setpoint is being lowered. As in the d swing test, the test was coordinated to provitie data for the process computer (ST-43) and Toose parts monitor (ST-44).

The unit trip from 100% powei (ST-38) war, coordinated with three startup tests; process computer (ST-43), loose parts moritoring (ST-44) and dynamic vibration (ST 51). Plant performance juring the trip was gancrally as expects.d. Three operational responries were noted; prer,mtizer pressure dropped below expected, and was reported to Westirighour.e,  ;

steam generator narrow range level spikud high and caused a feedwater isela. tion signal, and nn excess demand signal was c+ted durmg a mode change in the stearn dump system. The latter two responses were addressed with a design change and a p7ocedure clange respectively.

Naturai circulation (ST 22) was demonstrated immediately after the unit trip from 100%.

Natural circulation was verified to be :stablished in approximately eleven minuf es and was maintained for 30 minutes. There were no test exceptions.

Loss of offsite powdr (RT-?9) was coordinated with the plant computer test (ST 43). In gener al, test performance waa as espected. The main plant cora puter system (MPCS) degraded two seconds into the tect end a computer record of dier,el and sequencing was lost.

An observer, with a calibrated stopwatch, wai, able to provide the missing information. A test exception was taken. Threc " vital busses

• required raanual shifting from DC to emergency AC aQer the diescis starir,d, as crpected; and a non-vitvl battery charger failed.

Also, the control room non-vital lighting inverter did not )perate and the pressurizer Group A backup heaters could rot be manually energized. Eacr prohlt.m was addressed without need for a test exception, except for the cornouter failever, as noted.

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jl5 Testina at the 100% Power Levd Test PJetenu (Continued)

The full power radiation survey (ST 41) was conducted successfully. Seven sh eld survey discrepancies were found, but all were dispositioned in the procedure. Water chemistry (ST.

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42) results sgnn yielded results with contaminat!on indieuted, but Westinghouse and plant chemist'y upproved the results., The final test of procas and effluent radiation monitors

(ST 45) yicided six test exceptions. Two were the result offdecay of short lived isotopes before sample analysis was completed; also, an incorrect sample (valving error), a defective instrument, an activity level below a monitor sensitivity limit and a temporary raodification 4

whit,h prevented sample flow to a monitor. Each was dispositioned promptly. Ventilation sys';em operability (ST 46) yielded generally satisfactory results, but test data collected in certain areas of coutainmnt, the control building ar.d the east and west pipr, chases exceeded design limits. A test exception was taken, and problem areas are being evalnated

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by Engineering.

Three ten exceptions were required for the process computer (ST-43) procedure at full power, two'were related to transient tests. One exception, lack of available CPU resulting

, in a fallover is under study, the othovs required no action. One channel of the loose parts monitor (ST-44), failed acceptance criteria, and a test excent' as writteu. The channel was evaluated per instrument manual, and proper operr m %

r A total of 28 thermal expansion problems addres 9 m eAnn (ST 52) during '

the PAT program. All were dispositioned by engineci. ~ t . N ng vibration (ST.

56)'measureracnts were satisfactory. Remeasurements or ns were necessary p . . 4 when one' vibration meter failed a post measurement calit m *a g O Tbc NSSS acceptance test (ST 40) began on August 5,1990 atil700 hours, and ended on

. August 17,1990.it 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. The test was interrupted for two hours on August 6 for stop

/ and control ulve surveillance tests at a power level of < 95%, and for approximately 1%

days on Auguet 13 for repair of a leak in an EHC line. Power was reduced and the turbine tripped for the latter interruption. Performance was as expected, and there were no test exceptions.

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