ML20236Q074
| ML20236Q074 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/11/1987 |
| From: | Scalice J, Steiger W LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20236Q068 | List: |
| References | |
| NUDOCS 8711190167 | |
| Download: ML20236Q074 (14) | |
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LONG ISLAND LIGHTING COMPANY Shoreham Nuclear Power Station Supplement No. O to the STARTUP REPORT for the period August 1, 1987 to November 1, 1987 Approved:
J A. S;cslice
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~Da(te ssis dnt Plant Manager
.. i Approved: Y2 W. E.
e Stei/ Jet Date Plant Manager hDR O h P
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TABLE OF CONTENTS i
1' 1.0 Overview 2.0 Chronology.of Events ;)
3.0 Startup Activities Performed / Test Results 4.0 License Conditions ,
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~ l '. 0 OVERVIEW' l
This StartupfReport Supplement /has b'een' written'byotheLLongs 1
. Island Lighting Company (LILCO) for submittal.to the, .
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Nuclear, Regulatory: Commission?in' compliance'with Shoreham.
Nuclear Power, Station 1 Technical-Specifications, paragraphs '
6.9.1.11through 6.9.1.3~.and Regulatory Guide l.16,4
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Revision :. 4, section.C.1.a.
1 Technical Specifications andLRegulatory Guide;1'.16; require.
.that a. summary report'offplant startup.and~powerlescalation as testing be: submitted within 9~ months following initial; I criticality. ' Shoreham Nuclear L Power Station; (SNPS)'
achieved init'ial: criticality on~ February- 15,:1985, and'. 1 LILCO submitted a:Startup Report on November'15,.1985 1 The-
. scope of that.Startup Report'includedifuel load 1and initial:
criticality'underJ the .001% power ~ license,-NPF-19, Land low.
. power. testing; conducted under the 5% power: license,'NPF-36.-
Since SNPS has.not completed its startup. test program'.or-commenced commercial power operation,Jadditional LSupple -
ments~are~ required <nt a periodic. basis; This Supplement' covers the period from August 1, 1987 to Novemberil,;1987.
Shoreham was' shutdown from June 1987 to~ November'1987. LThe major work in progress.during.this. report!ng period involved. activities associated with1 portions of thefColt-diesel tie-in modification. !
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2.0 CHRONOLOGY OF EVENTS' l December 7, 1984 Received low power-license .001%
December 17, 1984 Sources loaded'in core.
December 21, 1984 Fuel loading commenced.
4 January 4, 1985 Partial core shutdown margin test.
January 19, 1985 Fuel loading completed. l 1
January 25, 1985 CRD open vessel' testing completed. i February 17,.1985 Initial critical and shutdown margin test. Completed open vessel' j testing.
June 4, 1985 CRD open vessel retest completed. j l
July 3, 1985 5% low power license received. j I
July 7, 1985 Reactor critical sequence B. Test <
condition Heatup. l1 July 7, 1985 Heatup to 250 F System expansion performed.
IRM performance completed July 8, 1985 Heatup to 325 F performed.
APRM calibration.
July 9, 1985 SRV functional test performed ,
(STP-26). J I
July 11, 1985 150 psig plateau reached. I System expansion DW entry.
RCIC testing.
HPCI system testing.
July 14, 1985 Reactor scram #1 on Rx level.
July 17, 1985 APRM calibration at 150 psig.
HPCI testing.
l System expansion testing.
RBCLCW performance-testing.
July 18, 1985 Reactor Shutdown for RPV level instrumentation work.
1 July 23, 1985 Reactor critical.
July 26, 1985 Reactor shutdown for RPV level instrumentation work.
l July 29, 1985 Reactor critical.
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1 2.0 CHRONOLOGY OF EVENTS - (continued)
July 31, 1985 Reactor pressure to 150 psig. j HPCI system testing. 1 August 1, 1985 350 psig plateau.
Drywell radiation' survey.
System expansion.drywell inspection, l system expansion data, j August 3, 1985 600.psig plateau.
System expansion.
RBCLCW performance.
CRD testing. i I
August 5, 1985 800 psig plateau. J System expansion. !
CRD testing. l .
August 7, 1985 Rated pressure plateau. I System expansion testing.
HPCI testing. a RCIC testing. 3 CRD testing.
RBCLCW testing.
Water level testing.
Process computer STP-13. testing. J Chemical and radiochemical testing. )
Radiation measurements.
LPRM testing.
1 August 23, 1985 Reactor pressure reduced to 150 psig. )
HPCI testing.
RCIC testing.
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August 24, 1985 Reactor shutdown after initial heatup. j August 30, 1985 Reactor critical sequence A.
August 31, 1985 Scram #2 on loss of instrument air.
September 3, 1985 Reactor critigal sequence A. Second heatup to 150 F.
i September 4, 1985 Heatup to 250 - 150 psig.
l System expansion testing.
September 6, 1985 Reactor pressure 350 psig.
System expansion testing.
l September 6, 1985 Reactor scram #3 due to surveillance
- on level instrument.
September 7, 1985 Reactor pressure 600 psig.
System expansion testing, j CRD testing.
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2.0 CHRONOLOGY OF EVENTS - (continued)
September 8, 1985 Unusual event due to_ reactor level indication problem.
September 10,-1985 Reactor shutdown for repair of reactor problem.
September 11, 1985 Reactor critical and heatup to investigate level problem.
September 12, 1985 Reactor scram #4 on low water level indication. Actual level did not-change. Level instrument problem investigated.
September 18, 1985 Reactor critical sequence A.- I September 21, 1985 Reactor pressure 800 psig.
System expansion testing.
CRD testing.
RPV level problem fixed.
September 21, 1985 Rated pressure reached.
System _ expansion testing.
Second heatup.
RCIC testing.
HPCI testing.
MSIV testing.
Water level testing.
CRD testing.
RWCU testing.
Radiation testing.
Chemistry testing.
September 27, 1985 Reactor shutdown.
Hanger placed.on B reference leg.
Miscellaneous maintenance.
October 3, 1985 Reactor critical sequence A. Third heatup to rated pressure.
System expansion testing.
October 4, 1985 RCIC vessel injection at rated pressure.
System expansion testing.
RWCU system testing.,
MSR relief valve testing.
October 6, 1985 Initial turbine generator roll to rated speed.
October 8, 1985 End of heatup testing.
Begin source replacement outage.
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l 2.0 CHRONOLOGY OF EVENTS-- (continued) l April 18, 1986 Reactor Mode Switch to Startup for generator synchronization and completion of Test Condition Heatup, u l
. April 24, 1986 Loose Parts ~ Monitor System testing.
Reactor Mode Switch to Shutdown due to condenser leakage problem.-
August 3, 1986 Mode Switch to startup'for 5%~ retest .
-program. .
August 4, 1986 Reactor critical, sequence A.
August 7, 1986 RCIC check valve cycling test,-150- j psig plateau. I l
HPCI tuning and. flow demonstration (CST' to CST) 150 psig plateau.
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System expansion data, reactor -)
building secondary'walkdowns', 150- i psig plateau.
August 8, 1986 RBCLCW performance test, normal'and l blowdown mode, 150 psig plateau.
August 10, 1986 RBCLCW performance test, normal-and j blowdown mode, 600 psig plateau.
August 11, 1986 Reactor cooldown to investigate /
repair a wide range transmitter.
Unusual Event declared..
August 13, 1986 Reactor water level measurements, J rated plateau. !
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System expansion data, reactor building secondary walkdowns, rated plateau.
Radiochemistry water chemistry ,
sampling data, rated plateau. I August 14, 1986 Scram timing of sequence A rods.
System expansion balance ~of plant walkdown: steam tunnel and turbine building.
Reactor cooldown-for maintenance work in the drywell and sequence- ;
exchange.
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2.0 CHRONOLOGY OF EVENTS - (continued) 1
. . l August 15,'1986 Commenced reactor heatup in' the B-2 1 sequence, reactor critical.
Drywell. entry at rated conditions )
for system expansion data. j i
Feedwater low flow controller testing.
Scram timing of sequence B rods. l August- 16,.1986 Commenced main turbine'startup j prerequisites. _
HPCI tuning at rated conditions .(CST to CST). l RBCLCW performance test at rated ,
l pressure plateau.
1 August.17, 1986 Main turbine roll.
1 Reactor building service water- !
performance test.
l August 18, 1986 RWCU blowdown and normal mode tests.
Reactor shutdown due to hurricane f warnings.
August 20, 1986 Reactor startup - heatup to rated pressure plateau.
System expansion balance of plant l
walkdown at rated pressure plateau.
August 21, 1986 RCIC tuning to the reactor vessel at rated pressure plateau.
RWCU bottom head drain flow
. calibration.
J August 22, 1986 CRD flow controller tune-up.
RCIC instrumentation piping vibration test.
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2.0 CHRONOLOGY OF EVENTS - (continued)
August 23, 1986 'HPCI tuning at rated '(CST to CST) .
Reactor cooldown to 150'psig
. plateau, Feedwater. low flow controller tuning in auto during cooldown.
August 24, 1986 RCIC Vessel Injection'and Stability Demonstration at 150 psig.
Heatup to rated pressure.
Feedwater low flow controller in ;
manual during heatup.- 1 l
' I HPCI tuning at rated conditions (CST i to CST). I I
August 25, 1986 Main turbine roll and excitation j l checks.
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' August 26,'1986 Main turbine generator- i synchronization tolthe grid and l 24 hr. run. I l August 27, 1986 Turbine generator off grid.
RCIC cold quickstart #1 (vessel-injection).
RCIC transient vibration test.
1 Process computer TIP hot alignment. I i
August 28, 1986 HPCI tuning at rated pressure plateau.
Reactor cooldown to 150 psig plateau. I I
HPCI quickstart (CST to CST) and stability demonstration at 150 psig.
Reactor heatup to rated pressure l plateau. l l
HPCI hot alignment verification.
August 29, 1986 CRD flow controller tuning.
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'2.0 CHRONOLOGY ' OF EVENTS ' (continued) l August 30, 1986 .RCIC cold.quickstart #2 (vessel.
injection). 1
.I RCIC transient vibration test.
Loose parts monitoring data collection during RCIC vessel injection.
Reactor cooldown and shutdown.
May 22, 1987 Reactor critical. I l
i May 26, 19D7 ADS valve 18-month surveillance 1 :
l May.27, 1987 APRM calibration. ;
l May 29, 1987 RCIC rated flow surveillance.
HPCI rated flow' surveillance and. i controller output limiter ~ l adjustment.
May 31, 1987 RCIC functional and stability.
demonstration from Remote Shutdown Panel.
June 1, 1987 Power reduction due to system load demand.
June 4, 1987 Generator synchronized for 8-hour run.
June 5, 1987 HPCI endurance run.
June 6, 1987 Reactor shutdown and cooldown. l l
3.0 STARTUP ACTIVITIES PERFORMED / TEST RESULTS The plant has been shutdown during the entire period covered by this Supplement. There are.no new results to report.
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14.0: LICENSE CONDITIONS' Technical' Specifications' require'thatEthe'Startup Reporte discuss the licenseEconditions-whichlaffectcplantastartups and power. escalation testing.1 Thefspecific;1icense-conditions are' delineated'in paragraph 2.C-of the'Shoreham ,
' Operating License (NPF-36,of July 3, 1985). Each' condition:
is summarized ~and its status,'as'itiappliessto the ,
- completed. portion of:the' test program,.is~provided below.
4 .1: Condition: ' The ' maximum- core thermal power shall: not L
exceed,5% rated. core thermal power.-
Status: During'the period covered byLthis Supplement, the reactor did notLexceed 5%-
rated core. thermal power.
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L 4.2 . Condition: The plant.shall-be operated in accordance-L with the Technical Specifications and the- 1' Environmental' Protection Plan.
u Status:- The Low ~ Power TestLProgram hasLbeen
. conducted in accordance with' Technical Specifications and the. Environmental Protection' Plan. .Any. deviation'from these documents is required to be reported to the NRC via'a License Event' Report (LER).
4.3 Condition
The plant shall maintain.the' fire protection program as described in the l Fire Hazards Analysis Report and in the l FSAR.
Status: The plant has adhered to the provisions 1 l of the Fire Protection Program. Any.non-compliance or missed fire watches'shall be the subject of a Licensee Event Report.
L 4.4 Condition: Changes to the initial test program shall l be reported in one month.
l Status: All changes to the test program.as l- described in Chapter 14 of the USAR will ~
be reported per the license condition.
4.5 Condition
The initial inservice inspection shall be developed and implemented before'the-first refueling outage.
,: Status: This condition is not affected by the Low l- Power Test Program.- Development of the L inservice inspection program is in.
progress.
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4.6 Condition:- Within' thirty (30) days after plant startup'following the first refueling outage, the licensee shall comply'with items 1,.2, and 3 of I.E.' Bulletin No.
79-26, Revision 1, " Boron ~ Loss From BWR Control Blades", and submit a written response on item 3.
Status: This condition ~is not yet applicable.
4.7 Condition
The provisions of the NUREG-0737 action plan described.in the SER, Supplement 1 and 4, shall be followed.
4.7.1 Status
The qualifications of the required
'seven backup STA's have been submittedEto the Commission, all have been approved.
4.7.2 Status
The requirement to mark control room.
indicators with operating limits and with trip and alarm setpoint values is not yet implemented. The requirements of the provision remain under review and shall be imple-mented prior to the completion of I the startup test program.
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4.7.3 Status
Modifications to the post accident sample facility, which will enable sampling using the' modified core damage procedure, are in-progress as '
noted in Section 3.21 of IE-Inspection Report 85-038. This requirement is being tracked by Region I as 50-322/85-04-19.
4.7.4 Status
The modifications required to imple-ment the emergency response capa- i bilities, as require by Attachment 1 1 to the license, are in progress.-
4.8 Condition
Prior to November 30, 1985, all i electrical equipment shall be qualified.
Status: Station modifications to environmentally qualify the required electrical 1 equipment are complete.
l 4.9 Condition: The remote shutdown system shall be
- improved prior to the first startup following the first refueling outage.
Status: The modifications will be implemented as required.
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i 4.10 Condition: The RIIR system may not.be op'erated in the .
steam condensing. mode except1under
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emergency conditions.
Status: The station procedures have been modified' to. preclude the steam' condensing mode of operation except as a last resort when all 'other methods of core and containment cooling have failed.
4.11 Condition: Two containment isolation barriers in. 1 series will be installed by the end of the first refuel'ing outage,
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Status: Modifications to satisfy this condition will be completed by the end of the first ,
refueling outage. {
l 4.12 Condition: The provisions of Attachment 3 to the. H license.shall be satisfied as they apply- i to the TDI diesel generators. l l
Status: Station procedures and maintenance schedules have been modified to include the required TDI diesel generator tests i and inspections. '
4.13 Condition: The results of the independent design j review shall be incorporated prior to l exceeding G percent power. '
Status: The requirements of this condition have
'been met.
4.14 Condition: a.) Prior to exceeding five percent power, radiation monitoring panels 1D11*PNL-117A, B and radiation.
monitoring pumps 1D11*P126, 134 shall be qualified, b.) The invessel storage racks shall be qualified prior to use.
Status: a.) The required qualification,for the radiation monitoring equipment has been completed, b.) The invessel storage racks have been administratively prohibited from use.
4.15 Condition: The plant shall have on-shift advisors as required by Attachment 2 of the license.
Status: The plant currently has sufficient numbers of qualified on-shift advisors to satisfy this condition. j 3
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4.16 ' Condition:-'The. Emergency.CorelCooling Syste'ms performance shall;befre' analyzed for;the-.
m .: second-cycle-and beyond,cutilizing.models
.thatiaccount for burnupugas. pressure-and:
- , local oxidation and.which are approved'by-
'the NRC;.
Status: .ThisLeondition willfbe' completed-by the >
'requiredLdate.'
1 4 4.17- Condition:l 'The~ licensee.shall: implement;the. response: l to Generic: Letter 83-28 onischedule. 1 l
Stat'us: All' provisions:stipulatedLin1SNRC-1013A '
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=1116,11184,iands1217.are complete:except -j "forithe provisionLthat~ requires thei !j
. Safety: Parameter Display Systemf(SPDS) to ibe operable' prior to.the,first. restart after;the;first refuelingLand/the' review ,
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- i. 'of Technical?Specificationctesting y J i Jintervals. This' review?will beidone asi
! committed to'in:SNRC-1184. In'a July >15, l 1987.NRC1(A. Thadani)lletter to the BWROG n
. (T. .Pickens)', the'NRC: approved the:BWROG.
methodology in an attached safetygevalu- j
.ation report. . We are. currently. reviewing a the BWROG methodology, forLapplicability; :)
to Shoreham. .The results:of this~ review i will be documented via a' separate-transmittal.
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