SNRC-1336, Suppl 6 to Shoreham Nuclear Power Station Startup Rept for Feb-May 1987

Suppl 6 to Shoreham Nuclear Power Station Startup Rept for Feb-May 1987

ML20214E511
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	05/14/1987
From:	Leonard J, Steiger W LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SNRC-1336, NUDOCS 8705220121
Download: ML20214E511 (13)

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r; LONG ISLAND LIGHTING COMPANY Shoreham Nuclear Power Station Supplement No. 6 to the 4

STARTUP REPORT for the period February 1, 1987 to May 1, 1987 l

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f.: ' s, TABLE OF CONTENTS.

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1.0 Overview

. s g - t' r '2.0 Chronology of Events- i

- 3 '. 0 '- :Startup Activities; Performed / Test Results

. ., 9r.3 4 .~ 0 's License Conditions

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• 1.~ 0 : OVERVIEW This Startup Report Supplement has been written by the Long Island Lighting l Company (LILCO) for submittal'to the

-N,uclear Regulatory Commission in compliance'with Shoreham Nuclear Power Station Technical Specifications, paragraphs; 6.9.1.1 through 6.9.1.3, and Regulatory Guide 1.16,

-Revision 4,.section C.l.a.

Technical Specifications and Regulatory Guide 1.16 require that a sumnary report of plant startup and power escalation testing be submitted within.9' months following: initial criticality. Shoreham-Nuclear PowerLStation1(SNPS) achieved initial criticality on February.15, 1985,'LILCO

' submitted'a Startup Report on November 15, 1985. The scope. 1 I

. of.that Startup Report included fuel load and-initial.

criticalityfunder the. 001% power license, NPF-19, and-low power-testing conducted under the 5% power license, NPF-36. .l 1

Since SNPS has not completed its startup test' program.or l commenced commercial power; operation, additional Supple--

ments-are required on a periodic-basis. This Supplement .

covers the period from February 1, 1987 to'May'1, 1987. l i

Shoreham has been shutdown since-September of 1986. Major

< modifications in progress during this reporting period are the Main Steam! Isolation Valves . (MSIVo) setpoint change from Level. 2 ' (-38") to Level l' (-132") reactor water level and the standby liquid control system compliance-(10-CFR 50.62) . modification, which will enhance the reactor  ;

shutdown capabilities in the event of an anticipated l transient without scram. <

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Other modifications in progress cn completed during-this I

period include work on the drywell vacuum breakers, the main circulating water systems and portions of the Colt diesel tie-in modification.

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'220: CHRONOLOGY OF EVENTS EReceivedilowjpowerLlicenseN001%

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' December' 7,11984'

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- December 117,':1984 -LSources": loaded in core.:

December'21,1 1984 _ Fuelf loading:: commenced.:

~~Januaryf4,,1985 Partial core-shutdown marginLtest;-

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-January- 19,.1985_ Fuel-loading; completed.

. January-25, 1985 _CRD'open vessel testing completed.

February.-17, 1985 Initial critical and' shutdown margini

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-test. " Completed:open vessel testingL 1 June-4, 1985 CRD openLvessel retest completed. ,

July 3,.1985: 5% low-power-' license-received.

July 7, 1985 Reactor.criticalisequence_B.. Test condition':Heatup.

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 .SRVifunctional test-performed (STP-26).

July 11, 1985 150 psig plateau 7 reached..

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System expansionLDW entry.

RCIC/ testing..

HPCI system testing. .

July 14, 1985 Reactor scram #1.on'Rx level ~.

-July 17, 1985- APRM calibration at1150 psig.

HPCI' testing.-

System expansion testing.

RBCLCW performance testing.

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' July 18, 1985 Reactor-Shutdown for RPV level.

instrumentation work.

-July 23, 1985 Reactor critical.-

July 26,.1985 Reactor shutdown for RPV-level-

', instrumentation work.

Julyf29, 1985

Reactor critical.

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4 2 .' O . CFRONOLOGY~ OF EVENTS -~ (continued)

July 31, 1985 Reactor-' pressure to 150 psig.

HPCI system testing..

August 1, 1985 350_psig plateau.

Drywell radiation survey.

System expansion =drywell inspection,

-system expansion data.

August 3,.1985 600~psig plateau.

System expansion.-

RBCLCW' performance..

CRD testing.

August' 5, 1985- 800 psig plateau.

System expansion. '

CRD testing.

' August 7, 1985 . Rated pressure plateau.

System expansion testing.

HPCI~ testing..

RCIC testing.

CRD testing.

RBCLCW testing.

Water level testing.

Process computer-STP-13' testing..

Chemical and radiochemical testing.

Radiation measurements.

LPRM testing.

August 23, 1985 Reactor pressure reduced to 150 psig.

HPCI testing.

3 RCIC testing.

August 24, 1985 Reactor shutdown after initial heatup.

August 30, 1985 Reactor critical sequence A.

August 31, 1985 Scram #2 on loss of instrument-air.

1 September 3, 1985 Reactor critiga] requence.A. Second heatup to 150 F.

September 4, 1985 Heatup to 250 . -

150 psig.

System expansion testing.

September 6, 1985 Reactor pressure 350 psig.

System expansion testing.

September 6,:1985 Reactor scram #3 due to surveillance on level instrument.

September 7, 1985 Reactor pressure 600 psig.

System expansion testing.

CRD testing.

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m 2. 0. : CHRONOLOGY OF. EVENTS: ^(continued)-

September 8, 1985 UnusualJevent-due$to reactor-levell

-indicationlproblem.

September' 10,l1985. sReactor:: shutdown-for repair of '

reactor. problem. . -

' Septemberill, 1985; Reactor" critical?and heatup;to:

= investigate' level problem.

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Reactor ' scram (4(on'-l'ow-water levell

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' September ~12' , 1985:

4 indication. ; Actual levelididlnot.

change. ' Level? instrument. problem

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. September 18, 1985' ;Reactorfcritical sequence A.-

Reactor 1 pressure 1800lpsig.

September 21, 1985 _

System expansion testing.1

- CRD - testing . . .

RPV level? problem' fixed.

September 21, 1985 Rated pressure reached.-

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' System expansion-testing.

Second;heatup.-

RCIC testing.s 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 traintenance.

i October 3, 1985- Reactor critical sequence A.- Third.

heatup to rated pressure.

System. expansion-testing.

August 13, 1986- Reactor water level measurements,-

rated. plateau.- .

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-SystemLexpansion~ data, reactor 1

~ building secondary 7walkdowns, rated plateau.

Radiochemistry water chemistry.

sampling data, rated plateau. _

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'2.0 CHRONOLOGY OF EVENTS 1(continued)

August 14, 1986' Scram timing of sequence A rods.

System expansion balance-of plant walkdown: . steam tunnel and turbineL building.

Reactor cooldown for maintenance.

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work in the drywell and sequence, exchange.

. August 15, 1986 Commenced reactor heatup in the B-2 sequence, reactor critical.

Drywell entry at rated conditions for system expansion data.

Feedwater low flow controller testing.

Scram timing of sequence B rods.-

August 16, 1986 Commenced main turbine startup prerequisites.

HPCI tuning at rated conditions (CST-to CST).

RBCLCW performance test at rated pressure plateau.

August 17, 1986 Main turbine roll.

Reactor building service water performance' test.

August 18, 1986 RWCU blowdown and normal mode tests.

Reactor shutdown'due to hurricane warnings.

August 20, 1986 Reactor'startupt heatup to rated pressure plateau.

System expansion balance of plant walkdown at rated pressure plateau.

August 21~, 1986 RCIC tuning to the reactor vessel at rated pressure plateau.

1 RWCU bottom head drain flow calibration.

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2 [ G'- l CHRONO' LOGY 10F EVENTS --(continued).

[ August:22,fl986' CRD ; flow Econtroller t tunekup'.-

RCIC instrume'ntation piping-

-vibration, test.-

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HPCI- tuning . at .' rated - (CST J to - CST) .- -

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Reactor cooldown cto 150 psig

. plateau.

'Feedwater.-low flow controller' tuning' _

in auto during cooldown.- j l August' 24, 1986 _

RCIC Vessel-Injection;and Stab:ility' '

1 Demonstration at-150 psig.

Heatup-to rated pressure.- ,

Fecdwater' low flow controller in

' manual during heatup.

4-I HPCI tuning'at rated conditions ((CST to CST). '

August 25, 1986 Main turbine roll and excitationt checks.

! August 26, 1986 Main turbine generator .

synchronization to the. grid ~and 24 . luc . run .

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August ~ 27, 1986 Turbine generator-offogrid.

RCIC cold quickstartLil (vessel injection).

H RCIC transient. vibration test.

Process computer TIP hot alignment. >

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. August 28, 1986 HPCI tuning at rated pressure:

' plateau.

Reacthr cooldown to 150 psigtplateau.

I' HPCI quickstart-(CST to CST). and -

stability demonstration;at 150 psig.

sReactor h'eatup to rated pressure

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'l HPCIEhot'ilignment verification.

3- August 29, 1986 CRD flow controller tuning.

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- 2.0 CHRONOLOGY OF EVENTS -:-(continued)'

August 30, 1986 RCIC' cold quickstart #2 (vessel injection).

RCIC transient vibration' test.

Loose parts monitoring data collection ~during RCIC vessel

^ injection.

Reactor cooldown'and shutdown.

- 3.0 STARTUP ACTIVITIES PERFORMED / TEST RESULTS The plant has been shutdown during the entire period covered by.this Supplement. There are no new test results' to report.

4.0 LICENSE CONDITIONS Technical Specifications require that the Startup Report discuss the license conditions which affect plant'startup and power escalation testing. The specific license 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 it applies to the .

completed portion of the test program, is provided below.

4.1 Condition

The maximum core thermal power shall not exceed 5% rated core thermal power.

Status: During the period covered by this Supplement, the reactor has been shut down thus core thermal power was less than 5% rated core thermal power.

4.2 Condition

The plant shall be operated in accordance with the Technical Specifications and the Environmental Protection. Plan.

Status: The Low Power Test Program has been conducted in accordance with Technical' Specifications and the Environmental' Protection Plan.- Any deviation from these documents is required to be reported to the NRC and be the subject of ..,

a License Event Report-(LER). .; -

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4.3 z Condition:: LThefp1'antVshall maintain'theifire- _. ,

- .  ; protection program as? described in the

' Fire Hazards Anal' ysis [ Report (andiin the

FSAR.-

Status: Theplanhlhasadheredto;theprovisions, U Jof the< Fire Protection: Program.: LAny.:

missed-fire watches shall"beithe' subject-of a Licensee-Event Report.-

. Condition: ..Changesjto theEinitial test program shall

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'be-reported inLone-month' .

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Status: .All changes to the test program-as-- ,

. described'in.: Chapter 14:of the1USAR will?

be reported'per..the~1icense condition.-

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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 Power TestiProgram. Development of:the inservice inspection: program isnin.

progress.

4.6 Condition

Within thirty '(30) days after plant

startup following the'first refueling outage, the -licensee :shall ' comply .with j items 1, 2, and = 3 of I.E. Bulletin No.: .

79-26, Revision 1,'" Boron Loss From-BWR Cont'rol. Blades", and submit a written =

response on item 3.-

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Status: This condition is not yet applicable.

4.7 Condition

The provisions of.the NUREG-0737 action plan described in the SER, Supplementil~

and 4, shall be followed.

4.7.1 Status

The qualifications of'the required ~

seven-backup STA's have been.

submitted to the Commission,Lall

" have been. approved.

4.7.2 Status

The-requirement to mark control room '

indicators with operating: limits-and' l'

with-trip and alarm setpoint! values is not'yet> implemented. The j requirements'of.the' provision remain under review and shall be implemented prior to the completion of:the startup-test. program.

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4.7.3 Status

Modifications to-the post accident sample facility, which will enableL sampling using the modified: core damage-procedure, are in progress as noted in Section.3.21 of IE Inspection ReportL85-038. 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-bilities,-as require by Attachment-1 to the license, are in progress.

4.8 Condition

Prior-to November 30,71985, all electrical equipment shall be qualified.

Status: Station modifications to environmentally qualify the required electrical equipment are complete.

4.9 Condition

The remote shutdown 1 system shall be improved prior to the first startup_ i following the first refueling outage.

Status: The modifications will be implemented as required.

4.10 Condition: The RHR system may not be operated in the-steam condensing mode except under emergency conditions.

Status: The station procedures have been modified to preclude the steam condonsing mode of operation except as a last resort when all other methods of core-and containment i cooling have failed.

4.11 Condition: Two containment isolation barriers in series will'be installed by the end of the first refueling outage.

Status: Modifications to satisfy this condition will be completed ~by'the.end of the first refueling outage.

4.12 Condition: The provisions of Attachment 3 to the license shall lua satisfied as they apply.

to the TDI diesel-generators.

Status: Station procedures and maintenance schedules have been modified to include the required TDI diesel generator tests and inspections.

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, 1 4.~13.. condition: The resultsfoffthe'independentcdesign-review:shall.beLincorporated prior.to?

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exceeding 5 percent power..

-Status: -The1 requirements of.this~ condition.have  ;

fbeen met.-

4.14~ Condit' ion:. Prior to' exceeding.five' percent.

a.). ipower, radiation monitoring panels

1D11*PNL-117A, } B and c radiation -

monitoring pumps.1D11*P126,.134 shall;be> qualified.

b.): -The invessel storageiracks shall be-qualified prior to use.

. Status:- 'a.) The' required qualification for1the i radiation monitoring l equipment has.

! been' completed.

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i. b.) The invessel' storage racks have-been l administratively prohibited:from use.

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4.15 Condition: The plant shal13 have on-shift advisors as required by Att'achment 2-of~the--license.

1 Status: The' plant currently has sufficient. '

numbers of qualified ~on-shift advisors to satisfy this' condition.

l 4.16 Condition: The Emergency Core Cooling Systems

performance shall be reanalyzed for the-

{ second cycle and beyond,' utilizing"models

!- that; account for burnup gas pressure:and-local oxidation and which.are approved by' '

! the NRC.

Status: This condition will be; completed by the ' '

required date.

Condition: The licensee shall implement the response. R 4.17 to Generic Letter 83-28 Eon schedule.-

Status: All provisions stipulated-in SNRC-1013,

, 1116,'1184,.and-1217-are complete except-

for the provision that requires the Safetyf Parameter Display System. (SPDS)- to ,

be operable' prior to.the first restart l afterrthe first. refueling and the: review I of. Technical Specification: testing

- intervals. This review will be done as committed to in:SNRC-1184.

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s f-i fg LONG ISLAND LIGHTING ~ COM PANY SHOREHAM NUCLEAR POWER STATION P.O. BOX 618. NORTH COUNTRY ROAD + WADING RIVER N.Y.11792 JOHN D. LEONARD, JR.

VICE PRESIDENT . NUCLEAR OPERATIONS

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MAY 151987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Supplement No. 6 to the Startup Test Report Shoreham Nuclear Power Station -. Unit 1 Docket No. 50-322 Gentlemen:

Attached is Supplement No. 6 to the Startup Test Report prepared by the Long Island Lighting Company in compliance with Shoreham Nuclear Power Station's Technical Specifications paragraph 6.9.1.1 through 6.9.1.3 and Regulatory Guide 1.16, Revision 4, section C.1.a.

This report covers the period from February 1, 1986 to May 1, 1987. Shoreham has been in an outage since September 1986. No startup activities were performed during this reporting period.

We have, however, been working on various other activities and those which required a major effort are identified in this report.

If there are any questions, please contact this office.

Very truly yours, f D. Leonard, r .

V ce President'- Tuclear Operations 0:ck V

Attachment cc: R. Lo h Region I Administrator C. Warren h