ML20138B531

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Forwards Supporting Preliminary Data & Summaries for SALP, Per 850924 Memo.Review & Comments Requested
ML20138B531
Person / Time
Site: Palo Verde  
Issue date: 10/08/1985
From: Kirsch D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Chaffee A, Crews J, Miller L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8510150388
Download: ML20138B531 (25)
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UNITED STATES g.

g NUCLEAR REGULATORY COMMISSION l

J, j-REGION Y g'

1450 MARIA LANE.SUlrE 210

%,*..*,d WALNUT CREEK, CALIFORNIA 94596 October 8, 1985 MEMORANDUM FOR:

J. Crews, RV A. Chaffee, RV L. Miller..RV A.' Hon, RV C. Sorensen, RV G. Hernandez, RV G. Fiore111, RV C. Bosted, RV J. Ball, RV R..Scarano, RV G. Knighton,.AD/L:NRR E. Licitra, Project Manager, NRR M. Ley Project Manager.-NRR.

D. Schaefer,-RV C. Sherman, RV R. Fish, RV-P.-Qualls, RV FROM:

' D. Kirsch, Acting Director

. Division of _ Reactor Safety and Projects, RV

SUBJECT:

SYSTEMATIC ASSESSMENT'0F LICENSEE PERFORFANCE (SALP)

FOR PALO VERDE (Period Apr11 1, 1984 through September 30, 1985)

Reference:

SALP Notification Letter to above from D. Kirsch dated September 24, 1985.

Por referenced. letter, enclosed are the supporting preliminary data and.

i summariesfor the Palo Verde SALP..Please review and provide any comments i

and corrections'to A. Hon ~.

. F. Kirs Acting Director Division' of Reactor Safety.' and Projects cc:'$J.: Davis,NMSS-

'R. Seyfrits'AEOD.

0. Shackleton,'OI/SFF0 R. Scarano,-RV

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SALP OPERATION ACTIVITIES Unit 1 During the first three months of the assessment period, Unit I was in the final stage of preoperational testing. Preoperational testing was completed and the Hot Pump Demonstration Test was successfully conducted from July 1 to August 3, 1984. Integrated Safeguards testing was completed satisfactorily on October 3.

A low power licensee (NPF-34) was issued on December 31, 1984 and initial fuel load began on January 7, 1985 and.was completed on' January 11.

Following the initial fuel load, conditions of the low power license were completed and the post core Hot Functional Test (HFT)-was conducted from April 21 to May 15 with acceptable results. Following the Post, Core HFT an outage to replace two weeping pressurizer. code safety, valves and twolleaking secondary safety valves was perform'ed f rom May' 16 to May 20. ' Af ter -this outage, initial criticality was achieved on May 25,-low power physics testing was commenced, and a full power license-(NPF-41) was issued. on June 1.

Low power testing was successfully completed on June 4.g, Mode.1 was entered for the first time on June 5 for power ascension testing. which was~ ongoing through the'end of the assessment. period.

During power ascension testing on June 14, 1985, the reactor tripped from 20%

full power (FP) on high pressurizer pressure following a trip of the main feedwater pump turbine. The reactor again tripped on July 1 on high pressurizer pressure following another loss of a main feedwater pump. Recctor power reacknd 50% FP for the first time on July.6 and testing at the 50% FP plateau continued until July 11 when unidentified RCS leakage of 1.2 gpm required that the reactor be shut down. Attempts by the licensee to locate the source of leakage were unsuccessful and reactor power was returned to 50%

FP on July 16 following repetitive RCS leakage calculations which verified that leakage had returned to within Technical Specifications limits. A reactor trip occurred on July 17 resulting from a malfunction in a memory card of a control element assembly calculator. The unit was returned to power on July 19, and was shutdown due to a main condenser tube leak on July 22.

The unit went to Mode 5 on July 24, because unidentified RCS leakage was again calculated slightly above the Technical Specification limit. The cause of the unidentified RCS leakage was determined to be from a packing seal on the "A" Charging Pump. _Fo] lowing seal repacking,'the plant remained in Mode 5 until August 2, when the unit went to Mode 4 for testing of modifications made to the post accident sampling system. The reactor was restarted, and power ascension testing was resumed on August 26, 1985.-

j On September 2, 1985, power was reduced from 50% to 11% because of main condenser tube leakage. One train of circulating water was secured and power

' was returned to 50% FP while several tubes. vere plugged. At the completion of testing at the 50% FP plateau on September 12, a load rejection test caused an unplanned reactor trip and loss of nonessential power. The reactor trip resulted from a loss of reactor coolant pump flow and a. safety injection occurred on low pressurizer pressure. Although not specifically needed during

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s fthis. event, the.: charging pumps.became~x v _ gas bound,and.were:unavailabic~during a v

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-portion of,the' transient.' The load' rejection test was successfully Treperformed-with.a" modified;testprocedure'onlSeptember16.[Afterthekoad e4 4

rej ection test.. power was - reduced ~ to '20% FP and 'a. shutdown'butside'1 control roomtestwassuccessf'ullycompleted.QAs'aresulblofthe'temporarylossof

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the charging pumps ~ during the September '12 ~ event described above,' the' licensee agreed co remain shut down until interim r easures were taken to. ensure.the _

reliability lof the charging pumps. with emphasis on1their function as part of

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the a' xiliary spray system. The unit was restarted on September 21 and power A

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was raised to the 80% FP testing ~ plateau on Septembar126. Power e.scension.

testing' continued'at 80% FP.through the end of'the' assessment period.

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3 SALP OPERATION ACTIVITIES p

. Unit 2 During the assessment period the. licensee's' activities included the

- continuation of construction from 91.1% to 99.9% completion, and the preoperational testing of plant equipment and systems.

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Project, milestones successfully achieved included completion of the primary system _ hydrostatic test-on November 9, 1984, completion of the secondary system hydrostatic test on November 13, 1984,-completion of the containment

' Integrated Leak Rate Test on February 8, 1985, completion of the Hot

Functional Test on-August 8,1985, and. completion of the Integrated Safeguards

-Test on. September-13, 1985.

The-fuel necessary for core loading was received on site, and 75% of the plant systems and' areas were. transferred from the Startup to the Operations organization.:

At'the conclusion of the assessment period, the plant was engaged in the

- completion of design changes, equipment maintenance, and construction items in preparation'for the conduct of required system surveillance tests.

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4 SALP OPERATION ACTIVITIES

. Unit >3 sDuring the assessment period,-the licensee's estimace of construction completion'was calculated to have progressed from 89.4%.(March 31, 1984) to 98.6% (September 30, 1985). During this period all major components, equipment, and structural concrete placements"were completed. The major construction activity currently in progress'is the installation of' electrical

.cabic and.. terminations, which is estimated,at.75% complete.

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-At-the conclusion of this, assessment peiidd[the plant was conductins'~

prerequisite and preoperational testington, class and non-class electrical i

subsystems. -Additionally, prerequisite *, testing.was,in progres5'on all major systems,-except for the Reactor. Coolant,' Safety' Injection and' Steam Generator / Main Steam. Prerequisite._ testing included, but was not necessarily limited to, initial instrument, cal'ibrationT flushing," Ele'aning and functional tests of components.

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.f PALO VERDE UNIT 1 Rep'ortable: Licensee Event' Reports.

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p (01/01/85 009/30/85')?

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'v LER' TITLE-

':SALP AREA /CAUSE CODE

  • n 85-01 INADVERTENTCONTROLROOkENSENTIALVENTILATION 2/D ACTUATION'DUE TO INADEQUATE SURVEILLANCE'

. PROCEDURE' 85-03.

.! AUTO ACTUATION OF BOP ESF. SYSTEM DUE TO A 1/5 SPURIOUS'HI RADIATION ALARM CAUSED BY'A, DEFECTIVE BOARD'-

85-04E AUTO ACTUATION'0F CONTAINMENT PURGE ISOLATION 2/E ACTUATION SIGNAL DUE TO A SPURIOUS FAILURE ALARM 85-0'5 AUTO ACTUATION OF.CPIAS AND CREFAS DUE TO A 2/E

~

SPURIOUS EQUIPMENT FAILURE ALARM ON RAD MONITOR 85-06 LOSS OF 0FFSITE POWER TO TRAIN A IE. BUS DUE 1/A TO OPERATOR ACCIDENTALLY HIT THE BREAKER CCITIROL ~

SWITCH.

85-07 AUTO ACTUATION OF NSSS ESFAS DUE.TOLA FAULTY 1/$

TRANSFORMER 85 SURVEILLANCE TEST DUE TO PROCEDURAL AND HUMAN ERROR ~

l85 AUTO ACTUATION OF BOP ESFAS CABINET DUE TO 1/D PROCEDURAL ERROR

' 85'- 11 ~

AUTO ACTUATION OF BOP ESFAS DUE TO. RADIATION 2/B

. MONITOR SOFTWARE ERROR '

--85 2/K CH LOW' STEAM PRESSURE SIGNALS WERE 1/B s

' SPURIOUSLY ACTUATED RESULTING IN PPSt OPERATING ALL 4 RX TRIP BREAKERS-l85-13 INADVERTENT:STARTIbFDG'DURING' ROUTINE 1/D SURVEILLANCE TESTING DUE TO AN ERROR IN PROCEDURE

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- Palo Verde-Unit _1.LER's

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TITLE SALP AREA /CAUSE CODE.

c85-14

' REMOVAL' 0F 125V DC DUE TO HUMAN ERROR DURING 1/A SCHEDULED MAINTENANCE CAUSED BOP /ESRAS 4

ACTUATION-l85-15:

.. FAILURE TO COMPLETE SURVEILLANCE-TEST AS 4/A REQUIRED BY TECH SPEC 4.1.2.7.B-

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s85-165 FIRE WATCH ROVING PATROLS D'ID'NOT' PROPERLY

~ ) 5/f'

CONDUCT HOURLY ROUNDS AS REQUIRED BY TECH, SPEC 3.7.12

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.- 85-17 '

WHILE CLOSING BREAKER, MOMENTARY _HIGH OUTPUT;',

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' CAUSED CREFAS TRIP AND ACTUATION 0F FILTRATIONAH p'd SYSTEM'-

.E, A

85-19

. REACTOR. TRIP'DUETOLIMPROPEROPERATION40F)Ls

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. MAIN FEED: PUMP 85-20, INADVERTENTSTART0FDCDURING. TESTING 1k3UE'

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tTO~A SNEAK CIRCUIT-

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' FIRE HOSE HEADER IN. CONTAINMENT WAS ISOLATED 5/A. ~

.WHILE: MAINTENANCE WAS PERFORMED - TECH SPEC-

. VIOLATION

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.JAUTO ACTUATION OF BOP /ESF DUE TO SPURIOUS M 2/E 85-22:

HIGH RADIATION ALARM IN FUEL-POOL. AREA (l

MONITOR.

'85 -INADVERTENT ACTUATION OF-EMERGENCY SAFETY 1/A.

~ FEATURE SYSTEM DURINGl SURVEILLANCE TESTING DUE TO ERROR-'

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85 : FAILURE TO VERIFY F RE D00R POSITION DUE TO 5/D -

.. " PROCEDURAL ERROR 4 s

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-85 27:

' AUT0' ACTUATION '0F CTR RM ESSENTIAL: FILTRATION L2/E

.DUE TO SPURIOUS:SIGEAL FROM,RU-29i DAMPERS f

FAILED.TO CLOSE 85-28

. INADVERTENT' ACTUATION OF-ESFAS DURING-1/D~,

1 SURVEILLANCE TEST OF ELECTRICAL SYSTEM

85 30 fBOTH ECCS TRAINS DECLARED INOPERABLE DUE TO
.

'1/D

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-FAILURE TO RETEST VALVES.PER ASME CODE PRIOR:

TO' MODE 41

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' AUTO-ACTUATION OF CONTROL. ROOM ESSENTIAL 2/E

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FILTRATION'DUE TO' SPURIOUS SIGNAL FROM RU-29?

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SALP AREA /CAUSE CODE LER TITLE

, 17 f 32-

, IMPROPER SAMPLE FROM FUEL HANDLING B DG DUE 2/A TO SYSTEM LINEUP

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'85-33

, UTO ACTUATIOKlOF. CONTROL ROOM ESSENTIALL 1/A

' FILTRATION & CONTAINMENT PURGE ISOL. DUE TO; TECHNICIAN ERROR

?.4 85-35

! FAILURE TO PERFORM ASME SECTION XI~REQdI' RED 1/D TEST REVIEW DUE TO PROCEDURAL ERROR t

85-36 "

~ IMPROPER SAMPLE FROM PLANT VENT DUE TO VALVE 2/A N

LINEUP IN SAMPLE CART e

[85-377

INVALIDATION OF GRAB SAMPLE DUE TO MOISTURE 2/B TS13.3.3.9 ACTION:40 e

.85-38; FAILURE TO MONITOR: CONTAINMENT AIR 1/A J85-39

.0PERATOR ERRO'R IN~ PERFORMANCE OF SAFETY 4/A SURVEILLANCE 85-40 i CONTINUOUS FIRE WATCH NOT PERFORMED,WHILE-5/A.

FIRE SPRINKLERS SYSTEM WAS ISOLATED ~

85 41:

CHANCES'TO ESF VENTILATION SYSTEM,' CONTROL:

2/D 2

RM. & PUMP RM.," DEFEATED ESF CAPABILITY TO REMOVE IODINE'

' " 42.

. PLANT, SHUTDOWN REQUIRED BY TECH SPEC DUE.TO 1/D 3

UNIDENTIFIED: LEAK GREATER THAN 1 GPM-8'5-43.'

REACTOR' TRIP ON HI' PRESSURIZER PRESSURE' 1/B v -

85-44.

-FAILURE TO TAKE. PLANT VENT BACKUP SAMPLE:

2/A s -.. 85 45-

' FAILURE TO PERFORM ASMI XI TEST-1/D s

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FIRE; WATCH PERFORMED LATE.,

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. INADVERTENT RPS ACTUATION DUE T0_ MALFUNCTION.

LOF. MEMORY. CIRCUIT: BOARD IN CEA CALCULATOR a..-

85 ISOLATION;0F PLANT PROTECTION CHANNEL DUE TO'

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. Palo Verde Unit 1 LERs V

85-52 POST' ACCIDENT SAMPLING SYTEM MATERIAL 2/B DEFICIENCIES

. 85-53 SUPRIOUS ACTUATION OF CONTAINMENT PURGE 2/E ISOLATION AND CREFAS DUE TO RADIATION MONITOR SIGNAL

' 85-55'

-INOPERABLE EFFLUENT MONITOR DUE TO 4/D SURVEILLANCE REQUIREMENTS NOT PERFORMED PRIOR TO MODE CHANGE 85-57' ENTERING A SPECIFIED CONDITION WITH 1/A

, INOPERABLE SAFETY INJECTION TANK DUE T0 TECH SPEC MISINTERPRETATION

.85-59L FAILURE TO SURVEII; UNLOCKED FIRE DOORS 5/D

. 85 FAILURE TO FUNCTIONAL TEST CVCS LETDOWN SNUBBERS 4/D

. PRIOR TO. INSTALLATION 58-61.-

IMPROPER SAMPLE LINEUP FOUND ON RADIATION. MONITOR 2/A o

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h PALO VERDE UNIT 1 SYNOPSIS OF REPORTABLE LICENSEE EVENT REPORTS **

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Functional SALP Cause Code *"

Area

-A-B C

D E

X.

Totals

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1.

Plant Operations-8 3

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Radiation Protection 4

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Maintenance 0

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4.. Surveillance 2

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Fire Protection 3

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"t ' 9 6.1 Emergency Preparedness 0

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7. - Safeguards 0

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Refueling LO 0

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Quality Programs and 0

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Administrative Controls Affecting Safety 0 J {0 '

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10.. Licensing 0

0 0.

0-

11. Training O'

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TOTALS 17 7

1

.16 9

0 50 1

  • "Cause Codes:

A-Personnel Error B-Design, Manufacturing or Installation Error

C-External Cause

.'D-Defective Procedures E-Component Failure

  • X-Other

' ** Synopsis includes LER nos. 85-01 to 85-61~ exclude; non--reportable LER's

. NOTE:

Several LER's categorized in multiple areas of cause codes.

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F-11 TABLE C

- REPORTABLE 10CFR 50.55(e) REPORTS Verbal.

Written Notification. Report APS Functional Date Date Description DER No.

Area 12/23/83 04/13/84 QA FAILURES / LACK OF 83-88 9~

PROCEDURES FOR TESTING AND STARTUP ACTIVITIES 01/24/84'

'05/25/84

-FWIV STUCK DURING TESTING 84-03 14 02/16/84 12/12/84 DEVIATIONS-IN FOXBORO 84-06 17 ALARM MODULES 02/09/84 07/13/84 FAILURE TO COMPLETE CORRECTIVE 84-07

-9 ACTION IN DER 80-21 02/29/84 07/24/84 ITT/BARTON TRANSMITTERS DID 84-08 17 NOT MEET SPECIFICATIONS 03/13/84 04/29/84

. PROBLEMS WITH HVAC ACCEPT-84-13 15 ABILITY CRITERIA

--03/21/84-08/02/84 ESFAS. CABINET BASEPLATES

' 84-16."

17

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DO NOT MEET SEISMIC CRITERIA'

- t 04/20/84 05/17/84 ROSEMOUNT TRANSMITTERS NOT,

'84-21 17

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TORQUED TO-SPECIFIED, VALUES 3

04/20/84' 08/01/84

-UNIT;l CEA SHROUD' SUPPORT

'84-22 15 CONTAMINATED WITH OIL

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04/15/84 07/12'/84 AUX.'FEEDPUMP YOKE'SLEEVEi k 84-23 14 LOOSE' CAUSING DAMAGE

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05/01/84 10/23/84 LIMITORQUE_ VALVE OPERATORS.

'84-24 14 LOOSE ON VALVE BODIES 05/01/84 11/27/84 CONTAINMENT SUPPLY REGISTERS 84-25 14 WOULD NOT CYCLE-05/10/84 09/21/84 PLUNGER INTERLOCK HAS BENT-84-26 17 C-SHAPED: CLIP

.05/10/84 12/12/84.-

IMPROPER HANDLING OF 84-27 17

. INSTRUMENTS FROM' WALDINGER -

05/11/84.-

09/25/84 DEFECTIVE COATING ON DG 84-29 14-COOLERS'

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12 Table C Reportable 50.55(e) reports; a

Verbal Written Notification Report APS Functional

-Date Date-

! Description DER No.

Area I

05/17/84 07/12/84 UNSEALED PIPING PENETRATIONS

~ 84-31 13

=IN THE MSSS (05/17/84 >

'10/26/84--

lBOLTSONSITANKKEYWAYSFOUND

~84-34 14 UNTORQUED 05/17/84-

-11/28/84 SI VALVE STALLED WHEN OPENING 84-36 14

( '

OR CLOSING'

-05/10/84 12/17/84-

'UNATHORIZED/ UNQUALIFIED HVAC 84 15.

DUCT SEALANT USED..

05/25/841

'09/18/84 IMPROPERLY-WELDED FLANGE IN

.84-38

'13

' UNIT 2 07/17/84~

09/24/84

- " PIPE SLEEVES CAN NOT WITHSTAND; 84-46 13

. STRESS FROM NOZZLE LOADS'

~ 7/24/84-l10/18/84 LIMIT: SWITCHES SUPPLIED WITH ~

84-48 17 0

WRONG MATERIAL' PIPE PLUGS a -

08/01/84f 09/26/84 cAFW SYSTEM EXPERIENCES 84-49 13 tHYDRAULIC RESONANCE 07/24/84

-10/25/84

MSIVS DO NOT CLOSE IN 5 SEC.-

'84 50 17 07/24/84L 09/26/84 2-

, TURBINE DRIVEN AUX FEEDPUMP[

84-51 14 FAILS TO START!FROM AMBIENTI

_m

-08/10/84" E Q09/26/84' % RESISTOR' BASE FLANCES ON.

84-52 14-

! ' ATMOSPHERIC DUMP VALVES OVERSTRESSED'

'4; 1'2/12/84 ;

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<08/17/84 T..3V y(/~

BE OPENED ELECTRICALLY :

SUMPFISOLATION VALVE COUND NOT 54

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w i08/17/84 * "'12/06/84R j"7 UNQU1LIFIED FOXBORO MODULES:

84-55'

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,08/22/84NhJ12/08/8'4";j.? FIRE. DAMPERS NOT' CLOSING FULLY 84-56 15

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,!08/22/841 fl0/09/84 CABLEJINSULATION DAMAGED ~BY 84-59

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. FIRE, STOPS' 08/27/84 _

11/12/84Y h

TWO INCOMPATIBLE LUBRICANTS:

84-60~

'13

.y USED IN, VALVE OPERATORS,

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Table ~ ~C Reportable' 50.55('e) (reports; 'y 1 :

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. Verbal'/ %,Writtence*T a,,

i,

. Notific.ation

. Report!,I h;.,.

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>APS Funetional 5

1DateK ? g Date g i Description DER No..

Area.

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.{'kh YI/hik SIXNNdBBERS)ARELOCKEDUP.

c84-64 13 i O9/04/841

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09/04/84 4(, ;,M {-Q10/03/84~;rj ; DOWNCOMER FWIV. F

. 84-66.

14

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s p CLOSE UNDER DYNAMIC TEST--

i 09/10/84 ',' ? /11/15/84"'; s;f. Y ' '"

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^

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. 3 #~;.

%,'v

~ r ~v l

u s3

..+

s

..=

.t t

a x

u 4

Allocations'of inspection ~ hours to each functional areascare approximations based.upon NRC Fora,!766 d.ata..

i

,c. '

s j

o

.., s 4.

m -x,. _.. A ye o,.t

+ w e

Seve.rity Levels'are inacco,rdanc.eswith'NRC Enforcement Policy.

A.

3 _T, n.

(10 CFR,i2,1 Appendix C).

.y u.

s m

m e,

_e

.s-e,

. q fData reflects Reports 84*,12 through 85-26.,

z

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s

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_p

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~d

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j w

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p

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P7 24' TABLE H INSPECTION ACTIVITIES AND ENFORCEMENT

SUMMARY

(4/1/84 - 9/30/85)

PALO VERDE UNIT 3 Inspections Conducted

. ~

Inspection Percent Enforcement Items 4

Functional Area Hours

  • Effort Severity Items **

I 'II III IV V Dev

~1.

Plant Operations.

7

.36 2.-

Radiological-Controls,

$44 2.2 3.i' Maintenance ', i

.o

2

.1

.+..

=-

i.

j'e-0 4.1 Surveillance. %,y.

O' t

s..

m

. +

5.. Fire Prot'ection -

-j.

[10 *

.52 1

6.

Emergency' Preparedness 10 0-

' -7.

Security and Safeguards ~

0.

0 i

8.

Refbeling

-0 0

'9.

Quality Programs and.

s,.1010 52.2 1

. Administrative Controls-Affecting Safety

'10.

Licensing Activities ^

15-

.78

11. Training 8

.41.

12. ' Containment Safety Related 35 1.8 Structures and Main Eteel Supports
13. Piping Systems and Supports

-121 6.3.

4~

14.. Safety Related Components --

326

-16.8 3'

1 Mechanical

15. Auxiliary Systems 0

0~

16. Electrical ~ Equipment and Cables 168.
8. 7.

I 1

1 17.

Instrumentation 170 8.8-18., Preoperational Testing-17

.88i

19. Startup Testing 1933 100 7

1 4

- 3 0

0 Totals 5

..m.1 i

~

I p

.x a

+- t 25 3-

, t S '

.' Q$

t1

, i pe-9 4-s-

.pt Table H' Unit 3.,w

)

4 r >

-m.

c s

s

- 1 v,

y.

NE

.k N

a 1 --

  • IAllocationsiof inspection, hours'to each functional areas'are approximations

' based upon NRClorm :766 data.'

- s

.t,

.',-*w- % p,s kJ

_),P +

c-

'(10 CFR;2.' Appendix C).-

i.

s

> i, i. - - i

,.; 1 Data: reflects Reports 84-07 through 85-21.

x b

W.

s.

J Y

k s

g 6

e 5

f

]

4 9

4 i

1 -

'^ >

Z t

a V

4

(

4 1

4 L

1 h

y v1.

p Y-('

ij-

,q.,

.2

w.. % - -
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