IR 05000275/1981020

IE Insp Repts 50-275/81-20 & 50-323/81-14 on 810810-14,26 & 27.No Noncompliance Noted.Major Areas Inspected:Licensee Actions on Task Action Plan items,50.55(e) Items,Ie Bulletins & Circulars

ML16340C063
Person / Time
Site:	Diablo Canyon
Issue date:	10/02/1981
From:	Bishop T, Burdoin J, Hernandez G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16340C061	List: IR 05000275/1981020 ML16340C060
References
50-275-81-20, 50-323-81-14, NUDOCS 8111020503
Download: ML16340C063 (20)

Text

50-275/81-20 Report No.

50-323 1-14 U. S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION V

Docket Ho.

5 7-32 LiCenSee:

Pacif'c and Electric Com an License No.

cPPR-39 cPPR-69 Safeguards Group P.

x 7442 Facility Name:

Inspection at:

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punt Calif r ia r Cor rate Offi e Inspection conducted:

Au st 10-14 and 26-27 1981 Inspectors:

F. Burdoin, Reactor Inspector Date Signed G

ernandez

> Reacto spector laz 8/

Date S gned Approved by:

T.

W. Bishop, Chief, Projects Section

Reactor Construction Projects Branch Summary:

i~/ski ate S gne Ins ection durin eriod of Au ust 10-14 and 26-27 1981 (Re ort Nos.

50-275 81-20 and 50-323 81-14).

Areas Ins ected:

Routine unannounced inspection by regional based inspectors of construction and modification activities including:

licensee actions on task action plan items, 50.55(e)

items, IE Bulletins and Circulars, and investigation of an allegation of falsification of weld records of crane rail filler plate welds.

The inspection involved 49 inspector hours by two'NRC inspectors.

Results:

No items od noncompliance or deviations were identified.

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RV Form 219 (2)

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DETAILS l.

Individuals Contacted a.

Pacific Gas and Electric Com an (PG6E)

+*R. D. Etzler, Project Superintendent

• M. N. Norem, Resident Startup Engineer

+*D. A. Rockwell> Resident Electrical Engineer

• J. A. Ammon, Resident Mechanical Engineer

+F. M. Russell, Acting Resident Civil Engineer

+*J. J. Foat, Lead QC Engineer K. A. Klee, QC Engineer W. V. Gragg, QC Group Supervisor P.

Palomo, QC Inspector R. P. Gilbreath, Instrumentation and Control Supervisor J.

S. Diamonon, QC Supervisor W. B. Scott, Power Production Engineer

• C. L. Markum, Instrumentation Technician Sub-Foreman

• T. C. Aclan, Instrumentation Field Engineer

• R. C. Washington, Instrumentation Field Engineer Various other Engineering and QC personnel.

b.

H. P. Foie Com an (Foie A. E. Moses, Project Manager V. H. Tennyson, QA Manager J. L. Thompson, QA Engineering Group Supervisor B. J. Anderson, QA Engineer H.

Arnold, Mechanical Field Engineer W. F. Price, QC Supervisor c.

Pullman Power Products (Kello

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J. A. Brasher, QA Supervisor

• Denotes attendees at> August 14, 1981 exit meeting.

+Denotes attendees at August 27, 1981 exit meeting.

NRC Resident Inspectors, Mssrs. J.

D. Carlson (+) and M. M. Mendonca (*/+) attended, exit meetings, as noted.

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2.

Plant Tour Upon arrival at the site'n August 10, 1981 the inspector toured Unit.1 auxiliary building.

Specific areas examined included:

CVCS holdup tanks (elev. 56'); charging pumps and containment spray pumps (elev.

73') t component cooli'ng water pumps (elev. 70')

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RHR pumps (elev. 60')

p waste gas compressors and gas decay tanks (elev. 65')~

and safety injection pump (elev. 85').

Work in progress included:

pouring of two small foundations for boric acid distillate pumpsi reflective insulation of piping systems; electrical work in auxiliary building control console; and modification to seismic bracing for RHR pump no. 1-1.

A deficiency was noted in that three hold-Bown clamps were missing for a vertical run of quarter inch stainless steel tubing located behind motor control center 12N 6 M at elev. 73'n the auxiliary building.

A work order, was written to correct this deficiency.

No deviations or, items of noncompliance were identified.

3.

Licensee 'Action on 50.55(e)

Items a.

(Closed for Unit 1) hlodification to Reactor Protection S stem Cabinet. Doors

- The licensee submitted a final 50.55(e) report, dated August 27, 1981, regarding a modification made to doors on equipment cabinets to allow easy removal for maintenance.

~ The modification involved replacing the existing hinges with hooks that will allow the door, once they are opened,'o be removed.

After the modification was made it was determined that~it hadthe potential to affect the seismic qualification of the enclosed equipment.

Accordingly,

" the doors have been returned,to "their original,recondition.

/

In order to prevent aC recurrence; of,'his typ'e of tpr'oblml additional

'instructions have been'given'o plant personnel',co'ncerning requirements for proper authorization of work'i andthe.:need'ufo'r an Engineering Department review of 'any work<which" might'ffect.,seismic qualification of equipment.

These requirements are no'w.,clearly stated in the Nuclear Plant Administrative Procedure NPAP,C-1 "Design Changes".

This inspector examined the cabinet/Boors an'd"verified that they have been returned.to their original condition".",

.a.-*'his item is clos'ed.

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b.

(Closed for Units 1 and 2) Item (81-17 81-11

'eficienc in Containment S ra Pum Startin

':f The licensee submitted a final 50.55(e) report dated July 31, 1981

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regarding spray pump start timing.

A series of diesel loading tests were performed> to demonstrate that coincident starting of the containment spray pump with the starting of other ESF equipment can be accommodated by the emergency diesel generators without creating an unacceptable undexfrequency or undervoltage condition.

This test data was forwarded to NRR for review and evaluation.

The test results were found acceptable in NRR letter of September l4, 1981.

Therefore, this item is closed.

l Task Action Plan Items'for Unit 1 I The following task action plan items, described in NUREG-0737 were inspected to verify that, the installation is completed in accordance with acceptable criteria, that, applicable drawings were changed and that the components and system have been tested and placed in service or are ready to be placed in service.

a.

II.F.l, Accident. Moni'torin Instrumentation-(1).

Containment Pressure Monitor - This modification requires the installation of two (redundant) instrument systems from the pressure sensing bellows inside containment, through the penetrations to the wide range pressure transmitters (0-200 PSIG), to two continuous indicating instruments on the PAM panel in the control room.

(2) Containment hater Level Monitor - This modification requires the installation of a continuous indication in the control room of containment water level.

A narrow range instrument.

is required to cover a range from the bottom to the top of the containment sump.

A wide range instrument is required to cover the range from the bottom of the containment to the elevation equivalent to 600,000 gallon capacity.

The narrow range instrumentation for the containment sump was included in the initial plant construction.

The wide range instrumentation includes high and low redundant sensors and redundant level transmitters located in the reactor cavity and electrical transmission of the level signals to two continuous indicating instruments on the PAM panel in the control room.

(3) Containment Hydrogen Monitor - This modification requires a continuous indication of hydrogen concentration in the containment atmosphere on two instruments on the PAM panel in the control room.

These three instrument systems were inspected for:

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(1) Identification and location - proper type of instrument component with proper range, rating and proper location.

(2) Supports and protection -'physical protection from missiles and high energy line breaks.

(3) Independence - physical separation between redundant instrument components at sensors and actuating device in control panels.

(4) Testing calibration of indicating instruments in the control room, and pressure of level transmitters (sensors).

(S) QC inspection including generation of inspection records during inspection activities by QC personnel.

(6) Records Inspection - Yiodification package and drawings changed.

It was noted by the inspector and brought to the attention of licensee that the hydrogen sampling return lines to the containment terminated approximately 9 inches below the maximum flood level (96'-1"). The licensee has issued instructions to raise the sampling return line ends to an elevation above maximum flood level.

This system will be released for operation upon completion of change to sampling return line.

The containment pressure and level monitoring systems have been released for operation.

The installations of these three instrument systems are acceptable.

b.

II.D.3, Direct Indication of Pressurizer Relief and Safet -Valve Position This modification involved the installation of valve position indication systems.

For the three power-operated relief valves (PORVs), valve mounted limit-switches indicate valve position and operate an annunciator alarm in the control room.

The three code safety valves are equipped with acoustical monitors to indicate valve position and operate an annunciator alarm in the control room.

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(2) Supports and protection physical protection from missiles and high energy line breaks.

J (3) Independence - physical separation between redundant instrument components at sensors and actuating device in control panels.

(4) Testing calibration of indicating instruments in the control room, and pressure and level transmitters (sensors).

(5) QC Inspection - including generation of inspection records during inspection activities by QC personnel.

(6) Records Inspection - modification package and drawings changed.

II', The position in'dication.systems for the pressurizer PORVs and ,safety valves 'have been released for operation.

r~ a ' J I I, i The in'stallations of,these:position indication systems are acceptable.

c.;;,II.K.:1'. Sub-'tem '.17 ',Delete Pressurizer Level as an In ut to " "'";,Safet -In ection Actuation-l I Il,

Low,*'pressurizer. level coincident with low pressurizer pressure

"initiated safety injection in the original design of the reactor ,. engin'flexed safety, system for Diablo Canyon Unit l.

Under task ~ action plan 'item'II,K.l. Sub Item 17, this logic was modified to':remove the coincident logi'c-and initiate safety injection ~...-on a two-out-of-four low pres'surizer pressure only.

\\ Th'is system was inspected for: I . (1) Recoxds Inspection - modification package for changes to safety injection actuation circuitry on two-out-of-four low pressurizer pressure only.

(2) (3) Independence - physical separation between redundant instrument components at sensors and actuating device in control panels.

Testing - calibration of indicating instruments in the control room, and pressure and level transmitters (sensors).

(4) QC Inspection including generation of inspection records during inspection activities by. QC personnel.

II (5) Drawing changes.

The modifications to safety injection logic to delete the low pressurizer water level coincident with low pressurizer pressure actuation logic, and to convert the protection system to a two-out-of-four low pressurizer pressure actuation only, are completed.

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d.

Other Task Action Plan Items The inspector examined a sample of the quality records for the following task action plan items: (1) II.B.l, Reactor Coolant System Vents (2) II.E.1.2, Auxiliary Feedwater Initiation and Indication (3) II.F.2, Saturation Meter and Reactor Vessel Level Indication The inspection of these items was not completed and will be continued during a subsequent inspection (50-275/81-20-1).

No items of noncompliance or deviations were identified for those modifications or records which were examined.

Licensee Action on IE Bulletins and Circulars The following IE Bulletins and Circulars were reviewed by the inspector to determine the thoroughness of licensee actions to correct or avoid those known or potential deficiencies: a.

(Closed for Units 1 and 2) IE Bulletin 78-12: At ical Weld Material in Reactor Pressure Vessel Welds This bulletin described the use of weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels.

The inspector examined records that demonstrate the licensee satisfied the requirements of the bulletin in submitting to NRR documentation identifying the weld material used in the reactor pressure vessel weldments at Diablo Canyon.

The inspector also examined documentation that verified that.the submitted material had been received, reviewed and favorably ruled-on by NRC (IE HDQTS). Therefore, this issue is closed.

b.

(Closed for Unit 1) IE Bulletin-'79-01A': 'eficiencies in the Environmental ualifications of Asco Sol'enoid Valves.

The inspector examined documentation on-site for replacement of gaskets and acetal plastic parts, verification of solenoid coil materials, and retesting of solenoid valves.

The licensee II

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C ~ has demonstrated modifications to for Unit l.

(Closed for Unit u to the inspector's satisfaction that the required the Asco,solenoid valves have been accomplished d 'a 2) IE Bulletin,80-09: H dra-Motor Actuator Deficienci'es a s ITT General Controls (ITT-GO)"reported the use of springs, having incorrect material, installed in some Models AH-90 and NH-90 series hydra-motor,*actuators.

The licensee has determined that Unit '2 has four -Model AH-90/NH-90 actuators.

These units were purchased in mid-1979 and were delivered in March 1980.

Prior to delivery, ITT-GC assured the licensee that the actuators did not have any defective springs and that the sizing was adequate.

This item is closed.

d.

(Closed for Unit 1 and 2) IE Bulletin 81-03: Flow Blocka e of Coolin Water Safet stem Com onents b Corbicula SP.

(Asiatic Clam) and M 'lus SP.

(Mussel Zt has been determined that Y~tilus sp larvae are found in the sea water at Diablo Canyon site.

The licensee has been aware of these larvae from years of operation of several coastal power plants.

As a result, Diablo Canyon Power Plant has been designed to facilitate demusseling on a monthly basis using rejected condenser heat.

Warmed saltwater is circulated through the various heat exchangers for a sufficient period to ensure mussel mortality.

An evaluation of the effectiveness of the system was conducted on June 9, 1981, when the inlet water box of the component cooling water heat exchangers for Unit 1'as dewatered and inspected.

No evidence of ~ntilus SP was discovered during the inspection.

This item is closed.

e.

(Closed for Unit 2) IE Circular 80-09: Problems with Plant Internal Communications S stems The inspector reviewed records and determined the internal communications systems are powered from vital buses at the Diablo Station and are assured to be operable during the loss of offsite powers Also a survey was performed to determine if false signals could be introduced into electronic equipment from portable radio transmitter used inside the plant.

Communications have been published instructing employees in the use of radio transmitters in areas susceptible to electro-magnetic interference.

This issue is close ~ i ~ ~ .">>>~>>ro;I'f '3<f:t 'f>>if 2 iroB:)ti i>ij'.9;>,) <<0,'.)c)q')ll" '><f'> ot.) 32>i'x. ')rro;Ir)5 0<ii'f >')"f.LE<1,'.".0>>.M no.'><f >vf~'f "I'>VE<iv 5?Olr'>ro'i gpA )xf'2 o~ .'.<Io< P >;)<,+r. )r) L 'W.ln>J 'X<<3K "U)'2<1<7-'t:); "ci)a') -ri.

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D F r-4) rl 1f! (Closed for Units 1'and 2 'ZE.Circular 81'-05:,-.Self-Ali nin Rod End Bushin s for Pi e'Su orts~ 'his circularr~ident3.fies generic deficiencies;in,"pipe, support sway strutswhich involve 'the clamp"end of the'way'.strut becoming loose and possibly being'iseng'age'd'>from.'the bushing.'his could result in a larg'e>gap in the, support system not,'accounted for in the original analysis.' r> The inspector examined records,,that demonstrate that the licensee has reviewed the snubbers at Diablo. Canyon and determined the p concerns of the circular does not exist for Units 1 and 2.

g.

(Closed for Unit 2) IE Circular 81-06: Potential Deficienc Affectin Certain Foxboro 10 to".50'illiam ere Transmitters Pl Two deficiencies have been identified in certain E-10 series Foxboro transmitters which could adversely affect their.operation during accident conditions.

The deficiencies involve the improper use of teflon insulation and an unsealed capacitor in, the amplifier section of these transmitters.

The transmitters in question operate at an output signal level. of 10 to 50 milliamperes (mA). Similar model number units operating in the range of 4 to 20 mA are not a concern in these matters.

The licensee has reviewed his records and determined that the 10-50 mA transmitters are not used at Diablo Canyon.

" h.

(Closed for Units 1 and 2) Item (81-17 81-11) IE Circular 81-08: Foundation Materials Insufficient compaction of foundation and backfill materials during the construction of nuclear plants has resulted in excessive settlement of plant structures at a number of sites.

The inspector reported on this item in detail in Inspection Report 81-17/8l-ll.

During the August 10-14, 1981 inspection, the inspector examined additional documentation which demonstrates that the licensee satisfied the requirements of this circular.

by an individual who alleged that: (1) "Lugs" (filler plates) welded to the Unit 1 Fuel Handling Building east crane rail did not meet AWS Dl.l requirements and; (2) that records for these welds are falsified.

The alleger further stated that welding of the crane rail'ugs (filler plates) was performed by the Guy F. Atkinson Company as part of the Hosgri modifications in 197 h r r>ai.'IC>r:fn-')gyp: Spo'g3 wf)IA;n'i!) tE,'R.'~a" J '>9:".ArJ ~0~) E:6",Of )) \\ '~,BJXO;I"~sr+~ r'0 f. 'Xor>,IP'ILSIBStff, E>aa7 Eio+ ~ X>rr'Irt~> at)i@ Sfi'f>LQ!I')Lof;>'>~> 8:..CSrl >r'> BDftr-'. f'?ElL'~XGf."0 Cio BLff.'ai,"Qoad =Etta:f~ gx'";rB cfV 3o E)a."'~fp,'0"~48 svrn>Fai,froid; ataxia"'Grt '.'>Aj';!;.Isd Qf.'J I!fox",.'j?)gr,pflgBL>)'ps>,iecE vt;BiBBc~ >)ga iBQQ.t'. I >XQ'I ">'.>8 I So") >6, "Qtf "f8:ff'V)I O'XC>'.g tfSB.r'I flL Crr>> ~'>@..GI .'"i Sli JQSBOX i(, ' BLfsvJG)fsi Lfs.'IL*-">.'xQ I>: EJ Ai ')f)PA >0 r ". '""0 JG!U.')iffy'XSBSIOS"'4f';f6'B c't) I')99X )all "'tffiSC') 'Xo'.-)'>A~AX 9SP O'N f)>a.. ~. r,P'> ) . >~6 flo+Ar)g c>k fai6:E6 f.'X">Of'ESSCIB f):)5 5'.)'79i S.)'X .R r;!f~: I B <<iver xcg 0',.irido Joa Bf>0"> xarX'sox,n I)'(J >0:. Ix;)oac>0 vf)a /~i >0'.> Ifsitn';.Jock:30-I3 vs.fuox.f..) .'".X (R .-SL'll'J an% Ere,.of..)) "-xoJ '>'-.r".Irx"'>x>n'"FIF'6 Qc!'" '-) < O'Fc)'fz~K ace". r).") '>aidon=tWA h 6!)ixoB Qf -,'lirDxoo Ai "-)iiiJarJf)i.IQO,C l)vsi:c, Bf>.foaoioiic)E) OIA'oi86xmo, x,) 0;E.>>.00~~'4'i gI').".x.)v."~6 &Ifsoo . foi I;I BxeJCi> lBIIG..S inc ",XQH <<0: Ic>x.NPi !)cd f>vE;)vf< BQ fOa!)Foi39.,) 9'E'~' BIIQF82 I>. 100 ~ AOE)i006 pflf'xf1; 'IgppiLrrt"6 I>"f'f af. 'Ir> p "06dttig F)rfGABAu ffG E)a ffoLJG ffJBIIr ao IQQ'p IIQ ')Bfs tfoiI~~.)ftp ffi,'O:S'LU(Bfrt)~:2 ~'" ~ BX!)5:V.K~IIGX~ f>ao:(J 40 aoiWD:~B . (Crl) l>XI)c.< iILitfVP. 00 (>K "0 fc)VOX. IG.II>ia Suflt!SO aG JG 6"trXQ~>'0 OR 0 i

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~ ~ Licensee Minor Variation Report (MWR) No. C-1124, dated August 21, 1979 describes a discrepancy where filler plates (34" x 6" x 4") welded by the Guy F. At3cinson Company on the Fuel Handling Building crane rails were found to have a number of weld discrepancies including fitup, undercut, insufficient and undersized welds.

The filler plate welds were subsecgxently reinspected and repaired by the H. P. Foley Company in accordance with the MVR disposition and,'these actions confirmed by licensee Quality Contr'ol:personnel on February'12, 1980.

Ot, r OO, O On August 27, 1981 the NRC inspector, examined all'of the east crane rail filler plate welds-and reviewed the associ'ated documentation.

The inspector found that all'of the',welds and',"the) documentation conformed to the recpirements of 'the, licensee',s drawings, 4nstructions, and AWS Dl.l recgxirements.; tO O /I No items of noncompliance'or deviations, were ridentifi'ed.

Mana ement Interview The inspectors met with 'licensee representatives';,,denoted in section

on August 14 and'7, 1981,to discuss the'cope and 'findings of the site inspection t ~ ~ ~ P A ~~~.~JC.

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