ML042940216

Condition Report Summaries

ML042940216
Person / Time
Site:	Davis Besse
Issue date:	05/01/2002
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0187
Download: ML042940216 (16)

Text

05/01/2002 13:19 4198980691 DBNRCRI O PAGE 02 61 01/16/02 05/01/02l 04/16/02 No BOE Review 2

No No 03/02/02 lNIA WINA

'No N/A DBE ICR 1999-0855.

CCO 961057 1100

'This CR is written to review the remaining open Items (10, 11, & 12) for CR 1999-0855. These items were tracking the

'replacement of the carbol steel yoke on RC2 with a stainless steel yoke. The EWR (01-0042) has not been able to obtain PRC approval. ThIs CR will allow the proposed actions of CR 1999-0855 (10, 11, & 12) to be reviewed to see if

'the enhancement to RC2 they identify is worth the cost. This CR colses Items 10. 11. & 12 for CR 1999-0855.

iThis Is only an administrative issue concerning review of follow up actions for CR 1999.0855.

1F =02/24/02 04/10/02 04/11/02 o

PE Review C02 N

iNo l

j

.1 04/10/02 lSU05701

=

No 57 NONE IEAKING INCORE FLOWIR POTS OHW 10575057 0575 lDuring the planned Incorf tank walkdown. tour incore flower pot' enclosure assemblies were identified as to have leaked Iduring last cycle. Enclosure numbers fS, #1 and #24 had noticeable boron on them. Enclosure # 25 had only a jslight amount. Plans are already in place this outage for FTI to replace the torque ring set screws and Install a new limproved design enclosufe seal (per EWR 01-0266) on these four enclosures per WOs 01-2727-000 and 00-3204.000 as iper the Incore maintenance schedule this outage. This leakage was communicated to the RCS System Engineer.

!Photos are available upof request.

kSee actions already in place described in Description of Condition and Probable Cause above.)

re1_03/02/02 1 04/24/02 l 04/24/02 l INO PE Review JT26 Q03 i.

I 1 04/16/02 lRepair JRCS cold legs I No 064-02 NONE NONE IRC COLD LEG THERMOYTELLS INSPECTION DURING 13 RFO HOW _0575 057 0575 2500 During the inspection of TWRC4A3 (RC loop 2 CLG Thermowell) small deposits of boric acid were noted arround the thermowell located on RGS piping. Subsequent inspection of 7WRC4B3, 484, and TWRC4A4 resulted In discovery of similar powder like deposits located around the thermowells on the RCS piping.

-Based on discussions with the Initiator, he observed boric acid around three of the four coldleg thermowells. He needs to confirm which three of the four thermowells Identified had boric acid deposits.

!it has not yet been deterrhined whether these are active leaks. The requirements of NG-EN-00324, Boric Acid Corrosion Controf will be followed.

SYME will perform walkdown of RC Loop 1&2 Hot Leg Thermrowells.

-IA 1I3/07/02 04/21/02 0

/0 N

o PE

]Review D00 No lNo Bl:

2 04/21/02 IRework TCS piping

-No 1064-02 INONE LOOP 1 RCS HOT LEG TPERMOWELL TERC3B3/4 LEAKAGEL HDW 10575 057 10575

-Boric acid was found out;ide TERC3B3/4 thermowell. Small amount of white boric acid was found on the piping.

7races of leakage down behind insulation indicale that the leak may be active during power operations.

TERC3B4 thermowell may need to be reworked or repnlaced Location needs to be cleaned. MDT 02-0794 has been.

initiated. SCR 13R-0529. has been Initialed. The System Engineer Is proceeding to address the deficiency In accordance with the Bori; Acid Corrosion Control Procedure NG-EN-00324.

CA_03/09/02 04/23/02 04/23/02 No E

Review LU No No l

74 No 064-01 NONE

'MISSING LEAKoTr PORI PLUG rOR RC74 HDW P575 057 0575

!RC74, CTMT DRAIN HEADER ISOLATION VALVE, Is missing the leakoff port plug. Without this plug, boric acid is leaking

!oul of this area.

Work Request 02-000763 generated.

1 C

A 03/12/02 l 04/26/02 l 04/25/02.

INo IPE lReview 04 No No

• l 1

04/26/02 l lDH21 No p49.02 INONE

!DH 21 BODY TO BONNEX LEAKAGE JHDW p75 057 0575 This CR identifies a corrective measures required by ASME Code. A VT-2 pressure test examination of the Decay Heat Return Line indicated body to bonnet leakagc at DH21.

H18

05/01/2002 13:19 4198980691 DBNRCRIO PAGE 03 iThe 1995, Addenda 96 SME Code Paragraph IWA-5241. requires the owner to examine the exposed surfaces for Evidence of leakage. Par graph IWA 5250 states If leakage Is Identified at a bolted connection, then one bolt shall be removed and a VT-3 vlsu 1 examination performed. Leakage was identified as dry boric acid located in two distinct places on the gasket cirumference, covering studs and nuts.

This condition report willjtrack and resolve this Issue. Work request 02-820 is written to remove and examine one bolt.

.The selected bolt.(nut anp stud) Is located at the 12:30 position with due north as the reference at 12:00 o'clock position. Until the corrective measures are completed this item Is a Mode 5 to 4 restraint.

Only evidence of leakage iwas observed. The leakage was not wet and the system was pressurized to return pressure of iapproximalely 20 psig. 411 bolting appears stainless and is In good condition. The system is capable of perform safety Ifunction.

IN/A 1CA 03/18/02 l 05/02/02 lNo iDPE Open I

ND N5/02/02 lUse-As-111RC 02.01 REACTOR HEAD INSULATI0N DEGRADATION

.1HDW 0575 057 0575 During removal of the reactor head insulation It was noted that some of the insulation appears degraded. Some boric

.acid was noted Inside th4 outer stainless steel box. Additionally. the Intemal layers of thin material appear discolered and brittle.

None. Insulation is beino removed as part of the repair effort. This CR should be assigned to Design Engineering for an assessment of the continled effectiveness of this Insulation.

CA 103/19/02 05/03/02 l 03/28/02 l lNo lDEE IReview Iiw FOO No No I_ I

-IB 05/03/02 IRework I/A

_ Y 059-01 MAIN MAIN UPPER CONTAINMENT VESSEL COATINGS DEGRADATION M0 0575 057 jo0 0550

'During performance of the scheduled ASME Xl, Categoty IWE. General Visual examinations of the Containment Interior surfaces. gross flaking, blistering, and peeling of the top-coat paint was observed In the elevations above 725'. The

!degradation Is similar to that reported In RFO12. See CR 2000D1051 for details. As was the case In RFO12, all the lpaint degradation Is restricted to the top coat and no signs of rust or degradation of primer/undercoating were observed. In comparisorto RFO12. the examiner performing the exams (same person that performed them In RF012) jstates that the degradatl n is slightly more extensive with more blisters and peeling at the lower elevations than there pwas before. Several bistrs that could be reached from the Polar Crane were popped and it was found that theywere Ivery brittle and crumblel into small pieces.

INo Immediate actions ta en.

A 103/20/02 05/04/02 0

Open

.Yes

{No I

3 05/04/02 JRework fTrlRC as 62-01 JDEBRIS (RUST) ON REACTOR HEAD UNDER INSULATION IS FME DURING OPERAT HOW 575 057 0575

.This is a condition reportthat resulted from Audit AR-02-OUTAG-01.

Photographs taken of thel reactor head at nozzle #3, just after a segment of the reactor head insulation was cut and

!removed. revealed a large amount of rust (scaled rust) In the vicinity of nozzle #3. The reflective insulation just above the reactor head Is fabricated of 100% austenltic stainless steel except for the support steel that Is located beneath the Insulation. The insulatidn's support steel is constructed of carbon steel ASTM A-36 grade and is susceptible to boric acd corrosion.

Drawing M-197.4-2 shows the insulation support steel details and indicates that the support steel was painted with one coat of $herwin-Williams paint # C905SC18 prior to its installation. The only carbon steel

components between theireactor vessel flange and the insulation. Is the insulation support steel, the reactor head itself

and the Jower service structure.

Photographs taken after nozzle 3 was removed, but prior to Insulation cutting/removal, revealed that minimal scaled rust existed on the reactor head.

.The amount eaid size of the rust (scale) noted in the photographs brings up a concern with FME (rust) that potentially still remains on portions of the Insulation support steel and lower support structure (or any other susceptible carbon steel components) during normal operation. During a postulated design basis accident. this foreign material debris has the potential to be washed down to lower elevations and cause potential clogging concerns, e.g. Containment Emergency Sump.

it is recommended that inspections of the insulation support steel and the crevasse where the lower support structure connects to the reactor head (welded area) be inspected for degradation. This area has been subjected to wet boric racid during washdown operations. The rust should be quantified and considered for wash down to lower elevations for potential clogging concerns post LOCA.

Also. inspection results of corroded areas/components needs to be evaluated

'for degraded structural capability i.e. seismic and LOCA loads capability.

Photographs attached to-this CR include:

05/01/2002 13:19 4198980691 DBNRCRIO PAGE 04 ElBefore Insulation remoiat

'Just after Insulation rei loval - (Large amount of slag, scaled rust throughout Image and portion of partially cut/rusted

angle Iron In upper right hand corner of Image)

. Informational sketch INo Immediate actions. F ecommend this be added as a mode 5 restraint to ensure the service structure and it's Iconnection have suffice structural capacity.

- 03/21/02 05/05/02

[No

,PE lOpen No lNo 1

=

I 1DF05/05/02 ]Rework In/a

/A No n/a WATER ON WALL AND F.OOR IN EAST/WEST TUNNEL

_HDW 1575 057 0575

During Boric Acid Corros on Control valve inspections water was found on the floor and wail of the East/West Tunnel.

The south wall of the tun el has water on it from top to bottom for about a 10 foot span. Boron can be seen on the wall

.and on the floor. The ref cling canal drain pump Is located In this area. The drain pump was Inspected to determine If iany water was originatIn from the pump. No water trails were found to come from the pump.

!System engineer for Spe t fuel pool was notified. No further actions have been taken.

03/22/02 05/06/02 No P E Open YeI 3

05/06/02 !

1E37.1 O3 Yes 0.05 1CORROSION PRESENT N CONTAINMENT AIR COOLER 1 & 2 COIL FRAMES =HDW 575 057 0575 fSeveral small holes werelidentified in both CAC 1 and CAC 2 cooling coil frames. The location was at the interface of the

!coil fins, the coil frame, And the drain shelf. The holes noted were approximately 1/2 to 2 square Inch.. Other similar Jocations on all three CA~s had boric acid buildup and the Interface joint was not visible.

Additionally the bottom horizontal and vertical supports were also beginning to show signs of corrosion.

It is recommended that IlI three CAC and coils be cleaned to have boric acid deposits removed and a detailed Investigation of the corroded areas performed and the structural Integrity of the CACs evaluated.

'Recommend processing As a CAQ because safety related equipment.

1 Oa CA03/25/02 l 05/09/02 No PE Open Yes No _

i 3

05/09/02 1 IN/A 4

Yes 060-05 1

BORIC ACID BUILDUP A4D CORROSION IN CONTAINMENT HOW 0575 05710575

.Boric acid buildup Is occirring on components throughout containment Most of the components affected are either

• below or in the vicinity of service water piping. In several locations (CAC plenum service water valve SW 392, and T 3952). corrosion is occulring.

Structural steel and corduits above PTRC2A5 and FTRCIA2

. Deposits and potential Corrosion on JT3951 and JT3952. Including the associated cable trays and JT flexible conduits and penetrations.

I

.SW 392 yoke

. Cable trays BLBE02 and BCBD02 located on the 585 elevation of containment where they penetrate the shield wall

. CAC plenum Boric acid buildup was aiso noted on CF1A packing area and CF 9 packing. A trail of boric acid was identified at the top of CFT 1..

The cause otthe CFT 1-1 buildup is not known. Plant engineering was notified of the CFT 1-l boric acid trail issue and notified thie potential hole in the CAC plenum.

The containment inspection also identified that the containment ventilation ductwork registers (565 elevation) need to

be cleaned. There is evidince of paint chips, etc in the registers. The potential for boric acid buIldup In the ductwortk talso needs to be evaluated.

ilt is recommended that an extent of condition be perform to ensure all areas susceptible to boric acid buildup due to

'condensation be performed. Affected components should be cleaned, inspected and repaired as required.

oPictures are located on the S:\\DBcommon\\Outage Pics\\CTMT boric acid buildup. Several pictures will also be scanned iinto this CR.

IRecommend processing Is a CAQ

• Basic Cause; mode 4 restraint.

1 CA 103/28/021 05/12/02 l INo PE lOpen I

No !No l I 1 05/12/02 1

MVDHII No 049-02 CATSTROPHIC FAILUREiOF LIMIT SWITCH COMPARTMENT GASKET IHDW 10575 057 0575 DURING PERFOMANCE OF 02-001894-000 IT WAS DISCOVERED THAT THE LIMIT SWITCH COMPARTMENT HAD MOISTURE INTRUSION. IT APPEARS THAT THE GASKET FOR THE COVER HAD FAILED ALLOWING THIS MOISTURE IN.

'THERE IS VISIBLE SIGNS OF RUST ON THE TERMILNAL STRIP AND ON THE INSIDE OF THE COMPARTMENT WALLS.

ITHE LIMIT SWITCHES A PEAR TO BE UNAFFECTED BY THE WATER. THERE IS WHAT APPEARS TO BE BORIC ACID ON ITHE TORQUE SWITCH. BUT NO SIGNS OF RUST. THE MOTOR WAS REMOVED UNDER THIS WORK ORDER BECAUSE

05/01/2002 13:19 4198980691 DBhlRCRI O PAGE 05

.OF A BAD MEGGER REAQINGS, TO BE SENT OFF AND REWOUND.

.The terminal strip will be evaluated for replacement and the gasket for the Limit switch cover will be replaced under WO 02I-R9.4-000.

MM=C 104/01/02 105/16/02 NoP pe 1

No Io BIC 1AcI DEPOSIB5E16W02 E

VSlRC F

R Yes H

62-01 0

-EVIDE NCE or BORIC AOID DEPOSITS BELOW REACTOR VESSEL FLANGE FROM 12 HDW 10575 057 10575_

The attached photographs from 12RFO document the presence of boric acid residue beneath the flange level of the

.Reactor Vessel. This Includes deposit trails on the vertical Insulation and deposits on the seam of at least one Insulation section underneath the Reactor Vessel. A third picture shows apparent boric acid tracks on the surface of the wall underneath the hot leg.

The purpose of this CR ii to ensure proper Investigation and resolution of boric acid deposits underneath the Reactor Vessel Flange.

1.

C040/2 05/18/02 I iNo PE Open No I

No 2 r-2n, 105/18102 lS UBO67-02 _:

INC 067-02

-BRCAILEKGINCMFULTASETUEAE HW 550707 iDuring the CTMT Mode 5 walkdown, evidence of boric acid streaming was found in the tunnel leading to the fuel transfer Itube area from Core Flood Tank Room 1. The boric acid leakage appeared to be coming out of the concrete wall/celling

'interface just before Fuel Transfer Tube #1. The leakage was dry, white In color and appeared fFeisThe leakage was In Ithe form of a stream that Is approximately 5-6 ft wide. Approximately 5 gallons of boric acid crystal Is present In clumps ion the wall and floor. The source of the leakage could not be determined because the area became a Locked High Rad

,area shortly after discovery.

Recommend a detailed Ihspection Is performed to discover the leakage source per the Boric Acid Corrosion Control procedure. NG-EN-00324. Initial inspection checklist Is attached.

!RP and Shift Engineer Informed of leakage at time of discovery.

_No MDT prepared because source of leakage Is indeterminate.

iRP and Shift Engineer informed of leakage found. A detailed inspection will be performed by the System Engineer to

[iscover source of leakap and followup action.

ICA 04/08/02 105/2,3/02 No BE pe i-No I

I I lL 1 05/23/02 1 1

T1RC 6

-Yes 64.02

• THE INCORE INSTRUMENT NOZZLES IN B&W PLANTS.

ERO 2779 260 2775 The following Information was received from FRA-ANP today (E.mail from G.K. Wandling to M.Shepherd):

'The incore instrument nozzles in B&W designed plants are Installed In the bottom of the reactor pressure vessel.

'These nozzles consist of the original Alloy 600 nozzle material attached by a partial penetration weld that was isubsequently stress relieved. As a result of failures that occurred at Oconee I during hot functional testing (attributed

,to FlV), the nozzles In all B&W plants were modified to Increase their resistance to FIV damage. This modification iconslsted of a much larger Alloy 600 nozzle at the vessel ID surface attached with a full penetration Alloy 182 weld. The lincore nozzles operate atTcold and. therefore, should be less susceptible to PWSCC than the CRDM nozzles and other

!hot leg Alloy 600 nozzles. However, failure of incore nozzles represents a high consequence situation In that failure would result In an unisolable leak.

The incore nozzles have been ranked-low in susceptibility to PWSCC. However. FRA.ANP document 51-5003018-00 (prepared for the B&WOG) ranked the incore nozzles as #1 in failure consequence. (Note: The CRDM nozzles ranked #2 in the consequence ranking.) A safety assessment for the Incore nozzles is documented in FRA-ANP document BAW-

2337P (also prepared for the B&WOG). The fact that a positive result was achieved by this safety assessment is based ion the determination that a "...flaw of this extent would produce leakage from the bottom of the RV head in the form of Ifashing steam and/or boric acid crystals depending upon the teak rate.. Boric acid crystals will then accumulate Ibeneath the RV over a period of time....it is very unlikely that this type of accumulation would continue undetected with Iregular walkdown Inspections of the lower RV head area (emphasis added)."

lAloy 82/182 weld metal appears to be more susceptible to PWSCC based on recent industry experience. The weld metal was neither evatuated nor ranked in the B&WOG evaluations.

Assurance that effective idisual Inspections of the lower reactor vessel head area (OD) are occurring is needed.

Development of new NDE techniques and repair processes would also be a prudent step. Some discussions on this Issue have occurred In various B&WOG meetings and more are planned. In light of the CRDM nozzle and RV head findings over the past 114 years. development of Inspection and repair capabilities should be substantially accelerated.'

Further evaluation Is required.

05/01/2002 13:19 4198980691 DBNRCRI O PAGE 06 No material deficiencies Jre known at this time. The incore nozzles should be Inspected and Included In the Boric Acid Control Program (or sim (lar)

}

CA 04/10/02 05/2/02 No PE Open

• No No 1

0l/2502 P36*1, P36.2 e

4.03 RCP 1-AND RCP 1-2 LtAKAGE AT GASKET DRAIN LINES HOW 0575 057 0575 During the performance of DB-PF-03065, Pressure and Augmented Leakage Test. inner casing gasket leakage was observed from RCP I an RCP 2 via the respective casing gasket collection system. ThIs Is a drain line between the iinner and outer casing g skets. The intent of the pressure test is to verify an operable leakage collection system. This

'was acceptable, howeverfleakage was observed.

Inner gasket leakage on ACp 1.1 was.01 gpm and on RCP 1.2 was.03 gpm. This condition does not reflect actual leakage because a visual!examination of all RCP casing bolting indicated no external leakage or boric acid residue.

Note: This test occurred at a RCS pressure of 893 psig during RCS shutdown. The system was In a temperature

,transient. See Work Order 01-01308, performed on 2/25/02, for documentation of visual examination. Similar leakage via the leakage collection pathway was observed in 12RFO.

This correction report Is being generated to ensure adequate review of this leakage. to address operational readiness issues, and to justify/plah RCP inner and outer gasket replacement. To date, there are no operability Issues associated with this leakage.

_N/A IA 04/12/02 05/27/02 o

1OBE Open NO No 2/02 2

C -

Yes 004 gOXIDATION AND MISSI PAINT AT PRESSURIZER LEVEL TAP HDW 575 057 0575 jDuring walkdown for IP-4-028, Alloy 600 Inspection Plan, It was noted that there was slight oxidation, missing paint/coating and faint ttace of some previous leakage at the nozzle for the lower tap of the Pressurizer Level

!Transmitter. LT-RC14-2. The root valve associated with this tap and adjacent to this tap is RC14A.

There are no signs of active leakage. There are no signs of any boric acid.

The oxidation is on the swrface of pressurizer In a narrow ring (perhaps 1/4) around the circumference of the nozzle

,penetration. (see attached picture) The reference to a fain trace of previous leakage refers to staining observed on the Isurface of the pressurize? paint below the nozzle. This cannot be readily seen in the attached picture.

'This inspection was done(as part of the extent of condition for CR 200240891.

1 104/18/02 06/02/02 No BE pen I

No INo 1

06/02/02 1 rT9-2 I

_Noo P5101 CORE rLOOD TANK 1 ALLOY 600 EXTENT OF CONDITION DISCREPENCIES HDW 0575 057 575 During walkdown of the Core Flooding Tank 1-1 for Alloy 600 Extent of Condition per IP-M-028 several Issues were noted that required further revitw:

CFTI.01. (Outlet Nozzle) Nozzle had numerous Indications of rust stains. Appears to be from elsewhere. No signs of leakage from the nozzle Itself.

-CFT1-02 (CF3B1) Nozzlelhad small rust stain on top of nozzle. No sign of nozzle leaking.

CFTI-04 (Sample Connection) Rust stains on the nozzle and a rusted area on the tank at the 10 o'clock position. No

signs of the nozzle leakin$.

iCFTI.05 (CF4BI) Minor White stains under the nozzle. Appears to be from elsewhere. No evidence of nozzle leaking.

,CFT1-06 (CF482) Signs of paint or possibly old boron In a longitudinal line down the nozzle @ 1 o'clock position. It idoes not rub ot or brush off. Also minor white stains under nozzle appears to be from elsewhere.

iCFTI-07 (CF103) Signs o! minor tank oxidation approximately 4 from nozzle.

Eue to white stains belngiseen on several of the components, this CR needs to follow the requirements of NG-EN-00324.

'Boric Acid Corrosion Procedure.

Contacted Jon Hook.

Identified per Reactor Held Degradation extent of condition program.

3 CA04/8/0206/2/0!

No08EK~pn

_______I I

CtiA 104/18/02 06/02/02 No

`DBE 10pen No NO ;

1 06/02/02 T9.2*

Yes 051-01 ICORE FLOOD TANK 2 ALLOY 600 EXTENT OF CONDITION DISCREPENCIES HDW 0575 057 0575 During walkdown of the Core Flooding Tank 1.2 for Alloy 600 Extent of Condition per IP-M-028 several issues were noted that required further review:

tCFT2-01 (Outlet Nozzle) Nozzle had streaks of white which appeared to be from elsewhere. It also had rust spots and

'streaks which appear to be minor but are numerous.

.CFT2.03 (CF3A2) Nozzle had streaks and spots of white. Appears to be from elsewhere.

CFT2-05 (CF4AI) Nozzle had minor white stains under nozzle. Appears to be from elsewhere. Adjacent area of tank has

• a 8-high x 4' wide area of surface rust.

CFT2-06 (CF4A2) Nozzle had streaks and spots of white. Appears to be from elsewhere. Band of horizontal rust marks under the nozzle and run several feet in each direction around tank. Appear to be possibly from a band or strap on the

05/01/2002 13:19 4198980691 DBNRCRIO PAGE 07 tank in the past that scratched the coating.

CFT2.r07 (CF 00) Nozzle had minor streaks and spots of white. Appears to be from elsewhere.

Due to the white material being found, this CR needs to follow the requirements of NG-EN-00304. Boric Acid Corrosion Procedure.

Contacted Jon Hook.

dcentified per Reactor Hehd Degradation extent of condition program.

1 iCA 104/19/02 06/03/02 No PE Open No INO I

1 06/03/02 IRCS 2 Hot Leg 4 Yes 064-02

INSPECTION PLAN IP-M028 ALLOY 600 FINDING ON INSULATION

=

HDW P0575 057 0575 The following conditions there identified during an IP-M-028 Alloy 600 Inspection for three nozzle located on the

Number 2 Hot Leg.

HL2.5 (Pressure Tap PTAI near valve RC2AI) had surface boric acid crystals located on the upper horizontal surface of the hot leg Insulation. This appears to be from the thermal well, which Is directly above this nozzle. InsulaUon has minor surface discoloration and the outer line Insulation (called a 'coffee can") has poor fit and form.

HL-2.6 (Thermal Well Tap:TWRC3A) and HL2-7 (Pressure Tap PTA2 near valve RC2A2) Insulation had minor surface "discoloration. There was huestion If a coffee can cover was installed at one time and Is missing.

This CR is written In accldance with the inspection plan, which directs writing a CR for any indications of leakage or corrosion. The CR shall!will comply with NG-EN-00324 Boric Acid Corrosion Procedure.

• Additional inspections will be required to determine source and corrective actions. These Inspections are detailed In the

'Extent of Condition plan.: No active leakage was Identified.

Identified per Reactor Hepd Degradation extent of condition program.

1 CbA 104/23/021 06/07/02 I No DBE Open I

No I

I l 1 06/07/02 l IOTSG 2 Hot Legl

_No 064-02 MISSING INSULATION ON OTSG 2 HOT LEG VENT AND FLOW TRANSMITTERS NO IHDW 0575 195 10575

-The following misssing Insulation conditions where Identified during an IP.M.028 Alloy 600 Inspecton for three nozzle

'located on the Number 2'Hot Leg. It appears that insulation was Installed, however it is currently missing.

iHL2-10. Insulation Hot Leg 2 Upper Vent Nozzle near RC44 (OTSG 2) appears to be missing the north Insulation box.

'This located on the upper part of the hot leg.

!HL2.3 and HL2-4, Insulatlion for Hot Leg 2 Flow transmitter at azimuth 337.5 degrees and 202.5 regrees are missing Insulation cover plates (pde pans). Located near RC1AA and RCIAB Isolation valves.

This CR Is written against configuration control of insulation not being installed or even If required. Request a determination If this lnsuatlon Is required and If so then have It replaced.

Identified per Reactor Heed Degradation Extent of Condition program.

Note, the only Issue Identified under this CR is missing Insulation. Since the missing insulation pieces are shown as installed on an 'Approved status vendor drawing M-197-00040, It Is recommended that this CR go to Maintenance to

-find or procure the missi4lg insulation and re-install.

7 W M ibA104/23/02 106/07/02

! No IDBE 1pen I

1NO I

I 06/07/021 RC3A1 4

Yes 4-02 INSPECTION PLAN IP-M-028 FINDINGS.

DW 0575 057 0575 iThe following conditions were Identified during an IP-M-028 Alloy 600 Inspection for RCS Hot Let Thermonwells TWRC3A1 and TWRC3A3.

'Inspection zone HL2-8 (VWRC3A1) had evidence of possible leakage 'trails' below and on the east side of the Ithermowell. In comparison to the general condition of the surrounding area, the mounting boss and adjacent area had

'been cleaned, but uncertain when this cleaning occurred. Discoloration of the RTD nut and RTD, and at the 10:00

'position around the thermowell was also noted. Reddish/brown oxidation was present on the underside of the RTD iconduit coupling weld and a white deposit was present on the conduit. Reddish/brown oxidation was present on the hot

.leg both above and below TWRC3AI, with heavier oxidation noted to the west and trailing down the hot leg. Unable to determine with certainty the cause of the oxidation.

Inspection zone HL2-9 (TWRC3A3) had evidence of possible leakage in the form of minor reddish/brown oxidation on the hot leg piping below TWRC3A3. The mounting boss Itself was very clean, but uncertain when cleaning occurred. Reddish/Brown oxidationywas also present In the seam of the insulation piece below TWRC3A3 and above TWRC3A.

Identified per Reactor Head Degradation Extent of Condition program.

No active leakage Identified.

05/01/2002 13:19 4198980691 DBNRI 0GO PAGE i38 ijhis Condition Report most comply with the requirements of NG-EN-00324, Boric Acid Corrosion Control Program.

0I4/23/02 06/07/02 1No PE lOpen I

N IYINo

.1 I 1 06/071021 iN/A V Yes 1064-02 INSPECTION PLAN IP-iY 028 ALLOY 600 FINDINGS HDW 0575 057 0575

'The following conditions rvere Identified during an IP-M 028 Alloy 600 inspection of RCP 2.1 Outlet UCL Temp. Conn.

TWRC4A] and TWRC4A3I The target areas (28' ID ARCS Pipe) for UCL Temp. Connections TWRC4A1 has slight oxidation (rust) on the pipe and nozzle surfaces. Likewisi, TWRC4A3 also has oxidation on the RCS pipe surrounding the nozzle however, to a lesser degree.

'This CR is written in accordance with the inspection plan, which directs writing a CR for any IndicatIons of leakage or icorrosion. The CR shall Comply with NG-EN-00324 Boric Acid Corrosion Procedure.

Identified per Reactor Hebd Degradation Extent of Condition program.

iNo active or inactive lealige was Identified. Additional evaluation of effected areas per the Extent of Condition Plan will

!be needed. No Immediate actions required.

M1 ICA 104/24/021 06/08/02 E

.n i

No es I1 06/08/02 IN/A p i es 164-02 INSPECTION PLAN IP. 028 ALLOY 600 FINDINGS lHDW 0575 057 0575 White residue was found tin the HPI nozzle (HP59) and RCS piping surrounding the nozzle. Residue Is confined to this area only (approx. 8 arojnd nozzle) with no evidence of of leakage on floor or surrounding areas. It is my opinion that this Is residue Is not bordn but from another source, possibably from ultrasonic couplant.

Also, the paint on the nozzle and RCS piping has been removed and slight oxidation on the pipe surface has occurred.

This CR is written in accordance with the inspection plan which directs writing a CR for any indications of leakage or corrosion. The CR shall Comply with NG-EN-00324, Boric Acid Corrosion Procedure.

cIdentified per Reactor Heed Degradation Extent of Condition program. Additional evaluation of effected areas per the

.,xtent of Condition plan ?wll be needed. No immediate actions required. This Inspection was performed per P.M.028.

b m

A l

04/26/021 06/10/02 l l INO

!PE Open 1

No I

I

{

I If 06/10/02 l

iT2-RC 14 as 64 HSPECTION PLAN IP-MK028 ALLOY 600 EXTENT OF CONDITION. PZR.14 9HDW 9

057 9999 f0uring Inspection of the mozzle of RC13A a white streak/stain was noted on the nozzle. It appeared that something may shave dripped on It In the past The streak does not extend and is not seen on other portions of the nozzle. Can not

confirm that It Is boric adid.

This Condition Report is generated based on Serial Number PZR-14 performed under Inspection Plan IP-M.028. The requirements of NG-EN-00324 need to be considered In the evaluation of this CR.

No immediate actions reouired.

IA 04/24/02 06/08/02

No iPE pen No Yes I

I 1 06/08/02 OTSG 2 Hot Leg!4 Yes 64-02

!DIRTY INSULATION ON OTSG 2 HOT LEG. IDENTIFIED DURING THE IP-M-028 PLAIHDW 0575 057 0575 The following insulation had reddish material and evidence of corrosion. This was Identified during an IP-M02B Alloy t600 inspection for two nOzzle located on the SG 2 Hot Leg.

HL2. 10. Insulation Hot Leg 2 Upper Vent Nozzle near RC44 (OTSG 2) has reddish particulate material located at base of hot leg insulation. This reddish material was found over most horizontal surfaces on the hot leg. Insulation cap appears to have surface corrosion material near inner buckle. Unable to determine source or reason. Insulation material Is stainless steel and does hot appear to be deteriorating. Form/lit and discoloration Is present. The location is on the upper part of the numbed 2 hot leg.

HL2.3 Insulation tor Hot Leg 2 Flow transmitter at azimuth 202.5 degrees. elevation 626' 7 has a reddish material located on the inner surface of the insulation penetration. This appears to be coming from the hot leg surface. The thermal well located directly above this penetration was leaking. Also there is the same reddish particulate material as found on top of the hot leg insulation on the horizontal flow transmitter isolation valve.

This CR is written in accordance with the Inspection plan, which directs writing a CR for any indications of leakage or corrosion. The CR complies with NG-EN-00324 Boric Acid Corrosion Procedure.

ldentified per Reactor Head Degradation Extent of Condition program. The requirements of NG-EN-00324 need to be addressed in the evaluation of this CR.

05/01/2002 13:19 4198980691 DBNRGRIO PAGE 09 1

-D ICA 04/24/02 06/08/02 lo E

pen No Etes l

I l

1 06/08/02, W

RC2; p es 064.02 INSPECTION PLAN IP+/-

28 FINDINGS lHDW 575 057 0575 iThe following conditions here Identified while performing inspections for IP-M-028 Alloy 600 Inspection program for

,package serial numbers insulation Inspections for HLI-4, HLI-5, HL1-6 and weld inspections for H-LI7 and HL1-8.

ilnspection zone HLI-4 I sulation (HL Temp Connection TWRC3B). The insulation for HL1-4 has boron or white

.powder noted on the hor zontal surface of the right insulation panel as viewed looking at the thermal well. In a slightly recessed area to the right of the white powder locations a reddish brown discoloration Is evident.

Inspection Zone HLI-5 Insulation (HL Pressure Tap Nozzle RC2B2 PTB2). The Insulation pertaining to HLI.5 has standard hot leg mirror vilth a small can at the pressure tap location and a box around the first valve. Reddish brown discoloration was present on the north side of the can and on the horizontal surface of the hot leg Insulation. White powder / discoloration is present on the horizontal surface of both hot leg mirror panels and the West side of the box in a dented area or Indentation.

r I

.1.

I.

Inspection zone HL1.6 lgsulatlon (HL Pressure Tap Nozzle RC2B1 PTB1). The insulation for HL1.6 has boron or white

.powder noted on both top horizontal surfaces for both insulation panels. Boron streaking is heavy on the back half-outer surface of the left panel is viewed looking at HL1-6.

Brownish red discoloration is present on the right side panel starting about mid panel approximately 1 Inch below the top and extending nearly 12 inches. Biriln-was noted In the vertical seam and resting around the bottom of the pipe penetration within the hot leg mirror.

Inspection zone HL1.7 Weld (HL RTE Mounting Boss Replaced TWRC3B1). Inspection identified a white powder type material which looks like.~boron on the threaded connection at approximately the 5:00 area. Streaks of white were found below the threaded connection on the nozzle and past the weld. All match marks contained white powder (possibly developer) In the stamped area. A weld strike mark was Identified at about the 2:30 position. Minor rust was located on painted portion of pipinglwhere scratches has removed the paint and near the band that is around the piping.

Inspection zone HL1-8 Weld (HL RTE Mounting Boss Replaced TWRC383). Inspection of weld area was conducted with the following discrepancies: Entire area was covered with a white powder which is believed to be developer from ISI weld inspection. Boron deposits were found on the threaded connection from approximately 9:00 to the 11:30 position and at the 6:00 position. Reddith brown streaks of stained areas were Identified at 6:00 below weld. All match marks are filled with white powder. :Most all of the scratched surfaces in the painted area of the piping have some corrosion and corrosion is apparent un4er the band around pipe. Boron deposits were found near the band around the piping (appears to be a previous location of the band Itself), located below the nozzle. The one deposit was located below and to the left of the nozzle (4pproximately 10 to 12 Inches in length by 0.5 to 0.75 inches in width), two smaller deposits

• were noted below and to the right of the nozzle (each approximately 3 inches In length by 0.5 inches In width). A large

-corrosion spot was foundl on the hanger above where the paint has scaled off.

This CR was written in accordance with the IP.M.028 inspection plan, which directs writing a CR for any indications of

-leakage or corrosion. The CR shall comply with NG-EN-00324 Boric Acid Corrosion Procedure This was Identified per t le Reactor Head Degradation Extent of Conditon program. No active leakage was Identified.

The requirements of NG. N.00324 need to be addressed In the evaluation of this CR.

_.1 M

l 04/26/02 06/10/02 No PE _Open

• N o

PN I I M 06/10/02 l

P E24-2 ALO 0es03-01 l

.INSPECTION PLAN IP4M028 ALLOY 600 EXTENT Or CONDITION - SG2-1 HOW 0575 057 P575 During inspection of Serial Number SG2-1 (Primary Drain Nozzle) signs of previous boric acid leakage from the manway was noted. Since the drdin nozzle is lower than the manway, gravity would cause this leakage to run down to the drain nozzle area. The area'between the manway and the drain nozzle shows minor areas where the original paint is missing

-and brownish color. No teavy rust or scale was noted.

This condition report is generated based on Inspection SG2.1 performed under Inspection Plan IP-M.028. The

.requirements of NG-EN t0324 need to be considered in the evaluation of this CR.

No Immediate action required 1

1 A04/26/02' 06/10/02 l

No

!PE Open No No 06100206/1E2 4

E2 1

14 1Yes 063.01 INSPECTION PLAN IP-M-028 ALLOY 600 (EXTENT OF CONDITION) - SGI-2 TDW 0575 057 0575 During inspection of Serial Number SG1.1 (Primary Drain Nozzle) faint signs/stains of whte can be seen around the nozzle (mostly in the north-east corner). It may be from some previous boric acid leakage. The source can not be determined the drain nofzle is lower than the nearbay manway. gravity would cause any other leakage to run down to the drain nozzle area. The area between the manway and the drain nozzle does not show any streaks to indicate that this may have been the source where the leakage may have been from.

There is also some slight rust colored surface in the same area since much of the original paint is gone. There is no corrosion or loss of metal noted.

05/01/2002 13:19 4198980691 DBNRCRI O PAGE 1 0 This condition report is generated based on Inspection SGI 1 performed under Inspection Plan IP-M-028. The

'requirements of NG-EN 0324 need to be considered in the evaluation of this CR.

Identified per Rcactor Hdad Degradation Extent of Condition program.

No immediate action required.

1 04/27/02= 06/11/02E No No l

1 06/11/02.

!NA

/A No N/A iINSPECTION PLAN IP."29 AREA 585-4S FINDINGS DW 0575 057 0575 Tithis Condition Report Is generated based on Inspection Area 585*4S performed under Inspection Plan IP-M-029. The

!requirements of NG-EN-00324 need to be considered In the evaluation of the CR.

'Floor elevation 603*-0 fioor structural beam between northwest stairs and Containment Vessel has minor surface rust

-along flange edge.

The above CR identifies a condition with minor surface rust. This minor surface rust will not adversely affect the structural integrity of theibeam.

~Contacted P. Mainhardt 0

110 -pe N

N CA 104/27/021 06/l 1/02:

l No PE Open No No I

1 06/11/02 I/a

/A o

N/A INSPECTION PLAN IP-Mp029 AREA 585-3S FINDINGS DW 575 057 10575 This Condition Report is generated based on Inspection Area 585-3S performed under Inspection Plan IP-M-029. The requirements of NG-EN-00324 need to be consideed in the evaluation of this CR.

1. Rust stains evident on!Containment vessel beneath mounting plates for conduit and cable tray supports. Back

surfaces of plates have never been painted due to accessiblity and have surface rust. Typical for all plates in area.

{photo file 585-3s.l.Ipg)

.2. Surface rust on restraint components for valve CV5010A Llmitorque actuator. (photo file 585-3s.6.Jpg)

.3. Surface rust on mounting pad welds for Core Flood Tank No. 1. (photo file 585.3s.2.jpg)

• 4. Pipe support clamps ftr 3/4 E1BB-5 sample line have some surface rust. Supports are located on wall east of Core iFlood Tank No. 1.

5. Rust staining on structural beam for elevation 603' floor. Location approximately one foot south and west of Core Flood Tank.

6. Underside of grating support angle for floor elevation 603'.0- has surface rust. Grating Is located between vessel and concrete floor area northwest of equipment hatch.

7. Pipe supports located In northeast corner of room 316 have boric acid deposits. The boric acid Is white and appears to have originated due to condensing of vapor on 3-CC line above. (photo files 585.3s-4.Jpg, 585-3s-5.Jpg)

The above CR Identifies a condition with minor surface staining and surface rust. This minor surface staining / rust will

-not adversely affect the structural integrity of the item.

Contacted P. Mainhardt 1

• i¶ CA 04/27/02 06/11/02 I to E

pen NoN JNo 1

06/11/021 AIJNO N/A -_ -/A

INSPECTION PLAN IP-M4O29 FINDINGS FOR AREA 585-SS HDW 0575 057 0575 This Condition Report is generated based on Area Inspection 585*SS performed under Inspection Plan IP-M-029.

requirements of NG-EN-00324 need to be considered in the evaluation of this CR.

The

1. Rust colored staining identified at joints in ceiling floor plugs. Staining extends to the flanges on some structural support beams. Staining appears to be caused by unknown fluid leaking through joints. (See representative Photos #

585-5S-1 & 2) 2 Spolty corrosion and water spotting identified on metal decking at ceiling. Corrosion appears to have begun to undermined the protective coating (blistering). (See representative Photos # 585-55-3 & 15)

3. An unknown red powder identified on angle member support for small bore pipe. Support is located on south wall in front of CAC 1.1 at approximately El. 589. No corrosion was identified. (See Photo X 585-5S.4)

4. Light surface rust and staining identified on Core Flood Tank No. 2 supports. (See representative Photo # 585-5S.5)

5. Boric acid residue. staining and surface rust identified on supports for small bore core flood line. Supports are

05/01/2002 13:19 4198980691 DBNRCRI O PAGE 1 1 located on east side of cOre flood tank (near valves CF1OO & CF15). Boric acid residue is from service waler piping sabove. (See Photo is 5Bq.5S-6)

16. Wide spread boric achy residue (white and rust-colored) and corrosion Identified on service water piping supports.

,Any evidence of flaking a pears to be limited to where the corrosion has began to blister the protective coating. Some possible minor loss of m terlal at comers of member flanges. (See representative Photos # 585-5S-7. 8. 9 & 20) i7. An area with very light surface rust Identified on the containment vessel liner. located between the elevator and CAC 1.2. (See Photo #.585-5$.10)

8. Surface rust identifie on drain piping rod hanger supports. Supports located in overhead south of CAC 1.3. (See representative Photo # 585-5S-1 1)

'9. Wide spread rust color staining of concrete floor, predominately beneath the service water piping and In the vicinity icf the CACs. (See representative Photos # 585-5S-12 & 13)

• 10. Surface rust and rust.colored staining (typical) on CAC base anchorage. Paint Is blistering, but there does not

?appear to be any materiak wastage on the nuts. (See representative Photos # 16 & 17)

11. Surface rust identified (typical) on CAC drain line supports located on floor. (See representative Photo # 585-5S-18)

12. Staining, surface rust and light boric acid residue Identified on small bore pipe supports. The supports are located off south wail near elevator at approximately El. 593', below service water piping. (See Photo N 585.5S-19)

The above CR Identifies a condition with minor surface staining, surface rust, and some boric acid residue. This minor surface staining / rust arid boric acid residue do not adversely affect the structural integrity of the Item.

Contacted P. Mainhardt 1A 04/27/021 06/11/02 l_No

_PE _pen No INO I

1 06/11/02 l IN/A N/A No N/A MiNSPECTION PLAN IP-Mo029 FINDINGS FOR AREA 603-2-S HDW

,575 057 p575

'This Condition Report Is generated based on Area Inspection 603-2-S performed under Inspection Plan IP.M.029. The requirements of NG-EN-00324 need to be considered In the evaluation of this CR.

!1) The area around and 4bove the Equipment Hatch shows signs of water streaking, however no rust was noted. It jappears that the streakirMg may be the result of past deconning operations.

'Note: The 'rust' color discoloration around the equipment hatch Is'not the result of rust. It appears to be residue left lver from tape that was applied to the equipment hatch In past outages.

Isee Photo #603.2-S-1

2) Directly in front of the equipment hatch are 6 vertical Service Water pipes. There Is a gang support for these pipes at the floor level. This pipe:support shows varying signs of boric acid buildup as well as surface discoloration, and surface rust. No loose rust was rioted.

See Photo #603.2-S-2. #603-2-S-3. and *603-2-S-4.

3) The 603 floor grating directly In front of the Item #2 above and the structural steel that supports the grating shows 1Signs of boric acid deposits, surface staining, surface rust and in a few Isolated location slight flaky rust. This appears lin tour locations.

iSee Photo #603-2-S-5 and #603-2-S-6.

4) Pipe support for a 1.1/2 inch diameter pipe (Green) at elevation 603'8" near Item *2 above (by PT RC 2A1) shows signs of surface discoloration and slight surface rust.

See Photo M603-2.S-7.

5) Service Water Pipe Support H44 (@ 613), Note, this is the first support north of the Equipment Hatch shows signs of

-boric acid deposits and surface rust at numerous locations at the pipe /,support interface.

See Photo 09603.2-S-8 arid s$603*2-S-9.

6) The pipe support for the 1-1/2 pipe (Green) above valve SW 391 shows discoloration and surface rust.

See Photo #603 2-S-10 and 4603-2-S.11

7) Service Water Pipe gang support (2-nd pipe support) shows signs of boric acid deposits at the pipe/support interlace, and the shims iof the support and surface discoloration and rust.

'See Photo #603.2-S-16, #603.2-S-17, M603-2-S-18. and #603-2-S-19

8) Structural Steel for floor grating and the grating Itself (under JT 4904) shows signs of boric acid deposit and light

05/01/2002 13:19 4198980691 DBNRCRIO PAGE 1 2 surface staining and rus Note, this Is common to he grating under the Service Water Pipes.

!See Photo # 603.2-S.20, which Is a representative photo of the area.

i9) The floor grating und4 the Service Water lines shows signs of surface staining and rust (near JT 4910)

See Photo #603*2-S-21

!10) Service Water Pipe gong support (3.rd pipe support) shows signs of boric acid deposit at the pipe/support Interface land light surface discoloration and surface rust.

tSee Photo # 603.2-S-22 Ond #603.2-S-23.

11) Pipe support (angle Jupport) for a 1-1/2 inch diameter pipe (Green) shows slight boric acid deposit at the pipe/support Interface, stirface discoloration and surface rust as well as very minor material wastage (flaky) at the end of angle support.

See Photo #603-2-5-24

.12) A 1-inch copper line above valve SW 391 has a UJ-bolt that shows signs of surface discoloration and surface rust.

See Photo # 603-2-S-25

13) A Tube Steel Support and its baseplate. anchor bolts and nuts shows signs of surface rust and the nut shows slight

,material wastage.

NOTE: There Is no equipinent currently mounted on this support.

See Photo # 603-2-S-26:

14) The concrete floor ditectly under the Service Water pipes shows signs of surface discoloration and surface staining.

See Photo # 603.2-S-27:for a representative photo.

15) Service Water Pipe gfng support (4-th pipe support) shows signs of boric acid deposit at the pipe/support interface, surface staining, and surface rust. This condition is also present on the brace for this support.

See Photo # 6032.S.28. :# 603-2-S-29. #1603.2-S.30, W603-2-S-31, and #603-2-S-32.

'16) The ISI 5034 Test Equipment (C. Daft) shows signs of surface rust and boric acid deposiL iSee Photo # 603.2-S-33.;

'17) Service Water Pipe g~ng support (4-th pipe support Identified as 47-H49) shows signs of boric acid deposit at the pipetsupport Interface bift no staining or rust.

See Photo # 603.2-S-34 End #603.2-S-35

18) The Pipe Whip Restriint Backing Plate / nut directly behind JT 3952 shows signs of surface staining and surface trust.

.See Photo V603-2-S-36

19) Service Water Pipe gang support (5-th pipe support identified as 41-HBC.47.-H29)

The baseplate shows signs of discoloration and surface staining.

See Photo # 603.2-S-37 The support adjacent to the Service Water Pipe shows signs of boric acid deposit at the pipe/support Interface, surface staining and slight surfade rusting.

See Photo is 603-2-S-38.#603.2-S-39, and #603.2-S-40

20) The pipe support for the 1-1 /2 pipe (Green) above the Pipe Whip Restraint shows signs of boric acid deposit, surface discoloration and surface rust. and slight material wastage at the end.

See Photo #603.2-S-41 121) The floor grating including the structural steel beams next to the outer DMRing wall by the stairs shows signs of boric iacid deposit. surface staining, and surface rust.

iSee Photo.# 603-2-S-42. This Is a representative photo of the area.

22) Service Water Pipe gong support (6-th pipe support north side of the outer D ring wall) shows signs cf boric acid deposit at the pipe/support interface, surface staining and surface rust.

See Photo #603.2-S-43 and #603.2-S-44 i23) Service Water Pipe gang support (7-th pipe support 46-H23) shows signs of boric acid deposit at the pipe/support

!interlace. surface stainring and surface rust.

See Photo #603.2-5-45 and #603.2-S-46

24) Support for SP 12A1A line shows signs of discoloration, surface staining, and surface rust.

05/01/2002 13:19 4198980691 DBNPCRIDO PAGE 13 3 ISee Photo #603-2-5-47

25) At the north boundai

-droplets residue / discol

See Photo #603.2-S-48

'26) Containment Vessel I no signs of boric acid del See Photo #603-2-S-49 127) Service Water Pipe ge Istaining and surface rust ISee Photo t$603-2-S-50

28) Large diameter nut(j stairwell (next to cable t Note: This is the only s See Photo #603-2-S-.53 y of Area 603-2 on the outer D-Ring wall several small bore pipe supports shows signs otwater ration. This does not appear to be rust related.

iy the stairwell (general) shows signs of discoloration and streaking on the surface. There are osits or rust.

ing support (8-th pipe support) at elevation 602 shows signs of boric acid deposit, surface nd 5603-2-S-51.

' bolt ?) located approximately 6-feet from the top of elevation 653 at the north end by the y BCCD-01) shows signs of surface staining.

lIning /.rust identified that Is located above the Service Water Pipes.

.nd N603-2-S-54.

The above CR Identifies condition with minor surface staining, surface rust, and some boric acid residue and in a few

.cases minor material wa tage. This minor surface staining / rust and boric acid residue as welt.zminor material wastage do not adverse affect the structural Integrity of the Item.

xContacted P. Mainhardt 1

104/26/021 06/10/02 I No MAIN Open NO NO l

I l

06/10/02 P

TSG I Hot Legl No 64.02 MISSING/LOOSE INSUITION ON OTSG 1 rLOW TRANSMITTERS NOZZLE AND YE HOW_

575 195 1575 The missing Insulation c nditions where Identified during an IP-M*028 Alloy 600 inspection for a nozzle located on the Number 1 Hot Leg. It appears that Insulation was Installed, however It Is currently missing. HLI.3 Insulation for Hot Leg 1 Flow transmitter at RCBB is missing coffee can insulation and insulation box on RCIBB. RCIBB and RC1BBA appears to be new.

IHLI9, Insulation Hot Lee I Upper Vent Nozzle near RC42 (OTSG 1) and the 36 inch line appears to be loose, requiring Ito be re-aligned and buckled. This Is located on the upper part of the hot leg.

fihis CR Is written against configuration control of Insulation not being Installed or If required. Request a determination It this Insulation Is required and If so then have it replaced. Insulation If Installed will be removed for further Alloy 600 Inspections.

Identified per Reactor ii~ad Degradation Extent of Condition program.

Note, the only Issue Iden ified under this CR Is missing insulation. Since the missing Insulation pieces are shown as installed on an OApproves status vendor drawing M-197-00040. it is recommended that this CR go to Maintenance to find or procure the miss Ih insulation and re-install.

W1 N

04/2606/10/02 INo PE Open -

NO 1

5 06/10/02 JRCIBA 1

CS 46-2 kEAKAGE IDENTIFIED A) RCIBA DURING INSPECTION PLAN FOR IP-M-028 ALLOY HOW P575 057 575 jDuring the Inspection of HL1-2 (Pressure Tap PTBI near valve RCIBA) boric acid crystals where located directly below the RC1BA yoke, but abcke the insulation box. Unable to determine if this is through wall leakage or residue leakage Ifrom packing. Yoke and dacking area located above this are reasonable clean.

INote: Both RCIBA and 4CIBAM are scheduled to be replaced this outage per WO 02.008430-00.

This CR is written in acc rdance with the inspection plan, which directs writing a CR for any indications of leakage or corrosion. The CR complies with NG-EN-00324 Boric Acid Corrosion Procedure.

Additional inspections wal be required to determine source and corrective actions. These Inspections are detailed in the

Extent of Condition plan. This Condition report was generated based on Inspection HLI-2 performed In accordance with IP-M-028. No active leakage was identified. This has been identified per Reactor Hcad Degradation extent of condition program.

1 CA 04/29/02 06/13/02 No DBE pen NoW J

_ 1..k 06/13/02 IN/A N/A INO IN/A INSPECTION PLAN IP-M-029 AREA 585-1S FINDINGS HDW 1575 057 0575 This condition report Is generated based on Inspection 585-1S performed under Inspection Plan IP-M*029. The Irequirements of NG-EN-C0324 need to be considered in the evaluation of this CR.

11) Concrete decking hasi corrosion throughout the ceiling ofthe room. Photo 585-1S.1

2) Support on steam geeierator blow down line immediately below the east side room entrance has surface rust. Photo

05/01/2002 13:19 4198980691 DBNRCRIO PAGE 14

.585.1 S-2

3) Incre instrument tan4 anchor bolts have surface rust. Photo 585-IS-4

.This CR identifies cornp ents with minor surface rust. This minor surface rust will not prevent them from performing

,their design function.

1A 04/25/021 06/09/02' No PE pe No I 1 06/09/02 IN/A Yes 064-02

,INSPECTION PLN IP.029 ALLOY 600 EXTENT Of CONDITION HDW 9999 057 9999

-White powder (resembling talc powder) was found on the HPI nozzle (HP51) and RCS piping surrounding the nozzle.

Powder Is confined to thl area only. It appears to be liquid penetrant developer overspray (not boron).

This CR is written in acci rdance with the inspection plan which directs writing a CR for any indications of leakage or corrosion. The CR shall

omply with NG-EN-00324. Boric Acid Corrosion Procedure.

'Identified per Reactor He id Degradation Extent of Condition program.

This Condition Report Is kenerated based on Inspection RCS12OUT-4 perfomed under Inspection Plan IP-M-028. The

-requirements of NG-ENC )324 need to be addressed In the evaluation of this CR.

No active or Inactive leaage was identified. Additional evaluation of effected areas per the Extent of Condition plan will be needed. No Immedia e actions required.

CA 104/25/02 06/09 No PE Open No Tes 06/09/02 1 N/A t'es 64-02 INSPECTION PLAN IP 1 028 ALLOY 600 EXTENT or CONDITION HDW 0575 057 0575 The paint on the nozzle End RCS piping has been removed and oxidation on the pipe surface has occurred.

This CR is written in accordance with the Inspection plan which directs writing a CR for any Indications of leakage or corrosion. The CR shall lomply with NG-EN-00324. Boric Acid Corrosion Procedure.

Identified per Reactor Head Degradation Extent of Condition program.

This Conition Report Is generated based on Inspection RCP22OUT-4 performed under Inspection Plan IP-M-028.

No active or inactive lea age was identified. Additional evaluation of effected areas per the Extent of Condition plan will be needed. No Immediate actions required.

1',

CA 104/29/021 06/1/070IN

- PE Moen No No 1

I 06/13/02 l 2rc r

res 064-04 BORIC ACID CRSYSTAL FOUND ON PRESSURIZER jHDW 99 057 9999 A small amount of lose ite material that could be boric acid crystals were found adjacent to the West lifting lug on the top of the pressurizer..

hese appear to be from elsewhere and not adhered to the metal at the lifting lug.

There were no signs of le kage of any of the adjacent components.

This condition report wa generated during Inspection of various pressurizer nozzles under IP.M.028.

The requirements of NG N-00324 need to be addressed in the evaluation of this CR.

CA 104/25

/02 06/09/02 INo oDBE pen No Yes 1

1 06/09/02 l 2-RC a4Yes 064-04 CORROSION FOUND o0 PRESSURIZER DURING IP-M-029 EXTENT OF CONDITION 1HDW 0575 057 0575

.During the extent of con ition walkdown of the Pressurizer, a small amount of corrosion was found around the nozzle of

,the sample tap (PZR-02)1 It extends around the nozzle but only extends out away from the nozzle by at most I /8'.

Identified per Reactor Head Degradation Extent of Condition program.

'This Condition Report is generated based on Inspection PZR-02 perfomed under Inspection Plan IP-M-028 The requirements of NG-EN-00324 need to be addressed in the evaluation of this CR.

'No immediate actions. there is no visible leakage and no signs of boric acid.

1 7

L

!CA f04/29/02 06/13/02 No DBE lpn NO No 1

06/13/02

/A N/A No

N/A INSPECTION FINDINGS TOR IP-M-029 INSPECTION AREA 585.5S HDW 10575 057 10575 This Condition Report is generated based on Inspection Area 585-6s performed under Inspection Plan IP-M-029. The requirements of NG-EN-00324 need to be considered in the evaluation of this CR.

1. Structural support beams for grating on floor elevation 603.-0 have minor surface rust primarily on the top of the bottom flange and at the junction of the bottm hang and web. (Photo file 585-6s-8.jpg)

2. Service Water piping supports located between D-ring wall and adjacent to elevator have surface rust and boric acid debris. (Phdto file 585-6s-2.jpg)

3. Pipe support u-bolts hpve surface rust. U bolts on supports for Instrument piping which Includes valves RC14AO and RC14BB and for support Identified as HIB. Supports are located on the outside.surface of the northeast diagonal wall of the DLring adjacent to the northeast stairway. Elevation of the supports is between 590 and 595'. (Photos 585.6s41.jpg and 585-6s-3.jpg).

05/01/2002 13:19 4198980691 DB3NRCRIO0 PAGE 1 5

4. Suriace rust observedion instrument piping protective cover adjacent to elevator on D-ring wall and on adjacent pipe supports. (Photo 1585-6s09.jpg)

5. Surface rust on support bolting for H36. Support Is located east of entrance to Incore tank at an elevation of approximately 590-0 J (Photo 585.6s.6.Jpg)

6. Surface rust on support structural member. Support located on outer surface of east wall of east Dring. (Photo file 585-6s-4.Ipg) iSurface rust Is minor and has no impact on structural adequacy of support structures.

.SE O

LA IP-.028 ALL4/29/02 O

06/13/02 0

HNo PE 5Open 5

NWo INO I

7 11 :!

1WM~S 06/1,3/02 l -

CF91 Yes p051-01 INPECTION PLAN IP-"W*28 ALLOY 600 ifINDINGS HDW p575 057 0575 The following conditions Were identified during an IP-M-028 Alloy 600 & Threaded/Bolted Components inspection of

.CF29 BOLTED (CFT 1.1 bo Rx Check Valve).

-The target area Includes the bolted flange, valve body and removed insulation. The valve is located in the East / West Itunnel, CFT 1-1 area. Thi removed insulation showed no evidence of bulges, boric acid crystals, corrosion or corrosion products. Approximately two table spoons of white boric acid crystals were found on the top surface of the bolted connection. The flange his 16 bolts. The crystals were located around one bolt. The bolt location is 175 CW from due

'North. There was no evidence of corrosion.

Digital photos were taken to document the inspection.

This CR is written In accdrdance with the inspection plan, which directs writing a CR for any indications of leakage or corrosion. The CR shall 4omply with NG.EN-00324 Boric Acid Corrosion Procedure.

.N/A

_1 F)CS1XEXR 4/25/02 l 06/09/027 'I No KP Open

.No yes l lfiM@

06/09/02 l

INM 4A A

yes N/A INSPECTION PLAN IP-NO28 ALLOY 600 FINDINGS

!HDW 9999 057 9999

,The following conditions Were identified during an IP-M-028 Alloy 600 inspection of PZR-07 insulation (Level Tap Nozzle Near RC14D).

The target area includes Insulation surrounding the pressure tap nozzle.

The Insulation showed nd evidence of bulges, boric acid crystals, corrosion or corrosion products.

No conclusive evidence of leakage was present. however a white powder residue was found on Insulation In the surrounding area. The inimediate area was Inspected for potential sources of the powder. No source was identified.

Digital photos were taken to document the Inspection. S:\\eng\\planteng\\mech\\lp.m-028 photos\\

pzr-07-1 Ins.jpg pzr-07-2 lns.lpg

!This CR Is written In accordance with the Inspection plan, which directs writing a CR for any indications of leakage or

corrosion. The CR shall domply with NG-EN-00324 Boric Acid Corrosion Procedure.

Identified per Reactor Hehd Degradation Extent of Condition program.

Inspection documented ger IP-M-028.

1 O2 i,

CA 104/25/02' 06/09/02!

No BE Open No es 2

06/09/02 T1 Yes :64.02 VISIBLE SIGNS OF COR4I OSION FOUND ON REACTOR VESSEL HDW 0575 057 0575 During a preliminary irnsoection of the underside of the rector vessel, corrosion was found. The corrosion appears to be the result of leakage frorri the upper vessel area between the 280 degree and 310 degree azimuth. The heaviest concentration of corrosion was noted around Incore guide lube number 1, which is expected since this incore Is the lowest point of the vessel. Further evaluation of this corrosion and determination of the source will be performed during the detailed reactor vessel Inspection using a magnetic crawler.

Identified per Reactor Head Degradation Extent of Condition program. This inspection was performed In preparation for the formal inspection that will be performed under IP.M.030. The requirements of the Boric Acid Corrosion Control Procedure NG.EN-00324 need to be considered in the evaluation of this CR.

l Z

1 CA 04/29/02 06/13/02 l

INo 1PE Open

.1 M

06/13/02 431 4

es 51-01 INSPECTION PLAN IP.MJ02B ALLOY 600 FINDINGS iHDW 0575 057 0575 The following conditions were Identified during an IP.M-028 Alloy 600 & Threaded/Bolted Components inspection of

,CF31 BOLTED (CFT 1-1 tb Rx Check Valve).

05/01/2002 13:19 4198980691 DBNRCRID PAGE 1 6 The target area Includes the bolted flange, valve body and removed insulation. The valve is located In the East / West Atunnel. CFT 1-1 area. Th removed insulation showed no evidence of bulges, boric acid crystals. corrosion or corrosion

!products. Less than one able spoon of white boric acid crystals were found around the seam of the bolted connection.

• There was no evidence o corrosion.

Digital photos were takei to document the inspection.

This CR is written In acc rdance with the inspection plan, which directs writing a CR for any Indications of leakage or

-corrosion. The CR shall iomply with NG-EN-00324 Boric Acid Corrosion Procedure.

,none.

• 1 fOR ILCA 04/29/02 06/13/02 I N 0 OBE 1Open No No l

06/13/02 IN/A

_3 Yes NA IINSPECTION FINDINGS FOR IP-M-029 INSPECTION AREA 565.6S H

DW 575 057 0575

'This Condition Report Is generated based on Inspection Area 565-6S performed under Inspection Plan IP-M-029. The requirements of NG-EN- 0324 need to be considered in the evaluation of this CR.

.1. Surface rust observedlon baseplate and instrument piping restraint straps for support assembly located above manifold valve LTCF3AI1 (Photo 565.6S.lj.pg)

2. Structural steel mem ers located just below floor elevation 585'-0 and southeast of Core Tank. Members appear t

,have never been painted (Photo 565-6S-2.Jpg)

3. Light surface rust on 9-bolt for instrument pipe restraint adjacent to valve CC42018 and on top of unistut member.

kPhoto 565.6S.3.jpg).

i4. Entire area north of C plenum has rust staining on concrete, general rusting of steel substrates and boric acid idebris. (Photo 565-Gs-9. pg)

S. Severe corrosion of V C plenum anchorage assemblies Including anchor bolts. Photos 565-6s.1O.ipg and 565.6s-I 1.Jpg are representativ( of as-found corrosion.

6. Piping, supports, plenjim surfaces are severely corroded. (Photos 565.6s.12.jpg and 565-6s.14.jpg)

• 7. Corrosion has caused through wall holes in CAC plenum. (Photo 565-Gs-13.jpg) During current cleaning process of interior surfaces water wi s observed dripping along bottom of plenum.

8. Rust staining on concrete beam/floor above plenum (Photo 565-6s-16.ipg).

9. Rust and boric acid dtbris at interface of structural floor beam and concrete flooring (Photo 565-6s.15.ipg) in accordance with IP-M4 29 Section 6.13.5. the Plant Engineering Manager or his designee was contacted concerning above Items 5. 6, and 7 is representing degraded conditons requiring further engineering evaluation.

The remaining items corjcern minor surface rust. This minor surface rust will not prevent the Items from performing

• their design function.

1 CA 04/25/02 06/09/02; 1

No PE Open No 1 DM 06/09/02 P36-3 4

_Y.02 INSPECTION PLAN tP~-08 rFINDINGS.

JHDW 0575 057 0575 Inspection zone RCP2111 1-1 (28' RCP 2-1 Inlel pipe): While Inspecting the underside of RCP 2-1, noted evidence of boric acid leakage from above; White boric acid trails are present on the pump bowl assembly and continuing onto the associated 28' Inlet plpijg. This is most pronounced on the north/west side. There Is some reddish/brown oxidation on the 28' RCP inlet pipig, and on the anchor lug welds for the anchor associated with this piping section. Divots were noted on the southeast 5ide of the weld, apparently from past grindingtblending efforts to remove Indications. There were no Indications of a dtive leakage.

Inspection zone RCP22111-2 (28' RCP 2-2 inlet pipe): Unidentified white markings (appears to be writing) on the west side of the nozzle leadirig from the RCP 2-2 inlet piping to valve RC34.

Identified per Reactor Hlad Degradation Extent of Condition program.

This Condition Report isigenerated based on inspection RCP21IN-1 performed under Inspection Plan IP-M-028.

No active leakage noted This CR must comply with NGGEN-0O324, Boric Acid Corrosion Procedure.

P CA 104/25/02 06/09/02 _

I PE lopen i

NO eS 5

Iff I/0YO NA 14 Yes p64-02 i

INSPECTION PLAN IP-4-028 FINDINGS HDW 10575 057 10575 iThe following conditionsiwere identified while performing inspections for IP-M-028 Alloy 600 inspection program for Jpackage serial numbersInsulation inspections for RCP1IIN*2, RCP121N.1 and RCP12iN-2.

iRCPI 1 IN2 (insulation..5 drain nozzle weld CLI -2. RC38) The inspection identified some streaking of white down

'the cold leg insulation to the drain line on the east side. Insulation was generally dirty / dusty, but in good condition.

Some minor spots of white were found that appear to be paint.

RCP12IN-1 Insulation RWP1.2 28' piping weld 90 deg. The Insulation for RCP121N*I has boron or white powder streak noted on the upper mirrOr West collar section just West of the North position vertical seam. This Is very light and japproximately 1" wide by 6 - long. Two oval spots of a white substance were noted on the under side of the upper collar

Oi/131/2002 13:19 4198980691 DBNRCRIO PAGE 17

'in the NorthEast quadra it. Very light Indications of dried water accumulation and dripping were present In the south end underside upper catar.

• RCP121N*2 Insulation R 40 2.5" drain Nozzle Weld CLI-2. The insulation for RCP121N.2 has light boron or white

,powder streaking noted ror the cold leg running to the upper collar for RCP121N-2. This streaking is present In multiple locations noted rom both the East and West views. The streaking is heaviest above this Insulation on the cold leg. The material conditi n Inspection of the insulation panels around RC12IN-2 Identified poor material condition as ithe insulation fit was not fit up well and straight and the seams In multiple locations had less than desired fitup.

This CR was written in alcordance with thelIP*M-28 Inspection plan, which directs writing a CR for any Indications of leakage or corrosion. Th! CR shall comply with NG-EN-00324 Boric Acid Corrosion Procedure This was identfied per l e Reactor Head Degradation Extent of Conditon program. No active leakage was Identified.

1 A04/25/02 106/09/02 No P

pen No es i

1 06/09/02

/A es p64-02 INSPECTION PLAN IP- -028 ALLOY 600 (EXTENT or CONDITION)

HOW p575 057 1575

-There are some old (ina ive) black drip marks on RCP pipe origionating from above the nozzle. The path of the old drip imarks go over the nozzl area. Also, the protective layer (skin) on the nozzle has been corroded away In some areas.

Kexam Identification; RC 1lout-2)

• This CR is written in accordance with the inspection plan which directs writing a CR for any indications of leakage or

'corrosion. The CR shall omply with NG-EN-00324, Boric Acid Corrosion Procedure.

ildentified per Reactor H d Degradation Extent of Condition program.

This Condition Report is enerated based on Inspection RCPllout-2 performed under InspectIon Plan IP-M-028.

No active leakage was I entitled. Additional evaluation of effected areas per the Extent of Condition plan will be needed. No immediate ctions required.

IZA 104/25/02 U 06/09/02.

INo PE pen No Yes I

I i 1 5/09/02 j IP36.1 14 fres 064-02 iINSPECTION PLAN IP-M4028 FINDINGS jHDW 0575 057 0575 The following conditions iere identified while performing inspections for IP.M-028 Alloy 600 Inspection program for package serial numbers i1sulation inspections for RCPI 11N.1W(RCP1-1 28 Inch piping weld, 90 degree bend, Inlet)

.The inspection for RCP1IN-1W (RCP1-1 28 inch piping weld, 90 degree bend, Inlet) Identified what appears to be an lactive leak. The inspecti n of the weld Identified active leakage on the North / Northeast underside of the pump bowl, ioriginating from above.

treaks of boron could be seen coming down the bowl and piping which appeared to be wet.

7The weld Itself appeared o be in good condition with no evidence of leakage. Boron deposits could be seen on the insulation around the bowl. Boron streaks can be seen over top of the dye penetrant / developer on the East side, Northeast side, and the rorth side of the pump bowl.

'This CR was written in aclordance with the IP-M-02B inspection plan, which directs writing a CR for any indications of leakage or corrosion. Thl CR shall comply with NG-EN-00324 Boric Acid Corrosion Procedure This was Identified per thI Reactor Head Degradation Extent of Condition program. Active leakage was Identified.