ML11258A139

Email from P. Polasek, Subj: Ptrg Report for IP3-2010-02682

ML11258A139
Person / Time
Site:	Indian Point
Issue date:	09/10/2010
From:	Polasek P Entergy Nuclear Operations
To:	Paul Cataldo Reactor Projects Branch 2
References
FOIA/PA-2011-0272
Download: ML11258A139 (78)

Text

McCarver, Sammy From: Polasek, Patrick J (ppolase@entergy.com].

Sent: Friday, Septembe, 10, 2010 5:37 AM To: Cataldo, Paul

Subject:

PTRG Report for IP3-2010-02682 Attachments: ipcpr029000.PDF PTRG report as requested.

Manager, Nuclear Information Technology Entergy Nuclear Operations, Inc.

Indian Point Energy Center Generation Support Building - 2nd Floor 450 Broadway Buchanan, New York, 10511-0249 . (

914-271.7238 Office (b)(6) Mobile i

'Coiproate IT-Help 06W~k 8-750-7300 or 800-224-3939 (Option 1) http://servicedesk.entergy.com Information in this record was deleted in accordance with the F do ma Act, exermpti thefrato

~

CAJil - os =

1

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION Page 16 of 40 Attachment 10.1 POST TRANSIENT EVALUATION.COVER SHEET Page 1 of 1 Unit..No.: P 1 Transient (CR) No.:]  :: Pe 3 ';-

• 0- 0 ,-

Transient Descriplion: Vni+ 3 cnd ý-r' Pipe& fJ3v- +sJ.i .Jý~ ~ic.~ _

Transient Date: /¢ý 0 0 Transient Time: 9 7 E-xct4T~- k usr A. Attachments:

V ttachment 10.1, POST TRANSIENT EVALUATION COVER SHEET Attachment 10.2, GENERAL INFORMATION

' Attachment 10.3, DATA

SUMMARY

Attachment 10.4, EVENT ANALYSIS Attachment 10.5, POST TRANSIENT REVIEW GROUP

SUMMARY

AND RECOMMENDED ACTIONS h El Attachment 10.6, ITRG TRANSIENT

SUMMARY

kP f rc' r"'c' cemmpmdeL rl Attachment 10.7, OSRC REVIEW LI Required prior to Restart/ Recovery U IF OSRC review is required THEN ISSUE CA to ensure Post Transient Evaluation is reviewed by OSRC within 14 days of approval date.

r- Attachment 10.8, OM REVIEW AND APPROVAL B. Revws and Approvals

,' Report final , ,/

PTRG Chairperson: ('4o IKCK.ekA Date: L///C El All recommendations properly resolved for restart/recovery AND all required regulatory approvals have been obtained.

OSRC Review Meeting No.: Date:

Assistant Operations Manager:, Date:

Operations Manager:_____________________ Date:

C. Plant Restart Recovery Authorized r] YES [I NO El N/R GM P0: Date:

- - 21' " MLL-- ýý ý 1ýi,,,,ýý ýý.

,IP7SMWOP-105 Rev: 6 POST TRANSIENT EVALUATION PagePa 17 17 of of 440 Attachment 10.2 G ENERAL;IN FORMATION:'

.-. m Page 1 of 3 Unit No.: Transient (CR) No:i Transient

Description:

Utl PAOýL k,ý r (r t h Transient Date:q E C Transient Time: c, 0 - , ý0-hO lS.

NOTE

• The tracking number for the trip 0 transient SHALL use the CA number that required the event investigation.

0 The report without ihe data package SHALL be attached to the CA that required the PTRG.

General Trini'Translent Information 1.0 Reactor Trip/Transient Actuated By: Manual Auto __

1.1 Reason for Manual T ip/Transient:.. Jcc e L f - , ,cFtrC

...'l

()1p,- 4 e.Fc#r itn~

1.2 Reason for the Auto Trip/Transient (include component/system):

2.0 P lant Personnel On Shi(print names)

SM STA/WE 0') e-CIe' fA CRS K'oh~ ('6rn FSS (5 nGcLQ2 FlO Chveis NilSýSen BOP -Chet V'~r' "NPO

• Other R,ao I ro

.3

• If involved with the Trip/Transient Event

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION P.e.8..4 Page 18 of 40 j Attachment 10.2 GENERAL INFORMATION Page 2 of 3 3.0, Notifications All notifications SHALL be made in accordance with IP-SMM-LI-108/, P-8.3/ AP-21 and documented in the plant logs.

0.NOL ,*4.

Comments: LLl Cýr~n, 4 4.0 Emergency Plan Implemented? YES NO IF yes, THEN give classification and explain:

5.0 Systems Identified with Inadequate Performance Document in General Information and Data Gathering, the plant parameters immediately prior to and V ~Fr, . .

after the trip or transient and identify any abnormal performance of plant systems and components.

3L/P-,

I K.- 3s 3';)3Cd, Jd /I6-f 7 yni A~p m-ý e r '-

6.0 S c%'r Off Normal Status of Any Trains/Porions of Safety Sy=tems ,

mG( c~~ em CA'AYZ2 7.0 Unusual or Abnormal Status of Other Plant Equipment. Systems Jone-

IP-SMM-OP-105 Rev: 6

....Page,,19 of 4 ev:

POST, TRANSIENT EVALUATION

Page 19 of 40 Attachment 10.2 GENERAL INFORMATION Page 3 of 3 8.0 List an AOTs/LCQs, in effect Vqcl-c ,

9.0 Testing/SurVeillance/Maintenance in Progress (pertinent to transient) 10.0 Plant Status E] Start-Up in progress L] Shutdown in progress "Power Operation - Other (Explain)

Other Informative Details:

Maximum , Minimum NIS Power Ranges ____"_'__

CETTemperature. ., jO F 5 < 3 0 RCS Pressure T 75 RCS Temperature 5-70~ 0 #1- or VC Pressure P..? -st VC Temperature i .

11.0 For reactor trips,, btain the 'Sequence of Events" and "Post Trip Logs" per Section 6.2.1.1 eference 3 fR 9'3 0 Completed: / 23 Otenitials f aDate Time Other Informative Details:__________________________________

IP-SMM-OP-105' Rejv: 6 POST TRANSIENT EVALUATION P Page 20 of 40 Attachment 10.3 DATA

SUMMARY

Page 1 of 8 1.0 Initial Plant Conditions Just Prior to TripITransient Phase 1. Part I 1.1 - Plant Parameters Reactor Power Level 0  %

Electrical Output /07,3 MWe RCS Temperature (Tave) -.F RCS Pressure y Z, psig Pressurizer Level 4-/&. Z% .

Control Bank Position Bank2/L Steps-. 2- )

RCS Boron ppm Condenser Vacuum. In.H9 1.2 Source and Status of Oftsite Power I,,,e STAAu* OOS 013 STBY GT Substatio OOS  !

APP RODG:/S QOS ISBY N/A 480 Volt Buses/EDGs:

2A: C/ OOS STBY EDG 22/ I/S

/i OCS 3A: I/S OOS STBY SA: ,/ 0OS STBY EDG 21/@ I/S OOS ST.

6A: OOS C/S STBY EDG 23/ 6' I/S O STBY 6.9 KV Buses I/S OOS STBY 008 STSYk 12:

1: it 3: ./S 00 STBY 4: I/S OOS STBY 5 .. 03 STBY 6: ooS ST-Y

- . - 2 - - - --

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION Page 21 of 40 .0.3 DATA-

SUMMARY

Page 2 of 8 1.3 Plant Equipment in Operation (circle appropriately)

Reactor Coolant 21 1 22(0 R3a3), _',24ý Pum ps , , , , .... ..

Charging Pumps. 21/31 22/32 23/ 33 Main Boiler 21(2) 223.32 Feed Pumps Aux. Boiler Feed 21/31 22/32 23/33 Pump. ,51ý*

Condensate' Pumps '21(

• 2D2.0 2* ,

Feed Rebg. 0ain Low Flow --Aux. Feed Valves Heater Drain 21(3 232(

Tank Pumps Condensate Partial Full Flow -((N-A Polisher C.P. Vessels in A B C D E F Service Circulating .. 1.*i3 22IO2 23 24/0).- 254 2&6W_)

Water Pumps Circulating Water Pump Speed 5 (o0 73 1.4 Status of Controllers (circle appropriately)

Rod Control AT MANUAL Condenser Sleam Dumps MANUAL TEMPERAT' ht PRESSURE PCS Makeup MANUAL Charging Pumps UT MANUA L PRZR Pfessure Control Channel I-PRZR Level Control Channel Main Feed Reg. Valves in AUTO 121/ 1j 2213ýD 231 3) 241 Steam Generator SF/FF: Steam Flow Channel. Fe~d Flow Channel 21/31 SIG A "B - A ,

221432S/G A A 23/ 33.S/G , A *B A 24134 S/G A Bý A B

POST TRANSIENT EVALUATION IP-SMM-OP-105 Rev: 6

~Page 22 of 40* 0.3 DATA SUMMA RY Page 3 of 8 1.5 PORV/ Block Valve Status (circle as appropriate) 535 OPEN CLOSED TRIP PULLOUT DE-ENERGIZED RCS-MOV-535 536 . E CLOSED TRJP PULLOUT DE-ENERGIZED RCS-MOV-536 PCV-455C OPEN CLOSED AUTO RCS-MOV-455C PCV-456 OPEN CLOSED AUTO RCS-MOV-456 1,6 Steam Generator Chemistry Parameters During Transient I

Chloride (highest) ppb Time--t 0-_

Cation Conductivity (highest) :7 itmho/cm Time -

Specific Conductivity (highest) 'm " ,.mho/cm ',Time g Sodium (highest) p. ppb Time. ':3 Maximum Minimum S/G Pressure psig

-l 0 psig SIG Level%  :,%

1.7 RCS Parameters During Transient 1.7.1 RCS Pressure remained above setpoint for automatic SI actuation NO N/A 1.7.2 RCS Pressure remained below selpoint for PRZR PORV or code safety valve actuation NO N/A 1.7.3 RCS temperature decreased less than 100 -Flhr NO N/A 1.7.4 Indicated PRZR level remained on scale NO N/A IF any of the above are tO, THEN EXPLAIN:

POST TRANSIENT EVALUA'TlONi':I:M . 'P15

., e:

,, ... i .. Page 23 of 40 0.3 ,,DATA'

SUMMARY

Page 4 of 8 1.8 ATTACH and CHECK below sequence of events printout and any other printout, chart, or data which canb'e usedftbidetermine the cause of there'actortransient or to show any abnormal condition durirg transient or transient recovery.R.efrehce 3.13)

Sequence of Events Alarm-Typewriter Printout (Unit 3)

Trend Typewriter Printout (Unit 3)

Log Typewriter Printout (Unit 3)

Plant InformationComputer System (Unit 2)

,, 4 SF/FF Level Charts/ Paperless Recorders S/G Reactor Power Charts/ Paperless Recorders RCS Pressure Chart/ Paperless Recorder PRZR Pressure Chart/ Paperless Recorder' PRZR Level Chart/ Paperless Recorder RCS Temp.. Chart/ Paperless Recorder Condenser Vacuum Chart Paperless Recorder i U unit Log NPO Logs Other Logs or Charts (Chemistry, RP, etc&)

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION Pag ...o 4 Attachment 10.3 . DATA

SUMMARY

Page 5 of 8 Plant response to Event Phase 1, Part 2 (Reference 3.2) 1.0 All Reactor Trip Breakers OPEN EW NO N/A 1.1 All Rod Bottom Lights YE NO N/A 1.2 Actuation Time Time Last Breaker Open . N/A Time of Initial Trip Signal 2 <- 5("

Difference L,* /jL. ,*".jeJ.

1,3 Reactor Trip First Out Annunciator N0'AC L "

OR 1.4 Turbine Trip First Out Annunciator 1.5 Did all Control Rods fully insert?

• (Unit 2) A rod is considered fully inserted if rod bottom light is lit and IRPI in e <12 steps. YES NO (Unit 3) A rod is considered fully inserted if roA om light is lit and IRPI indicates < 20 steps. NO N/A 1.6 IF any control Rods did NOT insert, THEN:

• RECORD the rod numbers that did NOT insert:

• INITIATE a CR

, CONTACT Reactor Engineering and DIRECT them to assess the operability of the affected rod(s) based on available data and performance trends of the rod(s)

NOTIFY Reactor Engineering to evaluate rod drop times and rod recoil and determine whether any tests need to be conducted.

n .....

POST TRANSIENT EVALUATION IP-SMM-Op.-105 Roy:6 P.Page 25 of 40 Attachment 10.3 DATA

SUMMARY

Page 6 of 8 NOTE (Unit 3 Only) The opening of the Trip Breakers can be obtained from the Sequence of Events print out. The initial trip time will be equal to zero milliseconds, and Reactor Trip Breaker opening is obtained from address Y00070 and Y0006D 1.7 What was'the digital point and its description which initiated the Sequence of Events printout?

~9/fl:

~ e~ci MAPA L r[

1.8 What was the real time corresponding to elapsed time 0 on the Sequence of Events printout?

1.9 Did either Reactor Trip Breaker open in 150 milliseconds or greater?

RECORD Time Breaker A _ /D_ _ milliseconds Breaker B 3. milliseconds 1.10 IF 150 milliseconds or greater, THEN INITIATEa CR and CONTACT I&C.

1.11 Did both Reactor Trip Breakers open within the following time periods from the time of the trip signal indication?

1.11.1 45.- 92 milliseconds (for auto trip) YES NO ,,,/o '

1.11.2 145 -190 milliseconds (for SI Initiated trip - time trom SI signal to aker opening)

YES NO (,4,4) , L 2.0 Feedwater Response: - , t Feedwater Isolation NO N/A Aux. Feedwater Auto Start NO NIA YES 3.0 SI Initiated On Demand? YES NIA 3.1 IF yes THEN CHECK safety features actuated Sl .iA Cont. Spray SI Train B ." M.S. Isolation Cont, Isol. Phase A SWS _,,,

Cont. Isol. Phase B 480V EDG Start 3.1 Did Si cause actual injection into the core? YES N/A

.)poSMM-OP-105 Rev: 6 POSi r TRANSIENT EVALUATION Page 26 of 40 Attachment 10.3 -DATA

SUMMARY

Page 7 of 8 3.2 Did any EDG fail to perform properly? YES NiA IF yes, THEN EXPLAIN:

3.3 Did any system fail to function properly? YES NO N/A 4.0 Did Pressurizer pressure and level fail to respond normally? YES N/A IF yes, THEN EXPLAIN:

5.0 Did any primary system fail to function properly? YES (,

IFyes, THEN EXPLAIN:

6.0 Oid any secondary system fail to function properly? YES ýO IFyes, THEN EXPLAIN:

7.0 Any unusual conditions during Rx transient or transient recovery? YES N/A LF yes, THEN EXPLAIN:

',,1PSM -0R-105 Rev: 6 POST TRANSIENT ...... EVALUATION

.... -Page..... S 27, of 40 Attachment 10.3 DATA S,UMMARY Page 8 of 8 8.0 Any unusual or unexplained annunciators during transient or transient recovery?.G NO IFyes, .THEN EXPLAIN: 5N(TC '2r0))) ~S .c~carvLA, Je._ X-9.0 Did Pressurizer PORV and Safetys fail'to perform properly? YES N/A IFyes. THEN EXPLAIN:

10.0 Did any Main Steam Safety Valves lift on demand? YES N/A IFyes, THEN EXPLAIN:

11.0 Control System Response 11.1 Turbine Runback YES NO IF yes: Runback from _ ___ MW to MW Rx Power from _ %to  %

12.0 Does Initiating Event agree with:

12.1 First Out Alarm Panel ? YES NO 12.2 Control Room Indications YES NO IF NO, THEN EXPLAIN:

13.0 Any radiological release: YES (

IF yes, THEN EXPLAIN:

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION Page 28 of 40 Attachment 10.4 EVENT ANALYSIS Page 1 of 2 Chronology of Events TIME EV[ENT DESCRIpTION 6oP (no) no4,ýiie4 6o A u-M 5e" Sero*,

(xao4 V feaýf-

'V a)17* 1 4tm e4~ CC~SC aihd r(dL',rc~ct I I - I k,. V P' :

unSu c crs r-fL) uapyoyfmotle- 3/4(rr)& lbc&Sd On cukr-4

- ~ -

POST TRANSIENT EVALUATION....

.. .. ...... " " P~age 29 of 40 Attachment 10.4. EVENT-ANALYSIS Page 2 ot 2 Description of Event (ATTACH additional sheets as necessary) l-o (solcJCc (,CxXS u*.ft unsUcce5ls4 4 o more space se d T. +rDUL ctA -

IF more space Is required, THEN DUPLICATE Page

POST TRANSIENT EVALUATIION, -' IPSM P-0,_e:6 Page 30 of 40 Attachment 10.5 POST TRANSIENT REVIEW GROUP

SUMMARY

AND RECOMMENDEDGACTIONS Page 1 of 7 Section 1: Preliminary Safety Assessment

P~~y After reviewing the data NOTE here an indications that are unexpecied or abnormal.

3 Lfkc a-- I-k 0 2 :/ 6PP re-tf'.4' i CO a, disenharyý-f&.

section 2 Initiating Cause for Reactor THWoTranlient S ~ryn ((Aji o- /n4 be(Ab- ýyntij osoi1ct'"

Section 3 Plant Parameters Consistent with FSAR. Techincal Specifications. Technical Requirements Manual, Desigjn Basis Doc'imnnts, and Safety Limits'fdr the Type of Transient Section 4 Unexpected Aspect of Trip/Transient Behavior

PO'ST TRANSIENT EVALUATION IP-SMM-.OP-105

.,*' i,:= Rev: 6

; Pago 31 of 40 Attachment 10.5 ',ýPOST TRANSIENT REVIEW GROUP

SUMMARY

AND

%RECOMMENDEDACTIONS Page 2 of 7 Section 5: Personnel Performance Problems Section 6 Was conservative declsion-making evident during the event?

maM~cdLI Ilk rcic~I~r £4}'4~n Section 7 Procedural Problems Section 8 Were actions taken outside established Procedures? Were they documented and evaluated? "Was a-CR Initiated? {Reference.3.3)

"

• IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION..,....

Page 32 of 40 Attachment 10.5 POST TRANSIENT REVIEW GROUP

SUMMARY

AND RECOMMEN6DED ACTIONS Page 3 of 7 Section 9: Any Detrimental effect on Plant Equipment Section 10 Any data unsupported by other diverse indications k/0.

Section 11 Additional Remarks (explain any degraded trends or equipment responsesi-unanticipated alarms or Indications. repeat transients, any areas of concern, or e-xtent of condition) yfl ofl e-Section 12 -i) needed? )

,e4r Any further reviews/evaluations & in Utdet4-an 129q t f-Jorq175 F

§) t~mrn~~1AJL4 CD0A cbschcnrgý. C1eY

~~~~~~ 3,C i 2 'RA f ,

POST TR*ANSIENT EVALUATION t:]P$-SMM-oP-105 .Rev:.6

,, - . .... - * '_ P age 33 of :40 ,

Attachment 10.5 -:STITRANSIENT REVIEW GROUP

SUMMARY

AND RECOMMEN6DD ACTIONS.

Page 4 of 7 Section 13 CORRECTIVE ACTIONS Section 13A: For Reactor Trips: Is c~-actlve' actionirecommended pdo~r to returnina to power?

NO NI'A Specify Recommended Corrective Actions prior to rejurning to power:

M 0cfkjt

• • .b-V10. q *L e no,'rcrd

'Y crYCMc o eeýn operi4*,as 3 3*.-(,3bfr ...

S~ ~~P "nr Gal 5 ....afce$1o "e;

CO (S Cr~

00"- ~veiI'

• Qe&Io(c,. or esct~t~ C Yc~c Section 13B:

Specify Recommended Corrective Actions after returning to power: (Include a CA to Simulator Support to benchmark and review the event for simulator and plant differences)

{*Jonle.,-

POST TRANSIENT EVALUATIONPae3of4

. IP-SM M-OP-I105 ' Rev:'6' Attachment 10.5 POSTITRANSIENT REVIEWGROUP.

SUMMARY

AND RECOMMENDED ACTIONS.

Page 5 of 7 Section 14: Plant Transient Response:: IF post-transient response is determined to be abnormal,.OR there were non-conservative actions/decisions made, OR the PTRG feels the need to have an additional review for any reason, THEN the PTRG canrecommend that an ITRG be convened, The basis for this -

recommendation must be explained below:

ABNORMAL Is the ITRG recommended: YES IF yes, THEN EXPLAIN:

Section 15: Recommended Changies to Plant Status (e.g., Proceed to Cold Shutdown) v, MoI& 'tu-recomrnatndeX, ac'4-1 ' f Ct_(c c oMP (L Section 16 I dlcate below any additional Information or remarks that could be usedito reconstruct thn ,w~nt oridAntlfv th~rnJ~A cA the tr,~n~i~nL th kvn rIdentiyte as f h raset

POST TRANSIENT EVALUATION - 1P-SW-.oP.10

-:. "Rv6 Re:

Page 35 of -40 Attachment 10.5 /: POST-T"R",NSIENT REVIEW GROUP

SUMMARY

AND SRECOMMENDED ACTIONS Page 6 of 7 Section 17: Event Determination 1.0 Is the cause, of the trip/ transient positively known (to the extent of a comrpohent, e.g., a fuse that requires detailed laboratory analysis for type of, failure need NOT be-krdwn'at.the lime of Trip/Transient Review) and has been corrected QOR appropriate corrective action restraints are in place AND either of the following:

1.1 All safety-related and other important equipment functioned properly during the transient OR 1.2 IFany safety-related or other important equipment did NOT function properly during the transieni, THEN the equipment malfunction has either been corrected OR appropriate corrective action restrgi Iare4 in place OR reduridant equipment is available.

(E) NOr 2.0 IFthe answer to question 1.0 (above) is YES, THEN review by an Independent Transient Review Group (ITRG) is NOT required due to the cause of the trip. OSRC review is required within 14 days of SVP signature) 3.0 IFthe answer to question 1.0 (above) is NO, THEN review by ITRG and OSRC is required prior to starlup. [Referenceý114) "

4.0 Was a safety limit violated during this transit?

YES NO 5.0 IFthe answer to question 4.0 (above) is YES, THEN ITRG, OSRC, and NRC approval is required prior to Startup.

iP-SMM=OP-105 Rev: 6 POST TRANSIENT EVALUATION*

Page 36 of 40 Attachment 10.5 POST TRANSIENT REVIEW GROUP

SUMMARY

AND RECOMMENDED6ACTIONS Page 7 of 7 Plant Transient Review Group Members PTRG Chairperson Department Date Time 4 S0 Member i ~~ ~CA

° Department

{I)iO

?/O/'o°a /2 dati 0-rim Date/ Time Member Deprtment 1-1 Date/ Time Member Department " Date/Time Operations Review and Appr val Reviewed:

Manager, Operations Date/ Time OM Review and Approval Is ITRG Required? YES NO Is ITRG Required prior to restart? YES NO List approved PTRG Recommended Actions (have PTRG member create and attach CR sheets)

Operations Manager Date/ Time

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION Page 37'of 40 Aa 1Page6 37 of 40 Attachment 10.6 *,, ITRG TRANSIENT

SUMMARY

Page 1 of 2 1.0 Unit No.: TransiE)nt (CR) No.:

2.0 Transient Date: Transient Time:

Adnniipiv and Accturacy nf PTR* Fu~whjj~ion" 3.0 Adenua ry and Accuracy of PTRQ4 9valuation:

4.0 Adequacy and Accuracy of PTRG Initiatincq Cause Determination:

5.0 Adequacy and Accuracy of PTRG Evaluation of Plant, PrOCedure. and Personnel Performance:

6.0 Evaluation of lrnIact of Criteria Requiring the ITRG:

IP-SMM-OP-105 Rev. 6 POST TRANSIENT EVALUATION Page 38 of 40 Attachment 10.6 ITRG TRANSIENT

SUMMARY

Page 2 of 2 7.0 Safety Significance of Event:

8.0 Recommended Corrective Actions:

Prior to Recovery Restart:

Following Recovery Restart:

9.0 ITRG Members:

Name Signature Date RCA Experienced Individual Licensing System Engineering Manager

POST TRANSIENT EVALUATION IPSMMOP-105 Rev: 6 Page 39 of 40 Attachment .10.7 OSRC REVIEW Page I ot 1 Unit No.: Transient (CR) No.:

Transient Dante:

OSRC Meeting Number: Date:

Detail any pertinent OSRC comments below:

Completion of Independent Review:

1. Forward a copy of this independent review to CA&A for the CR file,

2. Attach CR forms for all actions that resulted from the independent review and which :will be carried against the CR for' this event.

Presented by:

Name Signature Oate Assistant Operations Maiiager/ aesignee

IP-SMM-OP-105 Rev: 6 POST TRANSIENT EVALUATION .....

Page 40 of 40 Attachment 10.8 OM REVIEW AND APPROVAL Page I of I All required reviews complete YES NO The initiating cause of the transient has been identified YES NO Safety-related and other essential equipment has functioned properly.

during the transient ifrequired, and if NOT, corrective maintenance has been completed and the equipment satisfactorily tested OR appropriate restraints are in place. YES NO Provisions for additional monitoring ol plant equipment or personnel have been provided if required YES NO Extent of condition adequately addressed YES NO The plant is in a condition to restart/recovery and is consistent with the requirements of the FSAR, Technical Specifications, Technical Requirements Manual, and station procedures YES NO If a technical specification safety limit exceeded, NRC approval obtained YES NO N/A Plant Restart/ Recovery Recommended YES NO Name Signature Date/rime Operations Manager

Entergy ( CONDITION REPORT cR-IP3-2010-02682 Originator: Lewis,Matthew W' Origiihat6r'Phone: 8281 Originator Site Group: IP3 Operations Mgmt IP3 Operability Required: Y Sup~ervisor Name: DinelliJohn Repbrt.bilityRequired: Y Discovered Date: 09/09/2010 21:54 Initiated Date: 09/09/2010 22:06 Condition

Description:

Unit 3 was manually tripped at 2.l:29 due to water leak in the Exciter housing (Service Water, from the Exciter Coolers).

Anomalies noted on the plant trip: 34 RCP tripped during the 6,9KV Bus transfer (6.9KY Bus 2; Bus 2 did re-energize via UT2/ST5 tie breaker and Bus 2 did not receive an undervoltage), 31 MBEP suction relief valve lifted causing a C02 discharge on 31 MBFP (subsequently reseated and C02 secured).

Immediate Action

Description:

Entered E-0 and ES-0. 1.

Suggested Action

Description:

Additional parameters noted on 34 RCP following the trip: Standpipe high level alarm, loss of seal return flow on both indicators, RCDT trending up abnormally fast (frequent pump-downs); possible #2 seal failure.

Entergy CORRECTIVE ACTION CR-IP3-2010-02682 CA Number:

Site I Group Name Assigned By: IP3 Info Technology Mgmt 1P3 Polasek,Patrick J Assigned To: IP3 Info Technology Mgmt 1P3 PolasekPatrick J

~,fi~lat3,.5Il~r. I U3; Originated By: Polasek,Patrick J 9/9/2010 23:27:37 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/13/2010 Initial Due Date: 09/13/2010 CA Type: ACTION Plant Constraint: MODE I/PWR OPERATION CA

Description:

Perform a PTRG on the September 9, 2010 manual reactor trip.

Response

Subresponse:

Closure Comments:

Entergy CORRECTIVE ACTION ICR.IP32010-02682 CA Number: 2 Site Group J Name Assigned By: IP3 Info Teclnology MgMt IP3 Group PolasekPatrick J Assigned To: IP3 InfoTechnology Mgmt IP3 PolasekPatrick J Subassigned To:

Originated By: PolasekPatrick J 9/9/2010 23:36:26 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/23/2010 Initial Due Date: 09/24/2010 CA Type: ACTION Plant Constraint: #NONE CA

Description:

In accordance with IP-SMM-OP- 105, section 6.5.7, ensure OSRC review is completed within 14 days of the PTRG approval date.

Response

Subresponse : ,

Closure Conunents:

Entergy 'ORRECTIVE ACTION CR-IP3-2010-02682 CANumber: 3 Site I Group I Name Assigned By: 1P3 Info Technology Mgmt IP3 Polasek,Patrick J Assigned To: 1P3 Training Mgmt 1P3 Robenstein,Richard Subassigned To:

Originated By: Polasek,Patrick J 9/9/2010 23:45:44 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 11/29/2010 Initial Due Date: 11/30/2010 CA Type: ACTION Plant Constraint: #NONE CA

Description:

In accordance with procedure IP-SMM-OP- 105, benchmark the event fbr simulator and plant differences.

Response

Subresponse :

Closure Comments:

Entergy CORRECTIVE ACTION CR-IP?32010-02682 CA Number: 4 Site I Group J Name Assigned By: EP3 Info Technology Mgmt 1P3 Polasek,Patrick J Assigned To: EP3 Operations Watch Mgmt 1P3 Dinelliliohn Subassigned To:

Originated By: Polasek,Patrick I 9110/2010 00:06:03 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 10/21U20 10 Initial Due Date: 10122/2010 CA Type: ACTION Plant Constraint: #NONE CA

Description:

In accordance with procedure, IP-SMM-OP-105, section 6.7.3, Operations to assemble an operations performance review (OPRC) to evaluate crew performance during the transient.

Response

Subresponse :

Closure Comments:

Entergy CORRECTIVE ACTION fCR-IP3-2010-02682 CA Number: 5 Site 1 Group j Name Assigned By: IP3 Info Technology Mgmt IP3 Group Polasek,Patrick J Assigned To: I'P3 Maint Mech Mgmt IP3 BouderauGregory Subassigned To :

Originated By: Polasek,Patrick J 9/10/2010 03:36:13 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/13/2010 Initial Due Date: 09/13/2010 CA Type: ACTION Plant Constraint: MODE I/PWR OPERATION CA

Description:

• • MODE I ** Isolate exciter leak and repair.

Response

Subresponse:

Closure Comments:

Einte.. CORRECTIVE ACTION iCR-IP3-2010-02682 CA Number: 6 Site Group J Name Assigned By: IP3 Info Technology Mgmt IP3 Polasek,Pairick J Assigned To: IP3 System Eng Primary System Staff 1P3 Chan,Tat Subassigned To:

Originated By: Polasek,Patrick J 9/10/2010 03:39:20 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/I 1/2010 Initial Due Date: 09/11/2010 CA Type: ACTION Plant Constraint: MODE 2/STARTUP-CRITI CA

Description:

• • "MODE 2 ** Restore 34 RCP seals.

Response

Subresponse:

Closure Comments:

EnteWg CORRECTIVE ACTION CR-IP3-2010-02682

'CA Number: 7 Site Group j Name Assigned By: IP3 Info Technology Mgmt fP3 PolasekPatrick J Assigned To: IP3 System Eng Elec/I&C Mgmt 1P3 Andreozzi,Vincent Jos, Subassigned To:

Originated By: Polasek,Patrick J 9/10/2010 03:42:18 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/11/2010 Initial Due Date: 09/1 1/2010 CA Type: ACTION Plant Constraint: #NONE CA

Description:

Determine the cause of 34 RCP trip.

Response

Subresponse:

Closure Comments:

Entergy CORRECTIVE ACTION CR-P3,2010 0682 CA Number: 8 Site Groiup jName Assigned By: IP3 Info Technology Mgmt IP3 PolasekýP'atiick J Assigned To: IP3 Maint Elict'Mgmt 1P3 LijoiJohn I SubassignedTo:

Originated By: Polasek,Patrick J 9/10/2010 03:44:42 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/11/2010 Initial Due Date: 09111/2010 CA Type: ACTION Plant Constraint: MODE 2/STARTUP-CRITI CA

Description:

• • • MODE 2

• Return to normal operations IR-35, 36.

Response

Subresponse:

Closure Comments:

Entergy CORRECTIVE ACTION CR-IP3-2010-02682 CA Number: 9 Site Group JName Assigned By: IP3 Info Technology Mgmt IP3 Polasck,Patrick J Assigned To: IP3 System Eng Secondary System Mgmt IP3 Vasely.Michael J Subassigned To :

Originated By: Polasek,Patrick J 9/10/20 10 03:47:19 Performed By:

Subperformed By:

Approved By:

Closed By:

Current Due Date: 09/13/2010 Initial Due Date: 09/13/2010 CA Type: ACTION Plant Constraint: #NONE CA

Description:

Ensure CD-99-2 is understood and repair as necessary.

Response

Subresponse:

Closure Comments:

Ewergy CORRECTIVE ACTION CR-IP3-200 O2682 LA Number: IU Site Group Name Assigned By: IP3 Info Technology Mgmt IP3 PolasekPatrick J Assigned To: IP3 P&C Eng Codes Mgmt IP3 Troy,Michael J Subassigned To :

Originated By: Polasek,Patrick J 9/10/2010 03:49:11 Performed By:

Stibperformed By:

Approved By:

Closed By:

f'H," - nn n[I*[lt, f~ n t/ 2 /11) / **: 1" .. I*.d. f*ll illf .

• Ul, .1

.tll .11 UQ$* ;Ff 1)1. VJU Initial D)ue* ate,: UViXLUIU CA Type: ACTION Plant Constraint: #NONE CA

Description:

t.

Restore or establish compensatory, measures as required for C02.

Response

Subresponse : ~-A I Closure Comments:

Entergy ADMIN CR-IP3-2010-02682 Remarks

Description:

Closure

Description:

IPEC SITE QUALITY RELATED IP-SMM tMANAGEMENT AomitaSTRATivE PROCEDURE INFORMATIONAL Use LI-108 Page of 112 11 87Revision

"'Irgy MANUAL ATTACHMENT 10.2 NOTIFICATIONS Page 1 of 10 GENERAL INSTRUCTIONS Do not delay in making a required NRC immediate notification. Ifunable to contact an Entergy individual, proceed to the next appropriate step and try to contact the individual again after the attachment is completed.

INITIAL NOTIFICATIONS

• IEan Emergency Event, enter the Emergency Plan IP-EP-120, "Emergency Plan Classifications" and make required notifications (1-Hour NRC hotline notification is required),

2. IFa Non-Emergency Event (1-h4 8,7 or 24-hour NRC hotline notification is required), THEN NOTIFY the NRC Operation Center by the8;Ws N-f t e following which ever is successful within the time limit'specifieb InAttachment 10.1:

Telephone System Telephone Numbet

a. Emergency Notification System (Control Room Telephone) Lift Receiver

b. NRC Operations Center Commercial Telephone 1, Primary (301) 816-5100/ 800-532-3469

2. Backup (1' 301-951-0550/800-449-3694

3. Backup (2m) &3rd 301-415-0550/301-415-0553 Maintain a continuous open communications channel with the NRC when requested.

AS AN AID TO THE NOTIFICATION PROCESS, INFORMATION MAY BE FAXED TO THE NRC OPERATIONS CENTER AT (301) 816-5151 AFTER THE PHONE NOTIFICATION ISCOMPLETED. A FAX SHALL NTI BE USED IN LIEU OF TELEPHONE NOTIFICATION.

For contaminated spills/leaks or release of hazardous substances notify as follows:

ensure IPEC Communications and the Corporate Duty Manager is notified with direction'to notify ENN Government Aff airs-and ENN Corporate Communications with the need for them to'inform local, state and municipality stakeholders of the contaminated spill/leak. Notification of Slate, County, Town should be within one business day (See EN-RP- 113).

b. For releases of a hazardous substance In transportation accidents involving radioactive material that meet the criteria of Title 40 CFR 302.6, EPA Notification Requirements and Title 40 CFR 355.40, Emergency Planning and Nolificalion, refer to IPEC procedure OAP-039 (Transportaion' incidents Involving Radioactive Material). Reporting requirements are also contained in 6 NYCRR Part 597.2, Table 1 and Title 49 CFR, DOT, Subpart C, Hazardous Material, Part 171.15 and 171.16.

"k If NRC Region I Is specified for a Non-Emergency event on Attachment 10.1, THEN notify the NRC Region Office by the first of the following means which is successful within the time limit specified in Attachment 10.1:

USNRC Regional Office (610) 337-5000 Via NRC Operations Center (301) 816-5100

It'-bMM OEnterg IPEC SITE MANAGEMENT MANUAL Ii OuAUrry. RELA7!O, AVMINISTRATIYU PROCEDUIRE INoRnuxnmAL Use 1 Ir-uMM L1-108 Page Revision 11j 68of 112~

ATTACHMENT 10.2 NOTIFICATIONS Page 2 of 10

5. For &L notifications:

a. NOTIFY the first of one of the following:

Name Work Home B wpr/lMoblile Joseph E. Pollock 734-6700, 845-803-5785 (Site VP -IPEC) 734-6701 Anthony Vitale 734-5221 (b)(6) 6i6

)

(GMPO)

(OM) 598-5162 Anthony Williams _598-5162 (OM)

b. Ng*f the Corporate Duty Manager, WPO in accordance with corporate policy EN-OM-128.

ingE The individual contacted shall ensure the remaining personnel in step 5.a are notified as required.

c. IF unable to contact one of the individuals in Step 5.a, contact the following "designated manager*:

The designated manager contacted shall ensure the personnel in Step 4.a are notified.

d. Noq&y Communications by the first of one of the followlng:-

--J

- ~ I IEntity IPEC SITE MANAGEMENT

-,MANUAL I'

I OuAUrY RELATED ADMINISTRATFVE PROCEDURE lue~n A'e'^U~nI inoe J

I

• -lR-SMM

• A*A U'1 08 Revision ii I1 I n IU~P,, t,,*:ru "I~iI q UNP UI I14 ATTACHMENT 10.2 NOTIFICATIONS Page 3 of 10

e. Ntg& Emergency Planning by the first of one of the following:

Name' WOrk Home ,Beep8e4oblle Brian Sullivan 271.7479 (b)(6) 419AfVlJ1 Frank Phillips 271-7170 (Ensure Notification of the other Indian Point Unit Control Rooms Unit 2 numbers - (b)(6)

Unit 3 numbers - 4a~nw Q For. items of interest or of manaaement discretion,- the individual contact*ed in step 5.a or step 5.b shall review

,the event circumstancied an.d *expllici'det~ehinine the need for fihher nieporting Sd advise diectly the SM as to For reportable events notify an NRC Resident Inspector.

a. For an Item of Interest, notify an NRC Reslident Inspector QNL if told to do so by the Individual contacted in Step;,5.a or Step 5c.c... .

b. For Management Discretion, notify an NRC Resident Inspector if Item 80 is being reported.

0 1EFthe Senior Resident inspector CNoT be notified, call the alternate inspector:

I I....

1 I .........

Wok Ho U!

I I .[1 Unit 2 -1ResidentIhnsp6ctor Int; 734-5347 "OdtmaW-.A '* *

........ 2....L-/

Unit 3 -Resident(inspec*tor Int: 734-5347 Paul Cataldo jExt: 914-739-8585

, F the NRC Resident Inspectors cannot be contacted at work or at home, ITHE Notify the NRC Resident

'Inspector by dialing 739-8565, 739-9360 and leave a recorded message.

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• 1P3 UnitLOg Midnight Friday', September 10, 2010 OAP-5

9/9/2010 32 EDG C02 system placed in manual 1AW SOP-FP-3 to support 32 EDG outage 06:00:00 [Dignam, John, FSS]

• 9/9/2010 The following actions have been completed for STA turnover as-per OAP-002:

18:01:00 Reviewed the f1llowing: Shift Orders, Unit Log (since last watch or 5 days),

AOT/ODCM Tracking Log, Standing Orders, Policy book anda-Control Board walkdown with the off-going STA. [DeClemente, Vinnie, Shift Technical"Advisor]

• 9/9,/2010 PLANT STATUS: Unit on line @ 100%, 3-POP-2.1 in effect, 1-2-3 Essential SW 19:00:00 Header, Load Umit 1 in control; CPF bypassed via Post Filter Bypass. Aux steam inservice to Unit 2. EQUIPMENT OUT OF SERVICE: R-5, R-56C OOS. CETs R-10 & K-13 (Temp. Alt. R-10 removed from alarm ckt) OOS. Diesel Fire Pump PTO'd. 32"PZR BU Htr. Group Ckt #1 PTO'd. RCP Seal Water Return Filter PTO'd & bypassed. SFP Filter PTO'd & Demin bypassed for filter replacement.

C02 Tank 3-1 (North Tank) PTO'd & vented. C02 tank 3-2 (SouthTank) Low level alarm is up. FSB FakPTO'd w/T. Alt removing fan from alarm ckt. 31 PrimaryWater Pump PTO'd. OTHER: Rx Vessel Outer O-ring I/S. IA/AA x-tled. TCV-1103 bypass open to lower VC temp. LCV-1129 In "Man" @ 10%

open for CST temp control. Temp Alt. 31 EDG DF-LCV-1207B (disables limit switch for valve). SGBD I/S to SGBDR @ ,,20 gpm each. GE.Mobile.I/S to CST

@ 20 gpm. PROTECTED EQUIPMENT: Electric Fire Pump, Feeders95891*,

96951, 96952, 95331, 95332, 13W92 and 13W93, 32 Primary Wat&er Pump, 31

& 33 EDG's. [Yun, Cheehun, BOP Operator and key 211]

II 9/9/2010 19:16:00 Performed 50 gallon dilution. in accordance with 3-SOP-CVCS-003, Reactor Coolant System Boron Concentration Control, to offset core bum up-and maintain Reactor Power optimizednear 100 %. Total anticipated.Tave effect is less than 0.1 degree F. [Nilsson, Chris, Operator at the Controls]

II 9/9/2010 Dilution reactivity addition effect complete. Less than a 0.1 degree6F Tave 20:40:00 change. [Nilsson, Chris, Operator at the Controls]

ii 9/9/2010 STA Vital Area Tours completed as per OAP-115, Operations Commitments and 20:08:52 Policy Details. [DeClemente, Vinnie, Shift Technical Advisor]

lI 9/9/2010 Placed 32 Monitor Tank on Recirc @ 83 %. [Nilsson, Chris, Operator at the 21:00:00 Controls]

U 9/9/2010 Start 3-PT-Q028, Containment Isolation Valves PCV-1190, PCV-1191, and 1192 21:10:00 Pressure Relief System test. [Martin, Marc, Nuclear NPO and key 215]

U 9/9/2010 3-PT-QQ28, Containment Isolation Valves PCV-1190, PCV-1191, and 1192 21:20:00 Pressure Relief System test completed - Sat. [Martin, Marc, Nuclear NPO and key 215]

U 9/9/,2010 Manual Reactor Trip due to Service Water Leak in Generator Housing. 34 21: 29:00 Reactor Coolant Pump Tripped Immediately following Reactbr Trihp. [Hedges, Luke, MISC]

Page. 1 of 4 copied from prevlous copiedfromi shift previous shift ?age. I of 4

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[P3 Unit Log Midnight

• • OAP-5 Friday; September 10, 2010 M 9/9/2010 34 RCP tripped when Reactor was tripped. [Yun; Cheehun' BOP'Qperator and 21:30:00 key 211]

• 9/9/2010 34 Spray valve isolated. [Yun, Cheehuh, BOP Operator and key.,2. 1]

21:31:00 U .9/10/2010 No entry.text specified. [Hedges, Luke, MISC]

02:16:24 S9/9/2010 C02, Discharge at 31 MBFP. Cause determinedto'be high temperature ;-

S2!:33:00 resulting from lifting of the 31.,MBFP suctionrelief valve. [HedgespLuke, MISC]

M. 9/9/2010 Trainsitfoned to ES 0.1 Reactor Trip R.esponse [ledges, Luke, MISC]

.21:35:00,

• 919/2010 Entered 3-TS 2845 due to C02. inoperable due to low level in South C02 21:38:00 tank..(5,/o), Security providing eondtlnuous fire watch in 15' &33" Control Building &,Rovinig Fire watch in EDG cells Technical Specifications Unit: 3 Type: 3TRM Section: 3.7.A.7 Action"Stateenýn: 3TRM_3_3.7.A.7_A (2), Unit: 3 Type:; 3TRM Section: 3.7.A.7 ActionSta merý- TRM_3_3.7.A.7_B (1):

[DeClemente, Vinnie, MISC]

] .9/9/2010 345 KV Motor.Operated Disconnfect Swvitch F1-3' Open [Hedges, Luke, MISC]

21:39:00

• 9/9/2010 Both MBFPs verified tripped [Hedges;,Luke, MISC].

21:42:00

• 9/9/2010 Condenser Steam Dumps transferred, o Pressurýe Cbntrol Mod. . '-[l eIddegs

'!_Luke, 21:4.8:00 MISGI 13 '9/9/2010 Observed'no Seal Return Flow from'34 RCp. [Hedges, Luke, MISC]

21:50:00 U 9/9/2010 31.and 32 Source Range Detectors are energIzd with Source Ranqge Loss Of 21:52:00 Detector Voltage;Ala m still inalarm. -31,and.32,ntermediateRa0ge, Detectors observed to be pegged low. Reference CR;-P3. 2010-02686 [HAedges Luke, MISC]

• 9/9/2010 Source Range Loss Of Detector Voltage Clear.[Hedges, Luke, MISC]

21:53:00

[ 9/9/2010 Received Source Range Loss Of Detector VoltageAiarms. 31 and 32 Source 21:57:00 Ranige ,T*strunients "bserved to be'energizedrl[Hedges, Luke, MISC]

U 9/9/2010 Secured 32.and 33 Condensate Pumps[Hedges_,

• Luke, MISC]

21:55:00 M a/a/!f1fl Onlnpnrl thirhIne rirnin vxIlvpc rHdlninq I I HlkA I MTiiII 21:59:00 M 9/9L/2010 MSR DrainTank Non-Return Check Valve 33A did not close as expected.

22:00:00 [Hedges, Luke, MISC]

Page lot 4 R == Copied tram previous Copledfrom shift previous shift Page 2 of 4

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• IP3 Unit Log Midnight Friday, September-10, 2010 OAP-5 I2 9/9/2010 Reheat Steam Block Valves Closed. [Hedges, Luke, MISC]

22:00:00 1U 9/9/2010 33A is closed [Hedges, Luke, MISC]

22:18:00 U 9/9/2010 Performed 3-PT-W019, Electrical Verification - Offsite Power Sources and AC 22:00:00 Distribution - Sat. Performed due to the inoperability of 32 EDG due to being PTO'd for Maintenance. [Yun, Cheehun, BOP Operator and key 211]

• 9/9/2010 Completed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notifications IAW SMM-LI-108 to the following stakeholders:

22:50:35 NRC resident Paul Cataldo PSC Paul Eddy CDM Sam Davis Power Marketing Joe Zirella [Dewey, Donald, MISC]

[ 9/9/2010 Placed the Main Turbine Generator on the Turning Gear in accordance with 23:58:00 3-SOP-TG-TG-001, Main Turbine Turning Gear Operation. [Nilsson, Chris, Operator at the Controls]

• 9/9/2010 Main Turbine on the Turning Gear. [Hedges, Luke, MISC]

23:58:00

• 9/10/2010 Start 3-PT-V1, Source Range Analog Channel Functional Test. [Nilsson, Chris, 00:05:00 Operator at the Controls]

[ 9/10/2010 3-PT-V1, Source Range Analog Channel Functional Test completed - Sat.

00:47:00 [Nilsson, Chris, Operator at the Controls]

U 9/10/2010 Received "VC Sump Pump Running" alarm due to VC Sump Pumpout. Per 00:07:00 3-ARP-009 actions: Watch Chemist notified, from Unit Log last VC pumpout occurred on 09/05/10 @ 16:35 hrs. R11, R12, VC Humidity, and FCU Weir levels all normal. [Nilsson, Chris, Operator at the Controls]

] - 9/10/2010 "VC Sump Pump Running" alarm clear. VC Sump Pumpout Secured. [Nilsson, 00:10:00 Chris, Operator at the Controls]

• 9/10/2010 Informed by Unit 2 CCR that 138kV and 13.8kV voltages are Sat. [Nilsson, 00:14:00 Chris, Operator at the Controls]

• 9/10/2010 Secured 32 Rod Drive MG set. [Yun, Cheehun, BOP Operator and key 211]

00:20:00 U 9/10/2010 Initiated 4 & 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> verbal report to the NRC (Howie Crouch) for today's reactor 00:29:16 trip and aux boiler feed pump auto start.

NRC issued the event notification #46241 and recorded the notification time as 00:29. [Dewey, Donald, MISC]

• ] 9/10/2010 Energized VC Lighting and completed PAB prerequisites for VC Entry per 00:52:00 OAP-007. [Banse, John, MISC]

Page 3 of 4 Copie4 6pled from shift previous shift from previous .Page 3 of 4

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• IP3 Unit Log Midnight Fridayi September 10, 2010 OAP-5 M 9/10/2010 VC lighting secured due to VC entry completed. 46' inner crane wall cages 01:36:00 verified secured upon VC exit. [Banse, John, MISC]

[] 9/10/2010 Secured 32 and 35 Service Water'PupSnýip. [Yun,, Cheehun, BOP Operator and 01:30:00 key 211]

Page 4 of 4 from previous Copied from Copied shift previous shift Page 4 of 4

@ Allowed Outage Time for Indian Point 3 LCO Number Section Number Start Date Required Date Status Required Action Initiat ng Items 3-ODCM-06-O094 Radiation Monitor 56C being taken out of service due to spiking causing spurious auto diversions. (PLT Report Submitted 11/20/2006). The Monitr is currently disconnected to prevent alarming.

On 7/26/09 Channel failures on R-56A. B, &C also rendered R-56 A & B non-functional per ONOP-RM-00I. Ref WR 00170944 & CR IP3-2009-03; 1. R-56A and B are returned to service operable on 7/30/09 at 16:21. Refer to WO 00164743-01.

3ODCM R-56A/B. 10/17/2007 1:44:00 AM 10/18/2007 2:40:49 AM Exited 10/17/2007 direct the chemist to take grab samples daily 3-PRM -IXMITR-RD-56C 10:47:00 AM from the combined system for gross activity.

3ODCM R-56A/B. 10/24(2006 8:30:00 PM 11/23/2006 8:30:00 PM Exited 11/23/2006 explain why this could not be done to the Plant 12:00:00 PM Leadership Team (PLT) 300CM R-56A/B. 10/24/2006 8:30:00 PM 11/23/20068:30:00 PM Exited 11/20/2006 explain why this could not be done to the Plant 3:59:00 PM Leadership Team (PLT) 300CM R-56A/B. Potential Future direct the chemist to take grab samples daily Action from the combined system for gross activity.

300CM R-56A/B. 7/26/20097:19:00 PM 7/31/2009 10:45:48 AM Exited 7/30/2009 direct the chemist to take grab samples daily 4:21:00 PM from the combined system for gross activity 3-PTS 0414 R-5 did not perform all of its required function R-5 also has a Part 21 issue against it. Refer to CR-IP3-2009-3590 Unit 3FSB Exhaust fan has been rebuilt, however vibrations have been trending up steadily, on 8/31/10 Performance recommended no longer runn ng this Ian, the Exhaust fan is inoperable, FSAT32 inlet damper replacement 3TS 3.3.8.A.1 Potential Future A.1 Place FSBEVS in operation. 3-ARM -COMPTR-R-5 Action 3-HVFS -DAMPER-FSAT32 INLET 3TS 3.3.8.A.2 Potential Future A.2 Suspend movement of recently irradiated 3-HVFS -FAN -FSBEF-FAN Action fuel in the fuel storage building.

3TS 3.7.13-A. I Potential Future A.1 Suspend movement of recently irradiated Action fuel assemblies in the fuel storage building.

3TRM 3.7.F.B.t Potential Future B.1 Restore Operabittiy Action 3TRM 3.7.F.B.2 Potential Future 8.2 Isolate the FSBEVS when moving fuel in Action the FSB 3TRM 3.7.F.C. 1 Potential Future C.1 Suspend movement of irradiated fuel in the Action associated building.

3TRM 3.7FD1 Potential Future Present a report to OSRC on planned Action corrective action.

3-PTS 0416 Triennial Fire Inspection revealed CCR prompt evacuation or fire in CCR rn rvent securing PORVs by tripping 31/32 125VDC distribution panel breakers, and no RNO is provided. Hourly fire watch for all levels Control bldg.2tgrical ttun l and EDG's.

3TRM 3.7.B.OTF_ 4/17/2009 3:42:00 AM 9/13/2010 7:03:21 A Open 83.6 hrs left 1.1 Verity Fire Watches are being conducted as

ý resciibed 3TRM 3.7.8.8.1 419/2009 7:25:00 AM 4/9/2009 8:25:00 AM .1 Establish an hourly fire watch in the Fire 7:26:00 AM WatchArea(s) designated in Table 3.7.8-1 for the inoperable Function.

3TRM 3.7.BA. 1 2/8/2008 4:46:00 PM 2/8/2008 4:46:00 PM Exited 2/8/2008 A. I Enter the Condition(s) referenced in Table 4:46:00 PM 3.7.1-1, Thursday September 09, 2010 19:26 Page I of 7

Allowed Outage Time for Indian Point 3 LCO Number Section Number Start Date Required Date Status Required Action Initiating Items 3TS 3.2.2.A 1.2.1 Potential Future A.1.2-1 Reduce THERMAL POWER to < 50%

Action RTP.

3-PTS 0526 31 Source range Unable to set High Flux @ shutdown 3TS 3.9.2.A.1 Potential Future A.1 Suspend CORE ALTERATIONS. 3-RPC -IBISSW-NC-31-101 Action 3TS 3.9.2.A.2 Potential Future A2 Suspend positive reactivity additions.

Action 3TS 3.9.2.8.1 Potential Future B.1 Initiate action to restore one source range Action neutron flux monitor to OPERABLE status.

3TS 3.9.2.B.2 Potential Future B.2 Perforrn SR 3.9.1.1.

Aktion 3-PTS 0572 Fire detector FP-DET-2-11 (CS-2.11) - Cable Spreading Room (FDCP ZONE 2) - Failed as:per PT-SA13 3TRM 3.7.A.4.A.1 Potential Future A.1 Establish an hourly tire watch patrol, where 3-FP IXMITR-FP-DET-2-11 Action accessibility permits, in the aftected locationts).

3TRM 3.7.A.4.A.2 Potential Future A.2 Restore the required fire detectors to Action OPERABLE status, 3-PTS 0582 MET TOWER DIESEL GENERATOR out of service due to trip on high temperature during 3PT-M47 3TRM 3.3.B.A.1 Potential Future A-t DEMONSTRATE the ability to obtain 3-MTDG -MET-DIESEL GEN Action meteorological data, using IP-EP-510, 3TRM 3.3.8.A.2 Potential Future A.2 Notify IP2 of system inoperability, Action 3TRM 3.3.B.A.3 Potential Future A.3 Restore the inoperable Meteorological Action Instrument Channel to OPERABLE status.

3TRM 3.3.B.B.1 Potential Future B. I Prepare and submit a Special Report to the Action On-Site Safety Review Coimittee.outlining the actlons taken, the cause of the inoperability and the plans for restoring the meteorological monrtornBg Ins'trui.entati" n channels to OPERABLE-status.

3-PTS 0583 Flux drive V' inoperable, The drive is not producing reliable traces for Flux'Calculations. Refer to CR-IP3-2010-2015 and WA 00206100.

3TS 3.2.1.A. 1 Potential Future A 1- Reduce THERMAL POWER? 1% RTP for 3-INCOI -TOOL -NDDM-F Action each 1% F0(Z) exceeds limit.

3TS 3.2.2.A.1.1- Poten'tialf Future A.1 .. Restore FNDH to within limit.

Action.. "

3TS 32.2-A. t.2.1 Potential Future A.1.2.1 Reduce THERMAL POWER to < 50%

Action, RTP.

3TS 3.9.2.A. 1 -Potential Ftiture A.i Suslpend CORE ALTERATIONS.

Action 3TS 3.9.2.A.2 Potential Future A.2 Suspend positive reactivity additions.

Action Thursday September 09, 2010 19:26 Page 3 of 7

Allowed Outage Time for Indian Point 3 LCO Number Section Number Start Date Required Date Status Required Action Initiating Items 3TRM 3.3.E.B. 1 Potential Future B.1 Prepare and submit a Special Report, Action "Inoperable Seismic Monitoring Instrumentation,* PORC. outlining the cause of the malfunction and the plans for restoring the instrument(s) to OPERABLE status.

3TRM 3.3.E.B. 1 9/9/2009 9:00:(X) AM 9/19/2009 9:000 AM. Eyited 9/19/2009 B.1 Prepare ard submit a Special eport, 9:00:00 AM 'Inoperable Seismic Monitoring Instrumentation,* PORC. outlining the cause of the malfunction and the plans for restoring the instrument(s) to OPERABLE status.

3-IS 2579 32 EDG inop for Work Week 1037 3TS 3.8.1.6.1 9/9/2010 7:23:00 AM 9/912010 10:00:29P Open 26hrsleft B.1 Perform SR 3.8.1.1 for the offsite circuits. 3-EDG I-ENGINE-DE-32 3TS 3".8.1.8.2 9/9/2010 7:23:00 AM 9/9/2010 11:23:00 B.2 Declare inoperable the required features 7:27:00 AM supported by the inoperable DG when its required redundant feature is inoperable.

3TS 3.8.1.B.3.1 9/9/2010 7:23:00 AM 9/10/20107:23;00 AM Exited 9/9/2010 B.3.1 Determine OPERABLE DG(s) are not 7:27:00 AM inoperable due to common cause failure.

3TS 3.8.1.B.3.2 Potential Future B.3.2 Perform SR 3.8.1.2 for OPERABLE DGs.

3TS 3.8.1 .8.4 9/912010 7:23:00 AM 9/12/2010 7:23:00 Al B.4 Restore DG to OPERABLE status.

3TS 3.8.1.F.1 F. I Be in MODE 3.

Action 3TS 3.8.1 .F.2 Potential Future F.2 Be in MODE 5.

Action 3-TS 2676 Zone 117 for 32 RCP Smoke Detector (BSD-2) failed during the performance of 3PT-A39.

Report was submitted to OSRC and action completed 5/16/10 @ 1209 as per CR-IP3-2010-01243.

3TRM 3.7.A.4.A. 1 4/30/20109:00:00 AM 4/30/2010 10:00:00AM Exited 4/30/2010 A.1 Establish an hourly fire watch patrol, where 3-FP XMITR-BSD-2 9accessibility permits, in the affected location(s),

3TRM 3.7.A.4.A.2 4/30/2010 9:00:00 AM 5/14/2010 9:00:00 AM(Ov n -2U2.4 hi

• A.2 Restore the required fire detectors to OPERABLE status.

3TRM 3.7.A.4.C. 1 5/14/2010 9:00:00 AM 6/13/2010 9.00:00 AM Exited 5/26/2010 C.1 Submit a Special Report to the PORC in 12:09:00 PM accordance with specification 5.4.8.

3-TS .10-2713 'OAP-007 Operations Actions to support VC Entry (Weld Channel/Nitrogen isolated to 80' & 95' Air Locks -AOT and Incore Flux Drives off - PAOT) 3TS 3.2.1.A.1 Potential Future AA Reduce THERMAL POWER 1% RTP for 3-INCO I- -INCORE CONTROL PAN Action each'-- 1% FQ(Z) exceeds limit. 3-WCPE -VALVE -PS-24 3TS 3.6.10.A.1 6/5/2010 1:15:00AM 6/5/2010 5:15:00AM Exited 6/5/2010 A1 Isoaite the WC&PPS supply to the 3-WCP~c -VALVE -PS-25 1:35:00 AM affected components by use of at least one closed and de?activated automatic valve, 3-WCPE -VALVE -PS-26 closed manual~valv6; blind flange. or check 3-WCP', -VALVE -PS-27 valve with flow through the valve secured.

3TS 3.6.2.A.1 Potential Future A.1 Verify the OPERABLE door is closed in Action the affected air- lock.

Thursday September 09. 2010 19:26 Page 5 of 7

Allowed Outage Time for Indian Point 3 LCO Number Section Number Start Date Required Date Status Required Action Initialing Items 911/2010 1;51:00 PM 911/2010 2:51:00 PM Exited 9/1/2010 F.1 Establish an hourly fire watch patrol in the 2:00:00 PM Turbine Building(1 5' elevalion south loading well), ControlBuilding (15' elevation) and the Administration Service Building (15' elevation near the fire brigade room).

3TRM 3.7.A. I.F. I Potential Future F. 1 Establish an hourly lire watch patrol in the Action Turbine Building (15' elevation south loading well), Control Building (t 5' elevation) and the Administration Service Building (15' elevation near the lire brigade room).

3TRM 3.7.A.l.G.1 9/8/2010 1:51:00 PM 10/8/2010 1:51:00 Open 6d0.4 hrs left .1 Submit a Special Report to the PORC in ordAnicý&wth specification 3.7.A.8.C.

3TRM 3.7.A.1,.C Potential Future

-- C.1 For the diesel driven fire pump. enter Action Condito*n zF.

Thtjr.'day .Sepicimber09. 2010 19:26 Puge 7 of7

I Entergy CO.NDITION REPORT CR-IP3-2010-02682 Originator: Lewis,Matthew W Originator Phone: 8281 Originator SiteGroup: 1P3 Operations Mgmt IP3 Operability Required: Y Supervisor Name: DinelliJohn Reportability Required: Y Discovered Date: 09/09/2010 21:54 Initiated Date: 09/0912010 22:06 Condition

Description:

Unit 3 was, manually tripped at 21:29 due to water leak in the Exciter housing (Service Water, from the Exciter Coolers).

Anomalies noted on the plant trip: 34 RCP tripped during the 6.9KV Bus transfer (6.9KV Bus 2; Bus 2 did re-energize via UT2/ST5 tie breaker and Bus 2 did not receive an undervoltage), 31 MBFP suction relief valve lifted causing a C02 discharge on 31 MBFP (subsequently reseated and C02 secured).

Immediate Action

Description:

Entered E-0 and ES-0. 1.

Suggested Action

Description:

Additional parameters noted on 34 RCP following the trip: Standpipe high level alarm, loss of seal return flow on both indicators, RCDT trending up abnormally fast (frequent pump-downs); possible #2 seal failure.

.tntt3 I*: CONDITION' REPORT CR-1P3;2010-02683 Originator: Martin,Dustin Originator Phone: 5298 Originator Site Group: IP3 Operations Watch Staff IP3 OperabiiitflR&juired: Y Supervisor Name: BuchalTioii thy J Reportability Required: Y Discovered Date: 09/09/2010 22.0- Initiated Date: 09/09/2010 23:07 Condition

Description:

During unit 3 plant trip 34 RCPtripped during fast transfere of inside busses to outside power. Subsequently 34 RCP seal return flow both high and low indicators are currentlyreading zero and 34,RCP stand piperhigh level alarm is locked in.

Immediate Action

Description:

WR# 212295 for RCP trip during fast transfere WR# 212296 for RCP #1 seal return flow Suggested Action

Description:

Trouble shoot and repair EQUIPMENT:

Tag Name Tai Suffix Name Component Code Process System Code RCPCPC4 NC/SR/MR PUMP RCS

Entergy CONDITION REPORT CR-IP3,2010-02684 Originator: Martin,Dustin Originator Phone: 5298 Originator Site Group: IP3 Operations Watch Staff IP3 Operability Required: N Supervisor Name: BuchalTimothy J Reportability Required: N Discovered Date: .09/09/2010 23:11 Initiated Date: 09/09/2010 23:14 Condition

Description:

During Unit 3 trip CD-99-2 31 MAIN BOILER FEED PUMP SUCTION RELIEF VALVE relieved.

Immediate Action

Description:

WR# 212301 Suggested Action

Description:

Verify relief valve setpoint correct.

EQUIPMENT:

Tag Name Tag Suffix Name Component Code Process System Code CD-99-2 HCLM/NS. VALVE COND REFERENCE ITEMS:

Type Code Item Desc WON 212301

Int... CONDITION[ REPORT jCR-iP3-.2O03o02685 Originator: Martin.Dustin Originator Phone: 5298 Originator Site Group: IP2 Operations Watch Staff IP2 Operability Requii-d: Y Supervisor Name: Buchal,Timothy J Reportability Required: Y Discovered Date: 09/09/2010 23:16 InitiatedDate: 09/09/2010 23:24 Condition

Description:

Due to CD-99-2 31 MBFP suction relief valve lifting during unit 3 plant trip C02 was discharged on 31 MBFP.

Immediate Action

Description:

Posted 5' with danger tape and set up blowers to ventilate 5'.

Entered TRM action statement 3.7.A.7 and implement required actions for having less than required amount of C02 Suggested Action

Description:

none

Ertf gy CONDITION REPORT FCR4P3-2010-02686 Originator: *MartinDustin Originator Phone: 5298 Originator Site Group: IP2 Operations Watch 'Staff IP2 Operability Required: Y Supervisor Name: Buchal.Timothy J Reportability Required: Y Discovered Date: .09/09/2010 23:30 Initiated Date: 09/09/2010 23:33 Condi-"i'ioDssci Otioin:

During Unit 3 trip IR 35 and IR 36 did trend as expected and are now pegged low.

Immediate Action D6ecripio6n:

Verified SR eneized as required.

WO!# 212303,212304 Suggested AcMAn

Description:

Trouble s9Vtand repair if necessary N35, and N36 EQUIPMENT:

Tiaik Name. Tag Suffix Name Component CodFe Process System Code NIS SYSTEM NIS REFERENCE ITEMS:

XType Code Item Desc WON 212303,212304

CORRECTIVE ACTION &,ASSESSMENT WE 41TE Rev 2 PAGE 1. OF 3' I I IIII *l'*COR "lRECI VEr*,ACTIONJ & S E S IIIIE TW II lll]:B *"SIT Re""'

" 2 P O;'3 "G. ...

...EVENT RECOLLECTION Event Oclurrec

==

Description:==

-v to m wi*eDaIe pt PERSONAL STATEMEIS Use as many sheets as you need. Try to address as many of these questions as may be appropriate. For those questions you cannot answer write 'dId not observe or *do notknokW Inthe question. Peas;e enter times when things happen so an accurate chronological time line can be reconstructed.

1. Mat happened? Concentrate first on what Wu saw or know first hand, but also Include 'whatyou heard'. Don't be concerned Ifthere are 'holes' or inconsistee In,your un tndng theevent C0+/-r~i~,-4 £ee t~~-9 )ec,. Ji~k 41 e eticA'&-',USJ-A 44t A 4 A- iP-3 3 L ,ie e I - f. (e,.

2. What caused oto be aware of the event?

3. What conditions existed just prior to the event (note any abnormal or unusual Ilneuo)l?

4. Did you notice any specific PARAMETER VALUES you think may be particularly important?

(] YES &-N-O Ifyou answered "YES', then explain:

5. Did you note any relays, annunciators, computer alarms, that changed state during the event?

Cf YES INO Ifyou answered 'YES', then explain:

CORRECIV ACIN A ASSE'SSMEot' W88-SI'T'E Rs2PGO Rev

. 2. PAGE

ý I 2ý OF 31

. 11 EVENT RECOLLECTION (conrd)

. WHEN did various events occur? Any times you remember may help us re-construct the Incident

-I

,41V ,+1 A ,ft * ,ce 4-. jie !*, . Lo? 1i,(,qt, 41 ,of d,*3

7. What happened after the event?

8. Did you notice ANY UNUSUAL SENSATIONS? Noises - smells - heat - moisture or mugginess?

C] YES +/-r*o If you answered "YESO, then explain:

9. WAS HELP AVAILABLE when you needed it?

&'.YES 0 NO tf you answered *NOO, then explain:

10. Were COMMUNICATIONS audible and clear? Did they help you understand what was going on?

&,/YES I0 NO if you answered "NO%,then explain:

11. Have you ever seen or known of this type of event before?

Y"ES 0 NO if you answered "YES*, then explain:

Pr4V11~f UfI OLJ- "'

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CORRECTIV ACTION &ASSESSMENT WE sr ,Rev 2 PAGE 3OF 3

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,,EVENT RECOLLECTION )cont')

12. Were hep 5 dures adequate?

[7 YES 0 NO If you answered "NO',then explain:

13. Was Itnecessary to take any actions outside established produres? Nso, document those actions here.

14. Do you know of anry lessons learned from this event?

0 YES INO ff you answered "YES', then identify lessons:

18S. Do you know W was on watch that might have Information on what occurred?

b'ES [0 NO Ifyou answered "YES', then identify Individual(s):

18. Is there any other information that you believe Is relevant from your personal observations and experience with this event?

0 YES [iNO If you answered "YES', then provide details:

Oee YI-10 Print Name and Sign Extension K Date Phone Phone Extension ,

II CORRMNAA CORRI...CTiIV ION &ASSESSMENTWEB: SITE ACT.....IO A SSSiEN WE S Rev 2 PAGE I OF 3 IITERv PAGE 10I PEVENT RECOLLEC.TION Event

==

Description:==

Event Occurrence: Date q Z~u ,. Time 2 Statement; %a_______A________"

Name:_MW______o Dept: ~-k.~

PERSONAL STATEMENTS Usewas many sheets as you need. Try to address as many of these questions as may be appropriate. For thsose questions you cannot answer w"tt'-'dld not observe" or "do'-notrkw In the question. Please enter times when things happen so an accurate chronological time line can be reconstructed.

1. heard W 1pDnt Concentrate first on what yo saw or know first hand, but also Include 'what you heard.". Dont be concerned Ifthere are 'holes" or Incornsistencee In your understanding, of the event C0 . L~J - -u&.g4up, iq ~jO~t~tw*P~

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2. Mt~s you to be aware of fthevent?

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3. What conditions existed Just prior to the event (note any abnormal or unusual lineups)?

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4. Did you notice any specific PARAMETER VALUES you think may be particularly Important?

0 YES 0l NO ifyou answered "YES', then explain:

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'CORRECE EVENTRIIE ACTION &&8BESSMEN1 COLLECTIO A, 00 WEB8tITE

. Rev 2 PAGE 2OFr 3 EVENT RECOLLECTION (cont'd)

6. E did various events occur? Any Umes you remember may help us re-construct theIncident.

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7. What happened after the event?

8. Old you notce ANY UNSUOAL SENSATIONS? Noises'- sm1ls- ieat - moisture or muggnes's?

03 YES 0 NO Nyou answered "YES, then #04pluln:

9. WAS HELP AVAILABLE when you needed It?

Q-i*ES 0 NO, Ifyou answered "NO', then explain:

10. Were-COMMUNICATIONS audible and clear? Did they help you undstand w;1hat Was gohng on?

[4AYES -10NO Ifyou answered "NO', then explan:

11. Have you ever seen or known of this type of event before?

3'ES 0 NO If you answered 'YES*, then explain:

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- U-CORREGTIY ACTION & ASSESSMENT; WEB SITE Rev 2 PAGE 3 OF 3 EVENT RECOLLECTION(cont'd)

12. Were the procedures adequate?

[3'YES 0 NO if you answered *NO", then explain:

13. Was Itnecessary to take any actions outside established procedures? If so, document those actions here.

14. Do you know of any lessons learned from this event?

0 YES GrI0O If you answered 'YES', then.Identify lessons:

15. Do you know WHO ELSP was on watch that might have Infornation on what occurred?

[9* 8 I0 NO If you answered "YES", then Identify Individual(s):

1a. Is there any other Information that you believe Is relevant from your personalobservations and experience with this event?

[I YES [N0 If you answered 'YES, then provide details:

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Event Occurrence: Date 9z Time .I. .. mew mat/rv, "tate Name:,-V -4T)- Position. 5TA 0e,'O PERSONAL STATEMENTS Use 0as many sheets as you need. Try to address as many of these questions as may beappropriate. Fork, those quuestions you cannotanswer write "did not observe' or "do notIknow" Inth equistilon. Please enter times wihen things happen so an accurate chronological time lIe,can be reconsb.uctid..,

1. What h~owened? Concentrate first on what A' saw or know first hand, but also.Include "what you heard". Dontbe concerrnedlfthere are "holes' or lconslsd yf lnysIn tndtiitaindlg Of' i L 0~ *tAZ Ta levo + te~~~~~k~ M~~~c~I'31~O1~~(~ ~

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3. What conditions existedjust, prio-.to -eprent(note any abnormalor unusual.Iineupol? u-.: .

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4. Did you notice any specific PARAMETER VALUES you thInk may be particularly Inportant?

El YES NO tf1yo*u answered "YES",Athen explain:

5. Did you note any relays, annunciators, computer alarms, that changed state during the eveni?

D YES P'No If you answered "YES", then explain:

CORRECTIVE ACtION & ASSESSMENIT.WEBST Rev Rv 2 PAGH AG22 OF 3ý EVENT RECOLLECTION (cont'd)

8. WHE did various events occur? Any times you remember may help us re-construct the Incidont.

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7, What happened after the event?

S. Did you notice ANY UNUSUAL SENSATIONS? Noises - smells - heat - moisture or mugginess?

Q YES [*'NO If you answered *YES", then explain:

9. WAS HELP AVAILABLE when you needed it?

[(YES 0 NO Ifyou answered "NO0, then explain:

10. Were COMMUNICATIONS audible and dear? Did they help you understand what was going on?

0"YES 0 NO Ifyou answered "NOI, then explain:

11. Have you ever seen or known of this type of event before?

[5YES 7 NO Ifyou answered "YESO, then explain:

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12. Were the procedures adequate?

&("YES 0 NO Ifyou answered "NO", then explain:

13. Was Itnecessary to take any actions outside established procedures? ifso, document those actions here.

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14. Do you know of any lessons learned from this event?

[I YES [ANO If you answered "YES', then Identify lessons:

15. Do you know WHO E= was on watch that might have Information on what occurred?

[S/'YES 0 NO If you answered "YES",then Identify Individual(s):

. . ....  ; _, - . *d q m ,.-, C . .. .. , . ,,,e-e.--

18. Is there any other information that you believe is relevant from your personal observations and experience with this event?

0 YES ["/NO If you answered YES', then provldedktails::

Print Name and Sign,,, Date, Phone Extension

r7 CORRECTIVE -ACTION &ASSESSMENT WEB SITE Rev 2 PAGE: i OF 3

/EVENT RECOLLECTION Event Des~opton: Plea- / e b'

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Event Occurrence.: Date 7/r//'9 Time 21,2 -7 Statemne fl'rm Xy -~

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Name: C A ýr-j Position 69e Lf - Dept: z L. .

PERSONAL STATEMENTS Use as many sheets as you need. Try to address as many of these questions as may be appropriate. For those questions you cannot answer wrtIe "did not observe" or "do not knw In the question. Please enter times when things happen so an accurate chronological time line can be reconstructed.

1. What hopened? Concentrate first on what =' saw or know first hand. but also Include "what you heard". Donl be concerned Ifthere are "holes" or Inconsistencies In your understanding of the event.

2. What caused you to be aware of the event?

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3. What conditions existed Just prior to the event (note any abnormal or unusual lineuos)?

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4. Did you notice any specific PARAMEIE VALUES you think may be particularly Important?

0 YES C0 NO If you answered 'YES", then explain:

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5. Did you note any relays, annunciators, computer alarms, that changed state during the event'?

UýYES El NO If you answered "YES', then explain:

"CORRECTIVEACTION &ASSES SMENT WEB'8IITE- "--"

ý"R 2-PAGE*2ZOF 31,

. dEVENTnRECOLLECTION (coh t ud)

6. WI did variouse~vents occur?. Any times you, rememrber may hepu enstruct the Incident.

SY? // ~

7, What happened after the event?

8. Did you notice ANY:UNUSUAL SENSATIONS? Noises - smells - heat - molsture or mugginess?

0 YES N*-* f you answered,YES then explain:

9. WfAHQ E )LP AVILABLE when -you needed It?

["'SY NO if you answered NO0, then explain:

10. Were COMMUNICATIONS~audibleand clear? Did they help you understand what was going on?

(2/ES 0 NO If you answered "NOO, then explain:

11. Have you ever seen or known of this type of event before?

(B<ES C] NO If you answered "YES", then explain:

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CORRECTIVE ACTION & ASSESSMENT WEB SITE Rev2 PAGE 3 OF 3 9:V9: KT 19rFClfl I (Tfl)Nl Ir nfntirl

12. Were the r eures adequate?

r'YES C) NO Ifyou answered "NO", then explain:

13. WAstnecessary to take any actions outside established procedures? Ifso, document those actions here.

14. Do you know of any lessons learned from this event?

0 YES [INO If you answered -YES', then Identify lessons:

15. Do you knQwW LSF-was on watch that might have Information on what occurred?

0'YES 01 NO If you answered "YES", then identify Individual(s):

1e. Is there any other Information that you believe Is relevant from your personal observations and experience with this event?

C) YES G3NO If you answered *YESO, then provide details:

Print Name and Sign 7>-. Date Phone Extension I

TOMP I ese-

• T0400A.CFMS 548.16 DEG F O i0420A.CFMS 548.34 DEG F

• T0440ACFMS 547.69 DEG F 0 T0460A.CFMS 54r,.84 DEG F

• P0480A.CFMS 1700.

PSIG 2239.

PSIG 2255.

PSIG

• RCLA TEMP AVG

• RCtB TEMP AVG

• RCLC TEMP AVG o RCLD TEMP AVG w PRESSURIZER PRESSURE C PRESSURIZER PRESSURE

'PRESSJIRIZER C"RES$URE A PRESSURIZER PRESSURE

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EVEL o PRESSURIZER 2 LEVEL

• PRESSURIZER 3 LEVEL o PRESSURIZER LEVEL SETPOIP",

20 120 120 120 2.E-04 3.E-0N I.E05, 1.E+05 .

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• POWER RANGE CHANNEL 41: OU o POWER RANGE CHANNEL 42: OU

• POWER RANGE CHANNEL 43: 0U o POWER RANGE CHANNEL 44: OU w INTERMEDIATE RANGE DETECTO

• INTERMEDIATE RANGE OETECTO A SOURCE RANGE DETEC rGH N,_*

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DEG F

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. T002 1A.CFMS 58%8 OEG F

- T0023A ,CFMS 561.33 DEG F 5,4, I 1 553.67 CFMS I AII-- -- - - it -- -- - .II L - F DEG I- .-1~.L--~---A- --it 'I- - -- ___

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• HIGHEST OSPDS REP TEMP

!N CORE TEMP E03

• )N CORE TEMP E1

N CORF "FEMP F IP

• IN CORE TEMP K03

-;IN CORE TEMP LOI N CORE TEMP P13

0 T0034A.CFMS 557.25 DEG F

- T0035A.CFMS 556.67 DEG F

, T0037A.CFMS f~E.2------------~~-..--.---,-..--.-..---.---..__....-~-.--..--- ---.-- - --- 555.

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§ IN CORE TEMP AlI IN,'COPRE TEMP 806

[IN.CORE TEMPCI2

• +/- Cý6.oRF~ !IMpnQ09 a IN CORE TEMP E05 NG CORE TEMP F05

• ~NCORE TEMP H05

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• T0052A.CFMS 55725 7 --

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DEG.F ci TO .IA.CFMS 556.

DEG F

• T0054ACFMS 116.

DEG F T0060A.CFMS 5*55 nFEc F

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9/9/2010 9:00:00 PM 1.42 Hour(s) 919/2010 10:25:00 PM

• IN CORE TEMP J07 o IN CORE TEMP K 11

• IN CORE TEMP K13 - IN CORE TEMP N02 U IN CORE TEMP RIO

2 ~ 120 0.5 PSIG CP1001A.CFMS

• P1002A.CFMS 0.37241 PSIG Pt I003A.CFMS 0A7339 PSIG 0 P I1004A.CFMVS 0: i7704 PSIG

-iP1005A.CFMS 9.8901E-02 PSIG 111.82 DEG F

~L

• 1 i -1 .-1 70 9/9/2010 9:00:00 PM 1.42 Hour(s)

• CONTAINMENT PRESSURE LOOP o CONTAINMENT PRESSURE LOOP CONTAINMENT PRESSURE LOOP iG:0ONTAINMEN7 PRESSURE LOOP

• CONTAINMENT PRESSURE LOOP Q CONTAINMENT PRESSURE LOOP

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A'iCONTAINMENT TEMPERATURE CH

JFlow Steamn I Feed 1400 *F0405A.CFMS 0.

KLBIHR F0425A.CFMS 424.

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E KL&/HR K! S§HR 11F0403A.CFMS 0.

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,919/20109900:00)PM 1.42 Hour(s) 9/9/2010 10:25:00 PP

• SG #31 STEAM FLOW

,: SG #32 STEAM FLOW

• SG #33 STEAM FLOW S,. If-14 S I FAM V-1, OW a MAIN FD FLOW TO SG #31

• MAIN FD FLOW TO SG 432 MAIN FD FLOW TO SG 434

Ii II.

19'9/2010 9:00:00 PM

• STM GEN #31. LVL NR fi STM GEN #32 LVL NR 4,STM GEN #33 LVL NR

• ,S'[M GEN 0J34,MV Nfl SG #31 FEED WATER CONTROL SG #32 FEED WATER CONTROL SG 034 FEED WATER CONTROL

• F1200A.CFMS GPM

~F1201A.CFMS GPM

• F1202A.CFMS 64.3 1203A.CrbMS GPM m ZH4O6AD.CFMs 42,333 PCTCL ZH4068C).CFMS 36.177 PCTCL

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• AUX FD FLOW TO SG #31 AUX FD FLOW TO SG 032

• AUX FD FLOW TO SG 433 AUX F)Di-L OW r0 SG h34

• AUX FEED TO SG #31 AUX FEED TO SG V32 AUX FEED TO SG #34

ICharging Pump Status

'2

• i. -- ____________________________- __________ __________________________________

• Y0100D.CFMS OPEN SY0101 D.CFMS OPEN

• Y0102D.CFMS CLOSED

[

I I V

1 201 9/9 0 PM ,1.42 C:A0:0 Hour(s) 9t9Y2010 10:25:00 PM

-CHARGING PMP A BKR o CHARGING PMP B BKR

• CHARGING PMP C BKR

iReactor Trio Breaker Il

• YOOO6D.CFMS I OPEN Y0 007D-CFMS OPEN 0.6-K- - -- ____

F-I.- ____ ______________ ___________________ ___________________

01 919/ 0 9:00___0 ____ _.42  ::' ."ors "* 91912010 10:25:00 PM S REAC MAIN TRIP BRKR A ',) REAC MAiN I RIP BHK*R B

- . .- ~- ____