ML12214A584

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2012 Prairie Island Nuclear Generating Plant Initial License Examination Administrative Files
ML12214A584
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/14/2012
From:
NRC/RGN-III
To:
Shared Package
ML11354A142 List:
References
Download: ML12214A584 (38)


Text

2012 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE FILES

tl Xcel Energy*

JUL 19 2012 L-PI-12-064 NUREG-1021 Regional Administrator, Region III U S Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 2012 Initial Operator Licensing Examination Security Agreement Forms Pursuant to NUREG-1021, Revision 9, Supplement 1, Operator Licensing Examination Standards for Power Reactors, section ES-201, Initial Operator Licensing Examination Process, the facility licensee must submit the original examination security agreement forms to the NRC's regional office for retention after the examinations are complete.

Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits the original signed examination security agreements as Enclosure 1.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

~E~M~

Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Dell McNeil, US NRC Region III, with enclosure Hironori Peterson, US NRC Region III, without enclosure JUL 2 3 2012 1717 Wakonade Drive East

  • Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE 1 Original Signed Security Agreements (Form ES-201-3)

From the 2012 Prairie Island Nuclear Generating Plant (PINGP)

Initial Licensing Training (IlT) Examinations 5 pages follow

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\J ES*201 Examination Security_Agreement Form ES*201-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of s/'II of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the

"'4 as of the date NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration. except as specifically noted below and authorized by the NRC (e.g.* acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide director indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of~" .orb,ln. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE NOTE

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ES-201 Examination Security Agreement Form ES-201-3

1. Pre*Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of

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j z" as of the date of my signature. I agree that! will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. ! understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post*Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of'S"" 15'1,.,111*. From the date that I entered into this security agreement until the completion of examination administration. I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

ES*201 Examination Security Agreement Form ES-201-3

1. Pre-Examination ,I

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I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of ;Jfrt{tJ... as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ofsh'o-rhdrt.- From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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S;~F2~~l" 5'5 ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3

1. Pre* Examination Sl/'f~.e.. ct I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of '!l.2.ilj.".., as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e,g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2. Post*Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ofS1H(~kJromthe date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

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. .I ~noW!edge tl)at 1ha~ ~uir~d specialized ktrowledge aooutthe NRC licensing eXanlNtions seheduJed fQr~we~($)of fht.'/I'k"'as of the date ofmy~natu;e, t agree that .l Will no1.knu~gly Qivulge <!ny lm~rt.nattoll' about thee ~Inatlons to any peroo:tls Who have not been autllOr~dby 1I1e NRC <:ti!efexamlner, I understandtha11ar:n oot to instruct, e~te, or provide p~rfGtmance feedbaCk to those appficant,$ .schedule~ mba. adminiStered these licensing '6Xamjnations from this dateufltil complellonofe~a~on admlnlstration:, except asspeotfic~ noted below aM authorIZed by the NRC (e;9" acting as a sifTUllatorboollJoperafor orcommunioator is <i\o(1l:fptable. If the indIVidual ooesl'lot s~e.ct the~ ~onl:ento(pro\l!de 4Ife~ Qr indif:est feedbaCk).. ru;thermore. I am aware of the physlC;'![ securitY measures and' requirements {as dUQ~rnedinthe facilitY li~tll\ee's proceGlw:es). anq understand that vlotation*offhe ttQn(!ltloflS of this <ilgreemerWmayres\llt \Tl~l{ation of the exammatlolia andfO'r aQ Eitlf~ementaetlo!'lagaltl$t me or the facility Hce.nsee. (wit! immediately rfiport to faci\1tY management or Ule NRC Chief exalt:l:lner'any im:!ic.atiqp~or suggesUona that examltllii!tion security

, maY have b~en compr?"'lised.

2, PoSt.oElmminstiQ!l

-.'~ , T(} th~best ot,my knowle~, [dto notdiWlgeJoany unauthorized :p~tSQI'l$ anyfrdi~m1atlOtiOOnce:minst~NFtC fleerlsfl'llJ~mlnatl9trsadmini~

'. ;';, , ~u.rll'lg the week(a} ofS1dr~k.J'rom.th~dafethatl enteretlY !n~ thissecurltyi3.remenl wntilth~.~iilltion~f~~aminatiOl'lac!minlstration.J~g not'

, ,instruct, evaluate, or proVide per1'orltl$l1ca feedback to those ~l'Plicants ~ were edminlstered1heS=lteeJ'lsmge~oallons, eX'capt as.5pceQlfically noted

, , bek:!w atidauthorlZed by the NRC. '

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Es-m1, ~ Z'1 of 28 I

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Initials Item Descri tion a b c

1. k4t;4, ,.1/" ~
2. Answer key changes and question deletions justified and documented 11;11;~ "fA ),..t
3. Applicants' scores checked for addition errors reviewers s ot check> 25% of examinations 4:~ p/,. ~
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail ;fty?' ,,~ ~
5. All other failing examinations checked to ensure that grades are ustified Iv )J/A .)1-.
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed b half or more of the a licants J11~ w/A ..J,4v Printed Name/Signature Date
a. Grader M. Bielby / JbiJtM{; ~!;jIZ--
b. Facility Reviewer(*) n/a .,h..
c. NRC Chief Examiner (*) D. McNeill ~~41?~@ ~fpg!P'2
d. NRC Supervisor (*) --t:"5100t1t.,L I~ ~/(;;-4cJ-(*) The facility reviewer'S signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

The following pages were hand delivered to the chief examiner and comprise the Prairie Island Nuclear Generating Plant post-examination comments. No cover letter was provided with the submission.

2012 Prairie Island NRC ILT Exam Feedback Question #54 Student Comment:

MV-32314 & MV-32315 close at 80# in their respective air receivers (121 & 123), 121 and 122 Air Compressors are normally running, with 123 in standby. Without knowing receiver pressures, it is reasonable to assume that 123 Receiver lowered blow 80# before 121 receiver, closing MV-32315, isolating the leak and allowing 121 Receiver pressure to recover before dropping below 80#. If this is the case, answer C is also correct.

Prairie Island Response:

Disagree with student comment. Stem of the question clearly indicates a header pressure on both Instrument Air headers that would result in their associated isolation valves closing.

Attached:

Question 54 QF-1040-13, Exam Feedback Form

QF-1040-13 Revision 2 (FP-T-SAT-40) Page 1 of 1 Ifl XcefEnergy-1 EXAM FEEDBACK FORM Initiator's Name:

Evaluation ID: _ _ _ _ _ _ _ _ _ _ Question No. ~5~4..:..-______

Commetlts & Recommendations """-313 \L\ ¥ rJ\.\!- 32.3 \S L\AS~ a-.k 'is01t \ tl \~f,I"R v,~~ t.

A.\'R. ~ ~t..(.,~'\Iat~ (\1..\:t-\'l..l), \1.\.1.1'"\1:1.. A\R L~{l\r\',t.S)QR) A'i!.1a tJa~Ml-L.I/\ 1\O\.llolu*1 (,..;ItJII" \1..3 IN S'i)I~~V,. \,J\1'"i-\ou', \("\\i)*.H"l(,. \lE.t:~.\"t." ~r...~~liltE.!r.! 'i"f\~ ~~"l,~.~ 10 ~~')u,",E il-\A:i \1.3 R.e..("E.l.vE"-. Lq-JE\l.....E-V ""%-\..{)>J ~C#f. i>e.~o~<G. \1...\ \<--t-.("e\'lft; it I (A..o)\~ is" .1'\ \I ~ )').:~ 15. \S{) \.. ~"'N (...

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DO NOT WRITE BELOW THIS LINE lfor Training Department Use Only)

Resolution & Comments: Question ID: _ _ _ _ _ __

,0 No Action Required o Evaluation Change 0 Question Change

References:

Resolved By Instructor Date Reviewed By:

SME Date Approved' By:

Training Supervisor Date (Provide copy to initiator and file with exam key.)

Retention: Life of Plant

REACTOR OPERATOR Page 55 of 102 Question# 054 Given the following conditions :

There is a leak on Unit 2 Instrument Air to Containment.

f'Mi",p~~r~ .

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Unit 2 Instrument Air pressure continues to lower.

Unit 1 Instrument Air pressure is rising.

REACTOR TO ~E .. C70f\

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FTER ...., MOISTUR= A!'>ER MOISTURE t~~R ~E~.l..RATOR [OOLER $!:PARA TOR COO LER SEPARATOR INSTRUMENT AND STATION AIR SY STEM Which of the following could jeopardize the UNIT 1 instrument air supply?

a. Opening MV-32321, 11/21 INSTR AIR HDR ISOL VLV.
b. Opening MV-32314, INSTR AIR HDR ISOL VLV A.
c. Opening MV-32315, INSTR AIR HDR ISOL VLV B.
d. Closing CP-40-7, STATION AIR RECEIVE X-CONN TO INSTRUMENT AIR.

2012 Prairie Island NRC ILT Exam Feedback Question #54 Student Comment:

MV-32314 is and has been a valve open breaker motor [open] valve for some time.

Therefore, per the question, by MV-32315 opening would also be a correct answer.

Recommend accepting 2 correct answers.

Prairie Island Response:

Agree with student comment. Recommend accepting 'A' and 'C' as correct answers.

Multiple unique circumstances led to this recommendation.

1) MV-32314 has been Valve Open Breaker Open since August of2010 (almost 2 years).
2) During the performance of the exam, the candidate submitting the feedback asked if their response to a question should be based on theory or "how the plant would actually react." The response given was to refer the candidate to the rules read at the beginning of the exam. Specifically the following passage:

"Finally, answer all questions based on actual plant operation, procedures, and references. If you believe that the answer would be different based on simulator operation or training references, you should answer the question based on the actual plant."

3) Interview with candidate indicates choice of Distractor 'C' was based on these considerations.

With these extenuating circumstances, Prairie Island believes it is appropriate to accept

'A' and 'C' as correct answers in this instance.

Attached:

Question 54 QF-1040-13, Exam Feedback Form Copy of the Candidates question with Exam Administrators response Work Order/Clearance Order associated with MV-32314

QF-1040-13 Revision 2 (FP-T-SAT-40) Page 1 of 1 Ifl Xeel Energy- I EXAM FEEDBACK FORM Initiator's Name:


ID:

Evaluation 10:20 (']... N Rt RC> fe> T Question No. --,-S-~--11,--,----

Comments & Recommendations f\ V - 313 , 4 I' j o...,.,A kcU b<"~ ,.,. 0.. Va.. h. e. (j pe f\ tl {tG. k."e.f jVLo for

\Ja.\\l.e $-e<:...e {!..CH" Sc_c. +~Me. Th-erc:. f.ore., fer ike.. f lle/ i-\'4'" I by fW\v-1c2.3'Sop~1\~"', \vou\cl ~\.stJ be. ~ CorN~C+ Ci."swer:

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DO NOT WRITE BELOW THIS LINE (for Training Department Use Only)

Resolution & Comments: Question ID: _ _ _ _ _ _ __

.0 No Action Required o Evaluation Change 0 Question Change

References:

Resolved By Instructor Date Reviewed By:

SME Date Approved By: .

Training Supervisor Date I (Provide copy to initiator and file with exam key.) I Retention: Life of Plant

REACTOR OPERATOR Page 55 of 102 Question# 054 Given the following conditions:

There is a leak on Unit 2 Instrument Air to Containment.

A Instrument Air Header Pressure dropped to 73 psig.

B Instrument Air Header Pressure dropped to 74 psig.

Unit 2 Instrument Air pressure continues to lower.

Unit 1 Instrument Air pressure is rising.

REACTOR 6:J1LDiNG TO UN!":" 1 Te, CONTRO:" COMMON TO UNIT::-

SCREENHO-Une: ROOf.! SE:RV:Cf;S Ut FROM

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AFTER MOISTURE COOLER SEPARATOR INSTRUMENT AND STATION AIR SYSTEM Which of the following could jeopardize the UNIT 1 instrument air supply?

a. Opening MV-32321, 11/21 INSTR AIR HDR 1S0L VLV.
b. Opening MV-32314, INSTR AIR HDR ISOL VLV A.
c. Opening MV-32315, INSTR AIR HDR (SOL VLV B.
d. Closing CP-40-7, STATION AIR RECEIVE X-CONN TO INSTRUMENT AIR.

Facility PI Unit: 0 WORK REQUEST Request Date :r=9i7l!7!!J Time: 12:02 00059659 Requestor BYSTROM E WR Status ACTIONED Priority 3 PRINTED: OS/23/2012 Job Type CC PAGE 1 Defect/Request: ~ MV~~%~J STA AIR HDR ISOL MV A l'lork Against Information:

Unit:O Equ i P I D: 1iJ'"'""".,........ Equip Type: MV System:SA Name:STA AIR HDR ISOL MV A Mfr Model:

Serial UTC II: TS/SLC ReI: N Location IN 3" LINE E . 3/B.5 Eq Tag: Eq Alt Tag:

Deficiency Tag/Locn:33299 ON MV-32314 Work Planning Details:

planner Need Date 02/14/2011 A Mode Train Ops Review Y Discipline: MECH Unit Cond Rq: ANY LCO N Work Authorization:

SRO Authorization: Date: ___________________

(PassPort ID/Signature)

Reqs/Regs Value Comments Work Request Attributes: Value UOM Type Notes A.4 MANAGEMENT PRIORITY 4B ATRB ARDEC CC ATRB AR ITEM NO 01245144 ATRB Additional Description/Work to be Performed:

tiliiYli!¥)lk':JJiill~WliU:~9' see also CAP 1245144 and attached photos with no air leakage noted The component that broke was determined to be a coupling between the actuator shaft and the valve stem. The coupling was observed to fail at the start of

trying to close the valve as PMT for a breaker PM. Coupling did not move, s o valve should be open. Actuator shaft was observed to rotate in the clockwi se direction (when looking at the valve from the top) while trying to close t he valve.

uat'br, ly. ~"l¥ ;opiNtllI:bhe 1ii1'!!ra~~$~. _t.n_tM-...epo.n~ . Progress to work order to replace the valve. Niebeling and Prigge .

Work Plan Approval:

Approved By N129672 Date 08/20/10 Time 13: 30

Clearance Order: 00040030 000 01 Printed: OS/23/2012 Page: 1 CLEARANCE ORDER BOUNDARY Facility: PI Uni t  : 0 Op System: SA System: SA Division : Area  : Class :

Equipment Type  : MV Component Type  :

Equipment Nwnber: ~32.3.14 Component Nwnber:

Equipment: - 23.104 ,r STA AIR HDR ISOL I'1V A o TURB 705 IN 3" LINE E.3/8.5 Work Against: E EQUIPMENT Facility  : PI Unit: 0 Op System : System:

Work Item : Equip. List: UTC:

Mfg./Mod.  :

Name  :

Client  :

Location  : IN 3" LINE E.3/8.5

r-v C/o Title Prepared By  : DVSM09 DAVIS M A Assigned To  :

Tag Type Nwnber Tag Type Nwnber Tag Type Nwnber CTS 1 Total Tags: 1 Topic  : DESCRIPTION Last Updated By : BJRBOl Last Updated Date: 01/27/2011 WO-00411786 Topic  : PLACEMENT INSTR Last Updated By : BJRB01 Last Updated Date: 01/27/2011 Topic  : PLANT IMPACT Last Updated By : BJRB01 Last Updated Date: 01/27/2011

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Chk Chk Tag Required List Seq Action Type No. Position

-u u u, nIU'f~ - ~.]; ~ 0-0 Equip: rr~s- STA AIR HDR I SOL A IMV:-:::iZ3 OP/AUTO/CL CS 0 CONTROL PANEL A ACTUATOR TO VALVE STEM COUPLING FAILED.

PRAIRIE ISLAND NUCLEAR GENERATING PLAtH t..8NORMAL OPERATII~G PROCEDURE NUIViBER:

ELECTRIC POWER SYSTEM OPERA TfNG RESTRICTIONS C20 <3 AOP4 i AND UMfTATfONS LOSS OF REV: 6 2RX TRANSFORMER Page 4 of6 2.5 Recovery Actions No change is required to the Security Analysis voltage setpoint.

2.5.1 Notify Technical Engineering of the loss of 2RX Transformer and request their support in recovery.

2.5.2 Record the foliowing information for later evaluation:

  • Control Room alarms and relay targets
  • Local alarms and relay targets In the Plant 2.5.3 Verify BKR 21-4 is OPEN.

2.5.4 Verify BKR 22-4 is OPEN.

2.5.5 Verify BKR 12RXBT is OPEN.

in the Substation 2.5.6 Verify/OPEN 2RSX, 34.SKV GCB, by observing the green indicating light illuminated on Panel 23E.

2.5.7 Verify locally that 2RSX is OPEN.

2.5.8 OPEN 2RSX-B/DISC SW, 2RSX RES AUX XFMR 34.SKV B DISC.

In the Plant

'.. -~.; ',,-~ :.:: ' 5,' :;: .' WITH THE COMPLETION OF THE FOLLOWING STEPS,

. ' .. ' ::.-: ;: ,. ... . :. ,.'.- BUSES 21 AND 22 MAY POTENTIALLY BE SUPPLIED BY

" . .." "" ';;::;~;;>;i,:::('" . THE 1RX TRANSFORMER. WITH BUS~ 21 AND 22 CROSS CAlJ110N.: ' TIED TO UNIT 1, THE 1RX WINDING MAY BECOME

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... , .' ,," . ,,- , .., .. . : .: OVERLOADED IN THE EVENT OF A PLANT TRIP AND THE

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SUBSEQUENT AUTOMATIC TRANSFER OF THESE BUSES FROM 2M. REFER TO A ITACHMENT 1 FOR GUIDANCE TO LIMIT OVERLOADING, 2.5.9 GZO.~ection:s .9 Transfer of 4.16KV Busses 21 and 22 to 1R Transformer from 2RX Transformer up to the step which closes 12RXBT.

PRAIRIE ISLAND I>!UCLE.lIR GEh!:=RATlh!G PLAtH OPERATING PROCEDURE I ""UMBER:

2C20.5 C UNIT 2 - 4.16KV SYSTEM REV: 24

. . ..... Page 18 of 59

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" .. '.' ,'" . THE 1RX TRANSFORMER, WfTH BUSES 21 AND 22 CROSS

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TIED TO UNIT 1, THE 1 RX WINDING MAY BECOME OVERLOADED IN THE EVENT OF A PLANT TRIP AND THE

, . . :::<i'~, . '.~. ;".,! SUBSEQUENT AUTOMATIC TRANSFER OF THESE BUSES

..Of "~" '~'''''(-'.~ '1:l'~ ' FROM 2M I (9

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~*~';*~::~{,:';::;:.;2~FI~; ~ .RL 5.9.16 Rack BKR 21-4, 4.16KV BUS 21 2RX XFMR, to "CONNECT'.

5.9.17 Rack BKR 22-4, 4.16KV BUS 22 2RX XFrvlR, to "CONNECT".

5.9.18 Place CS-46829, 4.16KV BUS 21 2RX XFMR, in "NORMAL".

5.9.19 Place CS-46830, 4.16KV BUS 22 2RX XFMR, in "NORMAL".

PRAIRIE ISLAND NUCLEAR GENERATING PLAI\T OPERATING PROCEDURE

"'UfvlBER:

2C20.5

. . .. . C UNfT 2 - 4.16KV SYSTEM REV: 24 Page 57 of 59 Attachment 1 Guidance To Limit Loading On 1 R PURPOSE This Instruction will provide direction and guidance in mitigating the potential for overloading the 1 RX and 1 RY transformer windings and the associated bus ducts when either the 12RXBT or the 12RYBT bus ties are required to be used due to loss of either the 2RX or 2RY transformers .

The bus ducts that connect the 1RX and 1 RY transformer windings to the plant electrical system and the associated transformer windings are rated at 3000 amps maximum current.

In the case when either the 2RX transformer or the 2RY transformer is out of service, we must cross tie from Unit 1 via the 12RXBT and/or the 12RYBT bus ties which can potentially cause the associated 1 R bus ducts to exceed the maximum current rating .

GUIDANCE FOR OPERATION (2RX OUT OF SERVICE)

The 12RXBT ties the large motor buses (11 , 12,21 and 22) together. The only loads supplied by these buses are the Reactor Coolant Pumps (RCPs) and the Feed Water Pumps (FVVPs) . The bus duct and the associated 1RX winding is designed for 2 RCPs and 2 FWPs as a maximum load, therefore whenever the 2RX transformer winding is not available and the 12RXBT is closed, limit loading as per Table 1.

Table 1 Total Large Motors Running (Unit 1 + Unit 2) 3 RCPs - 0 FWPs 1 RCP -1 FWP 2 RCPs - 2 FWPs 1 RCP - 0 FWPs 2 RCPs -1 FWP o RCPs - 4 FWPs 2 RCPs - 0 FWPs o RCPs - 3 FWPs 1 RCP- 3 FWPs o RCPs - 2 FWPs 1 RCP -2 FWPs o RCPs -1 FWP Table 1 lists all possible combinations of RCPs and FWPs (not necessarily allowed combinations) that will maintain an acceptable current loading of less than 3000 amps on the 1RX winding and bus duct. RCPs and FWPs that cannot be allowed to operate should be secured by placing control switches in OFF and/or PULLOUT with Secure tags attached to prevent motors from starting and creating an overloaded condition on the 2RX transformer and bus duct. &:ImHDiJW'~tatSt!m~E:tt1e:Et..s dlI_ka::(lin~~I~bf<'-'"Ht~ - e*~'I--W' 1:CJ~8:E:a:rKtirtmled draJ[JSfE! c . :J:m:s omp ,

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