ML20209H624
| ML20209H624 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/16/1999 |
| From: | Bies M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9907210032 | |
| Download: ML20209H624 (600) | |
Text
UNITED STATES
- pa stoqt NUCLEAR REGULATORY COMMISSION i
$' % REGION til I f
e y 801 WARRENVILLE ROAD LISLE, IttlNOIS 60532-4351 l
%...../
July 16,1999 I
NOTE TO: NRC Document Control Desk
~
Mail Stop 0 5-D-24
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FROM: Mary Ann Bies, Licensing Assistant Jfg Operations Branch, Rill
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINISTERED THE WEEK OF MAY 17,1999 AT PRAIRIE ISLAND, DOCKET NOS. 50-282 AND 50-306 During the week of May 17,1999, Operator Licensing Examinations were administered at j the referenced facility. Attached, you will find the following information for processing i through NUDOCS and distribution to the NRC staff, including the NRC PDR:
Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070.
b) As-given operating examination, designated for distribution under i RIDS Code A070. l item #2 - Examination Report with the as-given written examination attached, designated for distribution under RIDS Code IE42.
Attachments: As stated h
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9907210032'99d716 PDR ADOCA 05000282 V PDR
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AS-ADMINISTERED OPERATING TEST PRAIRIE ISLAND EXAMINATION - WEEK OF MAY 17,1999 i
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AS-ADMINISTERED ADMINISTRATIVE JPMS PRAlRIE ISLAND EXAMINATION - WEEK OF MAY 17,1999 l 1 l
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Prairie Island Nuclear Station Date of Examination: May 17.1999 Examination Level (circle one): RO Operating Test Number 1999301 Administrative Describe method of evaluation:
Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct of P "
Rea ty Determine Dilution for an Estimated Critical Condition Control Conduct of Ope a "
p e e initiate a Temporary Change to a Procedure Changes A.2 P Con CP Determine Actions to Remove RCP Thermal Barrier HX from e ce Control A.3 Radiation Control / LHRA Prepare for Entry into a Locked r * "adiation Area Entry A.4 Emergency Plan / Initiate Emergency Local Evacuation Evacuation
PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET I
1 TASK TITLE: Determine Dilution For An Estimated Critical Condition JPM NUMBER: ADMIN-1.1 Rev. O l
RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 0040060101 KIA NUMBERS: 2.1.23 i APPLICABLE METHOD OF TESTING:
Simulate Performar,ce: O Actual Performance: @
Eva'uation Location: Turbine Building: O Auxiliary Building: O Simulator: O Control Room: O Other: Anywhere @
Time for Completion: 10 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
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Resp Grp: O Page 1 of 5 Assoc Ref: PITC TP 3.7 e i
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- l Det rmina Dilution For An Estimated Critical Condition l ADMIN-1.1 Rev. 0 l Operator: (SRO / RO / NLO)
Evaluator:
1 Date: _,
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS: 1 o The shutdown banks have been withdrawn to 228 steps in preparation for a Reactor startup. l c Current RCS boron concentration is 1300 ppm. j o An ECC has been completed and verified.
INITIATING CUES: l o The SS directs you to calculate the number of gallons of water needed to reduce the RCS boron concentration to the given ECC boron concentration and the dilution water flow rate necessary to perform the dilution in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per 1C1.2, step 5.5.5.
o Report the results to the SS. ;
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PITCO-089 Page 2 of 5 Rev 5 10/98 L j
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a l- ' l D:t:rmina Dilution For An Estimated Critical Condition l ADMIN-1.1 Rev. 0 l l
JPM PERFORMANCE INFORMATION R: quired Materials: Completed ECC with critical boron concentration at 1000 ppm.
l General
References:
1 C1.2, C1 A, C12.5 Tcsk Standards: 8,000 (t 1,000) gallons of water at 85 (t 10) gpm determined to be l necessary to dilute to ECC boron concentration in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
l Start Time: _
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid
, prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
l NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Pcrformance Step: Determine boron concentration change to be made. .
Critical X (S-1) 1 Standard: 300 ppm dilution determined necessary to change RCS beron concentration (1300 ppm) to ECC boron concentration (1000 ppm).
Performance: SATISFACTORY UNSATISFACTORY Comments:
P:rformance Step: Estimate the quantity of reactor makeup required to accomplish the Critical X (S-2) desired concentration change.
Standard: 8,000 (i 1,000) gal" is determined to be the quantity required to dilute 300 ppm using the 1-igure 6 (hot) nomograph.
Paformance: SATISFACTORY UNSATISFACTORY Comments:
i PITCQ-089 Page 3 of 5 Rev 5 10/98 j
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l Det:rmino Dilution For An Estimated Critical Condition l ADMIN-1.1 Rev. 0 l Performance Step: Estimate the reactor makeup flow rate required for the desired rate of Critical X (S-3) change of boron concentration.
Standard: 85 (i 10) gpm determined to be the flow rate required to dilute 300 ppm in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (200 ppm /hr) using the Figure 8 (hot) nomograph.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The candidate should report to the SS that, "8,000 (t 1,000) gallons at 85 (i 10) gpm is necessary to dilute to the ECC boron concentration in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />." At this point, inform the candidate that,"this JPM is complete."
Stop Time:
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1 PITCQ-089 Page 4 of 5 Rev 5 10/98 l j
TURNOVER SHEET INITIAL CONDITIONS:
o The shutdown banks have been withdrawn to 228 steps in preparation for a Reactor startup.
o Current RCS boron concentration is 1300 ppm.
o An ECC has been completed and verified.
INITIATING CUES:
o The SS directs you to calculate the number of gallons of water needed to reduce the RCS boron concentration to the given ECC boron concentration and the dilution water flow rate necessary to perform the dilution in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per 1C1.2, step 5.5.5.
. Report the results to the SS.
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l PITCO-089 Page 5 of 5 Rev 5 10/98
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1 PITCQ-089 - JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET l
TASK TITLE: Initiate A Temporary Change To A Procedure !
JPM NUMBER: ADMIN-1.2 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): 1 TASK NUMBER: 1190130301 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: C Actual Performance: @
Evaluation Location: Turbine Building: C Auxiliary Building: O Simulator: O Control Room: C Other: Anywhere @
l Time for Completion: 20 Minutes l
TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 l
REVIEWED BY: DATE: 1 APPROVED BY: DATE:
I Resp Grp: O Page 1 of 7 Assoc Ref: PITC TP 3.7
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l Initiat) A Tcmporary Ching3 To A Procedura l ADMIN-1.2 Rev. 0 l l Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR j l
l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. l When you complete the task successfully, the objective for this job performance measure will be satisfied.
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INITIAL CONDITIONS:
o Unit 1 is at 100%.
o The letdown heat exc1 anger needs to be isolated for maintenance. ;
o in order to ensure full isolation from all "otential sources of water, it is requested that when normal letdown is removed from service, Letdown Outside Containment holation CV-31339, be closed.
INITIATING CUES: l o The SS directs you to initiate a temporary procedure change per 5AWI 1.5.10, to add the following i step to the end of C12.1, section 5.3, Removing Normal Letdown From Service: )
Isolate the Letdown Heat Exchanger inlet by CLOSING CV-31339, LETDOWN OUTSIDE CONTAINMENT ISOLATION, using CS-46166.
o Deliver the temporary procedure change to the SS for review and approval.
l PITCO-089 Page 2 of 7 Rev 5 10/98
A l Initista A Temporary Chengo.To A Pmcedura l ADMIN-1.2 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: Form PINGP 1300 and a copy of C12.1.
General
References:
5AWI 1.5.10 Tcsk Standards: Temporary procedure change initiated for C12.1, section 5.3.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the l Indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to I meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Complete the following on the PINGP 1300:
- Critical- X _ (S-1) Procedure number, title, and revision number.
l Standard: Procedure number, title, and ievision number recorded on the PINGP 1300. Work order number should also be recorded.
! Evaluator Note: ~ This JPM may be performed without reference to procedure 5AWI 1.5.10.
Evaluator Cue: When the candidate asks, report that the, " work order number is 99-l 031."
i Performance: SATISFACTORY UNSATISFACTORY _
Comments: j 1
PlTCQ-089 Page 3 of 7 Rev 5 10/98 l l
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- l. l Initiata A Temporary Changa To A Procedure l ADMIN-1.2 Rev. 0 l l Performance Step: Complete the following on the PINGP 1300: l Critical X (S-1) Summarize the change (s)in adequate detail: include page number l l and/or procedure step (s) affected and the reason for the change. l L
Standard: Procedure change summary, including page and/or step number, recorded on the PINGP 1300.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Complete the following on the PINGP 1300:
Critical X (S-1) Documentation of the change:
Standard: Copy of the procedure marked up with temporary change (addition of step to section 5.3 to close CV-31339) and attached to the PINGP 1300. !
Evaluator Note: If the procedure change is adequately described on the PINGP 1300 (previous step), this step is not critical.
l Performance: SATISFACTORY UNSATISFACTORY 4 Comments:
Performance Step: Complete the following on the PINGP 1300:
Critical X (S-1) Identify if this is an OC (Operations Committee) reviewed procedure. OC reviewed procedure have requirements on reviewer qualifications and must be reviewed within 30 days by the OC.
Standard: Procedure identified as an OC reviewed procedure.
Performance: SATISFACTORY UNSATISFACTORY Comments:
l PITCQ-089 Page 4 of 7 Rev 5 10/98
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. l Initiat3 A Temporary Chanj To A Procedure l ADMIN-1.2 Rev. 0 l Performance Step: Complete the following on the PINGP 1300:
Critical Determine if a permanent procedure change is needed. If so, submit PINGP 436, Procedure Submittal Form, per SAW: 1.5.2.
Standard: Permanent procedure change determined not to be needed and indicated on the PINGP 1300 (no PINGP 436 necessary).
Evaluator Cue: If asked, report that,"a permanent procedure change is not needed."
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Complete the following on the PINGP 1300:
Critical X (S-1) Assign an Effective Date.
Standard: Today's date recorded on the PINGP 1300.
Evaluator Cue: If asked, report that, "the isolation will be done today."
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Complete the following on the PINGP 1300:
Critical Assign an Expiration Date, if required. Otherwise, mark the expiration date as "NR".
Standard: Expiration date determined not to be required and NR" recorded on the PINGP 1300.
Evaluator Note: An expiration date is not required by this temporary change.
Evaluator Cue: If asked, report that, "no expiration date is required."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 5 of 7 Rev 5 10/98
- l Initiato A Temporary Chango To A Procedure l ADMIN-1.2 Rev. 0 l
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Performance Step: Complete the following on the PINGP 1300:
Critical X (S-2) The Originator SHALL sign and date the PINGP 1300.
Standard: PINGP 1300 signed and dated by candidate.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The candidate should report to the SS that, "the temporary change (PINGP 1300) is ready for review and approval." At this point, inform the candidate that, "this JPM is complete." -
Stop Time:
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PITCO-089 Page 6 of 7 Rev 5 10/98
TURNOVER SHEET INITIAL CONDITIONS:
o Unit 1 is at 100%.
.o The letdown heat exchanger needs to be isolated for maintenance.
o in order to ensure full isolation from all potential sources of water, it is requested that when normal letdown is removed from service, Letdown Outside Containment isolation CV-31339, be closed.
INITIATING CUES:
o The SS directs you to initiate a temporary procedure change per SAWI 1.5.10, to add the following step to the end of C12.1, section 5.3, Removing Normal Letdown From Service:
Isolate the Letdown Heat Exchanger inlet by CLOSING CV-31339, LETDOWN OUTSIDE CONTAINMENT ISOLATION, using CS-46166.
o Deliver the temporary procedure change to the SS for review and approval.
PITCQ-089 Page 7 of 7 Rev 5 10/98
PING'P t300, Rev.1 h 6 years k TCN #
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. Document Type: 1.190 Effectiva D:ts: r J., a, n,,4, Expletion DIts: nR TEMPORARY CHANGE NOTICE Page 1 of eId (SAWI 1.5.10)
- 1. CHANGE REQUEST Procedure #: co_i Rev: n Project ID #: l
Title:
t r rn n t, u , c H a c e, r ra r , Aun sral LJ A T E R I M _T E r T f D AJ !
Description of Change: AJJ d,n L h n t ,,4,_ L, l J m, o L t> o = 9 9. o t e l
(,m ,., Ja k, %, .
l A 6tm 1,,I r_ ,_ _ J pm ,h ,, .1 s 4,_ L ., L L m J .1, A Lu,1 i t. L I s,ll&,_ &L, L 4 L .u H,mf E , .s ts , ., . le k c tacuG l c v . T t 4 4 cr t e rnou n ou rs e ne re,u r A ramp u r r <:o t A rin o a..g is this an OC reviewed procedure? Yes No *W -
Is a permancit procedu:3 change needed? Yes No (if Yes, submit PINGP 436)
Originator: u,. _ , 4 ,m ,A , ,. Employee #: Un. Date: n J.s A n,.1,.
- 11. REVIEW AND APPROVAL A. Is this temporary change a change in scope or intent? Yes No O (if No, go to 11.B)
- Does this temporary change:
1, include specific steps discutsed in the SAR? Yes No
- 2. Affect component operation specifically described in the SAR? Yes No
- 3. Affect plant configuration described in text or drawings in the SAR7 Yes O No if 1,2 or 3 is Yes, perform a Safety Evaluation Screening (PINGP 1229) SES #
Is a Safety Evaluation Required? Yes No SE#
+ Does this change affect Special Reviews (e g. EQ, App.R)? Yes No (if Yes document Special Review (s) in CHAMPS)
- OC review date (if procedure is OC Approval by procedure i reviewed, otherwise 'NR'): approver: l B Does this change affect plant operation or Tech Specs? Yes No (if Yes and work is in progress, Shift Supervisor l notified by (initial))
C. Do controlled copies need to be updated? Yes nod (if Yes Attach marked-up procedure pages to White COPY)
D. All master / working copies updated? YesO NA E. Is training on temporary change needed? Yes No (if Yes, PINGP 1268 or PINGP 1224 (Ops Only) issued) ;
1 F. Reviewer. Date: -
l (Unit Management Staft) l Gt Approver. Date:
(Unit Management Staff; SRO for OG reviewed procedures)
Forward white copy to Procedure Control lit. POST REVIEWS (required for OC reviewed procedures only; 'NR' if reviewed / approved in ll.A)
OC Review Date: Procedure Approver: Date:
IV. TEMPORARY CHANGE DELETION ('NR'If controlled copies not updated, refer to ll.C)
A. Is this temporary change deletion a change in scope or intent? YesO NoO (If No, go to IV.8)
- Does this temporary change deletion:
- 1. Include specific steps discussed in the SAR7 Yes NoO l 2. Affect component operation specifically described in the SAR? Yes No
- 3. Affect plant configuration described in ter.ct drawings in the SAR? Yes NoC l If 1,2 or 3 is Yes, perform a Safety Evaluation Screening (PINGP 1229) SES #
Is a Safety Evaluation Required? Yes NoO SE #
- OC review date (if procedure is OC Approval by procedure reviewed, otherwise 'NR'): approver:
B. Reviewer. Date:
(Unit Management Staff)
C. Approver. Date:
(Unit Management Statt; SRO for OC reviewed procedures) l Fa=SMe46(e-80 White Copy - Procedure Control Yellow Copy - Attach to procecure
f ggy
, PRAIRIE ISLAND NUCLEAR GENERATING PLANT -
NORTHERN STATES POWER COMPANY OPERATING PRoCEDUR2S
" "* NUMBER:
4k TITLE LETDOWN, CHARGING, AND C12.1 t i REV:
E SEAL WATER INJECTION 17
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- t . & na pageaof40 5.3.2 Remove normal letdown from service by CLOSING the following:
CV-31226 [CV-31230], LETDOWN LINE ISOL, using CS-46165 [CS-49536]
CV-31255 (CV-31279], LETDOWN LINE ISOL, using CS-46133 [CS-49667]
5.3.3 Verify the letdown orifice isolation valves are CLOSED:
CV-31325 [CV-31347), LETDOWN ORlFICE ISOL l 40 GPM, using CS-46170 [CS-49522]
CV-31326 [CV-31348), LETDOWN ORIFICE ISOL 40 GPM, using CS-46171 [CS-49521]
CV-31327 [CVb1349], LETDOWN ORIFICE ISOL 80 GPM, using CS-46174 [CS-49537]
5.3.4 While adjusting the charging pump speed to maintain seal injection flow, isolate charging to the Regen HX by closing CV-31198 [CV-31211], CHG LINE FLOW CONT, using 1HC-142 [2HC-142].
5.3.5 Place 1HC-135A [2HC-135A], LTDN PRESS CONT, in 1 MANUAL and OPEN to about 50%
'i. 3. 6 b l e.fc (Le Le4Jcan 16f Ex Layer iald b y CLO SE N G CV 3 833'), L6T00kIM OUTSIDE C ON TAtN B16N T l E50L A TION asing c,$ . LIL 6 L L, E, v4 l .i b r Nodo *. ThIs p )c is ncf CAITICAL if $lep
- h. be <.J J e J is e. J c .g c. f e yl d e s c e; L.) cn N PIMGP GOO. If ik;s pqe e6 <. Nc hed, t h e.
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. PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98
[ WORKSHEET 1
TASK TITLE: Determine Actions To Remove RCP Thermal Barrier HX From Service JPM NUMBER: ADMIN-2 Rev.0 RELATED PRA None l lNFORMATION (SEE PITC 2.3):
TASK NUMBER: 115.ATI.12 K/A NUMBERS: 2.1.24 APPLICABLE METHOD OF TESTING:
Simulate Performance: C Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O j Simulator: O Control Room: O Other Anywnere @
l Time for Completion: 10 Minutes TASK APP'llCABILITY: SRO: @ RO: @ NLO: @
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 5/6/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
Resp Grp: O Page 1 of 5 Assoc Ref: PITO TP 3.7
. Evaluator: .
Date: i l
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
Wheri you complete the task successfully, the objective for this job performance measure will be satisfied.:
V .
k INITIAL CONDITIONS.
o Unit 1 was at 100% power when a Thermal Barrier HX leak occurred on 11 RCP.
.o C14 AOP2 has been implemented.
o 11 RCP Thermal Barrier Coolant Outlet Valve (CV-31245) has been closed.
i INITIATING CUES:
o The SS directs you to determine the actions necessary and the plant conditions required to remove 11 RCP Thermal Barrier HX from service and isolate it from component cooling.
o' Report completion to the SS.
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{ i l-PITCQ-089 Page 2 of 5 Rev 5 10/98
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. l Det::rmina Actions To Remova RCP Thcrmal Barri:r HX From Service l ADMIN-2 Rev.0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
1C14 AOP2, NF-392451 Task Standards: Determination made that the reactor and th9n the 11 RCP will have to
~ be shutdown so that CC can be isolated from the 11 RCP Thermal Barrier HX by closing inlet (MV-32089) and outlet (MV32090, CV-31245, or CC-284) valves. ,
Start Time- l l
NOTEi When providing " Evaluator Cues" to the examinee, care must be sxercised to avoid prompting the examinee. Typically cues are'only provided when the examinee's actions warrant receiving the information (i.e.' the examinee looks or asks for the Indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: By using controlled plant drawing NF-39245-1, determine inlet and outlet Critical X (S-1) valves necessary to isolate 11 RCP Thermal Barrier HX fmm CC.
Standard: Containment isolation valves MV-32089 and MV-32090 determined to be I the inlet and outlet valves necessary to isolate CC from the 11 RCP l I
Thermal Barrier HX.
Evaluator Note: Candidate may discuss the following valves on the CC outlet, which would require containment entry to access:
. .CV-31245 closed in AOP (valve falls open and therefore, would l
L have to be secured in the closed position with handwheel). ;
e Manual valve (CC-284) Just down stream of CV-31245.
Evaluator Cue: Acknowledge the candidates determination of valves necessriry to isolate the 11 RCP Thermal Barrier HX from CC.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 3 of 5 Rev 5 10/98
. l Det:rmina Actions To Remove RCP Thermal Barrier HX From Service l ADMIN-2 Rev.0 l Performance Step: Detennine plant conditions required to isolate 11 RCP Thermal Barrier HX Critical X (S-1) _ from CC.
Standard: Determine that the reactor and then the 11 RCP will have to be shutdown prior to isolating 11 RCP Thermal Barrier HX from CC, since the valves that will be closed isolate all CC to the RCP.
Evaluator Note: Candidate may further discuss the necessity to cooldown, depressurize, and draindown to establish basically the same conditions required for RCP seal removal, to affect repairs on the Thermal Barrier HX. Work Contrcl will have to develop the package and isolation to affect repairs, as this evolution is not one specifically called out in a procedure (like RCP seal replacement).
Evaluator Cue: Acknowledge the candidate's determination of plant conditions
' required to remove 11 RCP Thermal Barrier HX from service and isolate it from component cooling.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The candidate should report to the SS the determination of the actions necessary and the plant conditions required to remove 11 RCP Thermal Barrier HX from service and isolate it from component cooling. At this point, inform the candidate that, "this JPM is complete."
Stop Time:
1 l
l PITCQ-089 Page 4 of 5 Rev 5 10/98 L
l TURNOVER SHEET INITIAL CONDITIONS:
o Unit 1 was at 100% power when a Thermal Barrier HX leak occurred on 11 RCP.
o C14 AOP2 has been implemented.
l o l 11 RCP Thermal Barrier Coolant Outlet Valve (CV-31245) has been closed.
INITIATING CUES:
o The SS directs you to determine the actions necessary and the plant conditions required to remove 11 RCP Thermal Barrier HX from service and isolate it from component cooling.
o Report completion to the SS. !
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PITCO-089 Page 5 of 5 Rev 5 10/98
c PITCQ-089 - JOB PERFORMANCE MEASURE Rev.5 10/98
, # WORKSHEET l
TASK TITLE: Prepare For Entry into A Locked High Radiation Area JPM NUMBER: ADMIN-3 Rev. 0 l RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 1190100301 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
l Simulate Performance: @ Actual Performance: O l Evaluation Location: Turbine Building: O Auxiliary Building: @
Simulator: O Control Room: O Other: O Time for Completion: 20 Minutes f TASK APPLICABILITY: SRO: @ RO: @ NLO: @ !
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
Resp Grp: O Page 1 of 7 Assoc Ref: PITC TP 3.7 l
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+ l Prepara For Entry into A Locked High Radiation Arac l ADMIN-3 Rcv. 0 l i
l Operator: __(SRO / RO / NLO) l l
Evaluator:
Date:
READ TO THE OPERATOR I will expla'n the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
l INITIAL CONDITIONS: .
o Water leakage has been repoded in the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area. j INITIATING CUES:
o The SS directs you to investigate and determine the source of leakage.
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PITCQ-089 Page 2 of 7 Rev 5 10/98 b
l Pr: para For Entry into A Lock d High Radiation Area l ADMIN-3 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
F2 Task Standards: Required preparations made for entry into and the location indicated for the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee,' care must be exercised to avoid !
prompting the examinee. Typically cues are only provided when the examinee's ;
actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Obtain the Locked High Radiation Area key.
Critical X (S-1)
Standard: Locked High Radiation Area key obtained.
Evaluator Note: This ' key is on the operator's key ring or in either the HP's or SS's office.
Evaluator Cue: Key is obtained.
1 Performance: SATISFACTORY UNSATISFACTORY Comments:
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PITCQ-089 Page 3 of 7 Rev 5 10/98 l i
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l Pr:: pare For Entry into A Locked High Radiation Area l ADMIN-3 Rev. 0 l Performance Step: At Access C'oltrol, determine the RWP for Locked High Radiation Areas.
Critical Standard: RWP 11 determined to be the RWP for Locked High Radiation Areas (Barrel Yard - Hot Drum Storage Area).
Evaluator Note: The candidate may ask RPS for applicable RWP.
Evaluator Cue: If asked, inform candidate that, "RWP 11 is the applicable RWP."
Performance: SATISFACTORY UNSATISFACTORY Comments:
P!rformance Step: Review the RWP for entry conditions and requirements.
Critical X (S-2)
Standard: RWP conditions and requirements reviewed and the following determined:
- 1. Dose rates need to be known or survey meter has to be used to survey the area.
- 2. Continuous RPS coverage is required for entry.
- 3. A pre-job briefing is required to review dose rates and allowable dose.
- 4. Stay time has been converted to your individual dosimeter Dose Alarm.
- 5. TLD and dosimeter required for entry with Dose Rate Alarm set at 5000 mR/hr and Dose Alarm set at 100 mrem.
- 6. Normal Full Suit-up required unless authorized less by RPS.
Evaluator Note: Candidate may use survey map in book, to determine if dose rates are currently known or may consult with RPS.
Evaluator Cue: If asked, inform candidate that, " current dose rates are posted at the entrance to the area."
Performance: SATISFACTORY UNSATISFACTORY "
Ccmments:
PITCO-089 Page 4 of 7 Rev 5 10/98 c
'* l Prepare For Entry into A Locked High Radiation Area l ADMIN-3 Rev. 0 l Performance Step: Request coverage and pre-job brief from RPS.
Critical X (S-2)
Standard: RPS coverag" assigned and pre-job brief completed.
Evaluator Note: Act as RPS to conduct pre-job brief and assign continuous RPS coverage.
Evaluator Cue: As RPS, conduct pre job briefing going over attached RWP 11 requirements with the following specific notations:
- 1. The survey map posted locally at the Barrel Yard - Hot Drum Storage Area, will be reviewed for current dose rates in the area.
- 2. Allowable dose for the job will be 20 mrem.
- 3. Dosimeter Dose Rate Alarm has been set to 5000 mR/hr and Dose
' Alarm has been set to 100 mrem.
- 4. Protective clothing required for the Job will be Bootie and Glove Sult-up.
- 5. RPS is to be notified when you are ready to enter and a HP will be sent to the area for continuous coverage.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Obtain electronic dosimeter and log-in on the Access Control Computer Critical X (S-2) System.
4 Standard: Dosimeter obtained and Access Control Computer System logged-in on.
Evaluator Note: Candidate should log-in on the standard RWP for operator's tours.
Evaluator Cue: If required, inform the candidate that," log-in should be on standard RWP for operators tours (RWP-1)."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 5 of 7 Rev 5 10/98 L
LPrepare For Entry into A Locked High Radiation Area l ADMIN-3 Rev. 0 l Performance Step: At the Barre! Yard - Hot Drum Storage Area entry gait, remove the lock Critical X (S-2) and open the gait.
Standard: Barre! Yard - Hot Drum Storage Area entry gait lock simulated removed and location of Locked High Radiation Area indicated.
Evaluator Note: The candidate need only indicate from the Barrel Yard - Hot Drum Storage Area entry galt, the location of the Locked High Radiation Area within. This may be performed by using the posted survey map as a reference and/or pointing to the area.
Evaluator Cue: When the candidate indicates that he/she would remove the lock on the Barrel Yard - Hot Drum Storage Area, inform the candidate that, "the lock need not be removed and indication of the Locked High Radiation Area location is all that is required."
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When the location of the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area has been indicated, inform the candidate that, "this JPM is complete."
Stop Time:
PITCQ-089 Page 6 of 7 Rev 5 10/98 L
L- -
I TURNOVER SHEET INITIAL CONDITIONS:
. Water leakage has been reported in the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area.
INITIATING CUES:
. The SS directs you to investigate and determine the source of leakage, PITCQ-089 - Page 7 of 7 Rev 5 10/98
l l ' PITCQ-089 ; JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET l
TASK TITLE: Initiate Emergency Local Evacuation JPM NUMBER: ADMIN-4S Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 0850110101 K/A NUMBERS: 2.1.23 l APPLICABLE METHOD OF TESTING:
Simulate Performance: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: @ Control Room: O Other: O l
Time for Completion: 5 Minutes l
TASK APPLICAblLITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/24/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
l Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
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- l Initi:t1 Emergency Local Ev:cuttion l ADMIN-4S Rev. 0 l 1
Evaluator: l Date: .
l READ TO THE OPERATOR l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
o A steamline break from Unit 2 has occurred in the Auxiliary Building.
o CAM alarms and fire alamis have been received, which indicate that steam is causing a hazardous atmosphere inside the Auxiliary Building.
INITIATING CUES:
o The SS directs you to initiate a local evacuation of the Auxiliary Building due to a steamline break per F3-9, Section 7.2.
o Report completion to the SS.
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l PITCO-089 Page 2 of 8 -
Rev 5 10/98 1
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l Initiato Em rgnncy Local Evacuation l ADMIN-4S Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
F3-9 Task Standards: Local evacuation of the Auxiliary Building initiated by actuation of the evacuation alarm and announcement'over the public address system.
Start Time:
NOTEi When providing " Evaluator Cues" to the examinee, care must be exercised to avoid l prompting the examinee. Typically cues are only provided when the examinee's )
actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Determine the appropriate assembly area for accountability.
Critical X (S-1)
Standard: Access Control HP Office determined to be the appropriate area for accountability for evacuation of the Auxiliary Building.
Performance: SATISFACTORY UNSATISFACTORY ;
Comments: _
4 PITCQ-089 Page 3 of 8 Rev 5 10/98
1 l Initiata Emergency Local Evacuation l ADMIN-4S Rev. 0 l Performance Step: Sound the evacuation alarm.
Critical ,_ X (S-2)
Standard: Evacuation alarm sounded by momentarily placing the EVACUATION ALARM switch to the "ON" position.
Evaluator Note: The Evacuation Alarm switch is located on the Deluge Panel behind i
'G' Panel.
Evaluator Cue: If this JPM is simulated, inform the candidate that, "the Evacuation I Alarm has been sounded."
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Announce over the public address system the location of the problem and Critical X (S-3) any evacuation instructions.
I Standard: The following announced over the public address system:
" Attention, all plant personnel. There is a steamline break occurring in the Auxiliary Building. All personnel should evacuate from the Auxiliary Building and go to the Access Control HP Office for accountability. Stay clear of the Auxiliary Building until further notified."
Evaluator Cue: If this JPM is simulated, inform the candidate that,"the announcement has been rr;ade."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 4 of 8 Rev 5 10/98
1
- l Initiata Em:rg:ncy Local Evacuation l ADMIN-4S Rev. 0 l Performance Step: Repeat the message to ensure that all personnel are informed. I Critical X (S4)
Standard: The following announced over the public address system:
" Attention, all plant personnel. There is a steamline break occurring in the Auxiliary Building. All personnel should evacuate from the Auxiliary Building and go to the Access Control HP Office for accountability. Stay clear of the Auxiliary Building until further notified."
Evaluator Cue: If this JPM is simulated, inform the candidate that, "the announcement has been repeated." l Performance: SATISFACTORY UNSATISFACTORY Commentm Terminating Cues: The candidate should report to the SS that, "F3-9 step 7.2.1 is complete."
At this point, inform the candidate that,"this JPM is complete."
l l Stop Time:
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PITCQ-089 Page 5 of 8 Rev 5 10/98
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!*- l Initiati Em:rgency Local Ev:cuation l ADMIN-4S Rev.0 l l
SIMULATOR SETUP instructor Guide:
o initialize the simulator to any stable IC.
o . Place the simulator in "RUN".
4 PITCQ-089 Page 6 of 8 Rev 5 10/98 I
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q TURNOVER SHEET INITIAL CONDITIONS:
o A steamline break from Unit 2 has occurred in the Auxiliary Building, o CAM alarms and fire alarms have been received, which indicate that steam is causing a hazardous atmosphere inside the Auxiliary Building.
i INITIATING CUES:
o The SS directs you to initiate a local evacuation of the Auxiliary Building due to a steamline break per F3-9, Section 7.2.
o Report completion to the SS.
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PITCO-089 Page 8 of 8 Rev 5 10/98 i'
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1 AS-ADMINISTERED WALKTHROUGH JPMS PRAIRIE ISLAND EXAMINATION - WEEK OF MAY 17,1999 l .
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ES-301 Individual Walk-Through Test Outline Form ES-301-2 Facility: Prairie Island Nuclear Station Date of Examination: May 17.1999 Exam Level (circle one): RO Operating Test No.: 1999301 1
System / JPM Title / Type Codes
- Safety Planned Follow-up Questions: I Function K/A/G - Importance - Description
- 1. CRD/ Withdraw Shutdown Bank B/ 1 a. 001K402#3.8# Bank overlap counter indications 1 N,S,L j
- b. 001 A302//3.7# Rod insertion limits ;
- 2. RHR/ Alternate in-Service RHR 4 a. 005A101#3.5NCooldown limitations Loops /
D.S.L b. 005K109//3.6# Filling refueling cavity
- 3. ECCS/ Manual Makeup to the RWST/ 2 a. 2.1.33//3.4#Heatup/startup limitations
- b. 004K412//3.1/NCT level response to failed equipment ;
)
- 4. PRM/ Transfer 1R-11/12 Sample 7 a. 073K301/3.6// Liquid release requirements Discharge from Containment to Aux Bldg Stack
- b. 073A202#2.7#1R-11 failure actions M. S
- 5. CCW# Respond to an RCP Thermal 8 a. 015K302#3.1//RCP Response to Loss of CCW Barrier Hx Leak N,A,S b. 008K402#2.9#CCW system automatic response to CCW leak
- 6. ECCS/Depressurize the RCS 3 a. 008A108//3.8// Unidentified leakage calculation Following a Steamline Break M,A.S b. 004K117//3.4// Requirements to use aux spray
- 7. CSS / Respond to High Containment 5 a. 2.2#3.4// Containment responses Pressure D,A,S b. 026A205#3.7// Caustic Standpipe effects
- 8. FP/ Emergency Starting of 122 Diesel 8 a. 086#2.5// Actions to establish sprinkler system Fire Pump flow D,A,P
- b. 2.4.27#3.0# inadvertent initiation of reactor head vent system
- 9. Cnmt CoolingNent Containment 5 a. 029K403N3.2NSpent Fttel Pool ventilation Using Post LOCA Vent System D.P,R b. 028K503#2.9# Hydrogen sources
- 10. AC Elec/ Transfer U2 480V Buses 6 a. 062K102#4.1# Tech spec requirements to their Attemate Supply D, P b. 062A401#3.3# Load sequencing
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ttemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA l
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PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET I l
l l TASK TITLE: Withdraw Shutdown Bank B JPM NUMBER: SIMUL-1 Rev. O I
RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 0010180101 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: @ Control Room: O Other: O Time for Completion: 5 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/25/99 REVIEWED BY: DATE:
l APPROVED BY: DATE:
l l
f Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7 l
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p I l- l Withdr w Shutdown B:nk B l SIMUL-1 Rcv. 0 l L
Evaluator:
Date:
i READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
~
INITIAL CONDITIONS:
o RCS heatup is in progress per 1C1.2.
o As directed by 1C1.2 step 5.1.7.H, shutdown banks are being withdrawn per 1C5.
o Shutdown bank A has been fully withdrawn.
o- Initial N31 and N32 countrate prior to Shutdown Bank A withdrawal was 500 cps.
INITIATING CUES:
o The SS directs you to fully withdraw shutdown bank B per 1C5 beginning at step 5.2.6.
o Report completion to the SS.
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l PITCQ-089 Page 2 of 8 Rev 5 10/98 l e .
r l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
1C1.2,1C5 Task Standards: Shutdown bank B fully withdrawn to 228 steps.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions _ warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Position CS-46280, ROD BANK SELECTOR, to the "SBB" position.
Critical X (S-1)
Standard: CS-46280 placed in the "SBB" position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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PITCQ-089 ,
Page 3 of 8 Rev 5 10/98 n _-
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l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l Performance Step: Pull CS-4S281, IN-HOLD-OUT lever, to the "OUT" position. Verify the
! Critical X (S-2) digital OUT direction lamp is LIT.
Standard: CS-46281 held in the "OUT" position and digital OUT direction lamp is verified LIT.
Evaluator Note: The critical part of this step is holding CS-46281 in the "OUT" position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify shutdown bank B group 1 step counter indicates the withdrawal Critical steps.
Standard: Shutdown bank B group 1 step counter verified to be indicating the withdrawal steps.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify the control rods in shutdown bank B are moving on the Rod Position Critical Indication System indicators.
Standard: Shutdown bank B rods are verified to be moving as indicated on the Rod Position Indication System.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Y l
PITCQ-089 Page 4 of 8 Rev 5 10/98 l
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l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l l
l Performance Step: Withdraw shutdown bank B rods to 228 steps.
Critical X (S-3)
Standard: Shutdown bank B rods are withdrawn to 228 steps, then CS-46281, IN-HOLD-OUT lever, is released.
Evaluator Note: The critical part of this step is to withdraw the rods to 228 steps.
Performance: SATISFACTORY UNSATISFACTORY 1
Comments:
1 Terminating Cues: The candidate should report to the SS that, " shutdown bank B has been fully withdrawn." At this point, inform the candidate that, "this JPM is complete."
Stop Time:
l PITCQ-089 Page 5 of 8 Rev 5 10/98
l Withdr:w Shutdown B:nk B l SIMUL-1 Rev. 0 l l SIMULATOR SETUP l
Instructor Guide:
o Initialize the simulator to IC-5.
- o Place the simulator in "RUN". .
o Fully insert shutdown bank B.
o Place CS-46280, Rod Bank Selector, to the "SBA" position.
l c - Verify RBU on ERCS is updated.
o Place the simulator in " FREEZE".
.o When the candidate is ready, place the simulator in "RUN".
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. PITCO-089 Page 6 of 8 Rev 5 10/98 J 1
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TURNOVER SHEET I
INITIAL CONDITIONS:
o RCS heatup is in progress per 1C1.2.
o As directed by 1C1.2 step 5.1.7.H, shutdown banks are being withdrawn per 1C5.
o . Shutdown bank A has been fully withdrawn.
e initial N31 and N32 countrate prior to Shutdown Bank A withdrawal was 500 cps.
INITIATING CUES:
o The SS directs you to fully withdraw shutdown bank B per 1C5 beginning at step 5.2.6.
o Report completion to the SS.
l PITCQ-089 Page 8 of 8 Rev 5 10/98
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JPM: 1 OPerator:
JPM QUESTION (Answer Sheet) l l
QUESTION 1 System: CRD
Subject:
l Startup Reset Switch Response K/A & Rating: 001K402 3.8/3.8 Given the following Unit 1 conditions:
-Reactor Power is 100% MOC.
-Rods are at the normal position.
The RO Inadvertently places the ' Rod Control Startup' switch to Question: STARTUP. The RO then places the ' Bank Selector' switch to MANUAL and places the 'IN-HOLD-OUT' switch to the OUT position.
~
When rod motion STARTS, what will the Bank Overlap Unit (count'er) indicate?
384 Bank A = 128 Answer: Bank B = 128 Bank C = 128 Total = 384 B5 Rev 2
Reference:
1C5, Sect 5.3, P. 6, Rev 4 Reference Material Use: IYes E No O I Pedigree: l New I
CANDIDATES RESPONSE: SAT: UNSAT: )
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JPM: 1 OPerator:
JPM QUESTION (Answer Sheet) l l
QUESTION 2 System: CRD
Subject:
l Rod insertion Limits KIA & Rating: 001A302 3.7/3.6 Unit 2 is at 70% power.
I Question: By how much (in rod steps) will the Rod Insertion Limit change if power is reduced to 35%?
Answer: 84 +/-5 Technical Specification Core Operating Limits Report, Unit 2 Cycle 18. Fig 4
Reference:
Curve Book, Fig C1-8 Reference Material Use: l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT:
l I
r PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98 l . .
WORKSHEET i
l TASK TITLE: Altemate in-Service RHR Loops l JPM NUMBER: SIMUL-2 Rev. O I
RELATED PRA None l INFORMATION (SEE PITC 2.3):
l TASK NUMBER: 005.ATI.18 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: l l'
Simulate Performance: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O i Simulator: @ Control Room: O <
Other: O Time for Completion: 11 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/25/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
l-Resp Grp: O Page 1 of 11 Assoc Ref: PITC TP 3.7
7 l Alt rn taIn-S:rvice RHR Loops l SIMUL-2 Rnv. 0 l Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
~ ~~
IN!TIAL CONDITIONS:
o RCS is in Cold Shutdown at 130 *F.
o - 12 RHR pump is running.
INITIATING CUES:
o: The SS directs you to shift from 12 RHR pump and heat exchanger in service to 11 RHR pump i and heat exchanger in service and place 12 RHR pump and heat exchanger in standby per 1C15 section 5.3. j o Report completion to the SS.
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1 PITCQ-089 Page 2 of 11 Rev 5 10/98 1
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l Altt: mate in-Service RHR Loops l SIMUL-2 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
1C15 Task Standards: 11 RHR pump and heat exchanger in service,12 RHR pump stopped.
Start Time:
~
NOTE: When providing " Evaluator Cues" to the e'xaminee, care must be exercised to avoid prompting the. examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the
> indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. ,
Perforraance Step: Start the standby CC pump.
Critical Standard: Both CC pumps verified running. 4 Evaluator Note: 12 CC pump is already running.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 3 of 11 Rev 5 10/98
l Alt:: mate in-Sen/ ice RHR Loops l SIMUL-2 Rev. 0 l Performance Step: Open the standby RHR HX CC inlet valve.
Critical Standard: 11 RHR HX CC inlet valve MV-32093 opened by placing CS-46023 in the OPEN position; red light lit, green light extinguished.
l 1
Performance: SATISFACTORY UNSATISFACTORY Comments:
l l
Performance Step: Verify CC flow through the standby RHR HX.
l Critical l
Standard: 11 RHR HX CC flow verified using 4102002 (11 RSDL HX CC INLT Flow) and 4102001 (11 RSDL HX CC OUTL Flow).
Evaluator Note: CC flow should indicate between 2000 and 2500 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify the standby RHR HX outlet flow control valve is closed.
Critical Standard: 11 RHR HX outlet flow control valve CV-31235 verified closed by observing 100% output on 1HC-624.
Performance: SATISFACTORY UNSATISFACTORY l
Comments:
1 i i
PITCO-089 Page 4 of 11 Rev 5 10/98
l Attemata In-Service RHR Loops l SIMUL-2 Rev. 0 l Performance Step: Verify the RHR HX inlet and outlet crossover valves are open.
Critical l Standard: Aux Building Operator requested to verify RH-2-3, RH-2-4, RH-2-5, and i
RH-2-6 are open.
Evaluator Note: The booth operator will act as Aux Building Operator to open RH-2-3, RH-2-4, RH-2-5, and RH-2-6.
Evaluator Cue: The booth operator will report as Aux Building Operator that, "RH 3, RH-2-4, RH-2-5, and RH-2-6 are open."
Performance: SATISFACTORY UNSATISFACTORY Comments: - - --
Performance Step: Start the standby RHR pump.
Critical X (S-1)
Standard: 11 RHR pump started by momentarily placing CS-46184 in the START position; red light lit, green light extinguished.
Evaluator Note: Running 2 RHR pumps with RHR flow < 2500 gpm, causes annunciator 47016-0604, "RHR System Trouble" due to low pump motor amps. No action is required for this alarm unless signs of cavitation also exist. The candidate may or may not stop at this point and review the Alarm Response Procedure depending on familiarity with this condition.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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l PITCQ-089 Page 5 of 11 Rev 5 10/98 i
T I Altarnate In-Service RHR Loops l SIMUL-2 Rev. 0 l Performance Step: Verify CV-31237,11/12 RHR BYPASS FLOW, maintains the desired total Critical RHR flow.
Standard: Total RHR flow verified to be approximately 2000 gpm by observing 1F1-626.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Open oncor.ing RHR HX outlet flow control valve 5%.
Critical
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Standard: "51 RHR t > !el flow control valve CV-31235 opened 5% by adjustini 1HC-62e , s5% output.
Performance: SATISFACTORY UNSATISFACTORY _
Comments:
Pedoimance Step: Verify the oncoming RHR HX function by observing RHR HX outlet I C ritir .. _ _ temperature,1TI-622 (local)is reading lower than 1TI-630, RCS HOT LEGS TO RHR (red pen).
Standard: Aux Building Operator requested to report 11 RHR HX outlet temperature as indicated on 1TI-622 and this temperature then verified to be lower than RCS Hot Legs to RHR temperature from the red pen on 1TR-630. j Evaluator Note: 11 RHR HX outlet temperature as indicated on 1TI-622 should be reported as some value slightly lower than RCS Hot Leg to RHR temperature.
Evaluator Cue: Report as Aux Building Operator,"11 RHR HX outlet temperature as indicated on 1TI-622 is 90 F."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 6 of 11 Rev 5 10/98
\
i
. l Alt mate in-Service RHR Loops l SIMUL-2 Rev. 0 l Performance Step: Gradually shift RHR cooling to the oncoming RHR HX by opening the Critical X (S-2) m.flet flow control valve while simultaneously closing the outlet flow control valve for the offgoing heat exchanger. Observe CV-31237,11/ .. RHR BYPASS FLOW, maintains the desired RCS temperature.
Standard: 11 RHR HX outlet flow control valve CV-31235 is opened by lowering tne output on 1HC-624 while 12 RHR HX outlet flow control valve CV-31236 is simultaneously closed by raising the output on 1HC-625. During this operation, total RHR flow is maintained at approximately 2000 gpm as indicated on 1FI-626.
Evaluator Note: RHR desired total flow should be approximately 2000 gpm.
Performance: _ _
SATISFACTORY UNSATISFACTORY , _ _ , _ ,
Comments:
Performaw;e Step: When the offgoing RHR HX outlet flow control valve is closed, then verify Critical the oncoming heat exchangeris maintaining the desire RCS temperature.
Standard: When 12 RHR HX outlet flow control valve CV-31236 is closed, verifies RCS temperature is maintained within approximately 5 *F of starting temperature as indicated on 1TR-630.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Stop the offgoing RHR pump.
Critical X (S-3)
Standard: 12 RHR pump stopped by momentarily placing CS-46185 in the STOP position; green light lit, red light extinguished.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 7 of 11 Rev 5 10/98
1 l Alt:rnat'aIn-Service RHR Loops l SIMUL-2 Rev. 0 l I
Performance Step: Verify CV-31237,11/12 RHR BYPASS FLOW, maintains the desired total Critical RHR flow.
Standard: Total RHR flow verified to be approximately 2000 gpm by observing 1FI-626.
Evaluator Note: RHR desired total flow should be approximately 2000 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If it is desired to stop one CC pump, then perform the following: --
Critical Standard: Both CC pumps left running.
Evaluator Cue: If asked, report that, "it is desired to leave both CC pumps running."
Pe:formance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The candidate should to the SS that, "12 RHR pump and heat exchanger are in service, and 11 RHR pump is stopped. At this point, inform the candidate that, "this JPM is complete."
Stop Time:
I f
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PITCQ-089 Page 8 of 11 Rev 5 10/98
c_
- l Altimata In-S rvice RHR Loops l SIMUL-2 Rev. 0 l 1 SIMULATOR SETUP l
Instructor Guide e initialize the simulator to IC-2. )
. Place the simulator in "RUN".
. Ensure CV-31237,11/12 RHR BYPASS FLOW, is in " AUTO" and maintaining total RHR flow at 2000 gpm. l
. Ensure ERCS screen RH1 is updated with correct valve positions as follows: )
. Select ERCS display RH1 on SDCON-5. 1
. Press F2 "D2VU". !
3 Enter the following valve positions:
. 32164 OPEN !
s . 32165 OPEN
. 32230 OPEN ~
. 32231 OPEN !
. 32084 CLOSED l
. 32085 CLOSED I
. 31235 CLOSED ;
. 31236 OPEN I
. 32064 CLOSED !
. 32065 CLOSED
. 32066 OPEN
. 31237 OPEN
. 32234 OPEN
. RH-2-5 OPEN
. RH-2-6 OPEN
. RH-2-3 OPEN
. RH-2-4 OPEN
. Save by pressing F4.
- Change ERCS RH1 screen setpoints to "RH1 Active" as follows:
. Select ERCS display RH1 on SDCON-5.
- Press F2 "D2VU".
. Press F5 two times to move ERCS field to Atarm Setpoints.
. Press F2 to toggle to RH1 Active.
- Press F4 to save.
T . Press CANC.
. Select RH1 display and verify RH1 setpoints active.
. Place the simulator in " FREEZE".
. When the candidate is ready, place the simulator in "RUN".
I PITCO-089 Page 9 of 11 Rev 5 10/98 j
_ l 8
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1 TURNOVER SHEET l l
i INITIAL CONDITIONS:
o RCS is in Cold Shutdown at 130 *F.
o 12 RHR pump is running.
INITIATING CUES:
o The SS directs you to shift from 12 RHR pump and heat exchanger in service to 11 RHR pump and heat exchangerin service and place 12 RHR pump and heat exchanger in standby per 1C15 section 5.3. l o Report completion to the SS.
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. PITCQ-089 Page 11 of 11 Rev 5 10/98 )
1
JPM: 2 OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 1 System: RHR
Subject:
l Cooldown Limitations K/A & Rating: 005A101 3.5/3.6 During a plant cooldown on Unit 1, the following RCS parameters were recorded:
Time T-cold Loop pressure 0000 547 2230 0015 536 1900 0030 520 1500 O U " 'I "
0045 504 1490 0100 488 1400 0115 467 1092 0130 444 720 0145 421 365 What (if any) limitations have been exceeded?
Teriip/ pressure not in the normal cooldown zone at 0145 (<50Deg Answer:
Subcooled).
Reference:
Figure C1-3B Reference Material Use: l Yes @) No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT:
I
r l
JPM: 2 JPM QUESTION OPerator:
(Answer Sheet)
QUESTION 2 System: RHR
Subject:
l Refueling Cavity Fill / Drain K/A & Rating: 005K109 3.6/3.9 You are the RO assigned to fill the refueling pool prior to refueling with the following conditions:
11 RHR pump and HX are providing shutdown cooling 12 RHR pump is in standby RWST level is 75% I While filling the refueling cavity using 11 RHR pump, you observe l Question: RWST level drop and refueling cavity level ini:rease at the expected rate. When the task is nearly complete, you notice: j RWST levelis 18% and stable Refueling cavity level is 752' and stable l All equipment is operating as expected There are no equipment failures or misalignments I Why has level stopped changing in both containment and the RWST?
Answer: RWST head is less than RCS head.
Reference:
C 4.1 rev. #7 pag e 32 Reference Material Use: lYes Z No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
i
)
l i
o PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98
. WORKSHEET !
l l
TASK TITLE: Manual Makeup To The RWST ,
1 JPM NUMBER: SIMUL-3 Rev. O RELATED PRA None ,
INFORMATION (SEE PITC 2.3):
TASK NUMBER: 004.ATI.13 K/A NUMBERS: 2.1.23 i
APPLICABLE METHOD OF TESTING:
l Simulate Performance: O Actual Performance: @
l Evaluation Location: Turbine Buildir.g: O Auxiliary Building: O Simulator: @ Control Room: O i
Other: O Time for Completion: 8 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: C (Check all that apply)
PREPARED BY: Mark J Jones DA TE: 3/25/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
Resp Grp: O Page 1 of 9 Assoc Ref: PITC TP 3.7
- l M'nual Mrknup To Th3 RWST l SIMUL-3 Rev. 0 l I
2 Operator: (SRO / RO / NLO) )
Evaluator:
J Date: I READ TO THE OPERATOR l l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be 4 s:tisfied. l 1
-- -' ~- -
INITIAL CONDITIONS: 1 o 11 RWST levelindicates 70%
- o. Unit 1 is at 100% power.
o No equipmen* OOS. ;
o Present RWST boron concentration is 2650 ppm. j INITIATING CUES: ;
! o The SS directs you to increase RWST level to 75%
o Report completion to the SS. !
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l l l l
l PITCQ-089 Page 2 of 9 Rev 5 10/98
A
- l M:nual Makaup To Tha RWST l SIMUL-3 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
. C12.5 Tcsk Standards: RWST level increased as indicated by makeup integrators counting up.
I Start Time:
NOTE: When providing " Evaluator Cues" to the exarninee, care must be exercised to avoid
, _ prompting the examinee. Typically cues s're only provided when the examinee's
~
actions warrant receiving the information (i.e. the exaidihee looks ~or asks fo'r flia ~ ^
in'dication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to i meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Using C12.5 Figure 1, Blended Flow Nomograph, estimate the setting for Critical HC-110, BORIC ACID FLOW CONT, to obtain the desired blended flow '
concentration.
l 1 Standard: HC-110 setting determined to be 65% (i S%).
Evaluator Note: The reactor makeup water manual loader, HFC-111, is norm *F . set at 45%.
Performance: SATISFACTORY UNSATISFACTORY Comments:
l PITCQ-089 - Page 3 of 9 Rev 5 10/98 C
4 1- l Manual Makeup To The RWST l SIMUL-3 Rev. 0 l Performance Step: Verify the boric acid and reactor makeup flow controllers are in " AUTO".
Critical i Standard: HC-110 and HC-111 are verified in " AUTO".
l l
l Performance: SATISFACTORY UNSATISFACTORY 1 .
Comments:
Performance Step: Place CS-46300, MAKEUP MODE SELECTOR, in " MANUAL".
Critical X (S-1)
Standard:- CS-46300 placed in " MANUAL"; CS-46457 green light lit, red light _ .
extinguished.
Performance: SATISFACTORY UNSATISFACTORY Comments:
~
Performance Step: To add makeup to 11 RWST, OPEN the following valves:
Critical X (S-1) VC-11-59, MANUAL MAKEUP HDR ISOL.
81-17-1, BLENDER TO RWST.
Standard: Aux Building Operator requested to open VC-11-59 and SI-17-1.
Evaluator Note: The booth operator will act as Aux Building Operator to open SI-17-1.
VC-11-59 is not modeled on the simulator.
Evaluator Cue: The booth operator will report as Aux Building Operator that, "VC 59 and SI-17-1 are open."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 4 of 9 Rev 5 10/98
l Mrnual Makeup To T ha RWST
__ l SIMUL-3 Rev. 0 l Performance Step: Set HC-110, BORIC ACID FLOW CONT, to the setting previously Critical X (S-1) determined.
Standard: HC-110 set to approximately 65%
)
Evaluator Note: The critical part of this step is setting the HIC-110 to at least 65% It is acceptable to set the controller above 65%
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Set batch integrators 1YlC110 and 1YlC111 near their maximum settings.
Critical X (S-1)
Standard: Boric acid and reactor makeup water batch integrators,1YlC110 and 1YlC111, set near maximum.
Evaluator Note: Operator may set integrators for a specific value. The critical task is satisfied when the integrators are set above zero.
Performance: SATISFACTORY UNSATISFACTORY Comments: .
l r-erformance Step: Momentarily place CS-46457, BORIC ACID MAKEUP, to " START", to Critical X (S-2) initiate manual makeup.
Standard: CS-46457 momentarily placed to " START"; red light lit, green light extinguished.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 5 of 9 Rev 5 10/98 L
l.
- l. l M" nuel Mak up To Tha RWST l SIMUL-3 Rev. 0 l Terminating Cues: When the makeup integrators begin counb..; p, Indicating flow, inform l the candidate that, "this JPM is complete."
Stop Time:
l 4
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l PITCQ-089 Page 6 of 9 Rev 5 10/98 l
C: '
l t
/* l M:'nuri Mrk"up To Tha RWST l SIMUL-3 Roy. 0 l SIMULATOR SETUP instructor Guide: !
- Initialize the simulator to 1C-10.
- Enter remote to adjust RWST level to 70%. (Relative Order 0)
. When the candidate is ready, place the simulator in "RUN".
. When directed during JPM performance, enter remote to open SI-17-1. (Relative Order 1) t l
l PITCO-089 Page 7 of 9 Rev 5 10/98 i
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TURNOVER SHEET j i
INITIAL CONDITIONS:
o 11 RWST levelindicates 70%.
o Unit 1 is at 100% power.
o' No equipment OOS.
-o Present RWST boron concentration is 2650 ppm.
INITIATING CUES:
o The SS directs you to increase RWST level to 75%.
o Report completion to the SS.
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PITCQ-089 Page 9 of 9 Rev 5 10/98
1 JPM:
JPM QUESTION OPerator:
l (Arawer Sheet) t QUESTION 1 System: CVCS
Subject:
l Tech Spec For RWST KIA & Rating: 2.1.33 3.4/4.0 in preparation for RCS heat up following a refueling, the following plant conditions are observed:
- 11 BAST at 12.3 weight /% concentration
- 11 BAST level at 65%
Quastion:
- 11 BAST temp is 172*F
- RWST level at 66%
Can the RCS exceed 200'F? Why or why not? ,
RWST does not meet the minimum volume of 200,000 gallons, which I Answer: corresponds to 68% level.
Reference:
Tech. Spec. 3.3.A.1.a and the Tank Book page 73 Reference Material Use: l Yes @ No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
I 1
Scr% W..
JPM: OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 2 System: CVCS
Subject:
l VCT Level Control K/A & Rating: 004K412 3.1/3.4 You are performing a cooldown on Unit 1, which requires significant RCS make up via the CVCS rystem when the following sequence occurs:
-A Manual make-up using the DILUTE mode is completed
-The MAKEUP MODE SELECTOR is placed in " AUTO" Question: -The BORIC ACID MAKEUP CONTROL switch is NOT taken to
" START".
l 1 -No other operator action is taken while the cooldown l continues.
Describe the sequence of events that occur over the next hour, with respect to the VCT level and any associated control functions.
VCT level will decrease to the auto make up setpoint (17%), but make up Answer: will not start. Level will decrease to the lo-lo level (2 to 4%), the VCT outlet will close and the RWST to charging pump suction will open.
Reference:
B-12A pages 14 - 19 Reference Material Use: 1Yes @ No O l Pedigree: l New CANDIDATES RESPON$E: SAT: UNSAT:
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o PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 .10/98 WORKSHEET TASK TITLE: Transfer 1R-11/12 Sample Discharge From Containment To Aux Bldg Stack JPM NUMBER: SIMUL-4 Rev. O RELATED PRA None I.NFORMATION (SEE PITC 2.3):
TASK NUMBER: 073.ATI.01 K/A NUMBERS: 2.1.23 l
APPLICABLE METHOD OF TESTING:
Simulate Performance: C Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: @ Control Room: O Other: O Time for Completion: 2 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/25/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
l l
Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
l.- 1 Transfer 1R-11/12 Sampl1 Discharg3 From Containm:nt To Aux Bldg Stack l SIMUL-4 Rev. 0 l Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
o 1R-11/12 sample discharge is aligned to the Containment.
o Containment pressure is approaching 0.7 psig.
INITIATING CUES:
o The SS directs you to transfer 1R-11/12 sample discharge from the Containment to the Aux Building stack per C11 section 5.1.
o Report completion to the SS.
PITCQ-089 Page 2 of 8 Rev 5 10/98
- l Transfer 1R-11/12 Sample Discharg3 From Containment To Aux Bldg Stack l SIMUL-4 Rev. 0 l JPM PERFORMANCE INFORMATION 1
Required Materials: None 1
General
References:
C11-Task Standards: 1R-11/12 sample discharge aligned to the Aux Building stack.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with an "X'? below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. l l
l Performance Step: Verify S103, SAMPLE SELECTOR switch, located on 1R-11 drawer in the l Critical "CONTAIN" position, j l
Standard: S103 verified in the "CONTAIN" position.
I Performance: SATISFACTORY UNSATISFACTORY Comments:
l l
l PITCO-089 Page 3 of 8 Rev 5 10/98 l
~
o L- l Transfer 1R-11/12 Sampla Discharge From Containment To Aux Bldg Stack l SIMUL-4 Rev. 0 l i
Performance Step: CLOSE SV-33786, VENT SAMPLE RETURN by depressing S107, R-Critical X (S-1) 11/12 DISCHARGE TO CONTAINMENT, until the yellow light on the switch is OFF.
l Standard: SV-33786 closed by depressing S107; yellow light extinguished.
l l
Evaluator Note: If both S107 and S108 are depressed, then neither valve opens and I the pump trips on low flow. Only one valve can be opened at time.
l l
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Immediately OPEN SV-33785, VENT SAMPLE RETURN, by depressing Critical X (S-2) S108, R-11/12 DISCHARGE TO AUX STACK, until red light on the switch I is ON.
Standard: SV-33785 opened by depressing S108; red light lit.
Evaluator Note: if both S107 and S108 are depressed, then neither valve opens and the pump trips on low flow. Only one valve can be opened at time.
l l Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: When 1R-11,12 sample discharge is retumed to Aux Bldg, then OPEN Critical RD-5-2,1R-11/12 RAD MON SAMPLE INLET TEST.
Standard: Aux Building Operator requested to open RD-5-2.
Evaluator Note: RD-5-2 is not modeled on the simulator.
Evaluator Cue: Report as Aux Building Operator, "RD-5-2 is open."
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 4 of 8 Rev 5 10/98 I
( -
l- l Transfar 1R-11/12 Sampla Discharge From Containment To Aux Bldg Stack l SIMUL-4 Rev. 0 l Terminating Cues: The candidate should report to the SS that, "1R-11/12 sample discharge has been transferred to the Aux Building stack." At this point, inform the candidate that, "this JPM is complete."
Stop Time:
PITCQ-089 Page 5 of 8 Rev 5 10/98
r=
l Tr:nsf:r 1R-11/12 Sampb Discharga From Containm:nt To Aux Bldg Stack l SIMUL-4 Rev. 0 l SIMULATOR SETUP I
Instructor Guide:
o initielize the simulator to IC-10.
o Enter override to cause Containment Pressure indicator (PI-4127901) to indicate = 5 psig.
(Relative Order 0) l- o Ensure light bulbs for sample discharge to Aux Building Stack and Containment Building are good.
o Ensure 1R-11/12 suction is not isolated (by a SI).
o When the candidate is ready, place the simulator in "RUN".
1 PITCQ-089 Page 6 of 8 Rev 5 10/98 1
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TURNOVER SHEET INITIAL CONDITIONS: l o 1R-11/12 sample discharge is aligned to the Containment.
o' Containment pressure is approaching 0.7 psig.
INITIATING CUES:
-c The SS directs you to transfer 1R-11/12 sample discharge from the Containment to the Aux Building stack per C11 section 5.1.
e Report completion to the SS.
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l PITCO-089' Page 8 of 8 Rev 5 10/98 L.
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l JPM: 4 OPerator:
JPM QUESTION l (Answer Sheet)
QUESTION 1 System: Rad Monitors
Subject:
l Liquid Release Rad Monitor Malfunction KIA & Rating: 073K301 3.6/4.2 Unit 1 is at power with the following conditions:
-121 ADT monitor tank is ready for release.
-R-18 background count rate is 5,500 cpm.
Question: In preparation for releasing 121 ADT monitor tank to the river, the CHECK SOURCE button is depressed on R-18 and the count rate is, 30,000 cpm.
What,if anything, must be done regarding radition monitors to release 121 ADT MonitorTank to the river?
gswer., Have HPs bug R-18 in the monthly bug position and verify Monthly Bug Point reading minus background is within 3 E+4 and 8 E+4.
Reference:
C21.1-5.1; 121 ADT Monitor Tank Release pp. 6-7.
Reference Material Use: l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT:
4 JPM: 4 OPeraton JPM QUESTION (Answer Sheet)
QUESTION 2 System: Rad Monitors
Subject:
l Rad Monitor Downscale Failure K/A & Rating: 073A202 2.7/3.2 Given the following Unit 1 plant conditions:
-Containment inservice Purge is in service
-Fuel Handling is in progress Question:
-All raditiation monitors are in service 1R-11 falls downscale and must be removed from service. What action, if any must be taken?
Answer: Terminate fuel handling operation.
C-11, Sect 6.4.4
Reference:
D-5.2 Reference Material Use: lYes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT:
1 1
4 PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET TASK TITLE: Respond To A RCP Thermal Barrier Hx Leak JPM NUMBER: SIMUL-5 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 008.ATI.11 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: @ Control Room: C Other: O Time for Completion: 8 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/26/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
. l R*:spcod To A itCP Thrrmil Btrri:r Hx Lenk l SIMUL-5 Rev. 0 l I
l
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to dmulate or discuss, and provide initiating cues.
When you complete the task successfully, the objectwe for this job performance measure will be satisfied.
~~ ~
INITIAL CONDITIONS:
. Unit 1 is at 100% power.
. Annunciator 47022-0109, HI RADIATION TRAIN A PANEL ALARM has just actuated.
INITIATING CUES:
. The SS directs you to respond to the alarm per the appropriate Alarm Response Procedure.
PITCO-089 Page 2 of 8 Rev 5 10/98
,4'
- l R:spond To A RCP Thtrmal Barri:r Hx Leak l SIMUL-5 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
C47022, C47047, C14 AOP2 Task Standards: 11 CC Surge Tank vent valve closed and 11 RCP Thermal Barrier Hx isolated.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid
~
prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee 15oks or asks foi the~ - ' '
indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Determine the initiating alarm and respond to the alarm as specified in Critical C47047, TRAIN A RADIATION MONITORING SYSTEM ALARM RESPONSE PROCEDURES.
Standard: R-39 determined to be the alarming rad monitor and C47047 transitioned to.
Evaluator Note: This step is prescribed in C47022. The operator may not refer to this procedure, but rather perform this action from memory.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 3 of 8 Rev 5 10/98
4 l R:spond To A RCP Thermal Barrier Hx Leak l SIMUL-5 Rev. 0 l Performance Step: Close 11 Component Cooling Surge Tank Vent valve MV-32088.
Critical X (S-1)
Standard: 11 CC Surge Tank Vent valve MV-32088 closed by placing CS-46024 in the CLOSE position; green light lit, red light extinguished.
Evaluator Note: This step is an automatic action that should be verified and since the valve will have failed to automatically close, it will have to be closed manually.
Evaluator Cue: If the candidate reports to the SS that he/she is closing the 11 CC Surge Tank Vent valve MV-32088, then provide verbatim repeat back to the candidate acknowledging his report.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Refer to appropriate actions as described in C14 AOP2, LEAKAGE INTO Critical THE COMPONENT COOLING SYSTEM.
Standard: C14 AOP2 transitioned to.
Performance: SATISFACTORY UNSATISFACTORY Comments: i l
PITCQ-089 Page 4 of 8 Rev 5 10/98
p l
~
1 l
l R spond To A RCP Thermal Barrier Hx Leak l SIMUL-5 Rev. 0 l l Performance Step: Check radiation monitor R-39. High radiation indicates contaminated !
i Critical water leakage into the Component Cooling System. Refer to Section C4 1 l
AOP1, Reactor Coolant Leak, for manual actions in the case of a reactor coolant leak into the Component Cooling System. Refer to Table 1 for l other possible sources of contaminated water.
Standard: C4 AOP1 referred to and/or SS informed that it needs to be implemented for RCS Leak and Table 1 reviewed for possible leak sources.
Evaluator Note: Another operator will implement C4 AOP1.
Performance: SATISFACTORY UNSATISFACTORY Comments: .
Performance Step: Check RCP CC outlet flow and temperatures. If flow or temperature is Critical X (S-2) higher than normal, then CLOSE the affected RCP thermal barrier heat exchanger CC retum valve.
Standard: 11 RCP CC outlet flow (F1-4127601) and temperatures (TI-4127602) determined to be higher than normal and 11 RCP THERM BARRIER CLNT OUTL valve CV-31245 closed by placing CS-46022 in the CLOSE position; green light lit, red light extinguished.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cuas: When the candidate closes CV-31245, inform the candidate that, "this JPM is complete."
l Stop Time:
- l l '
l l
l l
PITCO-089 Page 5 of 8 Rev 5 10/98 t .
. I Rispond To A RCP Thirmal Barrier Hx Leak l SIMUL-5 Rev. 0 l SIMULATOR SETUP instructor Guide:
. Initialize the simulator to IC-10.
. Enter overrides to fail auto closure of CC Surge Tank Vent. (Relative Order 0)
. Enter malfunction to cause 40 gpm leak in 11 RCP Thermal Barrier Heat Exchanger. (Relative Order 0) l . When the candidate is ready, place the simulator in "RUN".
. When the candidate places CS-46024 for 11 CC Surge Tank Vent valve MV-32088 in the CLOSE position, remove the overrides to fail auto closure. (Relative Order 1) l f
l l
PITCQ-089 Page 6 of 8 Rev 5 10/98
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, TURNOVER SHEET l l
l lNITIAL CONDITIONS:
. Unit 1 is at 100% power.
. Annunciator 47022-0109, HI RADIATION TRAIN A PANEL ALARM has just actuated.
)
INITIATING CUES:
l
- The SS directs you to respond to the alarm per the appropriate Alarm Response Procedure. I i
I l
l l
PITCO-089 Page 8 of 8 Rev 5 10/98 l
l l
JPM: 5 JPM QUESTION Operator:
(Answer Sheet)
QUESTION 1 System: CC
Subject:
l Actions For Leak On CC To RCP KIA & Rating: 015AK302 3.1/3.1 Unit 2 is at 100% power and all systems normal, when the following occur:
-21 CC Surge Tank Level begins lowering Question.*
-CC flow from 22 RCP indicates 80 gpm
-22 RCP motor bearing temperatures are increasing What actions are required in response to these conditions?
Trip the reactor Answer: Stop 21 and 22 RCP's isolate 21 and 22 RCP component cooling supply and return.
Reference:
2C14.AOP1 pp. 4-5; Rev. 4 Reference Material Use: l Yes @) No O _ l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT:
T ,
1 JPM:5 OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 2 System: CC
Subject:
l Expected Response Of Surge Tank 4 l
K/A & Rating: 008K402 2.9/2.7 l Given the following conditions: ;
l
-Both units are in a normal 100% power lineup
-No CC transfer is in progress Question:
A 25 gpm leak out of the CC system occurs. Assuming no operator action, what automatic actions will occur with respect to both unit's CC systems?
Both 11 and 21 CC Surge Tank levels will decrease and alarm at the low level set point, resulting in opening of their respective aut makeup valve.
Answer: Levels will oscillate between normal level and the low level alarm setpoint as the makeup valves open and close.
1C14 AOP1 Pgs. 2 and 3
Reference:
C47020:0203 NF-39245-1 l Reference Material Use: l Yes O No @ l Pedigree: lNew !
l i
CANDIDATES RESPONSE: SAT: UNSAT: l
PITCQ-089-- JOB PERFORMANCE MEASURE R3v. 5 - 10/98 WORKSHEET l
TASK TITLE: Depressurize The RCS Following A Steamline Break JPM NUMBER: SIMUL-6 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 301.ATI.19 ,
l K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
S'mulate Performence: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator @ Control Room: O Other: O Time for Completion: 6 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O ;
(Check at that apply) l l
PREPARED BY: Mark J Jones DATE: 3/26/99 REVIEWED BY: DATE:
I APPRO'/ED BY: DATE:
Resp Grp; O Page 1 of 8 Assoc Ref: PITC TP 3.7 k_
l Depressuriza Tha RCS Following A St:: mlina Braak l SIMUL-6 Rev. 0 l Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
.o Both SGs are depressurizing slowly in an uncontrolled manner. !
o - Uncontrolled depressurization of both SGs actions have been completed including 1E-0,1E-2, and 1ECA-2.1 through step 34.
o Letdown has been established per C12.1.
INITIATING CUES:
o The SS directs you to continue actions per 1ECA-2.1, starting at step 35.
l l
j PITCO-089 Page 2 of 8 Rev 5 10/98 l
i l D:: pressurize The RCS Following A Steamline Break l SIMUL-6 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
1 E-0,1 E-2,1 ECA-2.1 Task Standards: RCS pressure reduced to less than 400 psig using Auxiliary Spray.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the
. indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
' Performance Step: Check RCS Pressure - LESS THAN 400 PSIG. I Critical Standard: RCS pressure checked and determined to be greater than 400 psig.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine that auxiliary spray is to be used to depressurize the RCS.
Critical Standard: Normal spray determined to not be available due to RCPs being secured.
Auxiliary spray determined to be available since letdown is in service.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 3 of 8 Rev 5 10/98
i .
l D: pressurize The RCS Following A Steamline Break l SIMUL-6 Rev. 0 l l
' Performance Step: Depressurize RCS using auxiliary spray.
Critical X (S-1)
Standard: 1. CV-31329, AUX PRZR SPRAY FROM REGEN HX, opened by momentarily placing CS-46295 to "OPEN", red light lit, green light I extinguished.
- 2. CV-31328, REGEN HX CHG LINE OUTL, closed by momentarily i placing CS-46296 to "CLOSE"; green light lit, red light extinguished.
Evaluator Note: Candidate may adjust charging pump speed and charging flow control valve (CV-31198) to control spray flow.
Candidate shall not depressurize below 20 F subcooling.
l l
Performance: SATISFACTORY UNSATISFACTORY l i
Comments: l Performance Step: When RCS is reduced to less than 400 psig, stop depressurization, j Critical X (S-2)
Standard: 1. CV-31328, REGEN HX CHG LINE OUTL, opened by momentarily '
placing CS-46296 to "OPEN"; red light lit, green light extinguished.
- 2. CV-31329, AUX PRZR SPRAY FROM REGEN HX, closed by 1 momentarily placing CS-46295 to "CLOSE"; green light lit, red light '
extinguished.
Evaluator Note: Candidate shall stop depressurization prior to decreasing below 20
- F subcooling.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 4 of 8 Rev 5 10/98
l Deprassurize The RCS Following A St:amline Break l SIMUL-6 Rev. 0 l l
' Performance Step: Retum to Step 34.
Critical Standard: Step 35 completed and step 34 retumed to.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When the RCS is depressurized to less than 400 psig and the candidate indicates that he/she is returning to step 34, inform the candidnte that, "this JPM is complete."
Stop Time:
i 1
j l
l l
PITCC-089 Page 5 of 8 Rev 5 10/98
I. .
l Depr:ssurize Th3 RCS Following A Stramlin3 Bri:ak l SIMUL-6 Rnv. 0 l
! SIMULATOR SETUP Instructor Guide:
o initialize the simulator to IC-10.
o Enter malfunctions to cause a 5% steam line break, outside containment, on both A and B SGs.
(Relative Order 0) o Enter malfunctions to cause 1R breakers to fail to close, preventing Bus 11 and 12 transfer.
(Relative Order 0) o Place the simulator in "RUN".
o Trip reactor and initiate St.
o Perform E-0 and ECA-2.1 steps 1 through 34.
o Ensure the following conditions are established:
. Letdown is in service RCPs are secured
. Pressurizer heaters are secured
. RCS pressure is greater than 400 psig.
e Place the simulator in " FREEZE".
c ~ When the candidate is ready, place the simulator in "RUN".
1 I
PITCQ-089 Page 6 of 8 Rev 5 10/98
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l TURNOVER SHEET INITIAL CONDITIONS:
I o Both SGs are depressurizing slowly in an uncontrolled manner.
! o Uncontrolled depressurization of both SGs actions have been completed including 1E-0,1E-2, and 1ECA-2.1 through step 34.
o Letdown has been established per C12.1.
INITIATING CUES:
o The SS directs you to continue actions per 1ECA-2.1, starting at step 35.
l
[
1 l
PlTCO-089 Page 8 of 8 Rev 5 10/98 I
i
r JPM: 6 JPM QUESTION OPerator: 1 (Answer Sheet)
QUESTION 1 Pressurizer Effect Of Leaking Pressurizer Safety On j System:
Subject:
Pressure Control PRT K/A & Rating: 008AA108 3.8/3.8 Given the following unit 2 conditions:
-RCS daily leak rate surveillance results in leakage of 2 gpm.
-Unit 2 charging pump leakage is .025 gpm Question: -Unit 2 pressurizer safety valve is determined to be leaking.
-The PRT level has increased from 72.5% to 76% over 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
The SS asks you to determine what portion of the total leakage is unidentified leakage.
The PRT level increase is approximately 200 gallons in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Answer.,
200 gallons in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (420 min) equals approximately .475 gpm.
Add .025 gpm charging leakage Leaves 1.5 gpm (+/- 0.1) gpm unidentified. ,
Reference:
Tank book tab 70 l Reference Material Use: l Yes @ No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
l
9 JPM: 6 OPerator:
JPM QUESTION (Answer Sheet)
I QUESTION 2 mssuns Relationship Between Charging, Auxiliary System:
Subject:
Pressure Control Spray, And The Pressurizer K/A & Rating: 004K117 3.4/3.4 Given the following Unit 1 conditions:
-Letdown isolated
-12 charging pump in service
-PRZR Pressurs is 435 psig Question: -Loop T hots are 380.*F i
-Loop T colds are 378'F
-VCT temperature 111*F ,
-PRT temperature 79'F {
Can Aux Spray be used to reduce RCS pressure? Why or why not?
No, PRZR pressure corresponds to about 456 F - 111*F VCT temperature Answer: (345'F) would exceed Tech Spec 3.1.B.2.b limit of 320'F. ,
Steam Tables Referenee: T.S. 3.1.B.2.b 1C1.3 Limitation 4.1.5 Reference Material Use: l Yes O No @ l Pedigree: }New CANDIDATES RESPONSE: SAT: UNSAT:
l l
l l
l
. PITCQ-089 ' JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET TASK TITLE: Respond To High Containment Pressure (Manual Containment Spray Initiation)
JPM NUMBER: SIMUL-7 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
l TASK NUMBER: 0260050101 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: O Actual Performance: @
Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: @ Control Room: O Other. O Time for Completion: 7 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: O (Check all that apply) l l
PREPARED BY: Mark J Jones DATE: 3/26/99 1
L REVIEWED BY: DATE:
1 APPROVED BY: DATE:
i l
Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
I .
l
,- R:spond To High Containm:nt Pressure (Manual Containm:nt Spray SIMUL-7 Rev. O Initiation)
Evaluator:
Date:
READ TO THE OPERATOR I
l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
o Steamline break laside containment has occurred.
o 1E-0 has been performed, and transition to 1E-2 was directed.
o The SM detects an orange path in containment.
INITIATING CUES:
o The SS directs you to respond to the orange path in containment per 1FR-Z.1.
o Report completion to the SS.
l l
l l
l PITCQ-089 Page 2 of 8 Rev 5 10/98 l
4 Respond To High Containment Pressure (Manual Containment Spray SIMUL-7 Rev. O Initiation)
JPM PERFORMANCE INFORMATION Required Materials: None !
I General
References:
1FR-Z.1 I Task Standards: Containment spray pumps running with proper valve alignment.
Start Time:
l NOTE: When providing " Evaluator. Cues" to the examinee, care must be exercised to avoid
~ ~ ~
prompting ths.examinsi.~~ Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the j i indication).-
1 NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Verify Containment Isolation Valves CLOSED.
l Critical i Standard: All " Containment Isolation" lights on panel 44104 verified lit except for personnel and maintenance airlock doors and auxiliary feedwater isolation l valves.
1 Performance: SATISFACTORY UNSATISFACTORY Comments:
)
i i
i i
t PITCQ-089 Page 3 of 8 Rev 5 10/98 l
i I
L
4 R::spond To High Containment Pressure (Manual Containment Spray SIMUL-7 Rev. O Initiation)
Performance Step: Check containment spray- ACTUATED.
Critical Standard: Containment Spray Actuated alarm,47019:0103, verified lit.
Evaluator Note: The procedure cautions that if 1ECA-1.1, Loss of Emergency Coolant Recirculation has been implemented, containment spray should be operated as directed by that procedure.
Evaluator Cue: If asked, report that, "1ECA-1.1 has not been implemented."
l Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Check containment spray pump - RUNNING, if not stad.
Critical X (S-1) i Standard: Containment spray pumps determined to not be running and then started by momentarily placing CS-46008 and CS-46009 to " START"; red lights lit, green lights extinguished.
1 4
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Check containment spray system valves - PROPER EMERGENCY Critical ALIGNMENT (containment spray pump discharge valves MV-32103 and MV-32105).
Standard: MV-32103 and MV-32105 red indicating lights 44007 and 44008 verified lit.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 4 of 8 Rev 5 10/98 1
Respond To High Containment Pressure (Manual Containment Spray SIMUL-7 Rev. O initiation) ,
Performance Step: Check containment spray system valves - PROPER EMERGENCY Critical X (S-2) ALIGNMENT (containment spray pump suctions from caustic standpipe CV-31941 and CV-31938).
Standard: CV-31941 and CV-31938 opened by momentarily placing CS-46124 and CS-46125 to "OPEN"; red lights lit, green lights extinguished.
Evaluator Note: These valves will have to be opened manually.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When the containment spray pump discharge valves are verified open, inform the candidate that, "this JPM is complete."
Stop Time:
1 PITCQ-089 Page 5 of 8 Rev 5 10/98
f ~
1
~R spond To High Containmsnt Pressura (Manual Containment Spray SIMUL-7 Rev. O Initiation)
SIMULATOR SETUP l
Instructor Guide: l l o Initialize the simulator to IC-10. l l o Enter malfunctions to defeat auto start of containment spray pumps. (Relative Order 0) l o Enter malfunctions to fail auto opening of caustic addition valves. (Relative Order 0) o Enter malfunction to cause a 100% steamline break, inside containment, on 'B' SG. (Relative Order 0) o Place the simulator in "RUN".
o Perform E-0. I o When containment pressure peaks (about 18 psig), enter malfunction to cause a 100% steamline break, inside containment, on 'A' SG. (Relative Order 1) o Ensure 200 gpm AFW flow to SGs such that there is no red path on Heat Sink.
o When containment pressure is above 23 psig and orange path is indicated in containment, place l the simulator in " FREEZE".
l o When the candidate is ready, place the simulator in "RUN".
1 i
l l
l l
l I
l l
1 PITCO-089 Page 6 of 8 Rev 5 10/98 i
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TURNOVER SHEET INITIAL CONDITIONS:
o Steamline break inside containment has occurred.
o- 1E-0 has been performed, and transition to 1E-2 was directed.
o The SM detects an orange path in containment.
INITIATING CUES:
o The SS directs you to respond to the orange path in containment per 1 FR-Z.1.
o Report completion to the SS.
1 l
PITCO-089 Page 8 of 8 Rev 5 10/98
JPM: 7 OPerator:
JPM QUESTION '
(Answer Sheet)
QUESTION 1 System: CS
Subject:
l Heat Removal Capability (w/CFUs)
K/A & Rating: (W)E14K2.2 3.4/3.8 Unit 1 is in Hot Shut Down, in preparation for cooldown prior to refueling with the following conditions.
-11 Containment Spray Pump is OOS for a PM
-The RCS is borated to Cold SD A loss of bus 12 trips 12 RCP, causing an abrupt RCS pressure in rease. This results in a design basis LOCA and the following Question:
conditions:
-Containment pressure is 21 psig and increasing.
-All four CFCUs are tripped on overload.
-Containment Spray is manually actuated.
Explain how and why you expect containment pressure to respond over the next 15 minutes.
Containment pressure will continue to increase at a slower rate. One CS Answer.
ump cannot remove enough heat to reduce pressure in the short term.
Reference:
TS 3.3 bases page B 3.3-3 i Reference Material Use: lYes 3 No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
F ' .
JPM:7 OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 2 System: 1CS
Subject:
l Failure Of Caustic Addition During LOCA K/A & Rating: 026A205 3.7/4.1 Following a large break LOCA resulting in fuel failure, the RO notes that the Caustic Standpipe level is not decreasing after Containment Spray actuation.
Question:
What affect does the steady Caustic Standpipe level have on Containment conditions?
Containment pH will be lower than expected (which will result in higher Answer:
airbome iodine concentrations and increased probability for corrosion).
USAR 6.4.3.2
Reference:
B-18D page 8 Reference Material Use: l Yes O No @ l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
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[ e PITCQ-089. JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET l
TASK TITLE: Emergency Starting Of 122 Diesel Fire Pump l JPM NUMBER: PLANT-8 Rev. O RELATED PRA PRA important Event INFORMATION (SEE PITC 2.3):
TASK NUMBER: 086.ATI.12 / 086.ATI.14 l K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: @ Actual Performance: O Evaluation Location: Turbine Building: O Auxiliary Building: O Simulator: O Control Room: O Other: @
Screenhouse Time for Completion: 10 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: @
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
1 i l Resp Grp: O Page 1 of 9 Assoc Ref: PITC TP 3.7 l l
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- l Emergency Starting Of 122 Di:stl Fira Pump l PLANT-8 Rev. 0 l j Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
o The Unit i SS has ordered the Control Room to be evacuated per F5 Appendix B.
o .You have reported to the Screenhouse.
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o Using PI-11082, you have discovered header pressure is 0 psig and that 122 Diesel Fire Pump is not running. t INITIATING CUES:
o- The Unit 1 SS directs you to manually start the 122 Diesel Fire Pump per F5 Appendix B, 1 Attachment L.
o Report completion to the Unit 1 SS.
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PITCQ-089 Page 2 of 9 Rev 5 10/98
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. l Emnrgency Starting Of 122 Dissel Firo Pump l PLANT-8 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: Copy of F5 Appendix B, Attachment L.
General
References:
F5 Appendix B Task Standards: 122 Diesel Fire Pump is running.
Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the' indication).
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: At panel 136-2, place DSL FIRE PMP 121 OIL STG TK Pump local Critical _ AUTO / REMOTE / LOCAL control switch CS-19081 in " AUTO".
Standard: CS-19081 is placed in the " AUTO" position.
Evaluator Note: Panel 136-2 is on the north wall behind the Diesel Fire Pump.
Evaluator Cue: CS-19081 is in the AUTO position.
Performance: SATISFACTORY UNSATISFACTORY l Comments:
PITCQ-089 Page 3 of 9 Rev 5 10/98
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l Emsrgency Starting Of 122 Diessi Fira Pump l PLANT-8 Rev. 0 l l
Performance Step: Ensure the Battery Charger Control switch is in "ON".
Critical Standard: Battery Charger Control switch checked in "ON".
1 Evaluator Cue: Battery Charger Control switch is in "ON".
l Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Depress and release the RESET pushbutton CS-70394-04 located inside
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Critical of the diesel control cabinet.
Standard: CS-70394-04 depressed and released, l Evaluator Cue: Reset pushbutton has been depressed and released.
I Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Turn local 5-position selector switch CS-70394-01 to " MAN-A" or " MAN-B".
Critical Standard: CS-70394-01 tumed to " MAN-A" or " MAN-B".
Evaluator Cue: CS-70394 01 is in (selected position: " MAN-A" or " MAN-B").
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 4 of 9 Rev 5 10/98
l Em:rgency Starting Of 122 Dias:1 Fire Pump l PLANT-8 Rev. 0 l Performance Step: Depress START pushbutton CS-70394-02 to crank engine.
Critical Standard: CS-70394-02 is depressed for no longer than 30 seconds.
Evaluator Note: The engine is not to be cranked on one set of batteries continuously for longer than 30 seconds.
Evaluator Cue: Engine does not crank.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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Performance Step: Tum local 5-position selector switch to the opposite MANUAL position of
. Critical the position selected previously.
Standard: CS-70394-01 tumed to opposite " MAN-A" or " MAN-B" of the position selected previously.
Evaluator Cue: CS-70394 01 is in (selected position: " MAN-A" or " MAN-B").
Performance: SATISFACTORY UNSATISFACTORY Comments:
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PITCO-089 Page 5 of 9 Rev 5 10/98
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l Em:rg:ncy Starting Of 122 Dirs:1 Fire Pump l PLANT-8 Rev. 0 l l \
l Performance Step: Depress START pushbutton CS-70394-02 to crank engine. l Critical Standard: CS-70394-02 is depressed for no longer than 30 seconds.
Evaluator Note: The engine is not to be cranked on one set of batteries continuously forlonger than 30 seconds.
Evaluator Cue: Engine does not crank.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine if an Emergency situation exists.
Critical !
Standard: Emergency situation determined to exist. )
Evaluator Cue: 122 Diesel Fire Pump MUST be started to help combat the fire.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 6 of 9 Rev 5 10/98
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l Em::rg::ncy Starting Of 122 Diesel Fire Pump l PLANT-8 Rev. 0 l Performance Step: Tum the Manual Override Knob fully clockwise to bypass the electric Critical X (S-1) solenoid control and permit fuel flow.
Standard: Manual Override Knob turned fully clockwise.
Evaluator Note: The manual knob is a small yellow knob on the south side of the engine, located to the left of the oil filter.
Evaluator Cue: Manual Override Knob is fully clockwise.
Performance: SATISFACTORY UNSATISFACTORY ,
Comments:
Performance Step: OPEN cooling line bypass valve to the heat exchanger FP-121-3.
Critical X (S-2)
Standard: FP-121-3 0pened.
Evaluator Cue: FP-121-3 is open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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PITCO-089 Page 7 of 9 Rev 5 10/98
I Em:rg:ncy Starting Of 122 Diesel Fire Pump l PLANT-8 Rev. 0 l Performance Step: Lift CONTACTOR A START LEVER to the Emergency Start.
Critical X (S-3)
Standard: Contactor A Start Lever lifted to the Emergency Start.
l Evaluator Note: The Contactor A Start Lever is located on the north side of the engine, about knee high.
Evaluator Cue: 122 Diesel Fire Pump starts.
Performance: SATISFACTORY UNSATISFACTORY ,
Comments:
Terminating Cues: The candidate should report to the Unit 1 SS that,"122 Diesel Fire Pump is running." At this point, inform the candidate that,"this JPM is complete."
Stop Time:
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PITCQ-089 Page 8 of 9 Rev 5 10/98
l TURNOVER SHEET i
INITIAL CONDITIONS:
o The Unit 1 SS has ordered the Control Room to be evacuated per F5 Appendix B.
o You have reported to the Screenhouse.
o Using Pl-11082, you have discovered header pressure is O psig and that 122 Diesel Fire Pump is not running.
INITIATING CUES:
o The Unit 1 SS directs you to manually start the 122 Diesel Fire Pump per F5 Appendix B, Attachment L.
o Report completion to the Unit 1 SS.
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l PITCQ-089 Page 9 of 9 Rev 5 10/98 t
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JPM: 8 OPerator:
JPM QUESTION l (Answer Sheet) _
QUESTION 1 System: Fire Protection
Subject:
Interlocks That Protect The Turbine Generator Exciter KIA & Rating: 086K407 2.5/2.8 A fire has occurred in the Unit 1 turbine generator exciter. The turbine bearing pre-action valve (PA-14) has opened. Exciter bearing ne 24-9 is in alann.
Question:
What operator action (s) is(are) required to establish water flow through the sprinkler system?
a) Deenergize the exciter (open the field breaker)
Answer.
b) Open FP-134-1, Exciter Bearing Fire Protection Manual Valve F-5 App. A, Zone 24, Rev 5
Reference:
C31, 5.11, P. 52, Rev 23 Reference Material Use: l Yes @ No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
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l JPM: 8 Operator:
JPM QUESTION (Answer Sheet)
QUESTION 2 System: Fire Protection
Subject:
Action For Fire in The Plant (PRA Important Event)
K/A & Rating: 2.4.27 3.0/3.5 A fire alarm in Zone 19 has occurred. What action (s) must be taken to Question: reduce the probability of the Reactor Head Vent System inadvertently actuating and possibly causing core damage?
Open Panel 11, Ckt 18 and Panel 16, Ckt 18. (Deenergizes Panels 191 {
Answer: and 162 respectively) This is done to deenergize Reactor Head Vent Solenoid power.
F5 App. A, Zone 19, P.2, Rev 5
Reference:
F5 App. D, P. 39 & 40, Rev 4 ,
Reference Material Use: l Yes @ No O l Pedigree: l New !
CANDIDATES RESPONSE: SAT: UNSAT:
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PITCQ-089 JOB PERFORMANCE MEASURE Rev.5 10/98 WORKSHEET TASK TITLE: Vent Containment Using Post LOCA Vent System l JPM NUMBER: PLANT-9 Rev. 0 RELATED PRA None i INFORMATION (SEE PITC 2.3):
TASK NUMBER: 024.ATI.04 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: 2 Actual Performance: O Evaluation Location: Turbine Building: O Auxiliary Building: @
Simulator: O Control Room: C l l
Other: O Time for Completion: 6 Minutes l
TASK APPLICABILITY: SRO: @ RO: 2 NLO: @
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
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Resp Grp: O Page 1 of 6 Assoc Ref: PITC TP 3.7
4 l Vent Containm:nt Using Post LOCA Vant Syst:m l PLANT-9 R v. 0 l Operator: (SRO / RO / NLO)
Evaluator:
Date:
READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
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INITIAL CONDITIONS:
. Unit 1 is at power and containment pressure is at 1.3 psig.
. Communications with the Control Room have been established.
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INITIATING CUES:
. The Unit 1 SS directs you to vent Unit 1 containment using the post LOCA vent system (Train A 11 only) per C19.4, beginning at step 5.1.5.
. Report completion to the Unit 1 SS.
i PITCQ-089 Page 2 of 6 Rev 5 10/98
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- l Vcnt Containm:nt Using Post LOCA Vent Syst:m l PLANT-9 Rev. 0 l l
JPM PERFORMANCE INFORMATION j l
Required Materials: Copy of C19.4, Section 5.1.
General
References:
C19.4 Task Standards: Train A 11 post LOCA vent simulated in service to vent containment pressure.
Start Time:
I NOTE: When providing " Evaluator Cues", to the examinee, care must be exercised to avoid 1 l
prompting the examinee. Typically cues are only'provided when the examinee's l actions warrant receiving the information (i.e. the examinee looks or asks for the j indication). A NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
l Performance Step: Remove the control switch cover lock for MV-32271 Train A 11 Post LOCA l l Critical X (S-1) Hydrogen Control Vent isolation (Key 222).
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Standard: CS-70905-01 coverlock removed. I l
i Evaluator Note: This JPM is performed from the Hydrogen Post LOCA Panel located i on the 715' elevation. i l
l Evaluator Cue: CS-70905-01 cover lock is removed.
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Performance: SATISFACTORY UNSATISFACTORY !
l Comments:
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PITCQ-089 Page 3 of 6 Rev 5 10/98
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l Vcnt Containment Using Post LOCA Vent System l PLANT-9 Rev. 0 l Performance Step: OPEN MV-32271 Train A 11 Post LOCA Hydrogen Control Vent isolation.
Critical X (S-1)
Standard: MV-32271 opened using CS-70905-01.
r Evaluator Note: The candidate may discuss the requirement for an him/her to close this valve within one minute following an accident.
Evaluator Cue: Red light lit; green light extinguished for MV-32271.
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! Performance: SATISFACTORY UNSATISFACTORY Comments:
l Performance Step: Remove Train A Hydrogen Post LOCA Panel cage cover lock (Key 222). j Critical X (S-2)
Standard: Train A Hydrogen Post LOCA Panel cage cover lock removed.
Evaluator Cue: Train A Hydrogen Post LOCA Panel cage cover lock removed.
Performance: SATISFACTORY UNSATISFACTORY Comments: i Performance Step: Tum the Foxboro Air Switch (CS-28242), to the " MAX" position to align the Critical X (S-2) large flow control office.
Standard: CS-28242 tumed to the " MAX" position.
l Evaluator Cue: CS-28242 is in the " MAX" position.
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Performance: SATISFACTORY UNSATISFACTORY Comments:
l PITCO-089 Page 4 of 6 Rev 5 10/98 l
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l Vent Containment Using Post LOCA Vent System l PLANT-9 Rev. 0 l Performance Step: Increase the pressure setting on the manual Foxboro Air Controller ML-Critical X (S-3) 28124 to 10-15 psig to open CV-31923.
Standard: ML-28124 setting increased to 10-15 psig.
Evaluator Cue: ML-28124 pressure indicator reads 13 psig.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When the foxboro air controller is simulated being set at 10 to 15 psig, inform the candidate that,"this JPM is complete."
Stop Time:
PITCQ-089 Page 5 of 6 Rev 5 10/98 l
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TURNOVER SHEET INITIAL CONDITIONS:
. Unit 1 is at power and containment pressure is at 1.3 psig.
. Communications with the Control Room have been established. I 1
INITIATING CUES: !
. The Unit 1 SS directs you to vent Unit 1 containment using the post LOCA vent system (Train A 11 only) per C19.4, beginning at step 5.1.5. !
. Report completion to the Unit 1 SS. l I
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JPM: 9 OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 1 System: Inservice Purge Response To SFP High l Post LOCA Vent
Subject:
Radiation K/A & Rating: 029K403 3.2/3.5 I The following Unit 1 plant conditions exist initially:
1 l
- Plant in Refueling Shut Down '
- Fuel movement in progress in Containment & Spent Fuel Pool
- Spent Fuel Pool normal ventilation in service Question: - Containment inservice Purge in service The top nozzle separates from a spent fuel element on the SFP crane and R-25 is in high alarm What is the affect (if any) on Sent Fuel Pool ventilation?
121 SFP normal supply and exhaust fans stop, Answer: 121 Spent Fuel and in-Service Purge exhaust fan continues to run -
(discharge to Unit i exhaust stack).
B-11, Pg. 33, Table B11-1 C47047 for R-25
Reference:
NF-40757-1 ,
Drawing SFP-004 l Refersnce Material Use: l Yes @ No O l Pedigree: lNew ;
i CANDIDATES RESPONSE: SAT: UNSAT:
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r JPM: 9 OPerator:
JPM QUESTION 1
(Answer Sheet)
QUESTION 2 System:
C
Subject:
Sources Of Hydrogen in Containment KIA & Rating: 028K503 2.9/3.6 Following a design Basis LOCA, what are the three sources of Question: Hydrogen production?
Answer: Zirc Wa,ter reaction, radiolitic decomposition of water, corrosion of metals
Reference:
Tech Spec basis 3.6 page 8.3.6-2 Refarence Material Use: lYes O No @ l Pedigree: lNew _
CANDIDATES RESPONSE: SAT: UNSAT:
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. PITCQ-089 JOB PERFORMANCE MEASURE Rev. 5 10/98 WORKSHEET TASK TITLE: Transfer Unit 2 480v Busses To Their Altemate Supply JPM NUMBER: PLANT-10 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 062.ATI.32
)
K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: @ Actual Performance: O Evaluation Location: Turbine Bui.iding: O Auxiliary Building: O l
Simulator: O Control Room: O ,
Other: SBO @
Building 11me for Completion: 7 Minutes TASK APPLICABILITY: SRO: @ RO: @ NLO: @
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 l
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REVIEWED BY: DATE:
APPROVED BY: DATE:
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Resp Grp: O Page 1 of 9 Assoc Ref: PITC TP 3.7
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E- l Transfer Unit 2 480v Buss:s To Th"ir Alt:rnata Supply l PLANT-10 Rev. 0 l Operator: (SRO / RO / NLO)
Evaluator:
Date: I l
, READ TO THE OPERATOR 1
I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied. ;
l INITIAL CONDITIONS:
o Unit 2 is in Cold Shutdown.
o Bus 26 needs to be isolated for a PM. l INITIATING CUES:
e The Control Room Operator directs you to transfer busses 221 and 222 to their alternate supply I using 2C20.6, Sections 5.15 and 5.17 respectively, o Report completion to the Control Room Operator.
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PITCQ-089 Page 2 of 9 Rev 5 10/98
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l Transfer Unit 2 480v Bussas To Their Altemate Supply l PLANT-10 Rev. 0 l l
JPM PERFORMANCE INFORMATION Required Materials: Copy of 2C20.6, Sections 5.15 and 5.17 marked up as follows:
Steps 5.15.1 through 5.15.7 completed Steps 5.17.2 through 5.17.6 completed.
General
References:
2C20.6 Task Standards: Busses 221 and 222 transferred to their alternate supply. .
I Start Time:
NOTE: When providing " Evaluator Cues" to the examinee, care must be exercised to avoid l
prompting the examinee. Typically cues are only provided when the examinee's l action's . warrant receiving the information (i.e. the examinee looks or asks for the l Indication).
1 ~
NOTE: Critical steps are marked with an "X" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Rack BKR 221 A, BUS 221 SOURCE FROM 22A XFMR, to the
! Critical " CONNECT" position per C20.6-1.
Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 221 A racked to the " CONNECT" position.
Evalua' tor Note: Racking a breaker is a separate task. Just have the candidate indicate what safety equipment is required to be worn and where the equipment is located.
Evaluator Cue: BKR 221 A is in the " CONNECT" position.
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Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 3 of 9 Rev 5 10/98 l
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l Transfer Unit 2 480v Bussas To Their Attemate Supply l PLANT-10 Rev. 0 l Performance Step: Verify 7300426,22A XFMR 480V POTEATIAL IL Green, is ON.
Critical Standard: 7300426 green light on bus 221 and 222 control panel verified on.
Evaluator Cue: 7300426 green light is ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
i Performance Step: Place CS-7300407, BKR 221M BUS 221 SOURCE FROM 221M XFMR, Critical X (S-1) in "OPEN".
Standard: CS-7300407 placed in "OPEN".
Evaluator Cue: If checked, the following are indicated / observed:
. Bkr 221M indicates OPEN.
7300409, Bus 221 Voltmeter, indicates 0 volts.
In the CR, annunciator 47524-0206, Bus 221480 Volt Undervoltage, is ON.
1 Performance: SATISFACTORY UNSATISFACTORY l 1
Comments: ,
l PITCQ-089 Page 4 of 9 Rev 5 10/98
l Transfer Unit 2 480v Busses To Their Altemata Supply l PLANT-10 Rev. 0 l Performance Step: Place CS-7300410, BKR 2?_1 A BUS 221 SOURCE FROM 22A XFMR, in Critical X (S-2) "CLOSE". j Standard: CS-7300410 placed in "CLOSE".
Evaluator Cue: If checked, the following are indicated / observed:
Skr 221 A indicates CLOSED.
7300411,7300412, and 7300413 each indicate 320 amps.
7300409, Bus 221 Voltmeter, indicates 470 volts.
In the CR, annunciator 47524-0206, Bus 221480 Volt Undervoltage, is Clear.
In the CR, annunciator 47524 0506, Bus 221 Bkr 221 A Alt Source From Transformer 22A Closed, is ON.
CR indicator 4192302,480V Bus 221 Voltmeter, indicates 470 volts. '
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Rack BKR 221M to the " DISCONNECT" position per C20.6-1.
Critical j Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 221M racked to the " DISCONNECT" position.
Evaluator Note: Obtaining safety equipment was evaluated previously.
Evaluator Cue: BKR 221M is in the " DISCONNECT" position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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l PITCO-089 Page 5 of 9 Rev 5 10/98 l l
1 l Transfer Unit 2 480v Bussss To Their Attemate Supply l PLANT-10 Rev. 0 l Performance Step: Rack BKR 222A, BUS 222 SOURCE FROM 22A XFMR, to the Critical " CONNECT" position par C20.6-1.
Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 222A racked to the " CONNECT" position.
1 Evaluator Note: Obtaining safety equipment was evaluated previously.
Evaluator Cue: BKR 222A is in the " CONNECT" position. l l
Performance: SATISFACTORY UNSATISFACTORY Comments:
1 Performance Step: Verify 7300426,22A XFMR 480V POTENTIAL IL Green, is ON.
Critical l
Standard: 7300426 green light on bus 221 and 222 control panel verified on. !
Evaluator Cue: 7300426 green light is ON.
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Performance: SATISFACTORY UNSATISFACTORY
- Comments
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l PITCO-089 Page 6 of 9 Rev 5 10/98
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4 l Transfer Unit 2 4809 Busses To Their Alternate Supply l PLANT-10 Rev. 0 l Performance Step: Place CS-7300419, BKR 222M BUS 222 SOURCE FROM 222M XFMR, Critical X (S-1) in "OPEN".
l Standard: CS-7300419 placed in "OPEN".
l Evaluator Cue: If checked, the following are indicated / observed:
Skr 222M indicates OPEN.
7300421, Bus 222 Voltmeter, Indicates 0 volts.
In the CR, annunciator 47524 0205, Bus 222 480 Volt Undervoltage, is ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Place CS-7300422, BKR 222A BUS 222 SOURCE FROM 22A XFMR, in Critical X (S-2) " CLOS E".
Standard: CS-7300422 is placed in "CLOSE".
Evaluator Cue: If checked, the following are indicated / observed:
Bkr 222A indicates CLOSED.
7300423,7300424, and 7300425 each indicate 220 amps.
7300421, Bus 221 Voltmeter, indicates 470 volts.
In the CR, annunciator 47524-0205, Bus 222 480 Volt Undervoltage, is Clear.
In the CR, annunciator 47524-0505, Bus 222 Bkr 222A Alt Source From Transformer 22A Closed, is ON.
CR indicator 4192303,480V Bus 222 Voltmeter, Indicates 470 i I
volts.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 7 of 9 Rev 5 10/98 i
l Transfer Unit 2 480v Bussns To Thcir Altemate Supply l PLANT-10 Rev. 0 l Performance Step: Rack BKR 222M to the " DISCONNECT" position per C20.6-1.
Critical
- Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) '
obtained and BKR 222M racked to the " DISCONNECT" position.
Evaluator Note: Obtsining safety equipment was evaluated previously.
Evaluator Cue: BKR 222M is in the " DISCONNECT" position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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Terminating Cues: The candidate should report to the Control Room Operator that, " busses I 221 and 222 have been transferred to their alternate supply." The candidate may also indicate that he/she would inform the control room that they need to continue monitoring bus loading on ERCS. At this point, )
inform the candidate that,"this JPM is complete." i Stop Time: l l
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PITCO-089 Page 8 of 9 Rev 5 10/98
L.
TURNOVER SHEET l
l INITIAL CONDITIONS:
o Unit 2 is in Cold Shutdown.
c Bus 26 needs to be isolated for a PM.
l lNITIATING CUES:
o The Control Room Operator directs you to transfer busses 221 and 222 to their attemate supply 1 using 2C20.6, Sections 5.15 and 5.17 respectively. i e Report completion to the Control Room Operator. l l
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PITCQ-089 Page 9 of 9 Rev 5 10/98
JPM: 10 Operator:
JPM QUESTION (Answer Sheet)
QUESTION 1 System: AC Electrical
Subject:
l Operational Limits For Diesel Generator K/A & Rating: 062K102 4.1/4.4 The ERCS computer is OOS and therefore the following tank levels are reported by the Unit 1 Turbine Building Operator:
121 DSL GEN OIL STG TNK 15800 gal 122 DSL GEN OIL STG TNK 15700 gal Question: 123 DSL GEN OIL STG TNK 16100 gal 124 DSL GEN OIL STG TNK 15600 gal i 121 CL PMP OIL STG TNK 8600 gal 122 CL PMP OIL STG TNK 7800 gal Why or why NOT is Tech Spec Entry required?
Tech Spec entry is required because total usable fuel oil volume is less than 70,000 gallons.
(if local values are used for monitoring fuel oil requirements, the procedure ,
Answer: requires 1600 gallons to be subtracted from all tanks except 124 DSL GEN OIL STG TNK, which requires 2100 gallons subtracted (level use adjustment). Totalindicated levelis 79600 gallons. Subtracting the level adjustment of 10100 leaves 69500 gallons.)
Reference:
SP 1001 rage 13 l Reference Material Use:~lYes @ No O l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT: .
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JPM: 10 OPerator:
JPM QUESTION (Answer Sheet)
QUESTION 2 System: AC Electrical
Subject:
l Effect Of St Actuation On Either Unit I KIA & Rating: 062A401 3.3/3.1 Given a normal full power system alignment, in the event of a Sl on Question:
Unit 1, which 480V loads on train B will be rejected and restored?
122 Station Air Compressor,12 and 14 FCU's,122 Control Room Chiller, Answer:
122 Control Room Chilled Water Pump l
Reference:
B 20.5 Table B 20.5-3 page 16 Reference Material Use: IYes @ No ] l Pedigree: lNew CANDIDATES RESPONSE: SAT: UNSAT:
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l AS-ADMINISTERED SCENAiiiCS l
PRAIRIE ISLAND EXAMINATION - WEEK OF MAY 17,1999 i
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I l Simuirtrr Exercise Uuld) l File Number: 99 01
Title:
Load Reduction; FRV failure; PRZR Rev: 1 Level inst. Failure; BATP Trip; Loss of l Feed; IR Undercompensation l Lesson Plan: NRC Exam Duration: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Author: Jim Lash Approved by: Date:
OBJECTIVES:
- 1. Swap Component Cooling pumps per C14.
- 2. Perform a load decrease per C1.4.
- 3. Diagnose and respond to a FRV failing to manual per C47011:0305.
- 4. Diagnose and respond to failure of controlling PRZR level channel low per C51.
- 5. Diagnose and respond to a loss of normal boration due to a BATP trip pEr C47015:0403.
- 6. Diagnose and respond to a loss of Bus 12 resulting in a loss of main feedwater and reactor trip per E-0.
- 7. Diagnose and respond to failure of main steam header pressure instrument high and a failed open steam dump per E-0.
- 8. Diagnose and respond to loss of feed to both SGs per FR-H.1.
- 9. Diagnose and respond to under-compensated IR NIS per ES-0.1.
RELATED LER's, SER's, SOER's, etc.:
ERTF 96-12; Inadvertently cut cable feeding 21 BATP ERTF 93-04; Unit 1 Rx Trip caused by Bus 12 86 Lockout LER 93-05; Unit 1 Rx Trip due to loss of RCP caused by inadvertent relay operation RELATED PRA INFORMATION (See PITC 2.3):
Initiatina Event with Core Damaae Frequency:
Loss of Main Feedwater (4.4%)
Impodant Components:
12 MD AFW Pump impodant Operator Actions with Task Number:
Restore MFW following Rx Trip; CRO 311.006.06.01 I
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Title:
Lc d R:ducti:n; FRV f-ilure; PRZR Lc. val In:t. Fil] Number: 99 01
. Fcilure; BATP Trip; Lona cf Fccd; IR - R:v: :1 * ,
i Und:rc:mpensation '
p SCENARIO OVERVIEW Initial Conditions:
1
- . Current power is 89%
. Shutdown is in progress due to 11 SG tube leakage (Technical Specification 3.1.C.2.e) of approximately 5 gpm.
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. Action is in progress IAW C4 AOP2 (Action Level 2) at step 2.7.9 to have the Unit l shutdown in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
. Unit 2 is operating at 100% power.
12 MD AFW Pump is OOS due to grounds. Expected time OOS is at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l . 12 Boric Acid Transfer Pump is OOS for preventative maintenance. The pump is expected to be released to service this shift.
Seauence of Events:
Event 1: Swap CC pumps
. Swap per new procedure section in C14.
Event 2: Load Reduction
. Continue load reduction per C1.4. ;
i Event 3: FRV Fails to Manual ;
. During the power reduction,12 SG level control fails to MANUAL.
. Manually control feed to.12 SG to maintain proper level per C47015:0403 Event 4: Controlling Pressurizer Level Channel Falls Low
. Following at least a 5% power reduction, the controlling Pressurizer level channel fails low. Charging pump speed increases, PRZR heaters deenergize, and letdown isolates.
. Take manual control of charging pump speed & select a new controlling channel
. Restore letdown per C12.1
. Return charging pump speed to automatic.
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Titla: Load Reducti::n; FRV frilure; PRZR Ltv 1 InIt. Fil3 Number: 99 I l
. Fcilurs; BATP Trip; Lc a cf Feed; 1R i 'R;v: L1?
l Undercompensation l )
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Event 5: BATP Trip
. During a boration, the only operab!e (11) Boric Acid Transfer Pump will trip.
. The crew will be required to evaluate RCS boration during shutdown.
. Alternates include swapping Charging Pump suction to RWST or using another BAST.
Event 6: Loss of Bus 12 / Loss of Feedwater
. A loss of bus 12 will cause a loss of 12 MFP and 12 RCP and a reactor trip.
. A feedwater isolation will occur at 554 "F. -
. When the TD AFW pump starts it will overspeed and all feedwater will be lost.
. After steam dump control is taken to the pressure control mode, the Main Steam header pressure instrument will fail high and one steam dump valve will stick open. l
. The crew must take action to stop the steam release by shutting the MSIVs. l
. Entry into FR-H.1 will be required to handle the loss of heat sink now that SG levels are less than 50%.
. Action should be taken to establish MFW by resetting the feedwater isolation (this is a PRA significant task).
Event 7: IR Undercompensation
. At approximately 15 minutes following the reactor trip, the crew will be required to determine Source Range NIS failed to re-energize due to undercompensation of IR NIS channel N35.
. Manually reenergize the Source Range NIS.
. Scenario ends when stable plant conditions are established per step 15 of ES-0.1.
+ Critical Tasks
> Manually isolate steam dumps from the control room before an entry into an Integrity orange path or ECA-2.1 is required.
> Establish feed flow to at least one SG before RCS feed and bleed is required.
PRE-EXERCISE BRIEF
- 1. Follow NUREG-1021 Appendix E; Part E Page 3 of 19 w ,
Titis: _ Lecd R ducti::n; FRV fillurc; PRZR Lrv:1 In:t.
o File Number: 99 01
.y Fcilure; BATP Trip; Loss of Facd; IR ~ R ,v: 1 Undercompensation INSTRUCTOR GUIDE
- 1. Initialize to IC-21 and verify the following conditions:
- b. MOC Al displayed.
- c. Bank D step counters at 186, all others 228.
d .- All charts advanced and cleared of previous trends. l
- e. ERCS is on-line and functional with alarms acknowledged / cleared. l
- 2. Insert the following pre-existing conditions (Relative order of 0):
- a. 11 SG tube leak of about 5 gpm l
- b. N35 Undercompensation j
- 3. Perform the following:
- a. Place 12 BATP to pullout and hang a secure card.
- b. Place 12 MDAFW pump from service as follows:
- Place 12 MDAFW pump in pullout and attach a secure card. ;
- Place 12 MDAFW pump in MANUAL and attach a secure card.
- c. Place Rods in MANUAL
- d. Run the Valve Position Limiter down and then just off the limit
- 4. Arrange the following information:
- a. Take the simulator out of Freeze and ensure PID 1K0015 is as per Attachment A of C4 AOP2. Place QP "SGLEAK2" and SGLEAK on ERCS :
screens. Place QuickPlot "TAVTREF" on SDCON4.
- b. Cat I Vent opening sheet reflects no logged openings.
- c. Log books are open to a blank page.
- d. .C1.4 consumable is the same revision as the book and signed off through Section 5.2.7. Verify Rods in AUTO.
- e. Make a copy of C4 AOP2 "SG Tube Leak" and sign off appropriate steps through step 2.7.9 (transition from step 2.4.1) including Attachment A.
- f. Ensure TPM on NIS with Auto Scaling.
- g. Match Tave to Tref on SDCON4 QuickPlot "TAVTREF"
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p 1 L Titin: Load Riducti:n; FRV f;ilure; PRZR Lsv:1 Inst. File Number: 99 01{
- . Fcilure; BATP Trip; Lees of Feed; 1R -
iRev:L11 " '
l Undercompensation >
- 2
- h. Update and print and LCO log with the following information:
l -TS Time Reason L ' Component Number Limit Code Description - Date and Time 11 SG 3.1.C.2.e 1 HR SG tube leakage 30 min. ago l- 12 AFW 3.4.B.2.b 72 HR CM- Ground on motor Today 0100 pump L 5. Conduct shift tumover:
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- a. ' Use the shift tumover sheet provid'ed and provide the following information:
Current power is 89% Load decrease per C1.4 at step 5.2.8.
l Shutdown is in progress due to 11-SG tube leakage (Technical l Specification 3.1.C.2.e) of 715 gpd discovered about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.
Action is in progress IAW C4 AOP2 (Action Level 2) at step 2.7.9 to have the Unit shutdown in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. SG leakage is being monitored using SGLEAK.
12 CC pump needs to be shutdown in preparation for maintenance on its supply breaker 12 MD AFW Pump is OOS due to grounds. The expected time OOS is at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 12 Boric Acid Transfer Pump is OOS for preventative maintenance.
The pump is expected to be released to service this shift. j L
i -- Unit 2 is operating at 100% power.
- b. Allow time for swapping CC pumps and performing a load. change.
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- 6. At the discretion of the chief examiner (following the required power change), I insert failure of 12 SG FRV (Preferably when the Lead is near the D panel)
. (Relative order of1). l
- a. If esked to locally investigate 12 FRV, report that you don't see any problems with the valve.or valve controller.
, b. If asked to investigate 12 FRV, as the engineer or I&C, report that you will initiate a work order to investigate the failure. During investigation, remove the malfunction (Relative order of 2) and report that the digital feedwater control computer had an interruption, which has been resolved. Ask that the 12 FRV be returned to Automatic control.
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g Titix Load Rtdu:ti:n; FRV f;llure; PRZR Liv:I inIt. Fib f5$raber: 99 01 a '
. Fcilure; BATP Trip; Loss cf Feed;IR ,
WRivi[1l i, Undercompensation *
- V -
- 7. At the discretion of the chief examiner insert pressurizer level channel failure low (Relative order of 3).
- a. If directed, trip the bistable (Relative order of 4).
- b. Perform IV of the bistable tripping and generate work orders as directed.
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!- 8. At the discretion of the chief examiner insert failure of 11 Boric Acid Transfer l Pump (Relative order of 5). This will' remain unnoticed until the next boration is '
. performed.
- a. If asked to investigate, report that the breaker is tripped (MCC 1L1-BS) and the motor is hot to the touch.
- b. If asked, as an electrician or system engineer, report that you will investigate and write a work order.
- c. ' If asked to restore 12 BATP, report that you will check its status. Later
. report that the pump will be available in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The Work Control Center will handle closing the work package and clearing the isolation.
- d. If contacted, as chemistry acknowledge the use of the RWST.- Inform the CR that you will increase monitoring of RCS hydrogen.
- 9. At the discretion of the chief examiner insert Bus 12 lockout (Relative order of 6).
- a. ' When 11 TD AFW pump starts, then enter an overspeed trip on the pump (Relative Orderof 7).
- b. If asked to investigate, report that the 86 lockout has actuated and a 51G flag is present.
/ 10./; Reactor Trip and Loss of Heat Sink EOPs:
NOTE:
Be prepared to stick open the 1** Atmospheric Steam Dump prior to the operator taking action if possible allow the steam dump to fully open prior to sticking the valve.
- a. One minute after Steam Dump is placed in the Steam Pressure mode, fail PT-484 high (Relative order of 8) to cause all steam dumps will open AND THEN stick one steam dump open (Relative order of 9).
- b. If asked to isolate stuck open steam dump, then after 3 minutes insert remote and report that RS-6-1 is shut (Relative order of 10).
Page 6 of 19
Titla: LOcd Reducti:n; FRV friture; PRZR Livil in:t. Fil4 Number: 99-01 l
. Failure; BATP Trip; Los3 ef Fe:d; IR L R.1v: 1 Undtrc:mpenartien
! fallen apart. Maintenance reports that it will take at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to fix.
l d. If asked, as the unit 2 RO, to cross-tie AFW from 21 MD AFW pump,
! explain that you are using the pump and it is not available at this time.
'1 1. At the discretion of the chief examiner, (SR instruments reset) place the simulator in FREEZE. i l
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n Titix Lc d R duction; FRV f:llurs; PRZR Livil Innt. Fil2 Number: 99-01
. Fcitur;; BATP Trip; Lcca cf Fr:d; IR R:v: 1.
Und:rc:mpensati:n 'i n Name: Position: Lead RO Date:
Event Description KA Number KA Value Swap CC Pumps Time S/U Position Expected Response Perform actions per 1C14 Lead Notify Aux Bldg Operator to check bearing oil level and that there is no sealleakage Lead Start 11 CC Pump by placing CS-46036 to START Lead Verify MV-32145; 11 CC HX CLG WTR INLET opens Lead Direct Aux Bldg Operator to perform local checks of 11 CC Pump Lead Verify total CC flow is less than 4000 gpm and transition to section 5.3 Lead Stop 12 CC pump using CS-46037 by holding the CS until CC system pressure stabilizes (pump does not automatically restart)
Lead Close MV-32146; 12 CC HX CLG WTR INLET using CS-46047 Evaluator Note:
Comments:
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Titis: Lrd Reducti:n; FRV f;.ilure; PRZR Loval Innt. Fil3 Number:: 99 l . Fcilure; CATP Trip; Loss cf Feed; IR R:v: 21 Und:rcempen?ctirn -
Event Description KA Number KA Value Load Reduction Time S/U Position Expected Response Perform actions IAW C1.4:
SS . Power reduction directed by SS.
Lead . Lead observe turbine and generator limits per C1.4 RO . Commence boration RO . When Tave shows a decrease, Then reduces turbine load by setting the SETTER and depressing GO RO . Rods may be placed in MANUAL ,
Evaluator Note:
Comments:
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( Titis: Lccd Reducti::n; FRV f llure; PRZR Lcv:1 In:t. File Number: 99-01 >
i
!. Fcilure; BATP Trip; Losa cf F: d; IR . Rev: 1 Undercompensation Event Description KA Number KA Value l FRV Failure to Manual l l l Time SIU Position Expected Response l Feedwater Control Fall to Manual Alarm (C47011-0305) l l
Lead . Manually control 12 NR SG level within 5% of band per Figure !
C1-39. (39% to 49%)
SS/ Lead . Inform System Engineer and l&C to investigate Lead . Retum FRV to AUTO by depressing the AUTO button on 2HC-476 l Evaluator Note: j Comments:
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Titb: Load Reducti:n; FRV fillur ; PRZR Lsv:1 In:t. Fib Number: 99-01 Fcilure; BATP Trip; Leca cf FO d; IR >
R:v: .1 >
Undercompensation 4 i Event Description KA Number KA Value l Pressurizer level transmitter failure l'
Time S/U Position Expected Response C51.3 Pressurizer Level 1L-428 - Low RO e Take manual control of the charging pump speed to maintain level at program.
- Select position 2-1 on pressurizer level control selector switch.
- Restore pressurizer heaters for normal operation. The switches for heaters which were ON must be taken to OFF for 10 seconds to reset the anti-pumping feature.
RO e Retum charging pump back to auta RO . Switch pressurizer level recor6 a another channel.
Lead /RO . Inform SS to refer to T.S.3.5 (6 hr LCO for B/S tripping).
Lead /RO . Trip and independently verify bistables.
Lead /RO . Initiate work order on the failed channel.
Lead . Make appropriate log entries.
RO C12.1 Restoring Letdown e Place letdown temp UV in MANUAL at 50%.
- Place letdown press CV in MANUAL at 50%.
- Establish sufficient (at least 15 gpm) charging flow through the regen HX.
. Open a 40 gpm orifice isolation valve while adjusting the letdown press CV so letdown press does NOT reach 600 psig.
- Retum letdown temp and press control to AUTO.
Evaluator Note: ]
Comments:
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Titla: Lecd Reductirn; FRV f llure; PRZR Lcv;l In:t. Fila Number: 99 01.
. Fcilure; BATP Trip; Loss cf Fr:d; 1R R;v: 1 Undercompensation '
2 Event Description KA Number KA Value ,
Boric Acid Pump Trip l
Time S/U Position Expected Response Boric Acid Deviation Alarm C47015-0403 RO e Places makeup controller to OFF l
l 'RO e Continue load reduction using rods and/or swap charging pump suction to RWST.
-Open MV-32060 RWST Supply
-Close MV-32061 VCT Supply l Evaluator Note:
- 1. In order to close MV-32061; MV-32060 must be fully open.
Comments:
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F Titla: Lecd R ductinn; FRV f:llure; PRZR Lev:1 inIt. Fib Number: 199-01-:
. Fcilurs; BATP Trip; Lces of Fc d; IR l R;v: .1 - ,
Undercompensation Event Description KA Number KA Value Bus 12 Lockout / Reactor Trip I
- Time S/U Position Expected Response E-0 Reactor Trip or Safety injection RO e Verify reactor trip. - Rx Trip Bkrs; Flux; Rod positions Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized.
RO_ = Check if Siis required
-SG Pressure >500 psig
-PRZR Pressure >1815 psig
-PRZR Level >5%
-Subcooling >20'F
-Containment Pressure <4 psig SS = Transition to ES-0.1 Evaluator Note:
Comments:
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1 Page 13 of 19
1 Titla: Lecd R ducti:n; FRV fIilure; PRZR Levv. Inst. Fil3 Number: . 99 01 '
. Failure; BATP Trip; Lc:a cf Feed; IR Rnv: 41L Und rcampensation ,
Event Description KA Number KA Value Main Steam Line Header Pressure Instr Fajiuro High and Stuck open Steam Dumo.
l Time S/U Position Expected Response ES-0.1; Reactor Trip Recovery SS . Announce " Unit 1 Reactor Trip" i Lead . Place steam dump in " Steam Pressure" mode. l Lead . Notify TBO to isolate MSRs. I Lead . Check cooling water pressure A & B >75 psig RO . Check RCS T., controlling at 547'F Lead . Stop dumping steam by either (critical task)': l
-Shut both MSIVs
-Call Aux Operator to isolate Steam Dump by shutting RS-6-1 C47012:0502; 12 RC Loop Low Flow RO . Shut 'B' PRZR Spray Valve (CV-31225)
Evaluator Note:
- 1. Steam Dump must be isolated prior to entry into an orange path g.ndn prior to entry into ECA-2.1 i is required.
Comments.
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Load Reducti:n; FRV fillure; PRZR L1:v;l innt.
Titis: Fil3 Number; 99 01 Frilure; BATP Trip; Lc20 cf F cd; IR ;R:v:(1 Undercompensation
]
Event Description KA Number KA Value Loss of Feed / Loss of Heat Sink Time S/U Position Expected Response FR-H.1; Loss of Heat Sink RO/ Lead . Verify secondary heat sink is required.
-RCS pressure > SG pressure
-RCS Hot Leg >350*F RO/ Lead . Check for secondar to bleed and feed.' y heat sink,if none stop RCPs and skip directly Lead /SS
- Attempt to restore AFW flow:
- Attempt to cross-connect AFW from unit 2.
- Dispatch operator to locally restore AFW. ;
. Attempt to restore main FW flow.
Lead - Reset SI Lead -Investigate lockout on bus 12.
Lead - Check FW Containment isolation Valves open Lead - Depress all four FW lsolation reset pushbuttons ,
Lead - Determine 11 MFP available l Lead - Open FCV Bypass valve 5 #
Lead - Establish at least 200 gpm (1x10 1bm/hr) flow (crit / cal task )
e Check SG levels:
SS - if flow adequate and levels increasing, transition to ES-0.1 l
Evaluator Note:
' 1: - If secondary heat sink is still available after checking in step 2 then the crew SHALL stop RCPs and skip directly to bleed and feed when both SG WR levels are less than 7%.
Comments:
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Titb: Load Reductirn; FRV f:llure; PRZR L5v:1lict. File Number: 99 01 l 4
Fcilure; RATP Trip; Lses cf Fnd; IR >
Revi 1 '
Undercompensation - '
Event Description KA Number KA Value Reactor Trip Recovery Time S/U Position Expected Response ;
ES-0.1 Reactor Trip Recovery l Lead Check FW status I
-Reduce Main FRV demand to zero Verify FW flow >200 gpm' RO e Verify all control rods fully inserted RO e Check PRZR level trending to 21%
l RO C12.1 Restoring Letdown (if necessary) d
. Place letdown temp CV in MANUAL at 50%.
. Place letdown press CV in MANUAL at 50%.
- Establish sufficient (at least 15 gpm) charging flow through the
. regen HX.
. Open a 40 gpm orifice isolation valve while adjusting the letdown press CV so letdown press does NOT reach 600 psig.
. Return letdown temp and press control to AUTO.
ES-0.1 Reactor Trip Recovery (cont.)
RO e Check PRZR pressure trending to 2235 psig Lead e Control FW flow to establish 10 to 40% SG NR level Lead. . Verify off-site power available
-Identify lockout on bus 12 and does not restore power to it.
-Verify auto action of C47005-0102 Breakers 12-4 and 12-1 open 12 RCP and MFP tripped Refers to C20.5 AOP3 Lead . Open Turbine HP drains using CS-46392 C3; RCP Start
-RO e Verify support conditions for RCP start ;
e Start 11 RCP Oil Lift Pump l e Start 11 RCP Evaluator Note:
- 1. ERCS screen "FWi" provides FW flow information in bm/hr. 200 apm is about 1 X 10' lbm/hr l Comments:
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l Page 16 of 19
Titic: Lecd Reducti n; FRV f;ilure; PRZR Lcv:1 Inst. File Number. 99-01 i
Fcilure; BATP Trip; Losa cf Feed; IR :Rev:11 l Undercompensation Event Description KA Number KA Value
_intermediate Range Under-compensation Time S/U Position Expected Response ES-0.1; Reactor Trip Recovery (cont.)
RO . Check IR flux less than 5 x 10'" amps RO . Manually energize SR detectors by placing both SR Reset / Block switches to RESET RO . Transfer NIS recorder to SR N31 and N32 Evaluator Note:
Comments:
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i CHAMPS FORM KTF-D 2
. ' RETENTION:- 7 DAYS. E:
l UNIT 1 LPEO / PEO TURNOVER TIMEsN(1800-0600)
! SFGDS EQUIP OOS/LCO'S l 1 :12 AFW PUMP AS OF TODAY AT 0100 DUE TO A GROUND l 2 . 311 SG TUBE LEAKAGE AT 715 GPD 3 -
RAD MONS 005: ANNUNC'S 008:
1 OUTSTANDING SP'S FIRE DET/ PROT EQUIP IMPAIRMENT:
1 OTNER EQUIP OOS / STATUS:
- 1
- '12 BATP FOR PM 2 :
3 :
4 :
5 :
6 :
7 :
8 :
9 :
1 10 :
11 :
12 :
13 :
14 :
15 4
-16.:
17 :
MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE:
1 .
{
2' t' 3 : ;
4 -
5'- l OPERATIONAL PLANS FOR COMING SHIFT: j 1
- MONITOR LEAKAGE USING XT24 i 2 : SHUTDOWN PER C1.4 3 : SECURE 12 CC PUMP
-4 :
NEW PROCEDURES / INSTRUCTIONS:-
1 : C4 AOP2 ATTACHMENT A COMPLETE 2 1 3 : ;
l WATCHETANDERS LPEO: LASH PEO: JONES LPEO RELIEVED BY TIME: DATE:
i PEO RELIEVED BY: TIME: DATE:
CB WALKDOWN' - - > LPEO TIME:
- - > PEO :- TIME:
p
( l Simul:ttr Exercisa Guida l l.
File Number: 99-02
Title:
Load increase; PRZR Pressure Instr.
Rev: 1 Failure; Loss of Generator Cooling; Dropped Rod; Faulted SG Lesson Plan: NRC Exam Duration: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l Author: Jim Lash Approved by: Date:
OBJECTIVES:
- 1. Perform secondary lineup for power operation per C1.2.
- 2. Perform a load increase per C1.4.
- 3. Diagnose and respond to a high failure of pressurizer pressure controlling channel per C51.
S. flace. a sco%4 Ietobn oicikce. M ireala__
- 4. Diagnose and respond to a reduction in Main Generator hydrogen cooling per C47007:0401.
- 5. Diagnose and respond to a dropped control rod per C5 AOP4 and E-0.
- 6. Diagnose and respond to a failure of a main steamline isolation per E-0.
- 7. Diagnose and respond to a failure of one train of Safety injection to actuate and a trip of one Si pump per E-0.
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RELATED LER's, SER's, SOER's, etc.: 1 LER 96-01; Main Steam Safety found outside 1% tolerance LER 97-08; Unit 1 Reactor Trip caused by electrical ground in Rod Control system RELATED PRA INFORMATION (See PITC 2.3): l Important Components:
12 SI pump l i
D1 Diesel Generator Page 1 of 16
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l Titix - Lecd increncs; PRZR Pressure Instr. Failure; Fila Number:. 9942; o;
. Less of G:nsrcter Cooling; Drapped Rod; -
tRav:
l Faulted SG '
- ' S* u -
1 SCENARIO OVERVIEW i
c Initial Conditions: ;
i e' ' Current poweils 15% and has been held there for 20 minutes.
.' Unit startup is continuing with power increase to 100% power.
. ' Action is in progress IAW 1C1.2 step 5.6.23. All actions required in 1C1.2 have been completed with the exception of 5.6.23 (Electrical lineup) and 5.6.24 (Steam Dump alignment), which are to be performed following tumover. Power ascension will continue LAW 1C1.4.
. . Unit 2 is operating at 100% power.
- PORV PCV-430 has been leaking-by and is isolated.
.e The 12 BATP is OOS for preventative maintenance. The pump is expected to be released to service in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- D1 is in the process of being restored to service following repair of leak on the Jacket Coolant system Secuence of Events: )
Event 1: Load increase e ~ : Following shift turnover, the crew will continue the power ascension to the next plateau. The crew will complete the remaining actions of 1C1.2
. Transition to and continue per 1C1.4.
Event 2:' Controlling Pressurizer Pressure channel fails high ,
e . Instrument failure causes sprays to open. The RO needs to take manual control of pressure to stop the pressure reduction. !
'e Follow C51 to take the channel out of service. ,
. fsll kcl 2d Sack n 56 lv O* h Suo"A ch@ Pwp 4 Pl *- l a.secen I ov>novi - se r% >
Event 3: oss Hydrogen ng
~
-. Temperature sensor for Main Generator hydrogen cooling fails low causing the
. control valve CV-31360 to close. !
' e - - Hydrogen temperature will increase and alarm (C47007:0401) e~ Manual operation of the Hydrogen Temperature Controller restores hydrogen to its '
normal temperature range.
1 Page 2 of 16
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Titlo: Lc d incre:33; PRZR Presura inftr. Frilurs; Fib 'Number: 99-02
( . L:s3 cf gin:r;tcr Cscling; Dr:pped Red; M , Rsv: .1
! Faulted SG
. If NO operator action is taken a generator fault trip will be initiated on high temperaiure.
Event 4: Rod Drop l . A periphery control rod (J-10), will drop resulting in a Power Range negative rate trip l on one of the operable NI channels.
. The crew is expected to manually trip the reactor per C5 AOP4.
. The actions of E-0 should be initiated.
Event 5: Faulted SG i
. A Code Safety Valve on 12 SG fails open resulting in depressurization of the secondary system.
. Sl is actuated (automatic or manual)
. Train A equipment fails to respond to the "S" signal and must be manually operated.
. The 12 S1 Pump trips on its start, so the operator is expected to ensure the 11 SI Pump is manually started.
. When a steamline isolation is generated, the MSIV doesn't close.
. Actions of E-0 should be continued and transition should be made to E-2. !
. Upon completion of actions E-2 for isolation of the 12 SG transition is made to E-1.
- Scenario ends following evaluation for termination of Si at step 12 of E-1 or using the information page and ES-0.1.
l
+ Critical Tasks
> Establish flow from at least one high-head ECCS pump (11 SI Pump) prior to transitioning out of E-0.
> lsolate AFW to a faulted SG before transition out of E-2.
PRE-EXERCISE BRIEF
- 1. Follow NUREG-1021 Appendix E; Part E l
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I Page 3 of 16
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Titla: Lrd incrers; PRZR Pre:: cura Instr. Failure; Filo Number: 99 02' Los3 cf G:n:re.tsr Cscling; Dr:pped Rod;
- l. tR v:?.1i o Faulted SG l
lNSTRUCTOR GUIDE
- 1. Initialize to IC-16 and verify the following conditions:
- b. MOC Al displayed.
- c. Bank D step counters at 105, most others 228
- d. All charts advanced and cleared of previous trends,
- e. ERCS is on-line and functional with alarms acknowledged / cleared.
- 2. - Perform the following:
- a. Transfer busses 11 through 14 from the M to the R source.
l b. Place Steam Dump in Steam Pressure mode,
- c. Open Turbine HP Drains using CS-46392 c d. Remove 12 BATP from service by placing it in pullout and attaching a secure card,
- e. Adjust Turbine load rate to 0.5%/ Min
- f. Ensure _TPM is on NIS with Auto Scaling
- g. Display QUlKPLOT "LOADFOLL" on SDCON4 and match Tave-Tref
- 3. Remove D1 from service as follows:
- a. Place D1 control switch in pullout and attach a secure card.
- b. Place D1 output breaker control switch in pullout and attach a secure card.
- c. Place D1 speed control to lower until the governor ready lights extinguish.
- d. Place "D1 Out of Service" signs on the control board at various locations.
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- 4. Remove PORV PCV-431C from service as follows:
- a. _ Close PORV block valve, MV-32196, and attach secure card.
- b. Place a Work Order sticker next to PCV-430.
- c. Place an information tag on the control switch stating "PCV-430 leaking".
Sc Insert the following pre-existing conditions (Relative order of 0):
- a. Failure of MSIVs to auto isolate
- b. Failure of 'A' Train Si to actuate
- c. 12 SI pump trips when started.
- d. 12 SG safety opens when reactor trip switch is operated.
Page 4 of 16 b __
' l Titis: Lrd incrac2 ; PRZR Pre 2 cure In:tr. Fcilure; Fils Number: 99-02 )
L=3 cf G:n:r;t:r Cocling; Dropped Rod; Riv: :1 Faulted SG -
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- 6. Arrange the following information:
- a. Cat I Vant opening sheet reflects no logged openings.
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- b. Log books are open to a blank page. l l
- c. C1.2 consumable is the same revision as the book and signed off through I Section 5.6.22.
Attachment 'C' filled out with 1) 30; 2) 30 and 60; 3) 30; 4) 100; 5) I 100 and 0.85 f l
Fill in C1.2 step 5.6.20 at a time of greater than 30 minutes ago.
Sign off SPs as NA or complete at the end of C1.2.
- d. Update and print and LCO log with the following information:
Time Reason Date and Component TS Number Limit Code Description Time D1 3.7.B.1 7 days CM Jacket Coolant leak Yesterday 1200
- 7. Conduct shift turnover:
- a. Use the shift turnover sheet provided and provide the following information:
- Current power is 15% and has been held there for 40 minutes.
Unit startup is continuing with power increase to 100% power.
- Action is in progress IAW 1C1.2 step 5.6.23. All actions required in 1C1.2 have been completed with the exception of 5.6.23 (Electrical ,
lineup) and 5.6.24 (Steam Dump alignment), which are to be l performed following turnover. l a) Power ascension will continue IAW 1C1.4.
b) Fuelis preconditioned to 100% power with Bank D at 218 steps from a trip on May 13.
- PORV PCV-430 has been leaking by and is isolated.
- The 12 BATP is OOS for preventative maintenance. The pump is l
expected to be released to service in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />'. i i
Page 5 of 16 f
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Titix Lccd incr:cas; PRZR Pressure Instr. Fcilurs; File Number: 99 02 q'
. Leca of G:nircter Cscling; Dr:pped Rod; b Riv: 1-Faulted SG w D1 is in the process of being restored to service following repair of leak on the Jacket Coolant system Unit 2 is operating at 100% power.
- b. Allow 3-5 minutes for control board familiarization.
- 8. During the load increase:
- a. Open MSR isolations as directed (Relaftve order of 1).
- b. If called concerning starting the HDT pump, ask the CR to wait until you get some sample results on the secondary.
- 9. At the discretion of the chief examiner insert pressurizer pressure instrument failure high (Relative order of 2).
- a. Trip bistables upon request (Relative Order of 3).
- 10. At the discretion of the chief examiner (following the required power change),
insert the Generator Hydrogen temperature sensor failure downscale (Relative order of 4).
- a. If asked to investigate, report that you will initiate a work order.
- 11. At the discretion of the chief examiner drop a control rod (Relative order of 5).
- a. When the reactor is tripped, then ensure that 12 SG safety fails open.
- b. Open the CL orifice bypass as requested (Relative order of 6).
- c. If asked to investigate the lockout on 12 SI pump, report that the pump tripped on overcurrent.
- 12. At the discretion of the chief examiner place the simulator in FREEZE.
l Page 6 of 16 I
)
r 1 Titls: Lord incrzco; PRZR Prescure in tr. Failure; Fils Number: 99 02 Leca cf G:n:rcter Cxling; Drrpped Rod; R:;v: .1 j
l Fpult:d SG Name: Positirq: SM SS Lead RO :
Date:
)
Event Description KA Number KA Value Load increase Time _S/U Position Expected Response C1.2; Unit 1 Startup Lead . Transfer non-safeguards busses from 1R to 1M (1M breakers held J
for at least i second while observing ammeters) I Lead . Transfer Steam Dump to Tavg. mode C1.4; Unit 1 Power Operation l
Lead . Notify Duty Chemist Lead /SS .
Veri'iThermal Power Monitor is on NIS RO- . Verify all PRZR heaters ON Lead
- Carry ferward turbine loading rate from C1.2. '
Lead e Raise / verify Load Limiter to 100%
Lead /SS . Verify ITC negative and place turbine control in imp in RO . Dilute using Aft. Dilute RO e When Tavg increases, then depress GO on turbine Lead e Direct outplant actions for load increase j l
Evaluator Note:
Comments: ,
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i Page 7 of 16 e
r Titix Lc:d incre se; PRZR Prerure in:tr. Fcilure;
. File Number: 99 02.- l
. Leco cf G::n:rct:r Cooling; Dr:pped Rod; R v: 1 .
l Faulted SG -
1 Event Description KA Number KA Value Pressurizer Pressure Failure High Time SIU Position Expected Response C51.3 Pressurizer Pressure 1P-431 - High RO . Place pressurizer pressure controller in MANUAL and stabilize pressure. J RO e Select 2-1 on channel selector switch.
RO e Retum pressure control to AUTO.
RO e Select another channel on the pressurizer pressure recorder.
SS e Refer to T.S.3.5 (6 hr LCO for B/S tripping).
Crew . Identify and refer to T.S. 3.10.J if pressure <2205 psig.
Lead /RO . Trip and independently verify bistables.
- Lead . Initiate work order on the failed channel. --
Lead' e Make appropriate log entries.
RO e Shrt5 Fan O3 cb g mcj famp, Pub 89 $M b ^ onb5 -
y<+a.
Evaluator Note:
Comments:
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i Page 8 of 16 L.
[ Titis: Lecd incre;cc ; PRZR Pre 3 cure in:tr. Fcilurs; Fib Number: 99-02:
. Losa cf Grner;t:r C: cling; Dr:pped R:d; i R;v:11l Faulted SG Event Description KA Number KA Value Loss of Generator Hydrogen Cooling l
Time S/U Position Expected Response C47007:0401; Generator or Exciter Gas Hi Temp Lead . Determine source of alarm using recorder 47027 information Tags 001 to 009 and 029 to 031 ,
Lead . Check hydrogen pressure Lead . Increase cooling water flow by taking CV-31360 to manual and open.
Lead . Initiate a Work Order Lead . Make Log entry Evaluator Note:
Comments:
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Page 9 of 16 t.
Titis: L0rd increncI; PRZR Pres:ure in:tr. Fcilure; FiL1 Number: 99 02 Les3 cf G:n:rct:r Cooling; Drcpped Red; L : R:v:' i f Faulted SG j
l Event Description KA Number KA Value !
Rod Drop !
Time S/U Position Expected Response C5 AOP4; Dropped RCA RO e Identify that a rod has dropped.
RO . Manually initiates a reactor trip.'
Evaluator Note:
- 1. Immediate Action.
Comments: I l
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i Page 10 of 16 L j
Titis: Lr:d in:re:Os; PRZR Pre; sura Instr. Fcilure; File Number: 99-02s
. Los3 of C n:;rct:r Cooling; Dr:pped Rod; R::v: L1-Faulted S3 _ _ _
Event Description KA Number KA Value
( Reactor Trip Time S/U Position Expected Response E-0 immediate Actions RO . Verifies reactor tripped Lead . Verify turbine trip - both turbine Stop Valves Closed l
Lead . Verify safeguards buses 15 & 16 energized.
RO . Check Si actuated Status Light or Sl First Out ON RO . Actuates Sl if required (any of the following)
-SG Pressure <500 psig
-PRZR Pressure <1815 psig
-PRZR Level <5%
-Subcooling <20*F
-Containment Pressure >4 psig Evaluator Note:
Comments:
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Page 11 of 16 w.
y Titlo: Lecd Intrenco; PRZR Pre: sura In:tr. Fcilure; Fil1 Number: 9942
,.. Leco cf C;n:rCt:r Cooling; Dr:pped Rod; R:v: < 1 Fculted SG Event Description KA Number KA Value Reactor Trip (cont.) -
l Time S/U Position Expected Response E-0 continued Lead . Verifies component alignment Lead . Verify Train B ESF actuated Lead . Start 11 Si pump (criticaltask)'
Lead . Intiates Containment isolation signal for Train 'A' Lead . Align Train A components per Si Active Panel
-Start 11 RHR Pump
-Place 11 & 13 CFCU to SLOW and aligned to the DOME
-Place 12 CL Pump in Manual and Start (may return to Auto)
-Close CL Header Valve 'C'; MV-32036 -
4 -Close CL X-Over Viv A; MV-32144
-Close 11 CC Disch Valve; MV-32120
-Start 121 Aux Bldg Special Vent !
-Start 11 Shield Bldg Vent
-Direct Aux Bldg Operator to open 11/13 FCU Orifice Bypass RO . Closes "B" MSIV.
Crew . Verifies Air to Containment valves open Lead /RO . Closes MV-32115 (CC to SFP Cooling)
SS . Ensures communication with NRC is established w/i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Lead /RO . Opens turbine HP drains Lead /RO . Directs Outplant to stop TB roof exhausters and isolate the MSR's SS . Ensure Auto-Action Guide is implemented Lead /RO . Place SD in " Steam Pressure" mode Lead /RO . Maintains >200 gpm total AFW flow unless "B" SG level is >10%
Lead /RO . Closes 'A' MSlV if needed to control cooldown RO . Verifies RCP seal injection 6 to 10 gpm Crew . Diagnoses a Faulted SG and transition to E-2 Evaluator Note:
- 1. Establish flow from at least one high-head ECCS pump prior to transitioning out of E-0.
Comments:
1 Page 12 of 16 L
Titix L::d increro; PRZR Prerure Inztr. Fcilure; Fil] Number: 99-02 j
. Loso cf G:nertt:r Cooling; Dr:pped R:d; R~:;v: 1 '
l Fcult:d SG '
Event Description KA Number KA Value Faulted SG l
l Time S/U Position Expected Response !
E 2; Faulted SG isolation Lead . Verify 12 MSIV closed Lead . Verify 11 SG intact Lead . Identify 12 SG as faulted Lead . Verify Main Feed to 12 SG lsolated Lead .
Isolate AFW to 12 SG (crit / cal task)'
Lead . Close steam supply from 12 SG to TD AFW; MV-32017 Lead . Verify 12 SG PORV closed Lead . Verify 12 SG blowdown isolation valves closed Lead . Check CST levels > 5000 gallons Lead . Initiate SG samples SS . Transition to E-1 l Evaluator Note:
Comments: i I
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l Page 13 of 16 e
Titis: Lecd incre:ss; PRZR Prrisurs Instr. Failurs; Fil2 Number: 99 02 Lcca cf G:nsrctar Cocling; Drapped Rod; 3- - R:v:?l1:
Faulted SG
\
Event Description KA Number KA Value St Termination' Time S/U Position Expected Response ES-0.2; Si Termination Lead . Reset SI
' Lead . Reset Cl Lead . Verify IA to containment RO . Verify charging flow established Lead /RO e Stop both RHR pumps Lead /RO . Stop 11 SI pump Lead /RO . Close BAST suction valves MV-32081 and MV-32082 Crew . Verify Si flow is not required.
l Evaluator Note:
- 1. Transition to ES-0.2 is based upon the information Page of E-1.
Comments:
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[ Page 14 of 16
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CHAMPS. FORM KTF-D 2
. RETENTION: 7 DAYS DATE:
l UNIT 1 LPEO / PEO TURNOVER TIME N(1800-0600)
SFGDS EQUIP OOS/LCO'S:
1 :PORV PCV-430 LEAKING AT 2 GPM- ISOLATED 2 :D1 EDG'(REPAIRED) 3:
RAD MONS OOS: ANNUNC'S OOS:
OUTSTANDING SP'S: FIRE DET/ PROT EQUIP IMPAIRMENT: i PATHS FROM THE GRID DUE IN 4 HOURS OTNER EQUIP OOS / STATUS:
1 212 BATP FOR PM-2.
3 4
5 :
- I 6 :
7.:
8 :
9 10 :
11 +
12 13 :
14 :
15 : !
16 :
17 : 1 MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE:
1 .:D1 EDG RESTORATION IN PROGRESS 2 :
3-:
4 :
5 's OPERATIONAL PLANS FOR COMING BHIFT:
1 CONTINUE WITH C1.2 AND LOAD INCREASE PER C1.4 TO 100% POWER (c.85%/ MIN) l 2 : l 3 :
4 :
NEW PROCEDURES./ INSTRUCTIONS:
l' FUEL PRECONDITIONED TO 218 STEPS AND 100% - MAY 11, 1999 2 ITC VERIFIED TO BE NEGATIVE BY NUCS' 3 : ;
WATCHSTANDERS LPEO LASH PEO JONES LPEO RELIEVED'BY: TIME: DATE:
PEO RELIEVED BY: TIME: DATE:
CB WALKDOWN -- > LPEO TIME:
- - > PEO : TIME: j l
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1
' 1 l Simul:ttr Extrcl52 Guid) l l e
File Number: 99-03
Title:
Load increase; Loss of Charging Flow; )
Rev: 1 Tavg Failure High; Loss of Vacuum; '
Turbine Valve Failures; ATWS; SG Pressure Instr. Fall High; SGTR !
Lesson Plan: NRC Exam Duration: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Author: Jim Lash Approved by: Date:
l OBJECTIVES:
- 1. Sta;i; Occcad fc;Jyveur pernp per C28.2. A M WEach
- 2. Perform a load increase per C1.4.
- 3. Diagnose and respond to loss of air to a charging pump per C47015 and C12.1.
- 4. Diagnose and respond to a Tcoio instrument failure high per C51.
- 5. Diagnose and respond to trip of running Gland Steam Condenser Air Exhauster that results in decreasing vacuum per C47008 and C29.
- 6. Diagnose and respond to sequential closure of MSR Intercept valves per C23 AOP2.
- 7. Diagnose and respond to a failure of the reactor to trip per E-0.
- 8. Diagnose and respond to a SG pressure instrument failure high resulting in a SG PORV opening per C47011 or E-0.
- 9. Diagnose and respond to a SGTR per E-0 and E-3.
RELATED LER's, SER's, SOER's, etc.: None RELATED PRA INFORMATION (See PITC 2.3):
Initiatina Event with Core Damaae Freauency:
SGTR (7.1%)
ImpOttant Components:
Reactor Protection System 11 TD AFW Pump Important Operator Actions:
CRO 301.004.06.01; Cooldown and Depressurize from SGTR Before Overfill (E-3)
Page 1 of 19 L
o Titlo: Lecd incr =a; Losa of Ch:rging Flow; Tcvg Fil3 Number: 99 03-
, Fcilura High; Leca cf Vccuum; Turbino Vciva R:v: ni
( Fcilures;'ATWS; SG Pressure Instr. Fall High;
( SGTR SCENARIO OVERVIEW Initial Conditions:
. The scenario will begin at 50% power with two Condensate Pumps, two Heater Drain Pumps, and one Feedwater Pump running.
. Out-plant actions have been completed to support starting a second MFP.
. Following turnover the crew will start the MFP and continue the power ascension Seauence of Events: '
Event i: Load increase -
. Per C1.4. -- - -- - --
. Start a second MFP per C28.2 Event 2: Loss of Charging Flow
. Mechanical blockage in air supplyline results in the running Charging Pump speed reducing to minimum.
. The crew will be required to start another Charging Pump to restore normal charging and seal injection flow and maintain Pressurizer level.
1 Event 3: Tavg Failure high
. A Tcoto RTD fails.
. Control rods automatically insert, requiring operator to take manual control.
. Charging pump speed increases, requiring operator to take manual control.
. The affected channel is defeated and control systems are restored to automatic.
. Protective bistables are tripped to satisfy Tech. Specs per C51.
Event 4: Loss of Gland Steam Condenser Vacuum ;
. The running Gland Steam Condenser Air Exhauster trips.
. Due to the reduction in air removal from the gland seal system, gland steam !
condenser vacuum decreases. l
. The crew will respond by swapping to the afternate Gland Steam Condenser Air Exhauster per C29.
Event 5: Intercept Valve Closures
. One MSR Intercept valve will close.
. The crew will respond to turbine drains indications and alarms and direct t% Turbine Building Operator to investigate.
Page 2 of 19 w- ,
n Tit l3: Lecd incrosas; Loss of Chrrging Flow; Tsvg Fil? Number: 9943 -
.. Fcilure High; Lees cf Vacuum; Turbins Vciva '"
JRav:.1 W7 Failures; ATWS; SG Pressure instr. Fall High; 4 - , Y- -
SGTR ^'* "'
e ^ The crew will determine a MSR Intercept valve has failed closed due to EH fluid leak at actuator and perform actions of C23 AOP2.
- A second MSR Intercept valve will fail closed, requiring a reactor trip.
' Event 6: ATWS-
- The reactor trip breakers will fail to open and the crew will need to actuate the new DSS /AMSAC system to trip the unit.
Event 7: SG Pressure instrument Failure with Opening PORV -
e Following opening of the reactor trip breakers,12 SG PORV opens due to failure of the associated pressure channel input.
. The crew will be required to take the' Controller to MANUAL and shut the PORV when v SG pressure is below the normal opening setpoint of 1050 psig.
e: Si is NOT expected to have actuated or be required, so at step 4 of E-0 transition is
' made to ES-0.1 Event 8: SGTR e Upon transition to ES-0.1 a SGTR occurs in 12 SG (over a 4-minute period).
, ,e The crew should transition to E-0 and perform the actions beginning_with step 1.
. . At step 20 of E-0, transition is made to E-3.
- The scenario ends following depressurization of RCS to minimize break flow.
+ Critical Tasks
> Insert negative reactivity by either inserting control rods, establishing RCS boration; or directing local trip of the reactor prior to FR-S.1 Step 6.
> lsolate feed flow into and steam flow from ruptured SG before entry to ECA-3.1 is required.
> Establish and maintain RCS temperature to establish adequate subcooling to l preclude transition into ECA-3.1 and without causing an extreme challenge to the Subcriticality and/or Integrity CSFs.
1
.i PRE-EXERCISE BRIEF i '1. Follow NUREG-1021 Appendix E; Part E Page 3 of 19 L
Titis: Load incrers; Loss of Charging Fl:w; Tcvg Fil; Number: 99-03
,' . Fcilure High; Les cf Vccuum; Turbins Vcivs . - R;v: = 1 Failures; ATWS; SG Pressure Instr. Fall High; , .
SGTR t INSTRUCTOR GUIDE
- 1. Initialize to IC-19 and verify the following conditions: l
- b. MOC Al displayed.
- c. Bank D step counters at 177, all others 228.
l
- d. All charts advanced and cleared of previous trends. ;
- e. ERCS is on-line and functional with alarms acknowledged / cleared.
1
- 2. Insert the following pre-existing conditions (Relative order of 0).
- a. Mechanical Failure of Reactor Trip Breakers
- b. PT-449 failure low and bistables tripped
- c. Increase FW Pump casing temperatures i
- d. 1/O Valves associated with TD AFW Pump i
- 3. Establish the following conditions:
- a. Place a "l&C Channel in Calibration" placard near channel PT-449.
- b. Remove 11 TDAFW pump from service as follows ,
- Place 11 TDAFW pump in pullout and attach a secure card.
Place 11 TDAFW pump in MANUAL and attach a secure card.
- Close Steam Supplies to TD AFW Pump
- Close Discharge Valves from TD AFW Pump to 11/12 SGs
- c. Place a 2"d orifice in service. Start 12 Pump in MAN; place 11 in AUTO.
- d. Establish 1 MFP,2 Condensate pumps, and 2 HDT pumps running.
- 4. Arrange the following information:
- a. Cat l Vent opening sheet reflects no logged openings. j i
- b. Log books are open to a blank page. 4
- c. C1.4 consumable is the same revision as the book and signed off through Section 5.1.18.D. (Load Rate is unlimited / Rods preconditioned to 218 steps) Also sign off step 5.1.20.G for placing HDT pump to AUTO.
- d. Place Current Value of 1U2026AH on an ERCS display. !
- e. Shift TPM to NIS with Auto Scaling. l l
l- Page 4 of 19 l L j
r Titlo: Lecd incrores; Loca of Chrrging Flcw; Tcvg Fib Number: 99 . Failure High; Lc:s cf Vacuum; Turbino Vciva -
- Rsv: 1 Failures; ATWS; SG Pressure Instr. Fall High; SGTR
- f. Update and print and LCO log with the following information:
l TS Time Reason !'
Component Number Limit Code Description Dr.te and Time 11 AFW 3.4.B.2.b 72 HR CM Oilleak on oil cooler Today 0100 ,
pump l l
- 5. Conduct shift turnover I l
- a. Use the shift turnover sheet provided and provide the following information:
Current power is 50% with a load increase in progress. Ready to start a second MFP at C1.4 step 5.1.20.E. Shutdown was to repair a hydraulic line on turbine CV-1.
11 TD AFW Pump is OOS due to governor problems. The expected time OOS is at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I&C is performing a calibration of pressurizer pressure channel PT-449 (Yellow) which is expected to be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Unit 2 is shutdown.
- b. Allow 3-5 minutes for control board familiarization.
- 6. When requested, provide support for starting a second MFP.
- 7. At the discretion of the chief examiner insert loss of air to 12 running charging pump (Relative order of 1).
- a. After the Aux. Bldg. Operatcr has been directed to investigate the pump, l report that there is an air leak coming from the speed controller for the 12 charging pump.
- b. If maintenance is contacted regarding 12 charging pump, report that it you will initiate a work order. Estimated time for repair is about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 8. When charging has been restored AND one charging pump is in AUTO, Then at the discretion of the chief examiner insert yellow channel Teoio failure high (Relative order of 2). l 1
- a. Trip bistables upon request (Relative Order of 3).
1 i
Page 5 of 19 L.
g ]
I Titis: Lecd Ingreses; Loss cf Chrrging Flow; Trvg FiliNumber: 99 03-1 x l
. Fcilure High; Leca of Vccuum; Turbino Vcivs LRiv: .1( , F Failures; ATWS; SG Pressure Instr. Fall High; '
+
SGTR . ' '
fl
- 9. ' At the discretion of the chief examiner enter failure of gland steam air exhauster l and resultiag lowering of gland steam condenser vacuum (Relative order of 4). I
- a. If asked to investigate, report that the gland steam condenser air exhauster thermal overloads on MCC 1C1-B5 have tripped.
- b. As directed, report dampers positioned per C29.
- 10. At the discretion of the chief examiner fail one turbine intercept valve closed .
(Relative order of 5).
- a. If asked to investigate, report that there is a fog in the area of the actuator for CV-31167.
- b. At the discretion of the chief examiner fail a 2nd intercept valve Closed (Relative order of 6).
i
- c. If asked to increase power to 70%; direct a hold on the load change to evaluate repairs.
- 11. .When a reactor trip using DSS is performed, then perform the following:
- a. Insert PT-478; SG pressure instrument failure high (Relative order of 7)
- 12. During E-0:
- a. If asked, locally open the reactor trip breakers one minute after being directed (Relative order of 8).
- 13. During E-3:
- a. Wait a couple of minutes and report that a cation column frisk of 12 SG reveals activity above background.
- b. After containment isolation is reset, wait 5 minutes and report that a frisk of the SG sample bottle shows elevated activity in 12 SG. No elevated activity in 11 SG.
l' 14. At the discretion of the chief examiner (SI pumps off), place the simulator in FREEZE.
Page 6 of 19
F
' i I Titl3: Le d incre:00; Los3 cf Ch::rging Flew; Tcvg Fil3 Number: 99-03
. Fcilure High; Lt:s cf Vacuum; Turbina Valva : R:v: 1 Failures; ATWS; SG Pressure Instr. Fall High; SGTR l Name: Position: SM SS Lead RO Dato:
Event Description KA Number KA Value Start 2" MFP Time SIU Position Expected Response Lead C28.2; Start a Second MFP (Section 5.5) e Verify 2 Condensate Pumps running
. Place / Verify CV-31875 Recirc to Open Position
. Verify various alarms on 47010 NOT LIT l
. ERCS GRPDIS "OP6" to observe temperatures j e Start 12 MFP (Switch held until Recire valve open and permissive ON)
Evaluator Note:
Comments:
i Page 7 of 19
ct Titis: Load incr=C2; Los3 of Ch:rging Flow; Tcvg Fil: Number: 99 03.
. Fcilure High; Lesa cf Vccuum; Turbinn Vciva --R;v:'1.-
Failures; ATWS; SG Pressure Instr. Fall High; SGTR Event Description KA Number KA Value Load increase Time S/U Position Expccted Response C1.4 Load increase RO . Dilution started RO . . When Tavg shows an increase, turbine place in GO Evaluator Note:
Comments:
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Page 8 of 19
)
I .
Titis: Lecd increnco; Leca cf Chcrging Flow; Tevg Fil Number: 99 03 '
. Fcilure High; Lcc3 cf Vacuum; Turbins Vciva R:v:';.1" Failures; ATWS; SG Pressure instr. Fall High; >
SGTR l
Event Description KA Number KA Value ,
Loss of Air to Running Charging Pump j Time l S/U Position Expected Response C12.1 and/or C12.1 AOP1 i RO e Determine 12 charging pump low speed.
'RO e Stop 12 charging pump.
RO e Start 13 charging pump.
RO e Adjust seal injection flow to between 6 and 10 gpm per pump. ,
RO e Place running charging pump in AUTO.
Lead e Make appropriate log entries Evaluator Note:
Comments:
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l Page 9 of 19 l
' l Titix Load increzca; Los3 of Chrrging Flow; Tcvg FilJ Number.- 99 03_ l
. . Fciture High; Lesa of V cuum; Turbins Vciva .
R;v: t ;
Failures; ATWS; SG Pressure Instr. Fall High; i j SGTR '
Event Description KA Number KA Value ,
Teaa Channel Failure High l Time S/U Position Expected Response C51.4 Tavo Loop 1 A 1T-404 - High RO . Place charging pump in MANUAL and maintain pressurizer level.
RO e Select Yellow channel on TAVG defeat switch and pull out.
RO e Return rod control to AUTO.
RO e Return charging pump speed to AUTO.
- Refer to T.S.3.5 (6 hr LCO for B/S tripping). j RO/ Lead
- Trip and independently verify bistables.
RO/ Lead
- Initiate work order on the failed channel.
- Make appropriate log entnes, j I
Evaluator Note: i Comments: )
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Page 10 of 19 i
t_ J
Titis: Lecd incre ar; Loss of Chrrging Flow; Tcvg Fib Number: 99 03
. Fcilure High; Leca cf Vccuum; Turbins Vcivs - R;v:' ._1 Failures; ATWS; SG Pressure Instr. Fall High; . -
SGTR Event Description KA Number KA Value Loss of Gland Steam Condenser l
Time 1 S/U Position Expected Response '
C47008 and C29; Swap Gland Steam Air Exhausters Lead e Direct TBO to align and drain discharge Lead e Start Standby G.S. Air Exhauster Lead e Direct TBO to Open B Damper and Shut A Damper Lead e Verify between 12 and 16 inches H 2O on PI-4121901 Lead e Move discharge damper closed sign to 11 A exhauster Lead /SS e Direct Electrician to investigate and repair Lead e Make appropriate log entries Evaluator Note:
Comments:
l l
Page 11 of 19 L_
Titla: Lscd incrosas; Loss cf Chrrging Flow; Tcvg Fils Number: 99-03
, Fcilure High; Lc:s cf Vccuum; Turbina Vriva Riv: 1 Fcilures; ATWS; SG Pres 2urs Instr. Fsil High; SGTR Event Description KA Number KA Value Intercept Valve Failure l Time S/U Position Expected Response C23 AOP2; Malfunction of Turbine EH Control System (1" Valve)
Lead . Identify Intercept valve closed Lead . Direct TBO to investigate Lead . Inform crew of 70% power limitation d
C23 AOP2; Malfunction of Turbine EH Control System (2 Valve)
Lead e Identify 2 intercept valves closed on one turbine and need to trip Rx and Turbine Evaluator Note:
Comments:
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Page 12 of 19 L
Titlo: Lecd incre2 O; Loss of Ch rging Flow; Tcvg File Number: 9943 -
, Fcilure High; L :a cf Vccuum; Turbina Valva u _
R:v: 11 . : t-
. i Fcilure3; ATWS; SG Pre ::ure in3tr. Fall High; % - 4 ,
SGTR 1
Event Description KA Number KA Value Reactor Trip / ATWS Time S/U Position Expected Response E-0; Reactor Trip or Safety injection RO e Attempt to trip unit using Rx Trip Switches RO/ Lead . Trip unit using DSS switch (critical)'
RO . Verify reactor powerless than 5%
Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized.
RO e Check if Sl is required
-SG Pressure >500 psig
-PRZR Pressure >1815 psig
-PRZR Level >5%
-Subcooling >20'F
-Containment Pressure <4 psig ,
SS . Transition to ES-0.1 if no Si required. Continue in ES-0.1 until SI I is required. I I
Evaluator Note:
- 1. Insert negative reactivity by either inserting control rods, establishing RCS boration; or directing local trip of the reactor prior to FR-S.1 Step 6.
I Comments:
l I
l Page 13 of 19
1 Titla: Load incre2:2; Loss of C'n rging Flow; Tcvg Fila Number: :99-03
. Fcilure High; Le:3 cf Vccuum; Turbina Valv3 R:;v: di, j.
Failures; ATWS; SG Pressure Instr. Fall High; 1 e
SGTR Event Description KA Number KA Value SG Pressure instrument Failure High Time S/U Position Expected Response C47011 Lead /RO e Identify and inform crew of open PORV i Lead /RO . Shut PORV by taking PORV controller to Manual Lead e Control SG Pressure manually Evaluator Note:
Comments: j 1
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b .
r' Titl3: Lecd increnc:; Loss of Ch;rging Flow; Tcvg Fils Number:' 99 03 Fcilura High; Len cf Vccuum; Turbins Vciva R3v: : 1L Failures; ATWS; SG Pressure Instr. Fall High; j SGTR j i
Event Description KA Number KA Value SGTR; Sl Required or Actuated Time S/U Position Expected Response RO/ Lead . Si actuated Automatically or Manually SS . E-0 Re-entered E-0; Reactor Trip or Safety injection RO . Verify Reactor Tripped Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized.
RO e Verify SI actuated Status Light ON Lead . Verifies component alignment Lead . Closes MV-32115 (CC to SFP Cooling)
SS . Ensures communication with NRC is established w/i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Lead . Opens turbine HP drains Lead . Directs Outplant to stop the TB roof exhausters and isolate the MSR's SS . Ensure Auto-Action Guide is implemented Lead . Place SD in " Steam Pressure" mode Lead . Maintains >200 gpm total AFW flow unless "A" SG level is >10%
RO . Verifies RCP seal cooling I Crew . Diagnoses a Ruptured SG and transition to E-3 l Evaluator Note:
Comments:
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l Page 15 of 19
\
u
F 1 l .
Titis: Lead incre cc; Lc:s of Chirging Flow; Tevg Fib Number: 99-03
- Frilure High; Leca cf Vccuum; Turbino Vciva Rdv: 1 Failures; ATWS; SG Pressure Instr. Fall High; j l SGTR l
Event Description KA Number KA Value Steam Generator Tube Rupture Time S/U Position Expected Response E 3: SGTR RO/ Lead e identify 12 SG as ruptured.
Lead .
Isolate flow from 12 SG. (Crit / cal Task)'
- Close steam supply to TD AFW pump.
- Close MSIV.
- lsolate feed flow to 12 SG when NR is >10% (Cr/t/ cal Task)'
Lead /RO e ResetSt.
Lead /RO e Reset Cl.
Lead .
Initiate RCS cooldown (Critical Task)'
- Determine required CETC temperature.
- Cooldown at maximum rate using condenser steam dump.*#
- Maintain CETC temperature once desired value is attained.
Evaluator Note:
- 1. Isolate feed flow to and steam flow from a ruptured SG before entry into ECA-3.1 is required.
- 2. Establish and maintain an RCS temperature to establish adequate subcooling to preclude transition into ECA-3.1 and without causing an extreme or severe challenge to the Subcriticality and/or Integrity CSF.
Comments:
1 i
l Page 16 of 19 1
L J
T' Titl3: Lc:d incream; Losa of Ch:rging Flow; TEvg File Number:: 99 . Fcilure High; Lcco of Vacuum; Turbins Vciva R;v: 1 Failures; ATWS; SG Pressure Instr. Fall High; SGTR Event Description KA Number KA Value Steam Generator Tube Rupture (continued)
Time SIU Position Expected Response E-3 (continued)
RO . Establish maxim"m charging flow from RWST.
RO . Turn all pressurizer heaters OFF.
RO . Depressurize the RCS using normal spray at the maximum rate until either:
- RCS press < SG press and PZR level > SE
- PZR level >70%
- Subcooling <20*F.
RO . Verify RCS pressure increasing.
Crew . Verify Si termination criteria are met. l Lead . Stop SI pumps' Evaluator Note:
- 1. After SI pump are stopped, at the discretion of the Chief Examiner, the scenario may be terminated.
Comments:
I
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Page 17 of 19 L j
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CHAMPS FORM KTF-D 2
- RETENTION: 7 DAYS DATE:
l UNIT 1 LPRO / PEO TURNOVER TIME N(1800-0600)
SFGDS EQUIP OOS/LCO'S:
1 :11 TD AFW PUMP DUE TO GOVERNOR PROBLEM - EXPECT 24 HOURS FOR REPAIR 2 . : PT-44 9 FOR CAL 3
RAD MONS OOS: ANNUNC'S OOS:
OUTSTANDING SP'S FIRE DET/ PROT EQUIP IMPAIRMENT:
OTHER EQUIP OOS / STATUS:
1 5 2
3 :
4 :
5 6 : ,
7 s-B :
9 :
10 :
11 :
12 :
13 :
14 :
15 :
16 :
17 :
MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE:
1 EHC HYDRAULIC LEAK 2
3 :
4 : l 5 :
OPERATIONAL PLANS FOR COMING SHIFT 1 : START A SECOND MFP PER C1.4 AND CONTINUE LOAD INCREASE 2 :
( 3': ;
4 :
NEN PROCEDURES / INSTRUCTIONS:
1 :
2 :
3 :
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1 PEO RELIEVED BY: TIME: DATE:
CB WALKDOWN - - > LPEO : TIME:
- - > PEO : TIME: j l
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)
m 7 INITIAL SUBMITTAL OF THE EXAMINATION OUTLINES FOR THE PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 AD ~?o l
~1 h
Northem States Power Company Prairie Island Training Center h 5 8 68 March 5,1999 Mr. Dell McNeil NRC Region ill Division of Rx Safety - OLB 801 Warrenville Rd.
Lisle, IL 60532-4351
Dear Dell,
As agreed in a letter from Melvyn Leach dated January 25,1999, enclosed are the exam outlines for the RO exam to be administered the week of May 16,1999. Also attached is the ES-201 Quality Assurance Checklist.
Please withhold these materials from public disclosure until after the examinations are complete.
Thanks for your help thus far and if you have any questions regarding the exam outline, please call me at (651) 388-1165 x4053.
Sincerely,
,Y l im Lash Senior TechnicalInstructor l
enclosure: 1
{
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p
Item Task Description a b c
- 1. a. Verify that the outune(s) St(s) the appropriate model per ES-401, g
- b. Assess whether all sin knowledge and four abluty categories are appropriately sampled jggg f
- c. Assess whether the outEne over,...,.; ' es any systems, evoiutions, or generic topics. )4,.
- d. Assess whether the repetition from previous examination outlines is excessive. g %
- 2. a. Using Form ES-3015, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component feliures, and maior transients. Nk S
I b. Assess whether there are enough scenario sets (and spares) to test the ptojected number R4 and mix of appEconts in accordance with the expected crew composition and rotation j p scheduie without compromising exam integrity; ensure each applicant can be tested using at least one new scenario and scenarios win not be repeated over successive days.
f
- c. To the extent poselbie, assess whether the outEne(s) conform (s) with the qualitative and p quantitative criteria specined on Form ES-3014 and described in Appendu D. S,k.
- 3. a. Verify that the outune(s) contain(s) the required number of control room and in-plant tasks g and verify that no more than 30% of the test material is repeated from the last NRC er W examination l-T b. Verify that the tasks are detributed among the safety function groupmos as specified in ES-301; one task shed require a low. power or shutdown condtion, one or two shaE require the app 5 cant to *--_ _ r en aitomate path procedure, and one should require entry to the y %
RCA.
- c. Verify that dw required administrative topics are covered, with emphasis on performance- -
g based activities N
- d. Determine if there are enough efferent outilnes to test the projected number and mix of y appucants and ensure that ne more than 30% of the items are duplicated on successive days. gX
- 4. a. Assess whether plant-speciac priorities (including PRA and IPE insights) are covered in the g m_ enam section. /f b
- b. Assess whether the 10 CFR 55.41/43 and 56.45 sempung is - m ; ;e. AfM b
- c. Ensure that K/A 'n ; .;e ratings (except for plant-specific priorities) are at leest 2.5. Tilg b
- d. Check for dupacetion and overlap among exam sections. Mfg h e.~ Check the enere exam fa balance of covnage. Ag MH
- a. Author Ed .T 5", a < 2 t1 99
- b. Feeluty Reviewer (*) dw5 % L-a s L. WW AC - f.u-ep
- c. Chief Examiner '3ks iI $, Mf hlt< l Wt?/ WWW > OW$)
- d. mRc sup= visor % a /A r : /4 YA h o#E W6tI% yh r,q
( ) not appscabie f= mRC r y .meminavons 1
NUREG-1021 25 of 24 Interim Rev. 8. January 1997 1
~
f l Facility Prairie Island Date of Exam: 05/17/99 Exam Level: RO Tier Group K/A Category Points Point Total K1 K2 K K A1 A2 A3 A4 G
- 1. 1 2 2 16 Emargency 2 _3__2_ 17
& Abnormal 3 _,1_ ___
1 1 3 Plant Tier Evolutions Totals 6 4 7 7 36 1 3 1 1 2 1 1 1 3 5 2 3 23
- 2. Plant 2 3 1 1 l2[2l2l1 2l2l2d2 20 Systems 3 1 l2l l l1 l1l2l1 8 Tier Totals 7 2 2 6 3l3 1 3 5 8 6 6 51
- 3. Generic Knowledge and Abilities l Cat 1 l Cat 2 Cat 3 ! Cat 4 q l 5 l 3 2 3 13 l Note: -
Attempt to distribute topics among all K/A Categories: select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table.
Select topics from many systems: avoid selecting more than two or three K/A topics frr m a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
. The shaded areas are not applicable to the category / tier.
n 4- t s 1 1 1 1 1 1 1 1 1 1 1 5 1 1 1 1 1 1 P 1 0 7 .c 4
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l ES-401 G neric Knowledge and Abilitlis Outline (Tirr 3) ES-4015 Exam Facility Prairie Island Date: May 17,1999 _
Level: RO Category KA # KA Topic Imp. Points C:nduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.7 1 2.1.10 Knowledge of conditions and limitations in the facility license. 2.7 1 2.1.17 Ability to make accurate, clear and concise verbal reports. 3.5 1 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 2.1.3 Knowledge of shift tumover practices. 3.0 1 Total 5 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.0 1 2.2.24 Ability to analyze the affect of maintenance activities on LCO status. 2.6 1 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of 2.2.30 fueling operations, and supporting instrumentation. 3.5 1 Total 3 Knowledge of 10 CFR: 20 and related facility radiation control Radiation Control 2.3.1 requirements. 2.6 1 Ability to perform procedures to reduce excessive levels of radiation 2.3.10 and guard against personnel exposure. 2.9 1 Total 2 Emergency Procedures 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.3 1 Knowledge of low power / shutdown implications in accident (e.g.
and Plan 2.4.9 LOCA orloss of RHR mitigation strategies). 3.3 1 Knowledge of EOP implementation hierarchy and coordination with 2.4.16 other support procedures. 3.0 1 1
Total 3 Tl;r 3 Target Point Totti (RO/SRO) 13 J
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'ES-301~ Administrative Topics Outline Ferm-ES-301-1 Facility: PrairicIsland I & 2 Date of Fvamination: May 17,1999 j
, Examinationlevel: RO Operating Test Number: I j Administrative Describe method of enluation:
Topic / Subject 1. ONE Administrative JPM,OR Description 2. TWO AdministrativeQuestions i Al Plant Parameter Verification / 1. JPM K/A 2.1.7 3.7/4.4 i Determme Boration/ Dilution I for An Estimated Critical Condition ,
1 l
Procedure Modification / Initiate 1. JPM K/A 2.2.11 2.5/3.4*
a Temporary Change to Procedure A2 Clearance And Tagging / 1. JPM K/A 2.2.13 3.6/3.8 Review Prepared Isolation for Approval (Approver)
A.3 Protection From Radiation 1. JPM K/A 2.3.10 2.9/3.3 Exposure / Prepare For Entry Into High Radiation Area >
1000 mr/hr A.4 Emergency Plan / Initiate Local 1. JPM K/A 2.4.39 3.3/3.1 Emergency Evacuation f
NUREG-1021 Interim Rev. 8, January 1997 j c
i Admin Section Comments A.l.1 - Given critical wnditions and current plant conditions, candidate determines the dilution or boration (gallons of water or acid blend) required to reach ECC boron concentration. Procedure referena CI A ECC-1 and Cl2.5.
A.I.2 - Identify a procedure used by Control Room operators and state that due to recent changes in Plant a new step needs to be performed that involves operating a valve or setting a controller to a specific value (i.e., provide the operation step to the Candidate in Initial Conditions). His step was not incorporated when the procedure was updated but needs to be added to allow placmg the system in operation. He candidate is to initiate and get approval for the Temporary Change. Procedure
- reference AWI 1.5.10.
A.2. ' Have a isolation for some piece of mechanical equipment (pump or valve) and leave one isolation valve off list. Candidate is to review and determine that the isolation point (valve) must be added to isolation. Procedure reference AWI 3.10.0 section 6.11.3.d.
A.3- Candidate prepares for entry into a (proposed) Locked High Rad Area to perform some operation. His can be either an actual location or the Practice Area if set up for Training. 'lle candidate is expected to obtain proper entry authorization and access key (simulated), make RCA entry (get radiation detection device (s), check surveys, get HP briefing (if required), get proper Protective Clothing) and proceed to HRA for entry (Actual entry into area is N(Yr expected, uniess Training Area is setup). Procedure reference F2 sections 3.2.3 and 4.6.
A.4 - - Candidate initiates a local evacuation of tie Auxiliary Building in response to a steamline break. His is a control room operator action prescribed by F3-9 Section 7.2. This is performed in the simulator and the actions include determmation of the assembly area, sounding of the evacuation alarm, and making a plant page announcement.
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ES-301 hulividual Walk-Through Test OutHa* Form-ES-301-2 Facility: Praine Island I & 2 Date of Exanunation: May 17,1999 Examination Level: RO Operating Test Number. 1 System / JPM Title / Type Codes
- Safety Planned Followup Questions:
Function K/A/G-Importance -Description
- 1. Rod Control System / I a. 001 K4.02 3.8/3.8 Startup Reset pushbutton response l Withdraw Shutdown Banks b. 001 A3.02 3.7/3.6 Rod Insertion Limits (B only)
N S L .
- 2. Residual Heat Removal / IV a. 005 A1.013.5/3.6 Cooldownlimits AlternateIn Service RHR b. 005 Kl.09 3.6/3.9 Refueling Cavity fill / drain Imp [RH-6S]
D S L
- 3. CVCS /ManualMakeup to 11 a. 006 2.1.33 3.4/4.0 Tech Spec for RWST the RWST[VC-18] b. 004 K4.12 3.1/3.4 VCrlevel control D S
- 4. Radiation Monitoring / VII a. 073 K3.013.6/4.2 CNMT Sampling Rad Monitor Transfer IR-11/12 Sample b. 073 A2.02 2.7/3.2 Process system response and operator action to a detector Discharge From the failure Containment to the Aux Bldg [RM IS]
M S
- 5. Component Cooling / VIII a. 015 AK3.02 3.0/3.1 Actions required for leak on CCW to RCP Respond to Component b. 008 K4.02 2.9/2.7 Expected response of Surge Tank Cooling Malfunction (Failure of RCP Thermal BarrierHx AOVCV-31245 to Automatically Close)
N A S
- 6. PRZR Pressure Control 111 a. 008 AAl.08 3.8/3.8 Effect ofleakmg PRZR Safety on PRT System / D,Ms RCS b. 004 Kl.17 3.4/3.4 Relationship between charging, Aux. Spray and the PRZR i to Refill Pressurizer [EO-l 7SF-1]
M A S
- 7. Contamment Spray / V a. (W)E14 EK2.2 3.4/3.8 Heat removalcapability(w/ CFUs)
Response to High b. 026 A2.05 3.7/4.1 Failure of Caustic Addition during LOCA Containment Pressure (ManualContainment Spray Initiation)[CS-ISF-1]
D A S
- 8. Fire Protection / Ese, .cy VIII a. 2.4.27 3.W3.5 Action for a fire in plant (PRA Important Event)
Startmg of122 Diesel Fire b. 086 K4.07 2.5/2.8 Interlocks which protect the turbine generator exciter Pump [FP-2F-1] (PRA
. Important Event)
D A P
Vent / Vent Contamment b. 028 K5.03 2.9/3.6 Sources of hydrogen in contamment Using Post LOCA Vent System [HC-2]
D P R
- 10. AC Electrical / Transfer VI a. 062 K1.02 4.1/4.4 Operational limits for Diesel Generator Unit 2 480V Busses to'lheir b. 062 A4.013.3/3.1 Effect of SI actuation on either Unit
' Alternate Supply [EA 15]
D -P Type Codes: (D) Direct from bank, (M)odified from bank, (N)ew, (A)lternate Path, (C)ontrol Room, (S)imulator, (P)lant, (L)ow Power, (R)CA NUREG-1021 Interim Rev. 8, January 1997 i
1 Assumed Conditions for JPMs JPMs 1 & 2 Can be performed together or from same IC. JPMs 3,4 & 5 can be performed together or from same IC. JPMs 6 &
7 can be performed together or from same IC. The last ore may result in some problems and would have to be set up in different ICs.
JPM 1 Mode 4 or 5, Shutdown Banks A withdrawn with Bank Selector Switch in "SBA". Currently completed through step 5.2.1 E of ICS. May need to provide directions that actions performed IAW ICl.2 step 5.1.7 H. (Requires RCP running). Initiales action to withdraw "SDB" per remainder of 5.2.1.
1PM 3 Just like Facility JPM. (New JPM VC-185 was written to beperformedon the smulator, asJPM VC-18 is written to be Amulated)
JPM 4 Any at power IC, CNMT pressure normal and IRI1/12 aligned to Contamment. (Sl03, SAMPLE SELECIDR switch, located on IR-11 drawer, in the "CONTAIN" position; At S108, R-11/12 DISCHARGE TO AUX STACK, red light on the switch is OFF; At S107, R-11/12 DISCHARGE TO CONTAINMENT, yellow light on the switch is ON; Close RD-5-2, iR-11/12 RAD MON SAMPLE INLET TEST.) Actions to restore alignment to Aux Bldg Stack is 1AW C11, section 5.1.2. (New JPMRM-45 was written topmvide the suggestedmodification toJPMRM.
IS)
JPM 5 Any at power IC, fail auto closure capability for RCP 11 ' thermal Barrier Hx CC AOV CV-31425. When JPM initiated, insert small thermal barner leak sufficient enough to raise sensed flow > 75 gpm (Alarm 47015-0108 4 sctive). Would like to get rising levels on IR-39. Action should be taken IAW ICl4 AOP2 with co'npletion of Subsequent Manual Actions as endpoint. Will need CUE for step 2.4.1, that another operator will check actions of 4 1C4 AOPl. Step 2.4.3 becomes critical.
JPM 6 Post accident condition (steamline break on both SGs). RCS conditions require both RCPs stopped; letdown established; and RCS pressure > 400 psig. Steps of E-0 and steps of ECA-2.1 through step 34 need to be completed.
'the operator will determine that normal PRZR sprays are not available and will be required to use auxiliary spray.
When RCS pressure is reduced to < 400 psig, the operator will stop depressurization by closing aux spray. These actions are directed in ECA 2.1 step 35. (NewJPMEO-26SF-1 was written topmvide the suggestedmodification to JPMEO-7SF-1.)
JPM 7- Just like Facility JPM.
JPM 9 - Just like Facility JPM.
JPM 10 Just like Facility JPM.
2 EOP JPMs (6 & 7) l 2 AOPJPMs (5 & 8) [NOUi: JPM 10 could also be considered in this category since the performance is initiated due to off- l normal condition]
6 OP JPMs (1,2,3,4,9 & 10) l l
)
1 o c.
1 Questioninformation JPM 1 - a. The Rod Startup Switch is inadvertently operated while at power. Either identify the expected indications that are affected or identify the actions required to correct / recover for this action.
- b. Based on given power level or a transient that results in power change determme when the " Control Banks 14w/ Low Limit" would expect to actuate.
JPM 2 - a. Given a set of conditions on RHR with RCP running use the Cooldown/RCS operational curve to determme the minimum or maximum pressure for RCS. Or give cooldown rate and determine at what point given pressure can be l maintained during cooldown.
- b. Using P&ID or simplified drawing, describe the flowpath for filling and/or drammg Refueling Cavity. May wish to direct it to controls operated in Control Room.
JPM 3 - a. Provide plant conditions for RWST level (%) below Tech Spec value and required OPERABLE. Have Candidate determine level is inadequate and determine required ACTION.
- b. Given under current conditions of fill to RWST what occurs as far as auto actions /CR indications if a charging header leak develops (or PRZR level begins to fall). No operator action taken JPM 4 - a. Given situation where RI1/12 is NCfr aligned to CNMT (Ram.aHag Shield Bldg Vent??) what are the requirements for leak detection monitoring (Ref. Cl16.4.2) or plant effluent releases (Ref. Cl16.4.1)
- b. Describe the process monitor response and operator actions to a process rad monitor failure downscale.
JPM $ - a. If condition existed where leak was deternuned to be on CC supply to RCP inside CNMT what actions have to be taken (ref. ICl4 AOP12.4.5.C)
- b. CC Surge Tank response to RCP Thermal Barrier tube rupture (larger leak) with failure ofisolation valve to close.
(What occurs as Surge Tank fills)
JPM 6 - a. Typical isenthalpic throttle problem. Given initial PRZR conditions and PRT pressure, determine PRT temperature and state (subcooled/superheat)
- b. What step (s) have to be t ken to ensure maxunum aux spray flow with charging in service.
JPM 7 - a. Relationship between CS & CFUs in heat removal from accident. Provide failure of ONE train of CS and ask what components are required to operate
JPM 8 - a. What equipment should be deenergized for a fire in FA $9 (PRA Important Event).
- b. Interlocks / manual actions that prevent inadvertent discharge of generator exciter beanng spnnkler system (Ref. C31 ,
5.11) l l
JPM 9 - a. As stated. !
JPM 10 - a. Limit on bus (es) load when Alternate Source powered from Diesel. If operation NOT allowed then give for normal l source (provide cunent loading and determme which loads can be added) !
- b. As stated, what occurs to alignment (breakers affected) if SI occun on Unit I and/or on Unit 2. '
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Simulation Facility Praine Island I & 2 Scenari) No.: 1 Op Test No.: 1 Examiners- Operators: SEQ BQ BDE Objectives: 1. Perform a load decrease per C1.4.
- 2. Diagnose and respond to a FRV failing to manual per C47011-0305.
- 3. Diagnose and respond to failure of controlling PRZR level channel low per C51.
- 4. Diagnose and respond to a loss of normal boration due to a BATP tr) per C47015:0403.
- 5. Diagnose and respond to a loss of Bus 12 resulting in a loss of main feedwater and reactor trip per E 0 (PRA important event).
- 6. Diagnose and respond to failure of main steam header pressure instrument high and a failed open steam dump per E-0.
- 8. Diagnose and respond to under.compernwed IntM* Range NIS per ES-0.1.
Initial Conditions: 1. IC-21,89% power.
- 2. 11 SG tube leakage of 5 gpm steady state.
- 3. Remove 12 Boric Acid Transfer Pump from service.
Turnover. 1. Current poweris 89%
- 2. Shutdown is in progress due to 11 SG tube leakage (Technimi Specification 3.1.C.2.e) of approximately 5 gPart
- 3. Action is in progress IAW C4 AOP2 (Action f.evel 2) at step 2.7.9 to have the Unit shutdown in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 4. Unit 2 is operating at 100% power.
- 5. 12 MD AFW Pump is OOS due to grounds. 'lhe expected time OOS is at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 6. 12 Boric Acid Transfer Pump is OOS for preventative maintenana. 'Ibe pump is expected to be released to service in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
I
Event Malf. Event Event No. No. Type
- Description Preload SOOIA 10 5 apm tube leak in i1 SG (run to equilibrium)
Preload NIO4A,10 N35 Irmermediate Range channel improper compensation voltage SRO l R RO l
l' N BOP Reduce reactor power due to SG tube leakage BOP '
2 RX14B C SRO 12 Steam Generator level matrol fails to Manual l RO 3 RX10C, O I SRO Fallblue channelPRZRlevel to 0% i RO J 4 10 46161 C SRO 11 Boric AcidTransfer Pump trip RO BOP 5 ED09B M SRO Bus 12 lockout RX225,1400 BOP 6 MSIIB I SRO FT-484 MS Header press. instr. fails high and one steam dump valve fails open.
BOP 7 FW33 C SRO Turbine Driven AFW Pump overspeed trip RO h8 (preload) I SRO N35 Intermediate Range channel undercompensated
((N)ormal, (R)eactivity (1)nstrument, (C)omponent, (M)ajorTransient I
1 1
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[*..-.
I SCENARIO l-1
SUMMARY
- the scenario will begin at 89% power with (12) MD AFW Pump, and 12 Boric Acid Transfer Pump out of service. I1 SG has been diagnosed with tube leakage and has been evaluated at approximately 5 spm. C4 AOP2 " Steam Generator Tube Leak" is in progress with actions completed through step 2.7.9. Unit shutdown commenced approximately 30 minutes ago. Unit shutdown is t(
continue following turnover. 'Ihe leak rate has remained stable since the initial event. Following shiR turnover the crew will continue the power reduction to Hot Shutdown in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
During the power reduction,12 SG level control fails to MANUAL. Following the bumpless transfer to manual, the operator will be required to control feed to 12 SG to maintain proper level.
Following at least a 5% power reduction, the controlling Pressunzer level channel fails low. Charging pump speed increases, PRZR heaters deenergize, and letdown isolates. The crew will need to take manual control of charging pump speed, select a new controlling channel, restore letdown per C12.1, and return chargmg pump speed to automatic.
AAer actions are completed and affected bistables tripped, during the next boration, the only operable (11) Boric Acid Transfer Pump will trip. The crew will be required to evaluate RCS boration during shutdown Alternates include swapping Charging Pump suction to RWST or restoring 12 Boric Acid Transfer Pump.
A loss of bus 12 will cause a loss of 12 Main Feed Pump and 12 RCP and a reactor trip. A feedwater isolation will occur at 554 'F. When the 'ID AFW pump starts it will overspeed and all feedwater will be lost.
AAer steam dump control is taken to the pressure control mode, the Main Steam header pressure instrument will fail high and one steam dump valve will stick open. The crew must take actiosa to stop the steam release by shutting the MSIVs.
Entry into FR-H.1 will be required to handle the loss of heat sink now that SG levels are less than 50% Action should be taken to either cross-connect AFW from unit 2 or establish MFW by resettmg the feedwater isolation (this is a PRA significant task).
At approximately 15 minutes following the reactor trip, the crew will be required to determine Sourm Range NIS failed to re-energize due to undercompensation ofIR NIS channel N35. The crew will be required to manually reenergize the Source Range NIS.
Scenario ends when stable plant conditions are established per step 15 of ES-0.1.
Critical Tasks
- 1. Manually isolate steam dumps from the control room before an entry into an Integrity orange path or ECA-2.1 is required.
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a Simulation Facility PrairieIsland I & 2 Scenario No.: 2 Op Test N).: 1 Examiners: Operators: Sgg BQ DDE Objectives: 1. Perform electrical lineup for power operation and transfer Steam Dump control per C1.2.
- 2. Perform a load increase per Cl.2 and C1.4.
- 3. Diagnose and respond to a failure of a Power Range NIS channel low per CSI.
- 4. Diagnose and respond to a reduction in Main Generator hydrogen cooling per C47007:0401.
- 5. Diagnose and respond to a dropped control rod with the failure of an autcmatic reactor trip per E-0.
- 6. Diagnose and respond to failure of a main steamline isolation and an MSIV failure to close per E-0.
- 7. Diagnose and respond to a failure of one train of Safety Injection to actuate and a trip of one SI pump per E-0 (PRA important components).
Initial Conditions: 1. IC-16,15 % power (up from given 11%).
- 2. Place a WR sticker next to PCV-430 and an information tag on the control switch stating PCV-430 leaking. Close PORV block valve MV 321% and attach secure card.
- 3. Remove 12 Boric Acid Transfer pump from service.
- 4. Remove D1 from senice (PRA important component). ;
Turnover: 1. Current power is 15% and has been held there for 20 minutes.
- 2. Unit startup is continuing with power increase to 100% power.
- 3. Action is in progress IAW ICl.2 step 5.6.23. All actions required in ICl.2 have been completed with the
, exception of 5.6.23 (Electrical lineup) and 5.6.24 (Steam Dump alignment), which are to be performed following turnover. Power ascension will continue IAW 1C1.4.
- 4. Unit 2 is operating at 100% power.
- 5. PORV PCV-430 has been leaking-by and is isolated. !
- 6. 'llie 12 BA'IP is OOS for preventative maintenance. The pump is expected to be released to senice in tim next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 7. D1 is in the process of being restored to senice following rep .ir ofleak on the Jacket Coolant system.
Event Malf. Event Event No. No. Type
- Description Preload RP02A&B Failure of automatic reactor trip Train A & Train B RP06 Failure of MSIVs to isolate (automatic)
Preload IOS,46158 Failure of 11 SG MSIV as-is (open)
\ l l RP08A A Train Safety injection fails to actuale.
Preload S104B 12 Safety Injection pump trips when staned l
1 N BOP Transfer electrical loads to "at power" alignment {'
SRO R RO 2 N BOP Raise reactor power RO 3 N105C, O I SRO Power Range NIS channel N43 upper detector output fails to 0%
BOP 4 EG02 I SRO Generator hydrogen temperature sensor fails to ZERO RO BOP Dropped control rod J-10 results in ATWS (failure of reactor to automatically ;
5 RD07G C SRO trip)
RO BOP 6 MS07,100 M SRO Upon manual trip, (lowest setpoint) Code Safety valve on 12 SG fails open Upon SI actuation, Train A equipment fails to respond BOP 7 (preload) C SRO 12 S1 Pump trips upon start MSIV failto close automatically RO 8 (preload) C SRO 11 SG MSIV fails to close manually I
((N)ormal, (R)eactivity (1)nstrument, (C)omponent, (M)ajorTransient l
f SCENARIO l-2 SUMMAU.y The scenario will begin at 15% power. Pressurizer PORV MOV MV-321% is closed due to identified seat leakage for PCV-430, and the 12 Boric Acid Transfer pump is OOS for preventive maintenancru 'Ihe only actions remaming to be performed in IC1.2 are the electrical at-power alignment and transfer of Steam Dunip control. Following shift turnover, the crew will continue the power ascension to the next plateau. De crew will complete the remaming actions of ICl.2 and continue IAW IC1.4.
l During the power increase, Power Range channel N43 experieno:s a failure when its upper detector fails to 0%. He crew will respond to the NI failure and take the channel out of service.
Following at least a 5% power increase, the temperature senser for the Main Generator hydrogen cooling fails low causing the control valve CV-31360 to close. Hydrogen temperature will begin increase and when the crew is alerted, manual operation of the Hydrogen Temperature Controller is expected to restore hydrogen to its normal temperature range. If NO operator action is taken a generator fault trip will be initiated on high temperature.
AAer hydrogen cooling is restored, a periphery control rod (J-10), not in the same quadrant as the failed Power Range NI N43, will d op resulting in a Power Range negative rate trip on one of the operable NI channels. With N43 OOS, the coincidence cxists for a reactor trip signal on 2/4 PR negative rate trips. he reactor will fail to automatically trip. He crew is expected to manually trip the reactor. De actions of E-0 should be initiate 6.
l Upon the trip, a Code Safety Valve on 12 SG fails oren resulting in &mision of the secondary system. When SI is actuated (automatic or manual) the Train A equipment fails to respond to the "S" signal and must be manually operated. The 12 SI Pump trips on its start, so the operator is expected to ensure the 11 St Pump is manually started. Additionally when a steamhne isolation is generated, neither MSIV closes. He operator is expected to manually close each MSIV; however, the MSIV on 11 SG ,
will not close. Actions of E 0 should be continued and traasition should be made to E-2 based on SG pressure (s) decreasing in uncontrolled manner.
l Upon completion of actions E-2 for isolation of the 12 SG transition is made to E-1. Scenario ends following evaluation for termination of SI at step 12 of E-1 or using the information page (NOTE: One cycle through to step 16 back to step 2 may be allowed l if I1 SG pressure is still decressmg).
l Critical Tasks
- 1. Manually trip the reactor from the Control Room upon diagnosis of dropped rod, or on ATWS condition during E-0 immediate actions.
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- 2. Establish flow from at least one high-head ECCS pump (11 SI Pump) prior to transitioning out of E-0.
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l SimuGtion Facility Prasne Island I & 2 Scenaris No.: 2 Op Test No.: .L Examiners: Operators: SEQ EQ HQE Objectives: 1. Start a second feedwater pump per C28.2.
- 2. Perform aload increase per C1.4.
- 3. Diagnose and respond to loss of air to the runnmg charging pump per C47015.
- 4. Diagnose and respond to a Tcold instrument failure high per C51.
- 5. Diagnose and respond to trip of runmng Gland Steam Condenser Air Exhauster that results in decreasing condenservacuum per C47008.
- 6. Diagnose and itspond to sequential closure of MSR Intercept valves per C23 AOP2.
- 7. Diagnose and respond to a failure of the reactor to trip concurrent with a loss of Boric Acid Transfer Pumps per E-0 and FR-S.1 (PRA important component).
- 8. Diagnose and respond to a SG pressure mstrument failure high resulting in a SG PORV opening per FR-S.I.
Initial Conditions: 1. IC-8 (or 19),50 % power BOC (MOC).
- 2. Start second Condensate Pump and second Heater Drain Pump. Place tidrd Condensate Pump in standby (IfIC-19 used, shutdown second feedwater pump).
- 3. Take PRZR pressure channel PT- 449 OOS.
Turnover: 1. Cunent poweris 50%.
- 2. Currently at step 5.1.18.E of IC1.4.
- 3. Startup the second feedwater pump and continue load increase
- 4. Unit 2 is shutdown.
- 5. IAC is performing alibration on Pressurizer pressure channel 4 (yellow - PT-449). Expected to be completed within the next hour.
- 6. TD AFW Pump is OOS due to governor problems. The expected time OOS is at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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4 Event Malf. Event Event No. No. Typc* Description Preload RP07 Reactor trip breaker mechanical failure (fail to open)
SRO 1 ,
N BOP Place Feedwater Pumpin service SRO N BOP 3 R RO Raise reactor power RO 3 VC19A C SRO Loss of air to the running charging pump, speed reduced to minimum RO BOP 4 RX07D I SRO Yellow charmelTcold fails high 10 G-On R-Off BOP 5 On Off C SRO Gland Steam Condenser Air Exhauster trips TC07A&B RO MSR Intercept vahe fails closed, followed by a second MSR Intercept valve BOP closure resulting in a manual turbine trip-reactor trip with failure of reactor trip 6 (Preload) M SRO breakers to open 10 46161, RO l 7 FTL C SRO Running Boric Acid Transfer Pump trips when started in FAST RX216, BOP 8 1400 I SRO 12 SG PORV pressure channel FT-478 fails high RO BOP 9 SG02B,8 M SRO 12 SG tube rupture c(N)ormal, (R)cactivity (1)nstmment, (C)omponent, (M)ajorTransient
- 4 SCENARIO l-3
SUMMARY
- ihe scenario will begin at 50% power with two Condensate Pumps, two Heater Drain Pumps and one Feedwater Pump running. Field actions have been completed to support starting of the second Feedwater Pump. Following shiA turnover the crew will start the Feedwater Pump and continue the power asmnsion.
During the power ascension, mechanical blockage in air supply line results in the runnmg Charging Pump speed reducing to
' minimum. The crew will be required to stait another Charging Pump to restore normal charging and seal inyection flow and maintain Pressurizer level.
Following at least a 5% power increase, the yellow channel Tcold RTD fails high. Tave will increase and control rods will begin to insert in automatic due to Tavg > Tref. 7.wbr level will tend to rise to 33% due to the increased Pressurizer level setpoint. The crew will need to take manual control rods, stabilize plant conditions and take the effected channel out of service.
AAer actions are completed .wl effected bistables tripped, the running Gland Steam Condenser Air Exhauster trips. Due to the reduction in air removal from the gland seal system, condenser vacuum decreases. The crew will respond by directing the Turbine Cullding Operator to align and start the other Gland Steam Condenser Air Exhauster.
Following restosation of condenser vacuum, a adSR Intercept valve will close. The crew will respond to turbine drains indications and alarms and direct the Turbine Building Operator to investigate. The crew will determine a MSR Intercept valve has failed closed due to EH fluid leak at actuator and perform actions of C23 AOP 2. Upon field investigation, a second MSR Intercept valve will fait closed, requiring a reactor trip. The reactor trip breakers will fail to open and the actions of FR-S.1 should be initiated.
When the crew initiates the boration, the running Boric Acid Tnmsfer Pump will trip requiring the crew to align to the RWST as a boration source The reactor trip breakers will be opened approximately one minute aAer crew notifies operator (s) outside the Control Room (and no sooner than performance of step 4 of FR-S.1).
Following opening of the reactor trip breakers,12 SG PORV opens due to failure of the associated pressure channel input.
- !he crew will be required to take the Controller to MANUAL and shut the PORV when SG pressure is below the normal opening setpoint of 1050 psig. Upon completion of actions of FR-S.1, transition should be made to E4. SI is NOrl expected to have actuated or be required, so at step 4 of E4 transition is made to ES4.1.
_ Upon transition to ES4.1 a SGTR occurs in 12 SG (over a 4-n'inue period). The crew should transition to E 0 and perform the actions beginnmg with step 1. At step 20 of E-0, transition is rrsk to E-3. The scenario ends To!!owing 4 ization of RCS 13 minimize break flow.
Critical Tasks
- 1. Insert negative reactivity by either inserting control rods, establishing RCS boration; or directing local trip of the reactor prior to FR S.1 Step 6.
- 2. Isolate feed flow into and steam flow from ruptured SG before entry to ECA-3.1 is required.
- 3. Establish and maintain RCS temperature to establish adequate subcooling '.o preclude transition into ECA-3.1 and without causing an extreme challenge to the Suberiticality and/or Integrity CSFs.
- 4. Depressurize RCS to meet SI termination criteria prior to water release occurring from the ruptuted SG as indicated by raptured SG NR level 2100% with the SG PORV/ Safety valve (s) open.
- 5. Terminate SI prior to water release occurring from the mptured SG as indicated by ruptured SG NR level 2100% with the SG PORV/ Safety valve (s)open.
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, Simulation Facility Prairie Island I & 2 Scenario Ns.: 1 Op Test N2.: 1 Examiners: Operators: SRQ ED DDE Objectives: 1. Diagnose and respond to failure of CVCS letdown temperature controller and subsequent boration per C47015 0405.
- 2. Diagnose and respond to a safeguard pressurizer heater ground per C47012 0105.
- 3. Perform a load reduction per C1.4.
- 4. Dbgnose and respond to loss of component cooling per C47020 0101 (PRA important component).
- 5. Diagnose and respond to a RCP shaft shear and subsequent reactor trip per E-0.
- 6. Diagnose and respond to a loss of all AC power with failure of D1 output breaker to automatically close per ECA-0.0 (PRA important event and component).
- 7. Diagnose and respond to failure of AFW flow instrument per ECA-0.0 and C47.
Initial Conditions: 1. IC-17,96% power CDC.
- 2. Take PRZR pressure channel PT- 449 OOS.
- 3. Remove D2 from service (PRA important component).
Turnover: 1. Current poweris %%
- 2. Unit coastdown isin progress.
- 3. Unit 2 is operating at 100% power.
- 4. 1&C is performing calibration on Pressurirer pressure channel 4 (yellow - PT-449). Expected to be completed within the next hour.
- 5. D2 is in the process of being restored to service following repair ofleak on the Jacket Coolant system. I l
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, 1 Event Malf. Event Event No. No. Typc* Description Preload CCO2A 11 CC Pump fails to start Preload DG07A D1 fails to AUTO start 10 Preload 4122802,,,O TD AFW flow indicator to 12 SG fails low 10 4302502- RO CVCS letdown temperature controller fails to 68% (reduced CC flow to letdown 1 R1,,, 68 I SRO IIX) 10 RO 2 47012:0105 C SRO Safeguards PRZR heater ground SRO R RO 3 N BOP Reduce reactor power (due to equipment failure)
CC01B
[O 4 (preload) C DOP The running CC pump trips and the standby pump fails to start SRO RO 5 RCO3A M BOP 11 RCP shaft shear SRO RO 6 EDl4 C BOP Loss of ofTsite power SRO 7 (preload) C BOP D1 fails to AUTO sta't SRO 8 (preload) I BOP TD AFW flow indicator to 12 SG fails low VC01 SRO VCO2 RO 9 RCl4,55 M BOP 11 RCP #1 and #2 seal failures (SBLOCA via seals)
- (N)ormal, (R)cactivity (I)nstrument, (C)omponent, (M)ajor Transient
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SCENARIO 1-4
SUMMARY
1he emnario will begin at %% power with the D2 out of service and the Yellow channel (4, PT-449) being calibrated. The Unit is in coastdown to the scheduled refueling outage. Following shiA turnover the crew will continue coastdown operations.
- !he CVCS letdown temperature controller for TCV 130 fails to 68% in AUTO, resulting in hotter than normal letdown flow cream (135'F+). This should result in boration of the RCS as the hotter water picks up boron from the demmeralimrs. The crew is expected to diagnose as RCS temperstwe begins to drop faster than expected. The crew can take manual control and adjust to restore normalletdown temperature ofIl0*F AAer actions have been addressed to the CVCS letdown temperature controller failure, a ground develops on Train 'A' Pressurimr Heaters. Investigation reveals that two groups of heaters are isolated. The crew should recognim a jamiwr Tech Spec action of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Following notification, Operations Management will direct commanda- a normal Unit shutdown to begin the outage early..
The crew will initiate a shutdown to HOT SHUTDOWN conditions.
Following at least a 5% power reduction, the running (12) CC Pump trips and the 11 CC Pump fails to start. The crew will start the standby CC pump and monitor RCP bearing temperatures. If any of these reaches 200*F, the crew should trip the reactor and then stop the affected RCP(s). Upon the trip of tha reactor (and prior to stopping RCP),11 RCP shaA shears due to failure in the lower bearing.1 he crew will per ormr the actions of E-0 and transition to ES-0.1 based on S1 NOT actuated nor required.
Following transition to ES-0.1, a loss of offsite power occurs Unit 1 experiences a loss of all AC power due to the unavailability of D2 and failure of D1 automatically stant, and unavailability of unit cross-ties (Unit 2 fai:ures). ECA 0.0 is entered.
- Ihe crew is expected to mamtain at least 200 gpm flow to the 11 SG since the flow indicator from the TD AFW to 12 SG has failed low (Unit 2 MD AFW not available for cross-tie). The flow to 12 SG may be throttled and adjusted based on SG level trend. The 200 gpm flow is required until at least 10% level is reached in either SG. Bus 15 can be energized by manually starting D1. Once bus 15 is verified energized, the crew will transition back to ES-0.1.
Due to the shan shear and loss of cooling during the loss of all AC,11 RCP has a SBLOCA via the pump seals. The crew should recognia the A4g RCS pressure and PRZR level, nd manually initiate St. The crew will transition to E-1 at step 21 of E 0. The scenario ends at step 24 of E-1 when it is deternuned that transition should be made to ES-1.1. j l
Critical Tasks
- 1. Establish the minimum required AFW flow rate to the SGs on a loss of all AC before SG dryout occurs.
- 2. Energia at least one AC Emergency Bus so that transition to ECA-0.2 is not required upon completion of ECA-0.0.
INITIAL SUBMITTAL OF THE PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 t
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's Northem States Power Company Prairie island Training Center 1660 Wakonade Drive West Welch. MN 55089-9638 March 31,1999 Mr. Dell McNeil NRC Region lll Division of Rx Safety - OLB 801 Warrenville Rd.
Lisle, IL 60532-4351
Dear Dell,
As agreed in a letter from Melvyn Leach dated January 25,1999, enclosed are the exam materials for the RO exam to be administered the week of May 16,1999. Also {
attached are the Quality Assurance Checklists; ES-301-3, ES-301-4, ES-301-5, j ES-301-6 and ES-401-6. Note that the ES-301-5 and ES-301-6, attached as required 1 by ES-301-4, are revised from those sent with the exam outlines to reflect the actual scenarios developed for this submittal. Reference materials associated with each section of the exam are also included.
Please withhold these materials from public disclosure until after the examinations are complete.
We are prepared for an exam preparation week beginning May 3,1999. The simulator j is available for our use on Tuesday and Wednesday of that week. j l
if you have any questions regarding the exam materials, please call me at (651) 388- l 1165 x4053. !
I Sincerely, !
<-n Jim Lash Senior TechnicalInstructor enclosure: 1 gg0 1N j
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'D ES-301 Operatina Test Quality Assurance Checklist Form ES-301-3 i
)
Facility: PIN G P Date of Examination: I"? Pbv 199 9 Operating Test Number: l Initials
- 1. GENERAL CRITEH1A J i
a b c
- a. The operating test conforms with the previously approved outline changes are consistent with sampling requirements (e.g.,10 CFR 55.45, operationalimportance, safety function distribution). $/// 'b
- b. Repetition from operating tests used during previous licensing examinations is within acceptable limits (30% for the walk-through) and should not compromise test integrity. g#1fj (*
- c. Day-to-day repetition between this and other operating tests to be administered is within g acceptable lirnits (30% of bank JPMs for the walk through: none for the simulator). gnjf ,
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- d. Ovsrlap with the written examination and between operating test categories is within l acceptable limits. p
- s. It appears that the operating test will differentiate between competent and less than-competent applicants at the designated license level.
n g 17 I I
- 2. WALK-THROUGH (CATEGORY A & B) CRITERIA - - -
)
- a. Each JPM includes the following, as applicable:
- Initial conditions e initiating cues a references and tools, including associated procedures
- validated time limits (average time allowed for completion) and specific i designation if deemed to be time critical by the f acility licensee specific performance criteria that include:
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- detailed expected octions with exact criteria and nomenclature
- system response and other examiner cues statements describing important observations to be made by the applicant
- critoria for successful completion of the task
- Identification of critical steps and their associated performance standards restrictions on the sequence of steps,if applicable
- b. Prescripted (Administrative and JPM follow-up) questions are predominantly open referer.ce A and meet the criteria in Appendix C. g#/f
- c. There are no direct look-up questions; memory level questions do not permit the use of references. yffg .
- d. At least 20 percent of the JPMs and questions on each test are new or significantly modified.
h
- 3. SIMULATOR (CATEGORY C1 CRITERIA - , -
- a. The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-3014 and a copyis attached.
g/f4 g l Printed N / Signature Date
- a. Author DLL I 1m,i . Ml . *19
- b. Facility Reviewer (*) dmas\ Mk 7 b .3-J/- #
- c. NRC Chief Examiner (*) )f Li h, bNtt l / /d/89 l
- d. NRC Supervisor (*) Dew .' A 8. k' Y/Z.9/#/9
(*) The facility signature is not applicable for NRC-developed tests: two independent NRC reviews are required.
NUREG-1021 24 of 26 Interim Rev. 8. January 1997
i-O ES-301 Simulator Scenario Quality Assurance Checklist Form ES-301-4 Facility: PIN (;P Date of Exam:5 lWIScenario Numbers: ) / .2. / 3 c 4 Operating Tesi No.: 1 QUALITATIVE ATTRl8UTES ! Initials a b, c
- 1. 'fhe scenarios have clearly stated objectives in the scenario summaries. k M
- 2. The initial conditions are realistic,in that some equipment and/or instrumentation may be ,
out of service, but it does not cue the operators into expected events. #
- 3. The scenarios consist mostly of related events. /lf[ _
b 4 Each event description consists of
- the point in the scenario when it is to be initiated
- the malfunction (s) that are entered to initiate the event - g' b a the symptoms / cues that will be visible to the crew
- the espected operator actions (by shift position) *
- the event termination point (if applicable)
- 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. g/r . _
- 6. The events are valid with regard to physics and thermodynamics. $[ '
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- 7. Sequencing and timing of events is reasonable, and allows the examination team to obtain p complete evaluation results commensurate with the scenario objectives. gIl B. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time g' & .
constraints. Cuos are given. ,
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- 9. The simulator modelirr is not altered. Ng h
- 10. The scenarios have byn ; validated. Wg h
- 11. Every operator will be evaluated using at least one new scenario. All other scenarios have U
a .p j been modified in accordance with Section D.4 of ES-301.
- 12. All individual operator competencies can be evaluated, as verified using Form ES 3016 - g (submit the form along with the simulator scenarios). 4
- 13. Each applicant will be significantly involved in the minimum number of translents and p events specified on Form ES 3015 (submit the form along with the simulator scenarios). ,
- 14. The level of difficulty is appropriate to support licensing decisions for each crew position. A[ b TARGET QUANTITATNE ATTRIBUTES (PER SCENARIO) Actual Attributes f
- 1. Total malfunctions (5 8) 7 /b /7/ 7 38fk kS~
- 2. Malfunctions after EOP entry (12) 3 / 2 /1./ 4 /M M b- -
- 3. Abnormal events (2-4) 3 / 3 /t// 3 fff/ b
- 4. Major transients (1-2) l / l /2/ 2 lIf g &
- 5. EOPs entered / requiring substantive actions (1-2) I / 3 /l /1 8[ W
- 6. EOP contingencies requiring substantive actions (0-2) l / O/0/\ )ff M 1 To W u A A ntc q g op d g ,,c,n g NUREG-1021 26 of 26 Interim Rev. 8. January 1997
n ES-301 Transient and EventChecklist Form ES-3015 OPERATING TEST NO.:1 i
Applicant Evolution Minimum Scenario Number Type Type Number 1 2 3 4 Reactivity 1 21 2/ 21 31 ,
Normal 1 12 /t2 / t2 la RO instrument 2 3.si e 3/4 4 i4.8 ti7 Component 2 4 r s.7 5.si7 3i58 2.4 s i2 s.7 Major 1 515 818 1 7.917.9 5.B i5.8 Reactivity 1 MA ,
WA MA MA Normal 0 MA MA MA MA As RO Instrument 1 MA MA MA MA Component 1 MA MA MA MA Major 1 MA MA MA MA SRO-l Reactivity 0 MA MA MA MA Normal 1 MA MA MA MA As SRO Instrument 1 MA MA MA MA l Component 1 MA MA MA MA !
Maior 1 MA MA MA MA Reactivity 0 MA MA MA MA Normal 1 MA MA MA MA SRO-U instrument 1 MA MA MA MA Component 1 MA MA N/A MA Major 1 MA MA MA MA instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.
(2) Reactivity manipulations must be significant as defined in Appendix D.
NOTE: The */* in the cells for the 'R0"' applicant type represents the position the applicant is expected fillduring the scenario.
The events are listed for the identified position: RO I BOP.
Author: NI M. . I . J I ., , .
Chief Examiner hitN Ait A't,/ AWE Alt /4 D' 4//i/93
_ s .u *r9 NUREG-1021 1 of 26 Interim Rev. 8, January 1997
T ES-301 Competencies Checklist Form ES-301-6 Operating Test: 1 Applicant #1 Applicant #2 Applicant #3 RO/SRO4/SRO41 R0(BOP)/SRO4/SROU RO/SRO-l/SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 is.s as a4 1,57 4.7.8 44 2.5a gg gg g3 g3 Understand and Interpret ,
j, 12; 4
Annunciators and Alarms a 15.8 35 a4 1,57 4.7.8 44 2.58 g3 gg g3 gg Diagnose Events ,
j, 12; and Conditions a u.s 12 12 23 gg Understand Plant 2-5.s 2 2j.
, j ;, gg gg gg and System Response u.s 12 12 23 Comply With and 2-5.8 2 2j.
, j ;, gg gg gg gg Use Procedures (1) u.s 12 12 23 Operate Control 2.s.8 5
2 2j.
, j ;, gg g3 gg g3 l
Boards (2)
Communicate and 14 M 14 M M M 14 14 MA MA MA MA Interact With the Crew -
Demonstrate Supervisory MA MA MA MA MA MA MA MA MA MA MA MA Ability (3)
Comply With and MA MA MA WA MA MA MA MA MA MA MA MA Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optionalfor an SRO-U.
(3) Only applicable to SR0s.
Instructions:
Circle the applicant's license type and enter the event numbers that test the competency for each scenario in the set.
NOTE:
Author: N (( M,a .r r m Chief ExaminerTXoIN Mea.1 / diu13 /Mc IlD alefgc3 s.u.99 m
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SCENARIO USAGE MATRIX (Indicates, by Scenario Number, Number of Evolution Types per Candidate)
$N$$$i[Ci?2&53% RO1 RO 2 RO 3 REACTIVITY 1 2 3 NORMAL 2,2 3,3 1 INSTRUMENT 1,1,2 2,3,3 3,1 COMPONENT 1,2 2,2,3,3 3,1,1 MAJOR 1,2 2,3,3 3,3,1 l
l N.dsfRl6df22&IsfF RO1 RO 2 RO3 REACTIVITY 1 2 4 NORMAL 2,2 4 1 INSTRUMENT 1,1,2 2,4 1,4 COMPONENT 1,2 2,2,4,4,4 1,1,4,4,4 MAJOR 1,2 2,4,4 1,4,4 lShejisri6si.223[&% g RO1 RO2 RO3 REACTIVITY 2 3 4 NORMAL 4 2,2 3,3 INSTRUMENT 2,4 2,3 3,3,4 COMPONENT 2,2,4,4,4 2,2,3 3,3,4,4,4 MAJOR 2,4,4 2,3,3 3,3,4,4
)
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ES-401 ' Written Examination Form ES-401-6 Quality Assurance Checklist Facility: PIAlGF Date of Exam: 17 M.9 19?? Examlevel@SRO Initial item Description .
a b c
- 1. Questions and answers technically accurate and applicable to facility / pI// w
- 2. NRC KIAs and learning objectives referenced for all questions j gf/ w.
- 3. . RO/SRO overlap is no more than 75 percent, and SRO questions are Al/ F appropriate per 10 CFR 55.43 p #A N/4
- 4. Question duplication from [ practice exams, quizzes, and] the last two j licensing exams is no more than 25 percent [N/A for NRC-developed exams) g #/[ g
- 5. No question duplication from the license screening / audit exam j fit {/ h
- 6. Bank use meets limits (no more than 50 percent from the bank / at least 10 )
percent new) #[ M
- 7. At least 50 percent of the questions on the exam (including all new %, l questions) are written at the comprehension / analysis level ,
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- 8. References / handouts provided do not give away answers j W[/ p
- 9. Question distribution meets previously approved examination outline; deviations areJustified ,
NM k
- 10. Question psychometric quality and format meet ES, Appendix B, guidelines [ y#f/ v~
- 11. The exam contains 100, one-point, multiple choice items; the total is correct and corresponds to value on cover sheet k h
- Printed Name/ Signature Date
- a. Author- dtM .Le - d .J///If
- b. Facility Reviewer (*) trL,1 J I.,, b [ [ .99
- c. NRC Chief Examiner (*) llib /ddd//NM //d# V/ta/p>
- d. NRC Regional Supervisor (*) I b AE4.\%/ b d89/.//I Wzqht Note: (*) The facility reviewer's signature is not applicable for NRC-developed examinations; two independent NRC reviews are required.
() See specialinstructions (Section E.2.c) for shaded boxes.
e To 66 RfvaeWGo%M4 P(AP W(.E NUREG-1021 43of 39 Interim Rev. 8, January 1997
r; 1 INITIAL SUBMITTAL OF THE OPERATING TEST FOR THE PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 l
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INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE
- PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 t
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Sind2}RJf JOB PERFORMANCE MEASURE R@3!ggj10/98..
,_gM6:n5$A WORKSHEET !$ND?@sN$N TASK TITLE: Determine Dilution For An Estimated Critical Condition JPM NUMBER: ADMIN-1.1 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 0040060101 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING:
Simulate Performance: Actual Performance:
Evaluation Location: Turbine Building: Auxiliary Building:
Simulator: Control Room:
Other: Anywhere Time for Completion: 10 Minutes TASK APPLICABILITY: SRO: RO: NLO:
(Check all that apply)
PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE:
APPROVED BY: DATE:
Resp Grp: O Page 1 of 5 Assoc Ref: PITC TP 3.7
I l Determine Dilution For An Estimated Critical Condition l ADMIN-1.1 R:v.0 l
\
Evaluator: i Date: j READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be !
satisfied.'
INITIAL CONDITIONS:
. The shutdown banks have been withdrawn to 228 steps in preparation for a Reactor startup.
. - Current RCS boron concentration is 1300 ppm.
. An ECC has been completed and ventied.
INITIATING CUES:
o ' The SS directs you to calculate the number of gallons of water needed to reduce the RCS boron concentration to the given ECC boron concentration and the dilution water flow rate necessary to
. perform the dilution in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per 101.2, step 5.5.5.-
o Report the results to the SS.
4 i
. PITCQ-089 Page 2 of 5 Rev 5 10/98
1 l Determine Dilution For An Estimated Critical Condition l ADMIN-1.1 R3v. 0 l JPM PERFORMANCE INFORMATION Required Materials: Completed ECC with critical boron concentration at 1000 ppm.
General
References:
1C1.2, C1 A, C12.5 Task Standards: 8,000 (i 1,000) gallons of water at 85 (i 10) gpm determined to be necessary to dilute to ECC boron concentration in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Start Time:
IHOTEUstisiijiif691dly@hsiiUif6 EsiWhidillisis&6(sidihW6 pW!5fombti$ihWurWins?pr(DusiTf6%iiiiihif%[pi6 yisinh Bii G %Ei vim EFWhiW6H @ -
$22vMyathMNr$6MIM8Mihil6k(f(bMEN$$$Irge6]$$M$Isk(N6iijsdisf NOTE (CHti6silstepsjadtharsed MMsdrnfsiOthridaid}Minn$1'thlshtXiti416Misihiif6nisiridi5isp@hunitssM NiilestsisisisiGinknisiWMyii psisMlLdfis l
Performance Step: Determine boron concentration change to be made.
Critical X (S-1)
Standard: 300 ppm dilution determined necessary to change RCS boron concentration ,
(1300 ppm) to ECC boron concentration (1000 ppm). )
1 Performance: SATISFACTORY UNSATISFACTORY I Comments: 1 Performance Step: Estimate the quantity of reactor makeup required to accomplish the desired Critical X (S-2) concentration change.
Standard: 8,000 (i 1,000) gallons determined to be the quantity required to dilute 300 ppm using the Figure 6 (hot) nomograph.
Performance: SATISFACTORY UNSATISFACTORY Comments:
a PITCO-089 Page 3 of 5 Rev 5 10/98
l l Determine Dilution For An Estimated Critical Condition l ADMIN-1.1 Rsv. 0 l l Performance Step: Estimate the reactor makeup flow rate required for the desired rate of Critical X (S-3) change of boron concentration.
Standard: 85 (i 10) gpm determined to be the flow rate required to dilute 300 ppm in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (200 ppm /hr) using the Figure 8 (hot) nomograph.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The candidate should report to the SS that, "8,000 (f 1,000) gallons at 85 (i
- 10) gpm is necessary to dilute to the ECC boron concentration in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />." At this point, inform the candidate that, "this JPM is complete."
Stop Time:
l l
l PITCO-089 Page 4 of 5 Rev 5 10/98
TURNOVER SHEET INITIAL CONDITIONS:
o The shutdown banks have been withdrawn to 228 steps in preparation for a Reactor startup.
o Current RCS boron concentration is 1300 ppm.
.o An ECC has been completed and verified. ,
INITIATING CUES:
o The SS directs you to calculate the number of gallons of water needed to reduce the RCS boron concentration to the given ECC boron concentration and the dilution water flow rate necessary to perform the dilution in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per 1C1.2, step 5.5.5.
o ' Report the results to the SS.
PITCO-089 - Page 5 of 5 Rev 5 10/98
l l
{
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES
~
l ;>g %' .
TITLE NUMBER:
W , V:tv?:1/k , j- w.7 ESTIMATED CRITICAL FIG C1 A-1 qw, BORON CONCENTRATION REV: jg
,/ .
r " 7Sktiori /
a '
< 1 Page 1 of 7 l
Unit i Cycle icv Startup # 5 Expected Critical Data:
Date: Time: ( 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) I Critical Boron Concentration: 1000 ( 15 ppm)
Control Rod Position:
Maximum = Bank n @ i c4 s steps Estimated = Bank n @ so steps Minimum = Bank e @ ls steps Based on a computer code Prediction? YES/NO List of Actual Critical Conditions @ 104 Amos:
Date: Time:
Boron Concentration: ._ opm Rod Position: steps Tavg: 'F Prepared By: Date:
Reviewed By: Date:
Post Startup Review By Nuclear Eng: Date:
l O.C. REVIEW DATE:
REVIEWED BY: DATE: ((///kf
[ APPROVED BY: DATE: f[~//((/
/
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT f
l NORTHERN STATES POWER COMPANY OPERATING PROCEDURES Fy ;' TITLE NUMBER:
i ep;u % ESTIMATED CRITICAL FIG C1 A-1 l .. .. .,, J ? BORON CONCENTRATION REV:
10
%I **5SectlNJ s 1:. 3 s , ,-
U S ,
Page 2 of 7 1 UNIT i i
PRE-SHUTDOWN DATA 1.0 CONDITIONS PRIOR TO SHUTDOWN 1.1 DATE: / / TIME: -
1.2 Boron Concentration: Ais opm (1) l 1.3 Power Level: I60 % 1 1
1.4 Control Rod Position: Bank 0 @ 2is _ steps 1.5 Tave: Mo *F 1.6 Xenon Concentration -2Ano ocm 1.7 ITC - N. 7 p'.TF
1.8 Exposure
losoo MWO/nTu 2.0 BEACTIVITY DEFECTS PRIOR TO SHUTDOWN 2.1 Power Defect (-) Ref: -ms (2) 2.2 Control Rods (-) Ref: -24 (3) l 2.3 Xenon (-) Ref: -1400 (4) i
- 2.4 Tave Deviation (+) Ref: o (5)
- 2.5 Total (-) (2) + (3) + (4) + (5) -4 yon (6)
- (Tave - Tref) x ITC (for EOL Coastdown operation)
r- ,
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NERTHERN STATES POWER CCMPANY OPERATING PROCEDURES
' '> I l' TITLE NUMBER:
li ce at ESTIMATED CRITICAL FIG C1 A-1 U &, i j' BORON CONCENTRATION REV: jg
', 2 , . Section'.' E '
Page 3 of 7 STARTUP DATA 3.0 DESIRED CONDITIONS FOR CRITICALITY 3.1 DATE: / / TIME: -
3.2 Rod Position: Bank n @ 5a steps 3.3 Xenon Concentration: o ocm 3.4 Boron Worth (-) - 9.1 pcm/ ppm (7) 3.5 Exposure ios00 MWD /MTU 4.0 REACTIVITY DEFECTS AT STARTUP (Pcm) !
l 4.1 Power Defect (-) 0 (8) 4.2 Cmtrol Rods (-) Ref: - 900 (9) 4.3 Xenon (-) Ref: o (10) 4.4 Total (-) (8) + (9) + (10) = - 900 (11)
NOTES:
l
I l i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES p -E'W
~
NUMBER:
- TITLE e'T ESTIMATED CRITICAL FIG C1 A-1
'd ,S f'[~ BORON CONCENTRATION REV: gg
$15 ' '~
. Section j
. M. e .
Page 4 of 7 5.0 ESTIMATED CRITICAL BORON CONCENTRATION I 5.1 Reactivity Change = (6) - (11) = -44no -
-9on l
= -3500 pcm (12) l 5.2 Boron Change = Reactivity Chance Boron Worth
= (12) = (-3500 ) ocm (7) ( - 9.i ) pcm/ ppm
= 3gS ppm (13) l 5.3 ECC = Boron Concentration + Boron Change Prior to Shutdown
=
(1) + (13) = 615 + ARR
= foco opm 6.0 ACCEPTANCE CRITERIA FOR CRITICALITY 6.1 Hot Zero Power Rod insertion Limit = Bank C @ 47 Steps 6.2 Rod insertion Reactivity Defect -900 pcm (-) (9)
+750 pcm 1
Minimum Rod Insertion Defect -iso pcm (-) Max Rod Height for Criticality = Bank D @ 195 Steps i Ref: ci-u A (moc) l l l l l l 1
PRAIRIE I! LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES [ '
, TITLE NUMBER:
0'N?g , ESTIMATED CRITICAL FIG C1 A-1 4 . f* a BORON CONCENTRATION REV: jg Sectioni -
.D Page5of7 ,
I
- 6.3 Rod insertion Reactivity Defect -son pcm (-) (9) {
-750 pcm l
Minimum Rod Insertion Defect - i t,s o pcm (-) Min Rod Height for Criticality = Bank c @ 15 Steps Ref: ci-4 A (moc)
, , , n.
. "Ag
- If the minimum rod height for criticality is below the Rod Insertion Limit, then increase desired critical rod position by an amount sufficient to raise the expected
-gg?b ;. , ,f 4 ,
[erJfp] critical rod height a minimum of 750 pcm above the 4 L y J"h de Rod insertion Limit. This procedure must then be
'[ , ;
y :a g t*Peated. 7.0 1/M PLOT CRITICALITY PREDICATOR Complete 1/M plot as a predictive aid during approach to criticality. Attach both the 1/M plot I and ICRR data collection sheet to ECC form as part of the startup package. l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES l- 4,y[ , < TITLE NUMBER: M.jWk 4? AhL:64 3 ESTIMATED CRITICAL FIG C1 A-1 REV: gg BORON CONCENTRATION P'i Sectioii; '
- s % C '
Page 6 of 7 UNIT CYCLE DATE TIME APPROACH TO CRITICALITY Rod Pull Method 1
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- 3. , ki.;fdi
. WORKSHEET 2i___ . .
l TASK TITLE: Initiate A Temporary Cnange To A Procedure JPM NUMBER: ADMIN-1.2 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 1190130301 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Sirnulate Performance: Actual Performance: Evaluation Location: Turbine Building: Auxiliary Building: Simulator: Control Room: Other Anywhere Time for Completion: 20 Minutes l TASK APPLICABILITY: SRO: RO: NLO: (Check all that apply) I l PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: 1 APPROVED BY: DATE: Resp Grp: O Page 1 of 7 Assoc Ref: PITC TP 3.7
r- 1 l
- l Initiata A Temporary Change To A Procedure l ADMIN-1.2 Rev. 0 l Operator: (SRO / RO / NLO) l l l l Evaluator:
l l Date: ! READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS:
. Unit 1 is at 100%.
. The letdown heat exchanger needs to be isolated for maintenance.
e in order to ensure full isolation from all potential sources of water, it is requested that when normal letdown is removed from service, Letdown Outside Containment isolation CV-31339, be closed. i l lNITIATING CUES: j e _ The SS directs you to initiate a temporary procedure change per SAWI 1.5.10, to add the following step to the end of C12.1, sechon 5.3, Removing Normal Letdown From Service: Isolate the Letdown Heat Exchanger inlet by CLOSING CV-31339, LETDOWN OUTSIDE CONTAINMENT ISOLATION, using CS-46166. o Deliver the ternpciery procedure change to the SS for review and approval. i l l 9 l l l 1 PITCQ-089 Page 2 of 7 Rev 5 10/98
F' 1 1 l initiate A Temporary Change To A Procedura l ADMIN-1.2 R:v. 0 l 1 JPM PERFORMANCE INFORMATION Required Materials: Form PINGP 1300 and a copy of C12.1. General
References:
5AWI 1.5.10 l Task Standards: Temporary procedure change initiated for C12.1, section 5.3. ~ Start Time: 1 n or m
~
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. step shall resu.lt in f._ailu.r.e o.~f.th..is uPM
-- - xnawa.vem u_; u_.mL,#s 1
l Performance Step: Complete the following on the PINGP 1300: 1 Critical X (S-1) Procedure number, title, and revision number. Standard: Procedure number, title, and revision number recorded on the PINGP 1300. ] Work order number should also be recorded. ; i dido M a m us UadN we_ N N aJ$1".53_0 mwayma.m eava 6 Em h M I M. Mkw Hja"" $NNd*,u5g@ }{i W MMN a m4egh M %* M M 4 * @adu m -uAidi$j5r m,muumyme C 1
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( Performance: SATISFACTORY UNSATISFACTORY Comments: I PITCQ-089 Page 3 of 7 Rev 5 10/98 L
T ' l Initiats A Temporary Change To A Procedura l ADMIN-1.2 Rav. 0 l l Performance Step: Complete the following on the PINGP 1300: Critical X (S-1) Summarize the change (r.) in adequate detail: include page number ; and/or procedure step (s) affected and the reason for the change. Standard: Procedure change summary, including page and/or step number, recorded on the PINGP 1300. Performance: SATISFACTORY UNSATISFACTORY Comments: i Performance Step: Complete the following on the PINGP 1300: l Critical X (S-1) Documentation of the change: Standard: Copy of the procedure markb up with temporary change (addition of step I to section 5.3 to close CV-31339) and attached to the PINGP 1300.
$ aluanAEIEFi@Jd,l.ftOs/M~UIfd.~isiIdiIside(dide side %BiEMLsbnnu
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step),1this;
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~n n Performance: SATISFACTORY UNSATISFACTORY Comments:
i Performance Step: Complete the following on the PINGP 1300. ; Critical X (S-1) identify if this is an OC (Operations Committee) reviewed procedure. OC reviewed procedure have requirements on reviewer qualifications and must be reviewed within 30 days by the OC. Standard: Procedure identified as an OC reviewed procedure. Performance: SATISFACTORY UNSATISFACTORY Comments: l l l l PITCQ-089 Page 4 of 7 Rev 5 10/98
l Initiata A Tempor:ry Change To A Procedura l ADMIN-1.2 Rev. 0 l Performance Step: Complete the following on the PINGP 1300: Critical Determine if a permanent procedure change is needed. If so, submit PINGP 436, Procedure Submittal Form, per SAWI 1.5.2. Standard: Permanent procedure change determined not to be needed and indicated i on the PINGP 1300 (no PINGP 436 necessary).
- m.. m .
,m mm + ~~ >- v
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.rettame::een Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Complete the following on the PINGP 1300: Critical X (S-1) Assign an Effective Date. Standard: Today's date recorded on the PINGP 1300. n. LEvaluatorCuePgWamif.'a, n!re,wport,.that,J'the: Is . tio sked . ---,dla,. hMlliits, ,d6,,i,e, r 'tod_a " n ,.WW 79is but i / kii F ,c cum 2cih0H2Gade!Osunsi,;Id&&LkdO!his1DE&y.1 ;,0& *dh.wm d$ Performance: SATISFACTORY UNSATISFACTORY Comments: l l 1 l l 1 l l PITCQ-089 Page 5 of 7 Rev 5 10/98
1 l Initi"t3 A Temporary Change To A Procedura l ADMIN-1.2 Rsv. 0 l Performance Step: Cornplete the following on the PINGP 1300: ; Critical Assign an Expiration Date, if required. Otherwise, mark the ) expiration date as "NR". { l Standard: Expiration date determined not to be required and "NR" recorded on the PINGP 1300.
, _ , , ,, y M_ _th,yyy , ne ration ,m,_y,
.m.,
....d,a,t,e is,,n,o.m,,_m,l,u reg,=b dy thi th_m.m.,s.
im h us a gic,. oM M Mi;m t porary_,cha. legA i j hg ; suinmscemMmeihenM):licemessusase; g @e ,g X m set snew%$ 39,. l nem ,, n , s,-n -m , m _,, ,. m ,-m,o,, uator :m:ew p p g yi % , wy ,,.,,,,,,_,,,y as repo tFno,,,e,,-m o ati ,'r,e_qu re ,, .d."N #w,WW+1,,,, WEMEsissy E!UWAT$$NFGU!EnsL@sid@GsZnsMronisirsagi1GMuGeg;Wus GE!k 'Jssn;Qg;Q;;.3 l Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Complete the following on the PINGP 1300: Critical X (S-2) The Originator SHALL sign and date the PINGP 1300. Standard: PINGP 1300 signed and dated by candidate. l 1 Performance: SATISFACTORY UNSATISFACTORY i Comments: 1 Terminating Cues: The candidate should report to the SS that, "the temporary change (PINGP 1300) is ready for review and approval." At this point, inform the candidate i that, "this JPM is complete." l Stop Time: l l l l l l PITCO-089 Page 6 of 7 Rev 5 10/98
h l I TURNOVER SHEET l l lNITIAL CONDITIONS:
. Unit 1 is at 49%. 1 . The letdown heat exchanger needs to be isolated for maintenance. . In order to ens Jre full isolation from all potential sources of water, it is requested that when normal letdown is rennved from service, Letdown Outside Containment isolation CV-31339, be closed.
i INITIATING CUES': l l . The SS directs you to initiate a temporary procedure change per 5AWI 1.5.10, to add the following step to the end of C12.1, section 5.3, Removing Norrnal Letdown From Service: , Isolate the Letdown Heat Exchanger inlet by CLOSING CV-31339, LETDOWN OUTSIDE l l CONTAINMENT ISOLATION, using CS-46166.
. Deliver the temporary procedure change to the SS for review and approval.
I l l
}
I 1 PITCQ-089 Page 7 of 7 Rev5 10/98 l L
I PINGP 1300, Rev.1 TCN # Rekntu 6 years EffIctiva Dity' l Document Type: 1.190 Expiration Date: TEMPORARY CHANGE NOTICE Page 1 of (SAW11.5.10)
- 1. CHANGE REQUEST Procedure #: Rev: Project ID #:
Title:
Description of Change: is this an OC reviewed procedure? Yes No is a permanent procedure change needed? Yes NoO (if Yes. submit PINGP 436) Originator Employee P. Date: ll. REVIEW AND APPROVAL A. Is this temporary change a change in scope or intent? Yes No (if No, go to ll.B)
. Does this temporary change:
- 1. Include specific steps discussed in the SAR? Yes No
- 2. Affect component operation specifically described in the SAR? Yes No
- 3. Affect plant configuration described in text or drawings in the SAR7 Yes No if 1,2 or 3 is Yes, perform a Safety Evaluation Screening (PINGP 1229) SES #
is a Safety Evaluation Required? Yes No SE#
- Does this change affect Special Reviews (e.g. EQ, App.R)? YesC No (if Yes document Special Review (s) in CHAMPS)
- OC review date (if procedure is OC Approval by procedure reviewed, otherwise 'fM): approver:
B. Does this change affect plant operation or Tech Specs? Yes No O (if Yes and work is in pro 9re... Shift Supervisor notified by (initial)) C. Do controlled copies need to be updated? Yes NoO (if Yes. Attach marked-up procedure pages to white copy) D. All master / working copies updated? Yes NA E. Is training on temporary change needed? Yes No (If Yes, PINGP 1268 or PINGP 1224 (Ops Only) issued) F. Reviewer: Date: (Unit Management Staff) G Approver: Date: (Unit Management Staff; SRO for DC reviewed procedures) Forward white copy to Procedure Control 111. POST REVIEWS (required for OC leviewed procedures only;'NR' if reviewed / approved in ll.A) OC Review Date: Procedure Approver Date: IV. TEMPORARY CHANGE DELETION ('NR'If controlled copies not updated, refer to ll.C) A. Is this temporary change deletion a change in scope or intent? Yes C No (If No, go to IV.B)
- Does this temporary change deletion:
- 1. Include specific steps discussed in the SAR? Yes NoC
- 2. Affect component operation specifically described in the SAR? Yes No
- 3. Affect plant configuration described in text or drawings in the SAR? Yes No if 1,2 or 3 is Yes, perform a Safety Evaluation Screening (PINGP 1229) ECS #
is a Safety Evaluation Required? Yes nod SE #
= OC review date (if procedure is OC Approval by procedure reviewed, otherwise 'NR'): approver:
B. Reviewer. Date: l (Unit Management Staff) i C. Approver: Date: (Unrt Management Staff, SRO for OG reviewed procedures) Fonn 174645 (o.se) Whne Copy - Procedure Control Yellow Copy - Attach to procedure I
ATCN is NOT required for the following (PINGP 436, Procedura Submittal Form, should be submitted):
- 1. Obvious typographical errort..
NOTE: 2. Incorrect personnel titles.
- 3. Minor discrepencies between equipment identh'icahon in the procedure and on the component tag, provided sufficient information is available to ensure the proper component is being operated.
1 l CECTION I- CHANGE REQUEST l
- Originator completes Sechon 1.
- For work orders attached to standing procedures for tracking only, record the standing procedure number. For work orders or portions of standing procedures included with work orders, record the work order number.
- Summarize the change in adequate detail; include page number and/or procedure steps affected.
- Attach mark-up of change if necessary.
- Assign effective date.
- Assign expiration date if desired, otherwise mark as 'NR':
- Required for changes that 1) need to be incorporated in a revision by a specified date, or 2) need to be cancelled by a specified date.
SECTION ll- REVIEW AND APPROVAL
- Determine if proposed change is a change in procedure scope or intent. The following examples may be changes in scope or intent:
- 1. A change in the purpose of the procedure
- 2. Changes to the initial conditions that must be satisfied before performing the procedure
- 3. Changes to acceptance criteria
- 4. Modification or deletion of setpoints
- 5. Deletion or relocation of a " Hold Point'
- 6. Modification or deletior: of the method for meeting a commitment
- 7. Changes to numerical values such as torquing values !
- 8. Changes to a calculational formula
- g. Changes that would alter design values
- 10. Modificaten or deletion of independent verification requirements
- 11. Changes to equipment configuration
- 12. A change in the method of performing a task
- 13. A change based on an ECR
- WRAC serves as OC subcommittee for OC reviews of scopeAntent changes to cribcal work orders.
- For work orders, the Work Supervisor is the Procedure Approver
- if the change affects plant operation or Tech Specs and work is in progress (e.g. at status 80), then the Shift Supervisor SHALL L notified of the change. The individual notifying the SS initials in the blank.
- Reviewer responsibilities (Reviewer shall not be the Originator):
- 1. Verify the change is feasible and technically accurate:
- Change is appropriate for the current plant conditions
-Isolation is adequate for the work
- Equipment / circuit responses will not adversely affect other equipment
- Procedure steps are adequate to achieve the desired results
- Sequencing of steps is correct
- 2. Verify the change can be dearly and completely performed (workable):
- Content is understandable
- Expected equipment response is clear
- Contains no typographical errors
- 3. Determine need for cross <lisciplinary review of the change
- Approver responsibilities (may be either the Originator or Reviewer):
- 1. Compies with Tech Specs, OQAP, and corporate directives and will not cause a violabon of Tech Specs or other operability requirements
- 2. The change is safe.
- 3. Consistent with the scopefintent of the original procedure unless identified as a scoperantent change.
- 4. PINGP 1300 filled out completely and accurately.
- Additional requirements:
- 1. Security procedures not reviewed by 00-2 individuals ksr;t f-;+able in the area affected (Tech Spec 6.5).
- 2. Quality procedures - two individuals ksrci f;+M in the areas aWocted; one SHALL be a Quality supervisor (5AWI 14.5.0).
. 3. Design change procedures - the reviewer SHALL be the project engineer, the project coordinator, or a responsible supervisor from the procedure originahng organizaten
- 4. Wold control record - SHALL be reviewed (Special Review) a Level 11 or Level ll! Weld inspector, deletion of a non-mandatory, WCR inspechon point SHALL be reviewed (Special Review) by a Level ill Weld Inspector.
- Procedure Control SHALL assign the control number.
SECTION lli- POST REVIEWS
- This sedson is completed for OC reviewed procedures only. If the change was pre-reviewed and pre-approved, this section is 'NR'.
SECTION IV-TEMPORARY CHANGE DELETION
- This sechon is s,64 d for temporary changes which updated controlled copies.
- Review and Approvst requirements- same as in Section 11.
Form 17-8846 (s ok)(0-08)
i "Melensen:6
"'y"a*r*s ' TcN # b 00W l e Effective D:ta: /////ff , DecumentType:1.100 '
Expiration Date: MA TEMPORARY CHANGE NOTICE Page 1 of S ( (5AWI 1.5.10) l 1
- 1. CHANGE REQUEST Procedure #: C 12.d Rev- [7 Project ID #:
Title:
( GTDOVld , C3W490Tdit AAID SdAL WT6E G15ft'LTTOd Desersplion of Change: CtkAntsL /A nn $rrW -1D Pkctuc-rArrc n+r- U SL of: 1%k CDEk2.CtCAG TUfvlP PA' Cxci)b t Jc~ht46li M o o R 4 M e b X r U I',r A1 6 l l l la this an OC reviewed proccdure? Yes' No is a permanent te ( Yes) /*' b l Originator: No0 -Employee (if Yes, submit
#: UL.MO PINGP 436)8i ///Date: I II. REVIEWANDAPPROVAL A. la this temporary change a change in scope or intent? YesO Noh (if No, go to ll.B) j Does this temporary change: i
- 1. Include specille steps discussed in the SAR? Yes No I
- 2. A#ed component operation specdically described in the SAR? Yes No 1
- 3. Affect plant configuration described in text or drawings in the SAR? Yes No l if 1,2 or 3 is Yes, perfonn a Safety Evaluation Screening (PINGP 122g) SES #
is a Safety Evaluation Required? Yes No SE#
- DoesthischangeaffectSpecialReviews(e.g.EQ, App.R)? Yes No O (if Yes document Special Review (s) in CHAMPS)
. OC reviewdate (if procedureis OC Approval by procedure reviewed, otherwise 'NR'): approver:
B. Does this change a5ect plant operation or Tech Specs? Yes$ No (if Yes and work is in progress, Shift Supervisor notified by (initial)) C. Do controlled copies need to be updated? Yesh No (if Yes, Attach marked-up procedure pages to white copy) D. All master / working copies updated? Yes E. Is training on temporary change needed? Yes if Yes, PINGP 1268 or PINGP 1224 (Ops Only) issued) , F. R Af Date: / V/' f
/- t (unit
'a App.cen -
ZZd Date: / ~' M " N ' l (Unit :.; +; s..y . samor procedures) t Forward white copy to Procedure Control
. Ct. POST REVIEWS (required for OC reviewed procedures only;'NR'if reviewed / approved in ll.A)
OC Review Dels: Procedure Approver: Date: IV. TEMPORARY CHANGE del.ETION ('NR'if controlled copies not updated, refer to ll.C) A. Is this ter:iperary change deletion a change in scope or intent? Yes NoO (if No, go to IV.8)
+ Does this temporary change deletion: ,
- 1. Include speelRc olaps discussed in the SAR? YesO NoO l
- 2. Afted component operation speelReally described in the SAR? Yes No l
- 3. Affect plant configuration descrbed in text or drawings in the SAR7 Yes NoO if 1,2 or 3 is Yes, perform a Safety Evaluation Screening (PINGP 122g) SES #
l~ is a Safety Evaluation Required? Yes NoO SE#
- OC review date (if procedure is OC - Approval by procedure reviewed, otherwise 'NR'): approver:
B. Reviewer: Date: l (Unit Management Staff) (Unit Management Staff; SRO for DG reviewsd procedures) Fem n4ses (s4el While Copy- Procedum Control Yellow Copy - Attadi to procedure j
' ~ TcN IT77-oo78
. PRAIRIE Q.AND NUCLEAR GENERATING PLANT ' ,I, NORTHERN STATES POWER COMPANY fY *I 8 CPERATING PROCEDURES f * *?*" f TITLE NUMBER:
LETDOWN, CHARGING, AND C12.1 REV: l SEAL WATER INJECTION 47 Page 38 of 40 5.12 Checking Charging Pumo-Packing Leakage l This procedure is used to quantify any charging pump packing leaks, in running and/or I non-running pumps.
,a,.-- cau '
IE the pump's packing leakoff to the NARDT piping does f37 d l NOT feel warm to the touch, THEN the pump la probably
.y not leaking and therefore it does not have to be checked.
5.12.1 CLOSE the packing leakoff valve to the NARDT for the desired charging pump: VC-15-51 [2VC-15-51],11 [21] CHG PMP DRAIN TO NARDT VALVE CLOSED
.QB l
VC-15-53 [2VC-15-53],12 [22] CHG PMP DRAIN TO , NARDT VALVE - CLOSED
.QB VC- t 5-55 [2VC-15-55),13 [23] CHG PMP DRAIN TO NARDT VALVE CLOSED 5.12.2 OPEN the packing leakoff drain valve to the plastic container (1/4" SS Whitey Valve - not tagged) for the desired charging pump.
5.12.0 T.r.: the packing !cckof for at !cact Ope .T'nuto. , 0.12.4 Caterrain; th; cppicMmate quaindy vi vvaien i;y iiie inwhings On th; ccatainer. ,f 5.12.5 Z th; lcchc" quantity ic > 0.5 gpm, TliEN issuc ; Werk Order. '/ cuclly tri to dctccminc which cy'indcr(c) !c (arc)
- !cching.
/
r
,. C12.1 T4N1797-oo78 JMK 1/11/99 f $c 3 of g Page 38 A The operator should attempt to estimate the leakage rate and determine which graduated cylinder (1000 ml or 4000 ml) to use based upon this estimate.
The following step allows flow to stabilize prior to leakage collection and timing to improve the accuracy of the leakage check. 5.12.3 OPEN the 1/4 turn Whitey valve (no tag) which corresponds to the graduated cylinder which will NOT be used to determine the packing leakage. I l 5.12.4 WHEN flow through the open valve appears to be stable l THEN simultaneously:
. CLOSE the 1/4 tum Whitey valve (no tag) which corresponds to the graduated cylinder which will NOT be used to l determine the packing. leakage.
l AND l . OPEN the 1/4 turn Whitey valve (no tag) which corresponds I to the graduated cylinder which will be used to determine the I packing leakage. ' l l 5.12.5 Collect AND time the packing leakoff for at least one minute. l l l \ l l 5.12.6 CLOSE the 1/4 turn Whitey valve being used to determine the packing leakage. l L
C12.1
'TtN /197-vo7f IM(1/11/99 Page 38 B gage y of 5 l
5.12.7 Record the volume of water collected. ml I 5.12.8 Record the time that the valve was open. MINUTES l 5.12.9 Convert the volume from mi to gallons by multiplying the volume (in ml) recorded in step 5.12.7 by .000264: ml X .000264 = GALLONS 1 l 5.12.10 Determine the flow rate by dividing the volume (in gallons) by the collection time (in minutes) gallons / minutes = GPM 5.12.11 JE the leakoff quantity is > 0.5 gpm, THEN issue a Work Order. Visually try to determine which cylinder (s) is (are) leaking. 5.12.12 Verify that both of the 1/4 tum Whitey valves corresponding to the graduated cylinders are CLOSED. i l l i
. . . . . . . _.- -. a
. 1
- . l
. PRAIRIE Cl.AND NUCLEAR CENERATING PLANT T&N 1999- 007f l paje. 5 of .5-1 "~
NORTHERN STATES POWER COMPANY c,PERATING PROCEDURES
*t NUMBER:
Lli- TITLE
, ge/! LETDOWN, CHARGING, AND C12.1 DM SEAL WATER INJECTION REV: j7 z.
. MgW j
.. . ,- vu - Page 39 of 40
./g~g ' , $27 x; c{ IE the leakoff quantity is < 0.5 gpm, THEN packing does not warrant replacement at this time.
7 .w . . c :y 7 0.12.0 OLOOC the packing l ak;'f drain valve to the p;asti; 00 .ty .0' (1/'" SS Whit:y Valve not tagged) for the desired
,. . . . . . . . , ~ . . . , . .
p 5.12.7 OPEN the packing leakoff valve to the NARDT for the desired l 6,1Z,0 charging pump- l 1 VC-15-51 [2VC-15-51],11 [21] CHG PMP DRAIN TO NARDT VALVE OPEN OB VC-15-53 [2VC-15-53),12 [22] CHG PMP DRAIN.TO NARDT VALVE OPEN
.QB VC-15-55 [2VC-15-55],13 [23] CHG PMP DRAIN TO
' 6. lZ..N OPEN
.12.0 - IE any leakoff water accumulated in the plastic container, THEN drain it to the nearby floor drain.
6.0 ATTACHMENTS NONE ~
7.0 REFERENCES
7.1 Develonmental References 7.1.1 Flow Diagrams: XH-1-38, Chemical and Volume Control System XH-1-39, Chemical and Volume Control System XH-1001-4, Chemical and Volume Control System XH-1001-5, Chemical and Volume Control Systeni 7.1.2 Logic Diagram NF-40784, Chemical and Volume Control System u.-
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES [j%[NSND TITLE NUMBER: kj;!kM $9 LETDOWN, CHARGING, AND C12.1
%AC % SEAL WATER INJECTION REV:
37 0$kh.,EhkOdnil@.#fW[
~
m
- ~ jy .
Page 1 of 40 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE . . . . . . . . . . . E s.
. . . . . . . . . . . CONTINUOUS *USE ' ' ' ' ' ' ' ' '
2.0 PREREQUISITES . . . . . . .*. . . Continuous
.......... use. .of..- pro.c.ed. u. r.e required.
- - 2
- Read each step prior to performing.
3.0 PRECAUTIONS . . . . . . . .*. . Mark
......off. steps as. .they.a.r.e.c.om. p.le.ted.
..... . . ... - 2 Procedure SHALL be at the work location.
4.0 LI M ITATI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5.0 P R O C E D U R ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5.1 Startup of Letdown, Charging and Seal Water . . . . . . . . . . . . . . . 3 5.2 Changing Automatic Charging Purnps . . . . . . . . . . . . . . . . . . . . . 6 5.3 Removing Normal Letdown From Service . . . . . . . . . . . . . . . . . . 7 5.4 Re-establishing Normal Letdown . . . . . . . . . . . . . . . . . . . . . . . . . . 9 5.5 Placing a Second Letdown Orifice in Service . . . . . . . . . . . . . . . . 11 5.6 Placing Excess letdown In Service . . . . . . . . . . . . . . . . . . . . . . . . 13 l 5.7 Removing Excess Letdown From Service . . . . . . . . . . . . . . . . . . 14 5.8 Checking Charging Pump Desurger Pressure Prior to Placing i n S ervi ce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 5.9 Charging Pump Desurger Pressurization . . . . . . . . . . . . . . . . . . . 27 5.10 Chargir ' P urger Depressurization . . . . . . . . . . . . . . . . 34 5.11 Pin + - c t ers In Service . . . . . . . . . . . . . . . . . . . . . . . . . 33 5.12 C s Gharc ig Pump-Packing Leakage . . . . . . . . . . . . . . . . 38
- 6. 0 ATTAC H M E N TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
7.0 REFERENCES
............................................... 39 7.1 Developmental References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 7.2 Implementing References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 l O.C. REVIEW DATE: REVIEWED BY: -
#fg [f) DATE: /8-/
APPROVED BY:
/ DATE:
[8
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT i NORTHERN STATES POWER COMPANY OPERATING PROCEDURES I kh I[ TITLE NUMBER: I* h1 LETDOWN, CHARGING, AND C12.1 REV: i SEAL WATER INJECTION j7 L aw "$!@ik Page 2 of 40 1.0 PURPOSE The procedures for the Chemical and Volume Control System are grouped into severa! l general categories. Letdown, Charging, Reactor Coolant Pump Seal Water, Excess i Letdown, Charging Pump Desurger, Seal injection and Return Filter procedures are included in this section.
"The conditions of the plant during this procedure may involve the emergency plan.
Recommend to the Shift Supentisor to consider classification per F3-2, Classifications of
~
Emergencies. 2.0 PREREQUISITES 2.1 Section 3.2 of Technical Specifications lists requirements for CVCS. 2.2 The mixed bed ion exchangers are saturated with boron equal to or near the reactor i coolant system concentration. l 3.0 PRECAUTIONS 3.1 The reactor coolant pump No.1 seal bypass valve must be operated per C3, Reactor Coolant Pumps. l 3.2 WHEN letdown flow DB charging flow to the Regen HX must be stopped, first stop letdown flow to the Regen HX (to avoid flashing at the letdown orifices), THEN stop charging flow through the Regen HX (to reduce thermal stresses on the injection nozzle. 3.3 Flush floor drains with dilute water when draining a system containing concentrated boric acid, to prevent plugging floor drains. 4.0 LMITATIONS 4.1 Charging pump desurgers SHALL be pressurized to normal operating pressure prior to RCS pressure exceeding 250 psig. 4.2 The temperature of reactor coolant letdown discharged from the letdown heat exchanger should be maintained less than 140' F during normal operation for best ion exchange properties. 4.3 The letdown flow must be maintained below 90 gpm to limit the pressure drop across the ion exchanger resin retention screens. 4.4 Do not exceed 445 psig upstream of CV-31203 [CV-31216], LTDN PRESS CONT. The letdown line high pressure alarm annunciates at 445 psig to warn of impending relief (600 psig). 4.5 Limit charging pump discharge pressure to a maximum of 2600 psig to prevent lifting a pump d!scharge relief valve.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEoURES wo y LE NUMBER: IPI N LETDOWN, CHARGING, AND C12.1 ! gy, j SEAL WATER INJECTION REV: 17
$A i $bkN[ib Page 3 of 40 t 4.6 The VCT pressure should be maintained above a minimum of 15 psig for charging pump suction pressure requirements and RCP seal back pressure. '
4.7 Only one charging pump SHALL be operating when pressurizer level is
> 90%
" 4.8 Do not establish normal or excess letdown if radiation or contamination levels in the RCS are high.1E the RCS activity is = 1 X 10 4uci/ce, THEN do not establish letdown.
This would correspond to > 10 R/hr indication on the letdown monitor R-9. The charging pump rad monitor (R-4 or R-36) would also be pegged high at over 10 R/hr. Isolate letdown if these levels are reached. 1E alternate letdown methods are required, THEN refer to C12.1 AOP4, Alternate Letdown Flowpaths. 4.9 In the event of a fuel leaker, the charging pump hood drain valve can be isolated to prevent radioactive gas (outer seal leakage) from escaping. IE this drain valve must be closed AND the pump run, THEN outplant operators should daily check for any fluid buildup in the hood and drain, as necessary. The normally OPEN hood drain valves are: VC-15-185 [2VC-15-185],11 [21] CHARGING PUMP HOOD DRAIN VALVE VC-15-186 [2VC-15-186],12 [22] CHARGING PUMP HOOD DRAIN VALVE VC-15-187 [2VC-15-187],13 [23] CHARGING PUMP HOOD DRAIN VALVE , 5.0 PROCEDURES 5.1 Startuo of Letdown. Charging and Seal Water
% This procedure is used to establish letdown, charging, and
- s. p reactor coolant pump seal water flows during Filling and t i Venting (D8) and Unit Startup (C1.2). Letdown is j established with flow from RHR. Charging flow is then r initiated and RCP seal water and charging flows are g
s .. .. ... [j adjusted to the proper values. Further operations are detailed in D8, Filling and Venting and C1.2, Unit Startup. 5.1.1 Complete System Prestart Checklist C12-1 [C12-5], Chemical and Volume Control System Charging, Letdown, and Seal Water.
F PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES (L #{g$fthhQ TITLE NUMBER: k k LETDOWN, CHARGING, AND C12.1 m - SEAL WATER INJECTION REV: .g ;r [Emli& gsl y-1 g , k,g^sd,f:M5s Page 4 of 40 g ~ "b IF AN ION EXCHANGER HAS NOT BEEN PREVIOUSLY P" ** J BORATED, CARE MUST BE TAKEN TO AVOID d 4 '% UNPLANNED INSERTION OF POSITIVE REACTIVITY AS I j hkh hkib THE ANION IS CONVERTED TO THE BORATE FORM. dgDBi$g$&y:g g lon exchangers should not be placed in service during
$ds WGg oxygen scavenging operations involving hydrazine.
gpg
^
--=7h When a mixed bed lon exchanger is to be placed in BNOTE E service, the Duty Chemist will Initiate the "lon Exchanger M{@h Yj[ Request for Lithium Removal" form.
5.1.2 Request the Duty Chemist to initiate an "lon Exchanger Request for Lithium Removal" form for the mixed bed ion exchanger to be placed in service. 5.1.3 Review the "lon Exchanger Request for Lithium Removal" form. 5.1.4 IE the mixed bed ion exchanger needs to be borated (mixed bed effluent NOT within 20 ppm of letdown boron concentration), THEN borate the ion exchanger per C12.2, Purification and Chemical Addition. 5.1.5 Set the Reactor Makeup Control System to supply at the same boron concentration as the reactor coolant system in accordance with Automatic Makeup of C12.5, Boron Concentration Control, 5.1.6 OPEN MV-32234 [MV-32235], RHR TO LTDN LINE, using i CS-46175 [CS-46868]. 5.1.7 Pressurize one charging pump desurger in accordance with Section 5.9.
c r PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES y 994g g$d TITLE NUMBER: khjhiMjfs M[ LETDOWN, CHARGING, AND SEAL WATER INJECTION REV: C12.1 17 m EhN,. gggght* ye 323 ;: age 5 of 40
# CAD 710M IE STARTING A RCP WITH THE PRESSURIZER SOLID C ~W AND RCS TEMPERATURE > 150*F, THEN RESTRICT SEAL li% I 1 INJECTION FLOW TO THE RCPS TO LESS THAN
$NN 10 MINUTES PRIOR TO THE START OF THE FIRST RCP DS j TO MINIMlZE THE POSSIBILITY OF RCS OVER-
{ [{ jp% $ g h h PRESSURIZATION.
)
" I 5.1.8 IE startup of CVCS is per D8, Filling and Venting QB C1.2, Unit Startup AND RCS temperature is >150 F, THEN CLOSE or verify CLOSED seal injection throttle valves.
VC-14-1 [2VC-14-1], SI WATER INJECT TO 11 [21] RCP THROTTLE CLOSED VC-14-2 [2VC-14-2], S1 WATER INJECT TO 12 [22] RCP THROTTLE CLOSED 5.1.9 Start the charging pump in MANUAL speed control at its lowest setting. Inspect the pump for normal running conditions. 5.1.10 OPEN the loop B letdown isolation valves: CV-31226 [CV-31230], LETDOWN LINE ISOL, using CS-46165 [CS-49536] CV-31255 (CV-31279], LETDOWN LINE ISOL, using ' I CS-46133 [CS-49667] 5.1.11 OPEN all letdown orifice isolation valves. CV-31325 [CV-31347], LETDOWN ORIFICE ISOL 40 GPM, using CS-46170 [CS-49522] OPEN l CV-31326 [CV-31348], LETDOWN ORIFICE ISOL l 40 GPM, using CS-46171 [CS-49521] OPEN ( CV-31327 [CV-31349), LETDOWN ORIFICE ISOL 80 GPM, using CS-46174 [CS-49537] OPEN 5.1.12 Observe letdown pressure and flow to verify proper operation of 1HC-135A [2HC-135A], LTDN PRESS CONT. 5.1.13 Gradually increase charging pump speed to obtain a charging line flow of approximately 30 gpm.
r PRA!RIE ISLAND NUCLEAR GENERATlHG PLANT ( NORTHERN STATES POWER COMPANY OPERATING PROCEDURES MLE NUMBER:
@@@@dIhkk Nh h LETDOWN, CHARGING, AND C12.1 REV: $h5NME!$gh SEAL WATER INJECTION 37 l WNM@Nh?' p,g,eog4o l
5.1.14 Adjust the local seal injection throttle valves VC-14-1 and VC-14-2 [2VC-14-1 and 2VC-14-2] as necessary to equalize RCP seal injection flow rates. 5.1.15 Adjust 1HC-142 [2HC-142), CHG LINE FLOW CONT, to obtain a seal injection flow rate of 8 gpm to each RCP.
,, Readjust the local seal injection throttle valves if necessary to equalize the RCP seal injection flow rates.
5.1.16 Readjust charging pump speed and the charging line flow control valve to obtain a 30 gpm charging line flow while maintaining 8 gpm sealinjection to each RCP. 5.2 Changing Automatic Charging Pumps This procedure details the steps required to remove the charging pump in automatic speed control from service, while placing an alternate pump in service in automatic speed control, (J7f ' hll3(@j@ $* CARE MUST BE USED WHEN PLACING A 2ND CHARGING PUMP IN SERVICE TO PREVENT THE CHARGING PUMP m of m. DISCHARGE RELIEF VALVES FROM LIFTING. CHARGING h # ] PUMP DISCHARGE HEADER PRESSURE SHALL BE jpg ggd. LIMITED TO A MAXIMUM OF 2600 PSIG. 5.2.1 Verify the dischcrge desurger is pressurized in accordance with Section 5.8. 5.2.2 Transfer the inservice charging pump from AUTOMATIC to MANUAL speed control per C7, Reactor Control System. 5.2.3 Place the speed controller of the charging pump to be started in MANUAL at minimum speed. 5.2.4 Reduce the speed of the inservice charging pump until the seal injection flow drops from 8 gpm to approximately 6 gpm. 5.2.5 Verify charging pump discharge header pressure 1PI-133 [2PI-133] is less than 2400 psig.
;f
'i TO MINIMlZE THE POSSIBILITY OF LIFTING A CHARGING k@gjg77' M - ggp{ PUMP RELIEF VALVE, BE PREPARED TO REDUCE THE t - INSERVICE CHARGING PUMP SPEED WHEN THE WSPkid.m h
[5 ONCOMING CHARGING PUMP IS STARTED. 5.2.6 Start the alternate charging pump.
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: 3
$ hSeiNdkMME ~ ~i i LETDOWN, CHARGING, AND C12.1 1
" _W$ SEAL WATER INJECTION REV:
17
--. W ectionMyg6 AW a Page i of 40 5.2.7 Adjust the inservice charging pump speed to maintain charging pump discharge pressure,1PI-133 [2PI-133] less than 2550 psig and approximately 8 gpm seal injection.
5.2.8 Simultaneously increase the alternate charging pump speed, and decrease the inservice charging pumps speed, keeping
,, seat injection flow between 6 gpm and 10 gpm.
5.2.9 WHEN the inservice charging pump is at minimum speed, THEN adjust the alternate charging pump speed until seal injection flow is approximately 9.5 gpm, THEN stop the inservice charging pump. 5.2.10 Adjust the new inservice charging pump speed to maintain seal injection flow at 8 gpm. 5.2.11 Transfer the new inservice charging pump from MANUAL to AUTOMATIC speed control per C7. 5.3 Removing Normal Letdown From Service This procedure is used to remove normal letdown from service. Excess letdown is placed in service. Normalletdown and charging to the regenerative heat exchanger are then isolated.
-......i RCS ACTIVITY WILL INCREASE AND H CONCENTRATION GM WILL DECREASE WHEN NORMAL LETDOWN IS
$hhh N wasj ISOLATED.
' ' '^
Mf(f !! LETDOWN FLOW SHOULD BE STOPPED PRIOR TO g@jg s STOPPING CHARGING TO THE REGEN HX TO AVOID gggg ,, } FLASHING AT THE ORIFICES. MMOTIOlV ig{: IE THE RCS IS AT ELEVATED PRESSURE (600 psig), THEN 3 4 ISOLATING LETDOWN DOWNSTREAM OF VC-26-1 ( y;c [2VC-26-1] CAUSES THE LETDOWN RELIEF VALVE TO
&" i LIFT. A SECONDARY ISOLATION DOWNSTREAM OF THIS !
Q l RELIEF VALVE MAY ALSO CAUSE LIFilNG,IF THE FIRST ! e f ISOLATION VALVE LEAKS BY ITS SEAT. MONITOR D ..m f ANNUNCIATOR 47015-0608 [49015-0608), LTDN RELIEF ,
$$ ;sg g LINE TO PRT H1 TEMP.
l 5.3.1 Place excess letdown in service per Section 5.6.
i } PRAIRIE ISLAND NUCLEAR GENERATING PLANT I NORTHERN STATES POWER COMPANY OPERATING PROCEDURES NUMBER: f Q di$$ TITLE LETDOWN, CHARGING, AND C12.1 k is! I REV: i SEAL WATER INJECTION 17 y
-- . . %EeWM J Page 8 of 40 5.3.2 Remove normal letdown from service by CLOSING the following:
CV-312E5 [CV-31230], LETDOWN LINE ISOL, using CS-46165 [CS-49536] i CV-31255 [CV-31279], LETDOWN LINE ISOL, using l CS-46133 [CS-49667] 1 5.3.3 Verify the letdown orifice isolation valves are CLOSED: CV-31325 (CV-31347), LETDOWN ORIFICE ISOL 40 GPM, using CS-46170 [CS-49522] l CV-31326 (CV-31348), LETDOWN ORIFICE ISOL 40 GPM, using CS-46171 [CS-49521] CV-31327 [CV-31349), LETDOWN ORIFICE ISOL 80 GPM, using CS-46174 [CS-49537] 5.3.4 While adjusting the charging pump speed to maintain seal injection flow, isolate charging to the Regen HX by closing CV-31198 [CV-31211], CHG LINE FLOW CONT, using 1HC-142 [2HC-142]. l 5.3.5 Place 1HC-135A [2HC-135A], LTDN PRESS CONT,in MANUAL and OPEN to about 50% L- - l
f PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY DPERATING PROCEDURES p '$[Ik? [. TITLE NUMBER:
/jNIM ^ M@$. LETDOWN, CHARGING, AND C12.1 pMdM$WEwnm$is
.ppf sj SEAL WATER INJECTION REV:
.l 7 o<
ym n gag.%insM42Sectiormw J i Page 9 of 40 5.4 Re-establishing Normal Letdown r ~ , ~ up i g i gi
@g@4m#gjpg This procedure assumes normal letdown had been in l u.M operation prior to going on excess letdown and that all 7 NOTE! bgg!Wg manual valves have been returned to their normal letdown
$i i % ff4 ) $ M flowpath position. Assure proper lineup to prevent lifting
[ @$ h h h @j!ofgVC-25-2 [2VC-25-2], LTDN RELIEF TO PRT. mm .w%.amm e*,C DO NOT ESTABLISH NORMAL LETDOWN IF RADIATION yg;g.- pgp OR CONTAMINATION LEVELS IN THE RCS ARE HIGH. E EQ@AUTIONfBMn% E Nud @ad9d @y$ THE RCS ACTIVITY IS a 1 X 104 ucl/ce, THEN DO NOT ESTABLISH LETDOWN. THIS WOULD CORRESPOND TO > idP9sisg@h@jh"$, Q
$k 10 R/HR INDICATION ON LETDOWN MONITOR R-9. THE 4:; CHARGING PUMP RAD MONITOR (R-4 OR R-36) WOULD p ALSO BE PEGGED HIGH OVER 10 R/HR.
kd!gj ! ISOLATE LETDOWN IF THESE LEVELS ARE REACHED. h 3.r
?
br> WN!h gh E ALTERNATE LETDOWN METHODS ARE REQUIRED, di E d?L? %g4 THEN REFER TO C12.1 AOP4, ALTERNATE LETDOWN
^
kk ' h d$ h yt h h When re-establishing normal letdown, high Ictdown Bjgr# temperature can result in releasing boron from the ion exchangers and ADD negative reactivity to the core.
$@%ud%ghdIk@Q29h hu CMy&g ? Low letdown temperature can result in absorbing boron in h y b ff k hh the ion exchangers and ADD positive reactivity to the core.
5.4.1 Place 1HC-130 [2HC-130], LTDN TEMP CONT, in MANUAL and OPEN to 50%. Adjust controller to maintain letdown temperature at 110' F. 5.4.2 Place 1HC-135A [2HC-135A], LTDN PRESS CONT, in MANUAL and OPEN to about 50% 5.4.3 Position CV-31204 [CV-31217], LTDN DIVERT TO PURIF, to the desired position, using CS-46167 [CS-46895). 5.4.4 Verify the flowpath from CV-31205 [CV-31251], LTDN DIVERT TO HOLDUP TNK, to the desired tanks.
l . PRAIRIE ISLAND NUCLEAR GENERATING PL ANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES lj ~ dhg;gg" TITLE NUMBER:
$ LETDOWN, CHARGING, AND C12.1 ff; Q [N u;ym ikh[
kg;g, ? p[/h
. SEAL WATER INJECTION REV: j7 Page 10 of 40 5.4.5 Establish charging to the Regen HX by adjusting the charging line flow control valve and the inservice charging pump speed.
Verify sufficient charging to prevent flashing of letdown. 5.4.6 OPEN CV-31339 [CV-31430], LTDN LINE CNTMT ISOL, using CS-46166 [CS-49503). Letdown valves can only be opened when pressurizer level
%df&i$$$dk I* "" " *'*" W 4'8 N '
5.4.7 OPEN the loop B letdown isolation valves: 1 CV-31226 (CV-31230], LETDOWN LINE ISOL, using f CS-46165 [CS-49536] CV-31255 [CV-31279), LETDOWN LINE ISOL, using CS-46133 (CS-49667] 5.4.8 OPEN the desired letdown orifice isolation valve while adjusting 1HC-135A [2HC-135A), LTDN PRESS CONT, so the 600 psig letdown relief doesn't lift and the desired flow rate is obtained. CV-31325 [CV-31347], LETDOWN ORIFICE ISOL 40 GPM, using CS-46170 [CS-49522] OPEN CV-31326 (CV-31348], LETDOWN ORIFICE ISOL 40 GPM, using CS-46171 [CS-49521] OPEN CV-31327 [CV-31349], LETDOWN ORIFICE ISOL 80 GPM, using CS-46174 [CS-49537] OPEN l i 5.4.9 Return 1HC-135A [2HC-135A], LTDN PRESS CONT, to AUTO per C7. 5.4.10 Return 1HC-130 [2HC-130], LTDN TEMP CONT, to AUTO per C7. l l .
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY l OPERATING PROCEDURES {
# 's'I e EN $N@NT TITLE NUMBER:
M$h"$ M LETDOWN, CHARGING, AND C12.1 {
#99h 5 Wdkh /S$$denj%%I 4M SEAL WATER INJECTION REV:
47 p p; gouuw.6 2 Page 11 of 40 5.5 Placing a Second Letdown Orifice in Service This procedure is used to increase purification flowrate or allow increased RCS dilution rates. This procedure assumes one charging pump is in service with 40 gpm letdown ! flow. A second charging pump is started and a second orifice is placed in service. l I I
- C4(/TIO)
'~p,. e: ?,
.3 c?',',
CARE MUST BE EXERCISED WHEN PLACING A SECOND
^ CHARGING PUMP OR LETDOWN ORIFICE IN SERVICE TO j
,,9'<,/,, A
, 3
^ td 4
,s,, PREVENT LIFTING RELIEF VALVES. )
;CM(JTIOllt]- i' LETDOWN FLOW MUST BE MAINTAINED LESS THAN t 90 GPM.
y
.. W %, r y, , .3T 5.5.1 Verify the discharge desurger of the charging pump to be started is pressurized in accordance with Section 5.8.
5.5.2 Transfer the inservice charging pump from AUTOMATIC to MANUAL speed control per C7. 5.5.3 Place the speed controller of the charging pump to be started in MANUAL at minimum speed. 5.5.4 Perform either of the following: Reduce the speed of the inservice charging pump until the seal injection flow drops from 8 gpm to approximately 6 gpm. DB OPEN 1HC-142 [2HC-142] CHG LINE FLOW CONT, until seat injection flow drops from 8 gpm to approximately 6 gpm. 5.5.5 Verify charging pump discharge header pressure 1PI-133 [2PI-133] is less than 2400 psig. 5.5.6 Start the second charging pump. 5.5.7 Increase charging pump speed, while maintaining 8 gpm seal injection to each RCP, to obtain approximately 70 gpm charging flow to the Regen HX.
F l PRAIRIE ISLAND NUCLEAR GENE'RATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES N/ TITLE NUMBER: [ flip'Dq - ff[ N LETDOWN, CHARGING, AND C12.1 REV: ih@S!9 Jdl$hh SEAL WATER INJECTION .g 7
$$nR5Q vJ;;$ e ssj QPQ s4- Page 12 of 40 5.5.8 Place 1HC-135A [2HC-135A], LTDN PRESS CONT, in MANUAL Maintain letdown pressure < 445 psig to prevent lifting the low pressure letdown relief valve.
I 5.5.9 OPEN the second 40 gpm letdown orifice isolation. j CV-31325 [CV-31347], LETDOWN ORIFICE ISOL 40 GPM, using CS-46170 [CS-49522] OPEN
.QB CV-31326 (CV-31348], LETDOWN ORIFICE ISOL j 40 GPM, using CS-46171 [CS-49521] OPEN l 5.5.10 Return 1HC-135A [2HC-135A], LTDN PRESS CONT, to AUTO.
5.5.11 Transfer one of the inservice charging pumps from MANUAL to l AUTOMATIC speed control per C7. l l D
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES l MNbiIdpb TITLE NUMBER: [$$b[7 $$hb LETDOWN, CHARGING, AND C12.1 REV: l Nh% SEAL WATER INJECTION j7 p'$$rAk a%166kk WW 7% l ~2 Page 13 of 40 1 5.6 Placing Excess letdown in_ Service This procedure is used to place excess letdown in service. After component cooling flow is established to the excess letdown heat exchanger, excess letdown flow is slowly initiated and adjusted.
'- .; . ,w, ~
i,.,,-/mL CAUTION!/^6 DO NOT ESTABLISH EXCESS LETDOWN IF RADIATION OR CONTAMINATION LEVELS IN THE RCS ARE HIGH. IE
'f f G _ i l'a </Jca, THE RCS ACTIVITY IS = 1 X 10 4 ucl/ce,IHEN DO NOT
' S dO,,,f,, :c ESTABLISH EXCESS LET DOWN. THIS WOULD
' #! ~ 5 - % * '^ CORRESPOND TO > 10 R/HR INDICATION ON THE js<>s,e 4 p' l ist S '. LETDOWN MONITOR R-9. THE CHARGING PUMP RAD J L
- b ',1 ^t j. MONITOR (R-4 OR R-36) WOULD ALSO BE PEGGED HIGH 1 9 *' FfW;'3,0 ir' OVER 10 R/HR.
g y, ' n' 'p:pl y :g g;:Vfl,; ';y;' ;l t '74 ISOLATE EXCESS LETDOWN IF THESE LEVELS ARE e; ;; g REACHED. 1 ',ll :
" c' a +,y - :,1gv
' TCf':3:1 c: <. ? /t' IE ALTERNATE LETDOWN METHODS ARE REQUIRED, o.;g l M.7 :d j ' .' r '5 THEN REFER TO C12.1 AOP4, ALTERNATE LETDOWN
']' ' 'i. ' - -l f;;
, FLOWPATHS.
g:p%u_ _qq g
.tCAUT/ONige MAINTAIN EXCESS LETDOWN HEAT EXCHANGER 1pygp:vec VTC OUTLET TEMPERATURE ON SCALE, TO PREVENT p 'll u m r dlE5M49 D 4 $ FLASHING
@ TO THE SEAL WATER RETURN LINE.
5.6.1 Verify CV-31210 [CV-31222], EXCESS LTDN FLOW CONT, is CLOSED, using 1HC-123 [2HC-123]. l NM IE excess letdown le to be used as an aid in reducing N [g%gTE:h. g jg .pp$y@g pressurizer level during a heatup, THEN position the divert valve to the resctor coolant drain tank (RCDT). 5.6.2 Verify CV-31333 [CV-31424], EXCESS LTDN DIVERT TO I RCDT, is positioned to the "V.C. TK" position, using CS-46169 [CS-46862). - i 5.6.3 OPEN MV-32095 [MV-32130], EXCESS LTDN HX CC l lNLT/OUTL, using CS-46030, [CS-46533] to establish l component cooling flow to the excess letdown heat exchanger ; by placing . The component cooling outlet valve, CV-31252 i [CV-31253] will also OPEN.
- yv PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES lj V # g i O$b TITLE NUMBER:
bk skNMg% k h LETDOWN, CHARGING, AND C12;1 REV: o s! SEAL WATER INJECTION ISh g$# JFha;i6tipl$%$ v" , 1 s Page 14 of 40 l 5.6.4 OPEN CV-31330 [CV-31422), EXCESS LTDN HX INLT, using CS-46168 (CS-46896]. 5.6.5 Slowly OPEN CV-31210 [CV-31222], EXCESS LTON FLOW CONT, using 1HC-123 [2HC-123]. Observe the heat exchanger outlet temperature and pressure and pressurizer { level to obtain the proper setting of the outlet valve. l l 5.7 Removing Excess Letdown From Service This procedure is used to remove excess letdown from sentice. The heat exchanger is isolated and component cooling water flow is stopped. , j 5.7.1 CLOSE CV-31330 [CV-31422), EXCESS LTDN HX INLT, using CS-46168 (CS-46896]. I 1 5.7.2 CLOSE CV-31210 [CV-31222], EXCESS LTDN FLOW CONT, I using 1HC-123 [2HC-123]. ! 5.7.3 Allow ample time for the heat exchanger to cool THEN CLOSE MV-32095 [MV-32130], EXCESS LTDN HX CC INLT/OUTL, using CS-46030 [CS-46533], to stop component cooling water flow to the excess letdown heat exchanger. The component cooling outlet valve CV-31252 [CV-31253] will also CLOSE. j
l . PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY OPERATING PROCEDURES ,
#$f/ . N Nk TITLE NUMBER:
l [ oMhi' LETDOWN, CHARGING, AND C12.1 N o hgr# _$$h 8 -jg' SEAL WATER INJECTION REV: 17 iMe%$M y d$ndi 'Jan Page 15i of 40 5.8 Checking Charging Pomo Desurger Pressure Prior to Placing in Service d6 N$O UIA Charging pump desurger pressurization and d pressurization sections s.9 and s.10 will be necessary to [CNOTE Nghljb!$g[{ s di?{. perform this section. 5.8.1 11 Charging Pump A. Place CS-46292,11 CHG PUMP, in " PULLOUT". l NyID Discharge and suction valves must be CLOSED when EW [!Qjf,c(g$@,p@a d ENOTE gp charging a desurger to contain any potential N2 leakage and to allow depressurization of the charging pump 4 l discharge line (CVCS side) because of check valve 6$' UMP 66wd,@g@!?g Mt$$6gjjs@
. 44%, ym ieakmge.
B. CLOSE VC-39-1,11 CHG PMP DSCH. ! I C. CLOSE VC-6-5,11 CHG PMP SUCT. D. Depressurize 11 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitey drain valve downstream of PT-17119.
- 2. OPEN PT-17119, PRESSURE TAP DRAIN VALVE.
E. Verify CLOSED NG-39-2, DESURGER N 2ROOT VALVE. F. OPEN NG-39c.1, DESURGER N 2ISO.LATION VALVE. G. Record "As Found" desurger pressure using PI-11483 (Desurger N2 Gauge). psig
F . PRAIRIE ISLAND NUCLEAR GENERATING PLANT f NORTHERN STATES POWER COMPANY OPERATING PROCEDURES hhldk jh $f Ih TITLE NUMBER:
$ usxkW LETDOWN, CHARGING, AND C12.1 MMi SEAL WATER INJECTION REV:
$7 D@4
;; ;cp hbyv ort a:n%.ey [dI Page 16 of 40 1
n = Ieggae b.. ,j The "As Found" desurger pressure should be between I
@g Jiqi 1950 and 2050 psig. Continue with this procedure as de R ME A follows-wk $r /dk l
#9M B@ 1. IE pressure is 1950 - 2050 psig, THEN do Step H, {
NA titeps I and J. TNDIE$N@M@W l bh j@ ;
} 2. IE pressure is < 1950 psig, THEN do Step I, NA steps H and J.
- 3. IE pressure is > 2050 psig, THEN do Step J, ghg gk NA Steps H and I.
H. JE the "As Found" desurger pressure is adequate, THEN CLOSE NG-39-1, DESURGER N 2ISOLATION VALVE. k DO NOT ADD N2TO A CHARGING PUMP WITH A FAILED khkhhhhhlj$.
%qppgr%wu%w Aus 26 DESURGER.
- 1. JE the "As Found" desurger pressure is low, THEN perform the steps in Section 5.0, Charging Pump Desurger Pressurization, to determine if the bladder has failed QB 1
just needs to be pressurized. J. 1E the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Section 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain lina to verify no further flow from the drain line. Water or N2 flow indicates discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 trapped in the piping could gas bind the running charging pump. Leave the pump suction valve CLOSED until flow from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to sec if pressure is decreasing due to N2 leakage. I' L. OPEN VC-6-5,11 CHG PMP SUCT. 1 M. Independently verify VC-6-5 is OPEN. IV
F PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURE!E
$Pyleg'Ejg$'5 'tply [ TITt.E NUMBER:
LETDOWN, CHARGING, AND C12.1 l Ib$:k$ f s kf l M $Ydk gN Eg[j$' d$ih; SWE 7I$ctl$ni'i~ J SEAL WATER INJECTION REV: j7 4 , Page1 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17119 and the Whitey valve downstream. O. OPEN VC-39-1,11 CHG PMP DSCH. P. Independently verify VC-39-1 is OPEN. Q. Return CS-46292,11 CHG PUMP, to " NEUTRAL" 6.8.2 12 Charging Pump A. Place CS-46293,12 CHG PUMP, in " PULLOUT." k!hh[ !!M@h$$NR Discharge and suction valves must be CLOSED when 4%s M@ charging a desurger to contain any potential N2 leakage
$NOT6 om h and to allow depressurization of the chargitsg pump
$dkffEEE .0 discharge line (CVCS side) because of check valve leakage.
NN$ hhhfMv/3fb: B. CLOSE VC-39-2,12 CHG PMP DSCH. C. CLOSE VC-6-6,12 CHG PMP SUCT. D. Depressurize 12 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitey drain valve downstream of PT-17121.
- 2. OPEN PT-17121, PRESSURE TAP DRAIN VALVE.
E. Verify CLOSED NG-39-4, DESURGER N 2ROOT VALVE. l F. OPEN NG-39-3, DESURGER N 2ISOLATION VALVE. ! G. Recora "As Found" desurger pressure using PI-11484 l (Desurger N2 Gauge). I _ psig
PRAIRIE 12 LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES s NUMBER: hk ., TITLE C12.1 l #jpg ' $ LETDOWN, CHARGING, AND l l Mid y V d SEAL WATER INJECTION REV: 17 "Ij@%MM@ m y s 5, 8 U Page 18 of 40 g k$il $$ l(th The "As Found" desurger pressure should be between
!! lgih $ 1950 and 2050 psig. Continue with this procedure as W. ROgg follows:
i@f E thqjg&g4 m $ h kN 1. IE pressure is 1950 - 2050 psig, THEN do Step H,
$NDTESINhg
^
NA Steps I and J. [ds g hh h 2. JE pressure is < 1950 psig,IliEN do Stop 1, fj y Q iG J g NA Steps H and J. jW QP Sy - W4T R1 fp bs 3. IE pressure la > 2050 psig, THEN do Step J, [kb [,kgg $ fj g NA Steps H and I. H. IE the "As Found" desurger pressure is adequate, THEN CLOSE NG-39-3, DESURGER N 2ISOLATION VALVE. d DO NOT ADD Na TO A CHARGING PUMP WITH A FAILED
}h-{dONbN!%dh M yp ?% DESURGER.
- 1. IE the "As Found" desurger pressure is low, THEN perform the steps in Section 5.9, Charging Pump Desurger Pressurization, to deterrnine if the bladder has failed or just needs to be pressurized.
J. IE the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Section 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain line to verify no further flow from the drain line. Water or N2 flow indicates ! discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 , trapped in the piping COULD gas bind the running charging i
- pump. Leave the pump suction valve CLOSED until flow from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to see if pressure is decreasing due to N2 leakage.
! L. OPEN VC-6-E,12 CHG PMP SUCT. l M. Independently verify vC-6-6 is OPEN. IV ; l 1 . ! l l J
PRAIRIE ist.AND NUCLEAR GENERATING PLANT ! NORTHERN STATES POWER COMPANY OPERATING PROCEDURES j%%fM4M M7 TITLE NUMBER: l C12.1 k Tgff9hi_ " #% n LETDOWN, CHARGING, AND SEAL WATER INJECTION REV: j7 l NI ' Page 19 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17121 and the Whitey valve downstream. 1 O. OPEN VC-39-2,12 CHG PMP DSCH. l P. Independently verify VC-39-2 is OPEN.
,y O. Return CS-46293,12 CHG PUMP, to " NEUTRAL" 5.8.3 13 Charging Pump A. Place CS-46294,13 CHG PUMP, in " PULLOUT."
fMbdh$ki$$^ $:f Discharge and suction valves must be CLOSED when didREAdhdMi charging a desurger to contain any potential N2 leakage ii;; ifNOTEfW[? i
& ]Mb d 74$$ g$
3s leakage. {'lk and to allow depressurization of the charging pump discharge line (CVCS side) because of check valve j B. CLOSE VC-39-3,13 CHG PMP DSCH.
)
C. CLOSE VC-6-7,13 CHG PMP SUCT. I l D. Depressurize 13 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitey drain valve downstream of l
PT-17123.
- 2. OPEN PT-17123 (pressure tap drain valve).
E. Verify CLOSED NG-39-6, DESURGER N 2ROOT VALVE. F. OPEN NG-39-5, DESURGER N 2ISOLATION VALVE. G. Record "As Found" desurger pressure using PI-11485 (Desurger N2 Gauge). l psig i
E l PRAIRIE ISLAND NUCLEAR C ENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES f NUMBER: TITLE g!ggggfip$guhk 9 we.-
& W awM LETDOWN, CHARGING, AND C12.1 $ M SEAL WATER INJECTION REV:
17
$N. M M 6_$;$e$$
- aymmpp m . page 20 of 40
! The "As Found" desurger pressure should be between
- ggsPJ13pggh 1950 and 2050 psig. Continue with this procedure as g 2W - f._ g4 follows:
$$$ ' #hg$$rl E8Q3ssA%Mg@f1. IE pressure is 1950 - 2050 psig, THEN do Step H, j NA Steps I and J.
Yh0TESF4Ms l ix wn 4%s%@g l s "i@6 2. IE pressure is < 1950 psig, THEN do Step 1, j NA Steps H and J. g h Ocgh-d g)h ;[*? s
- 3. IE pressure is > 2050 psig, THEN do Step J, NA Steps H and I.
)
H. 1E the "As Found" desurger pressure is adequate, THEN CLOSE NG-39-5, DESURGER N 2ISOLATION VALVE. wn. ~ smmw ~ NCAUTIONMS DO NOT ADD N2TO A CHARGING PUMP WITH A FAILED j gg; { jf]Qg DESURGER.
- l. IE the "As Found" desurger pressure is low, THEN perform the steps la Section 5.9, Charging Pump Desurger Pressurization, to determine if the bladder has failed or just needs to be pressurized.
J. IE the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Section 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain line to verify no further flow from the drain line. Water or N2 flow indicates discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 trapped in the piping could gas bind the running charging pump. Leave the pump suction valve CLOSED until flow from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to see if pressure is decreasing due to N2 leakage. l L OPEN VC-6-7,13 CHG PMP SUCT. M. Independently veriff VC-6-7 is OPEN.
,y
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES l
@ "i;d!~'PRt TITLE NUMBER:
C12.1 h s L. MkN LETDOWN, CHARGING, AND REV: 4yb5 SEAL WATER INJECTION 17 I MsEtisiM@l
'i~4 - avpr senwrw Page 21 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17123 and the Whitey valve downstream.
O. OPEN VC-39-3,13 CHG PMP DSCH. P. Independently verify VC-39-3 is OPEN. Q. Return CS-46294,13 CHG PUMP, to " NEUTRAL" 5.8.4 21 Charging Pump l A. Place CS-49550. 21 CHG PUMP, in " PULLOUT." ; 1 1
%I $$d Dischar;. and suction valves must be CLOSED when
$NOTEg aig RE
*" ((h.
charging a desurger to contain any potential N2 leakage and to allow depressurization of the charging pump l 0 $Maki e discharge line (CVCS side) because of check valve IhfNIO8%ph leakage. B. CLOSE 2VC-39-1,21 CHG PMP DSCH. C. CLOSE 2VC-6-5,21 CHG PMP SUCT. D. Depressurize 21 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitey drain valve downstream of PT-17125.
l
- 2. OPEN PT-17125 (pressure tap drain valve).
E. Verify CLOSED 2NG-39-2, DESURGER N 2ROOT VALVE. l F. OPEN 2NG-39-1, DESURGER N ISOLATION 2 VALVE. 1 G. Record "As Found" desurger pressure using PI-11486 (Desurger N2 Gauge). psig l
PRAIRIE I! LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES NM t YIs:N$$ TITLE NUMBER: hh.dk k $$N LETDOWN, CHARGING, AND C12.1 shMfW M&ue.y q hyesg Wg@n%p; EEL Niio is SEAL WATER INJECTION REV: 37 Page 22 of 40_ s, gunummye w r , gyeWe F The "As Found" desurger pressure should be between ) 3 1950 and 2050 psig. Continue with this procedure as j [5f{be[gd/M
%jf n WN%
{@Qh@j follows. l l ERN M M O @Ad 1. E pressure is 1950 - 2050 psig, THEN do Step H, iNdINNN{ibj}gy!Sp NA Steps I and J.
" mv y 49p1 h$9 tQFeys 2. E pressure is < 1950 psig, THEN do Step I, y N jfS NA Steps H and J.
.% ggh$gg@@
,!eigggm-Qj& & & jMiM 3. IE pressure is > 2050 psis,IHEN do Stop J, id@yM3%f@bhfhMb NA Steps H and 1.
% -sw H. IE the "As Found" desurger pressure is adequate, THEN CLOSE 2NG-39-1, DESURGER N 2ISOLATION VALVE.
?CAUflDN[ d DO NOT ADD N2 TO A CHARGING PUMP WITH A FAILED c r , ',
- o.
t ' : a , e Ic
, - :,: s DESURGER.
- 1. IE the "As Found" desurger pressure is low, THEN perform the steps in Section 5.9, Charging Pump Desurger Pressurization, to determine if the bladder has failed or just needs to be pressurized.
J. 1E the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Seciion 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain line to verify no further flow from the drain line. Water or N2 flow indicates discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 trapped in the piping could gas bind the running charging pump. Leave the pump suction valve CLOSED until flow from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to see if pressure is decreasing due to N2 leakage. L. OPEN 2VC-6-5,21 CHG PMP SUCT. M. Independently verify 2VC-6-5 is OPEN. IV 1 I
l PRAIRIE ISt.AND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PRoCEDUFiEs N NUMBER: g/ b)u h!h NI TITLE LETDOWN, CHARGING, AND C12.1 I3$h 'd%$1
> /phg jd SEAL WATER INJECTION REV:
17 (pW:, SI $SebtiodtO - k i# 1ag& WF W. Page 23 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17125 and the Whitey valve downstream. O. OPEN 2VC-39-1,21 CHG PMP DSCH. P. Independently verify 2VC-39-1 is OPEN. 1 Q. Return CS-49550,21 CHG PUMP, to " NEUTRAL." 5.5.5 22 Charging Pump 1 A. Place CS-49551,22 CHG PUMP, in " PULLOUT." l hh Discharge and suction valves must be CLOSED when 1 gp9mMNiiE 2 h charging a desurger to contain any potential N2 leakage 1 NOTE!Wi'? 1 and to allow depressurization of the charging pump discharge line (CVOS side) because of check valve p.E$ Q'l!@#My) AS:!? 4 new ;; < m *: leakage.
,tn w; B. CLOSE 2VC-39-2,22 CHG PMP DSCH.
l l C. CLOSE 2VC-6-6,22 CHG PMP SUCT. D. Depressurize 22 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitsy drain valve downstream of PT-17127.
- 2. OPEN PT-17127 (pressure tap drain valve).
E. Verify CLOSED 2NG-39-4, DESURGER N 2ROOT VALVE. I F. OPEN 2NG-39-3, DESURGER N 2ISOLATION VALVE. 1 i G. Record "As Found" desurger pressure using PI-11487 j (Desurger N2 Gauge). l i psig I l 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1 NORTHERN STATES POWER COMPANY OPERATING PRoCEC UREs i.
~ $ $h k TITLE I NUMBER: )
- LETDOWN, CHARGING, AND C12.1
- s. E REV:
j [ SEAL WATER INJECTION j7 kw . .stan . r f! Page 24 of 40 1 l NI! j tj , h{ gy The "As Found" desurger pressure should be between 1950 and 2050 psig. Continue with this procedure as ij follows: rp 5
- 1. 1E pressure is 1950 - 2050 psig, THEN do Step H, .
NA Steps I and J. F S 6 f .
- 2. 1E pressure is < 1950 psig, THEN do Step I,
] NA Steps H and J.
k$ Nky 3. 1E pressure is > 2050 psig, THEN do Step J, NA Steps H and I. l r
...m 1
H. IE the "As Found" desurger pressure is adequate, THEN l CLOSE 2NG-39-3, DESURGER N 2! SOLATION VALVE. l b[hkhNhh M N NM $j g DO NOT ADD Na TO A CHARGING PUMP WITH A FAILED DESURGER. I. 1E the "As Found" desurger pressure is low, THEN perform the steps in Section 5.9, Charging Pump Desurger Pressurization, to determine if the bladder has failed DB just needs to be pressurized. J. IE the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Section 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain line to verify no further flow from the drain line. Water or N2 flow indicates discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 trapped in the piping COULD gas bind the running charging pump. Leave the pump suction valve CLOSED until flow from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to see if pressure is decreasing due to N2 leakage. L. OPEN 2VC-6-6,22 CHG PMP SUCT. M. Independently verify 2VC-6-6 is OPEN. ,y
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES j@ ~ \> w TITLE NUMBER: ma r a. Q;"N.gh3
@J . he;@ LETDOWN, CHARGING, AND C12.1 REV:
Ad' M Jhpd SEAL WATER INJECTION j7
$,. '. ,iSk. t. i,ds$p.'
.g Page 25 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17127 and the Whitey valve downstream.
O. OPEN 2VC-39-2,22 CHG PMP DSCH. P. Independently verify 2VC-39-2 is OPEN. Q. Return CS-46551,22 CHG PUMP, to
- NEUTRAL."
5.8.6 23 Charging Pump A. Place CS-49552,23 CHG PUMP, in " PULLOUT." m, ,
$g$r l Discharge and suction valves rnust be CLOSED when is .aA[.2 jdqmp%..
sigvP !@, charging a desurger to contain any potential N leakage 2 and to allow depressurization of the charging pump TNOTE[#Pi'.$m.d gq f44lj{9 discharge line (CVCS side) because of check valve
'&udW6 01 I*
- k* 9 *-
B. CLOSE 2VC-39-3,23 CHG PMP DSCH. C. CLOSE 2VC-6-7,23 CHG PMP SUCT.' D. Depressurize 23 Charging Pump discharge line (CVCS side) per the following:
- 1. OPEN the small Whitey drain valve downstream of PT-17129,
- 2. OPEN PT-17129 (pressure tap drain valve).
E. Verify CLOSED 2NG-39-6, DESURGER N 2ROOT VALVE. F. OPEN 2NG-39-5, DESURGER N 2ISOLATION VALVE. G. Record "As Found" desurger pressure using Pl-11488 (Desurger N2 Gauge). psig
PRAIRIE !! LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES
@tB ',.
f*pf$$ TITLE NUMBER: dhM b hfxh LETDOWN, CHARGING, AND C12.1 REV: T"D $$f f $ SEAL WATER INJECTION 17
. _ & mg ^c -g'p A jt Page 26 of 40 "d0f!A@h(Nh L.,> ,$'" hef The "As Found" desurger pressure should be between 1950 and 2050 psig. Continue with this procedure as
$R follows:
PWL _kw mn,g!f N Ejh*$$ @ F b 1 E Pressure is 1950 - 2050 psig, THEN do Step H,
%MD;TES ~, ,, $iji$A@dNA Steps I and J.
- s. {p c.e-
- da .
- 2. E pressure is < 1950 psig, THEN do Step I, NA Steps H and J.
% dud c mmz?%w@u 1- J f s IMi 3. E pressure is > 2050 psig, THEN do Step J,
@! % %j@yg . NA Steps H and I.
H. IE the "As Found" desurger pressure is adequate, THEN 1 CLOSE 2NG-39-5, DESURGER N 2ISOLATION VALVE. ) i I m .n. \
+. jjhst DO NOT ADD N2TO A CHARGING PUMP WITH A FAILED l
i ~ TIONi
$mgIM5bd$ DESURGER.
I. IE the "As Found" desurger pressure is low, THEN perform the steps in Section 5.9, Charging Pump Desurger Pressurization, to determine if the bladder has failed or just needs to be pressurized. J. IE the "As Found" desurger pressure is high, THEN depressurize the desurger to the range of 1950 - 2050 psig in accordance with Section 5.10, Charging Pump Desurger Depressurization. K. Check the discharge pressure tap drain line to verify no further flow from the drain line. Water or N2 flow indicates discharge desurger boot leakage (or isolation valve leakage). OPENING the pump suction valve with N2 i trapped in the piping could gas bind the running charging pump. Leave the pump suction valve CLOSED until flow j from the pressure tap is nearly stopped. The desurger N2 pressure can be rechecked to see if pressure is decreasing due to N2 leakage. L. OPEN 2VC-6-7,23 CHG PMP SUCT. M. Independently verify 2VC-6-7 is OPEN. ,y
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES dh8N..u i$$ y[$$N TITLE NUMBER: h - d#hk LETDOWN, CHARGING, AND C12.1 bd d f SEAL WATER INJECTION REV: j7
* - Sbk ong 3
~ 4L gam:RO 5$3 4 Page 27 of 40 N. WHEN a steady flow of liquid is observed, THEN CLOSE PT-17129 and the Whitey valve downstream.
O. OPEN 2VC-39-3,23 CHG PMP DSCH. i P. Independently verify 2VC-39-3 is OPEN. Q. Return CS-49552,23 CHG PUMP, to " NEUTRAL." 5.9 Charging Pumo Desurger Pressurization
<.>-...m.v., -m INQT6fli{
E5eWWWi% T
? T.S.3.2 requires two operable charging pumps per unit.
dM $3 hhhf itProperly is very important that charging pump desurgers are pressurized prior to starting a charging pump, to
$3 E[fh0TEi fd[$b5 Preclude a failure of the bladder due to a pressure
^
igg wm a O imbalance between the nitrogen applied to one side of the [A h5.M:$Yj!T W bladder and the discharge pressure of the charging pump Nkkhben kjji[I applied to the other side of the bladder. 5.9.1 Place the desired charging pump control switch in PULLOUT: CS-46292 [CS-49550),11 [21] CHG PMP PULLOUT CS-46293 [CS-49551),12 [22] CHG PMP PULLOUT CS-46294 (CS-49552],13 [23] CHG PMP PULLOUT p / ag;.; +'A YM
.gMU@.
7p $ Suction and discharge valves must be CLOSED when
#NOTESA pst pressurtzing a desurger to contain any potential N2 Nh!bhk 3$s ' *
- 9
5.9.2 CLOSE the appropriate charging pump discharge isolation valve: VC-39-1 [2VC-39-1],11 [21] CHG PMP DSCH CLOSED VC-39-2 [2VC-39-2],12 [22] CHG PMP DSCH CLOSED vC-39-3 [2VC-39-3],13 [23] CHG PMP DSCH CLOSED i I
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES
'I TITLE NUMBER:
$ '~ kf@$t.[
C12.1 l E $ %@ LETDOWN, CHARGING, AND , l hMl
%$E@L t pe,
[iffe;$E SEAL WATER INJECTION REV: j7 l ETSW & w/d8I!2 Page 28 of 40 5.9.3 CLOSE the appropriate charging pump suction isolation valve: ! l VC-6-5 [2VC-6-5),11 [21] CHG PMP SUCT CLOSED : VC-6-6 [2VC-6-6],12 [22] CHG PMP SUCT CLOSED VC-6-7 [2VC-6-7],13 [23] CHG PMP SUCT CLOSED 5.9.4 Bleed the pressure off the charging line via the appropriate pump discharge pressure tap. Leave the pressure tap OPEN. Flow should stop if the isolation valves are leak tight and the desurger boot does not leak N2 : hhy ![ kh ggg[gg High pump discharge pressures must be bled off before (g desurger pressurizing to obtain propor N2 gas volume. PT-17119 [PT-17125],11 [21] CHG PMP DSCH PRESS TAP OPEN PT-17121 [PT-17127],12 [22] CHG PMP DSCH PRESS TAP OPEN PT-17123 [PT-17129],13 [23] CHG PMP DSCH PRESS TAP OPEN hhhh $$2 , Ensure the N2 regulator is indicating zero.
%#2$dj9dNhf8, 5.9.5 OPEN the desurger isolation and root valves for the desired desurger:
A. 11 [21] Charging Pump: NG-39-1 [2NG-39-1),11 [21] CHG PMP DESURGER ISOL VLV NG-39-2 [2NG-39-2],11 [21] CHG PMP DESURGER ROOT VLV
r
]
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY , , OPERATING PROCEDURES 1 mgM 3 ; gik ) g-y/n TITLE BER: l l g"" C121 { LETDOWN, CHARGING, AND i i kpsere W , J#pf 5 SEAL WATER INJECTION REV: j7 j ? M ~ WTsk'nsh?%s mgg 4 v "^ s Page 29 of 40_ i i B. 12 [22] Charging Pump: l NG-39-3 iNG-39-3],12 [22] CHG PMP DESURGER t l SOL VLV NG-39-4 [2NG-39-4],12 [22] CHG PMP DESURGER ROOT VLV C. 13 [23] Charging Pump: NG-39-5 [2NG-39-5],13 [23] CHG PMP DESURGER ISOL VLV l NG-39-6 [2NG-39-6],13 [23] CHG PMP DESURGER I ROOT VLV 5.9.6 Momentarily OPEN the appropriate desurger drain valve. JE water is present, THEN bleed the water off the desurger. (A large volume of water would indicate a failed desurger bladder. This will be checked when the bladder is pressurized.) i NG-33-2 [2?:G-35-13],11 [21] CHG PMP DSRGR DRAIN NG-33-3 [2NG 35-14],12 [22] CHG PMP DSRGR DRAIN NG-33-4 [2NG-35-15],13 [23] CHG PMP DSRGR DRAIN 5.9.7 RECLOSE the desurger drain valve. 5.9.8 Ensure the appropriate N 2HP Regulator is adjusted to O psig: NG 34-1 [2NG-34-1],11 [21] DSRG N 2HP REGULATOR NG-34-2 [2NG-34-2],12 [22] DSRG N2HP REGULATOR l l l NG-34-3 [2NG-34-3],13 [23] DSRG N 2HP REGULATOR l l l l
l I PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES g[ [ TITLE NUMBER: ShdiSE sidi A ,keyjg N h"?@ LETDOWN, CHARGING, AND SEAL WATER INJECTION REV: C121 j7 BMM$$.
;;m ny wg hid+%)1 s Page 30 of 40 l 5.9.9 OPEN the N2HP Regulator outlet for the desired desurger:
NG-29-4 (2NG-35-2],11 [21] DSRG N2 HP REG OUTLET NG-29-7 [2NG-35-5],12 [22] DSRG N 2HP REG OUTLET 1 NG-29-10 [2NG-35-8],13 [23] DSRG N 2HP REG OUTLET 5.9.10 OPEN the N2HP Regulator inlet for the desired desurger: NG-29-3 [2NG-35-1],11 [21] DSRG N2HP REG INLET NG-29-6 [2NG-35-4],12 [22] DSRG N 2HP REG INLET NG-29-9 [2NG-35-7],13 [23] DSRG N 2HP REG INLET l DO NOT PRESSURIZE TOO QUICKLY - THIS CAN CAUSE hhkhNDMhhh{hhy{"]geQ?3:DESURGER FAILURE. 5.9.11 Slowly adjust the N2HP Regulator to pressurize the desired ; desurger. Monitor desurger pressure using the pressure gauge at the regulator. Bring pressure up at 500 psig intervals, stopping for about 1 minute between pressure increases, until a final pressure of 1950 - 2050 psig is reached. NG-34-1 [2NG-34-1],11 [21] DSRG N HP 2 REGULATOR i NG-34-2 [2NG-34-2],12 [22] DSRG N 2HP REGULATOR NG-34-3 [2NG-34-3],13 [23] DSRG N 2HP REGULATOR l 5.9.12 CLOSE the appropriate N2HP Regulator outlet and inlet valves: A. 11 [21] Charging Pump: NG-29-4 [2NG-35-2],11 [21] DSRG N2HP REG OUTLET NG-29-3 [2NG-35-1],11 [21] DSRG N2 HP REG INLET B. 12 [22] Charging Pump: NG-29-7 [2NG-35-5],12 [22) DSRG N 2HP REG OUTLET NG-29-6 [2NG-35-4],12 [22] DSRG N2 HP REG INLET e__
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT N_ORTHERN STATES POWER COMPANY OPERATING PROCEDURES Syjj TITLE NUMBER:
! sMk LETDOWN, CHARGING, AND C12.1 s.
mgyian gg 5 SEAL WATER INJECTION REV: j7
$3f)GS$hEk
- imFY f Page 3i of 40 i C. 13 [23] Charging Pump:
NG-29-10 [2NG-35-8],13 [23] DSRG N2HP REG OUTLET NG-29-9 [2NG-35-7],13 [23] DSRG N2 HP REG INLET
~
- i. 5.9.13 Vent-off the appropriate N2HP Regulator by turning the control handle counterclockwise until the regulator pressure gauge indicates zero.
5.9.14 CLOSE the appropriate desurger isolation and root valves ensuring the local desurger N2 gauge reads between 1950 and 2050 psig: A. 11 [21] Charging Pump: NG-39-1 [2NG-39-1],11 [21] CHG PMP DESURGER ISOL VLV NG-39-2 [2NG-39-2],11 [21] CH3 PMP DESURGER ROOT VLV B. 12 [22] Charging Pump: NG-39-3 [2NG-39-3],12 [22] CHG PMP DESURGER ISOL VLV NG-39-4 [2NG-39-4],12 [22] CHG PMP DESURGER ROOT VLV C. 13 [23] Charging Pump: NG-39-5 [2NG-39-5],13 [23] CHG PMP DESURGER ISOL VLV NG-39-6 [2NG-39-6],13 [23] CHG PMP DESURGER ROOT VLV l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES
$$NNaOb
*3 *TfNNU TITLE NUMBER:
%R (
$$y$ Jiy65%# LETDOWN, CHARGING, AND C12.1 REV:
!h- $:s - ge SEAL WATER INJECTION j7
%e Secti dssi,
'M Xf ~h1 Page 32 of 40 5.9.15 Check for desurger bladder failure as follows:
A. Check the desurger pressure tap drain: IE Nitrogen is vented, THEN the desurger bladder has failed. 1E a small amount of water is drained, THEN an isolation valve is leaking. B. IE Nitrogen is present at the desurger pressure tap drain, THEN initiate a work order for a failed desurger bladder. IE BLADDER FAILURE HAS OCCURRED, THEN DO NOT 7bMdN6h quWMp%ggg: [! OPEN THE PUMP SUCTION VALVE (PROTECTS THE PUMP gy*gjh?flig FROM GAS BINDING). 5.9.16 OPEN the appropriate charging pump suction isolation valve: VC-6-5 [2VC-6-5),11 [21] CHG PMP SUCT OPEN VC-6-6 [2VC-6-6],12 [22] CHG PMP SUCT OPEN VC-6-7 [2VC-6-7],13 [23] CHG PMP SUCT OPEN 5.9.17 CLOSE the appropriate charging pump discharge pressure tap after a steady flow of liquid is observed: PT-17119 [PT-17125],11 [21] CHG PMP DSCH PRESS TAP CLOSED PT-17121 [PT-17127),12 [22] CHG PMP DSCH PRESS TAP CLOSED PT-17123 [PT-17129],13 [23] CHG PMP DSCH PRESS TAP CLOSED 5.9.18 OPEN the charging pump discharge isolation valve closed in Step 5.9.2: VC-39-1 [2VC-39-1),11 [21] CHG PMP DSCH VC-39-2 [2VC-39-2],12 [22] CHG PMP DSCH VC-39-3 [2VC-39-3],13 [23] CHG PMP DSCH
PRAlRIE ISLAND NUCL8 EAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: fffhIfh[h
!j[$f!Mi .kjn$ LETDOWN, CHARGING, AND C12.1 gppzf;, ,og{js
$R$$ SEAL WATER INJECTION REV:
37 p 5.9.19 Independently verify the appropriate charging pump suction isolation valve is OPEN: VC-6-5 (2VC-6-5],11 [21] CHG PMP SUCT IV VC-6-6 [2VC-6-6],12 [22] CHG PMP SUCT IV VC-6-7 [2VC-6-7],13 [23] CHG PMP SUCT IV 5.9.20 Independently verify the appropriate charging pump discharge isolation is OPEN: VC-39-1 [2VC-39-1),11 [21] CHG PMP DSCH IV VC-39-2 [2VC-39-2],12 [22] CHG PMP DSCH IV VC-39-3 [2VC-39-3],13 [23] CHG PMP DSCH IV 5.9.21 Return the appropriate charging purnp control switch to NEUTRAL-CS-46292 (CS-49550),11 [21] CHG PMP NEUTRAL CS-46293 [CS-49551),12 [22] CHG PMP NEUTRAL CS-46294 (CS-49552],13 [23] CHG PMP NEUTRAL l l
PRAIRIE 12 LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES {["I6 ~[ TITLE NUMBER: Wh b if ND
-J
$ LETDOWN, CHARGING, AND SEAL WATER INJECTION 5.10 Charging Pumo Desurger Deoressurization REV:
C12.1 17 page 34 of 40 g hhhgg@ IN ACCORDANCE WITH DESURGER NAMEPLATES, f. ['. NITROGEN PRECHARGE PRESSURE MUST BE AT LEAST h
- a BETWEEN 55% AND 70% OF CHARGING PUMP
}$$g DISCHARGE PRESSURE. SINCE THE CHARGING PUMP
,. jj +i DISCHARGE CHECK VALVES LEAK, THE DESURGERS
$ l MUST BE PRESSURIZED AT ALL TIMES.
A i ( , fqf ""' - THE 55% TO 70% RANGd ASSUMES THE N2 iS CHECKED
.e 8
1 4 AND CHARGED WHEN THE FLUID SIDE OF THE j DESURGER IS DEPRESSURIZED. IN THIS WAY THE g j DESURGER BOOT EXPANDS PROPERLY WHEN THE h . . - . #"M
- m.:_gmar - -
} D DEPRESSURIZED WHEN RCS PRESSURE IS LESS THAN a g 250 PSIG. HOWEVER, AT CHG TO REGEN HX FLOWS OF
$ + GREATER THAN 115 GPM, THE PlPING HEAD LOSS
E CREATES A BACK PRESSURE AT THE PUMPS. SINCE 6 ./ THIS FLOW RATE IS UNEXPECTED, DESURGER
(( DEPRESSURIZATION IS NORMALLY RECOMMENDED. [ TfB + kk ! DURING MAINTENANCE TAGOUTS, DO NOT DEPRESSURIZE THE DESURGERS UNTIL THE PUMP Ms DISCHARGE VALVE IS CLOSED AND THE DISCHARGE PRESSURE IS BLED OFF. brewoJ@ 1 Mh. 5.10.1 OPEN the desurger isolation and root valves for the desired desurger. A. 11 [21] Charging Pump: NG-39-1 [2NG-39-1),11 [21] CHG PMP DESURGER ISOL VLV NG-39-2 [2NG-39-2],11 [21] CHG PMP DESURGER ROOT VLV I i
l l PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
- NORTHERN STATES POWER COMPANY OPERATING PROCEDURES l NUMBER
l ff3$0 hknh[(f[ TITLE l Nhk LETDOWN, CHARGING, AND C12.1 IP$$ REV: I l
$/ SEAL WATER INJECTION j7 i
Q~J{..<
.Ws;f Ssction s 4 %{p,q m 9 ih'!P;[n[NNj Page 35 of 40 B. 12 [22] Charging Pump:
i NG-39-3 [2NG-39-3),12 [22] CHG PMP DESURGER i ISOL VLV l l NG-39-4 [2NG-39-4],12 [22] CHG PMP DESURGER ROOT VLV C. 13 [23] Charging Pump: NG-39-5 [2NG-39-5],13 [23] CHG PMP DESURGER ISOL VLV NG-39-6 [2NG-39-6],13 [23] CHG PMP DESURGER ROOT VLV 5.10.2 Depressurize the appropriate desurger to approximately 5 psig by cracking OPEN the N2 line drain valve to the floor: NG-33-2 [2NG-35-13],11 [21] DSRGR N2LINE DRAIN NG-33-3 [2NG-35-14),12 [22] DSRGR N2 LINE DRAIN . NG-33-4 [2NG-35-15],13 [23] DSRGR N2 LINE DRAIN I 5.10.3 CLOSE the N2line drain valve OPENED in Step 5.10.2. 5.10.4 CLOSE the appropriate desurger isolation and root valves: A. 11 [21] Charging Pump: l NG-39-1 [2NG-39-1],11 [21] CHG PMP DESURGER ISOL VLV NG-39-2 [2NG-39-2],11 [21] CHG PMP DESURGER ; ROOT VLV l l L j
~
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES l 'dF;$in/' E*UEJ$P TITLE NUMBER: ! wn.tssi C dyw-; l K h]- l$; LETDOWN, CHARGING, AND C12.1 l b 6 SEAL WATER INJECTION REV: 37
't11977 ";aet@~~'
ectioNI$$?!? . Page 36 of 40 B. 12 [22] Charging Pump: NG-39-3 [2NG-39-3],12 [22] CHG PMP DESURGER ISOL VLV NG-39-4 [2NG-39-4],12 [22] CHG PMP DESURGER ROOT VLV C. 13 [23] Charging Pump: NG-39-5 [2NG-39-5],13 [23] CHG PMP DESURGER ISOL VLV NG-39-6 [2NG-39-6],13 [23] CHG PMP DESURGER ROOT VLV j 5.11 Placing _Signdby Filters In Service This procedure is used to place a standby seal water return or seal water injection filter in service and to remove the used filter from service. i 1 r
'jgag ;%(';jp/]
Y The letdown filter elements have been removed. The filter bypass valve is normally OPEN. 5.11.1 OPEN the appropriate standby filter inlet and outlet valves: A. VC-7-16 [2VC-7-16),11 [21] SEAL WATER INJECTION FILTER INLET OPEN j VC-7-17 [2VC-7-17],11 [21] SEAL WATER INJECTION FILTER OUTLET OPEN B. VC-7-14 [2VC-7-14],12 [22] SEAL WATER INJECTION i FILTER INLET OPEN VC-7-15 [2VC-7-15],12 [22] SEAL WATER INJECTION FILTER OUTLET OPEN I
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES MTQJ$%N~?M TITLE NUMBER:
%{[49f! '
ehe LETDOWN, CHARGING, AND C12.1 REV:
%?
p:hp! SEAL WATER INJECTION 17 l /W "j Q3;g 72QRQ Page 37 of 40 C. VC-6-1 [2VC-6-1],11 [21] SEAL WATER RETURN FILTER INLET OPEN VC-6-2 [2VC-6-2],11 [21] SEAL WATER RETURN FILTER OUTLET OPEN D. VC-6-30 [2VC-6-30],12 [22] SEAL WATER RETURN FILTER INLET OPEN VC-6-31 [2VC-6-31],12 [22] SEAL WATER RETURN l FILTER OUTLET OPEN 5.11.2 Remove the used filter from senrice by CLOSING the appropriate MANUAL valves. A. VC-7-16 [2VC-7-16],11 [21] SEAL WATER INJECTION FILTER INLET VC-7-17 [2VC-7-17],11 [21] SEAL WATER INJECTION FILTER OUTLET B. VC-7-14 [2VC-7-14],12 [22] SEAL WATER INJECTION FILTER INLET l VC-7-15 [2VC-7-15),12 [22] SEAL WATER INJECTION l FILTER OUTLET OPEN C. VC-6-1 (2VC-6-1],11 [21] SEAL WATER RETURN FILTER INLET OPEN VC-6-2 [2VC-6-2],11 [21] SEAL WATEP RETURN ; FILTER OUTLET OPEN l D. VC-6-30 [2VC-6-30],12 [22] SEALWATER RETURN FILTER INLET OPEN 1 VC-6-31 [2VC-6-31],12 [22] SEAL WATER RETURN FILTER OUTLET OPEN I L
PRAIRIE ISLAND Nuct. EAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES 3h [$ [ Mkb TITLE NUMBER: 3t;5 edhk LETDOWN, CHARGING, AND C12.1 ihyLA. f M! d SEAL WATER INJECTION REV: 37
!I Page 38 of 40 5.12 Checking Charging Pumo-Packing Leakagg This procedure is used to quantify any charging pump packing leaks, in running and/or non-running pumps,
- s. 3$$NEk IE the pump's packing leakoff to the NARDT piping does pp
[INOTEga#63$$k:[Mfh5h(g[;;::., NOT feel warm to the touch, THEN the pump is probably not leaking and therefore it does not have to be checked. 5.12.1 CLOSE the packing leakoff valve to the NARDT for the desired charging pump: VC-15-51 [2VC-15-51),11 [21] CHG PMP DRAIN TO NARDT VALVE CLOSED 1
\
DB 1 I VC-15-53 [2VC-15-53),12 [22] CHG PMP DRAIN TO NARDT VALVE CLOSED DB VC-15-55 [2VC-15-55],13 [23] CHG PMP DRAIN TO NARDT VALVE CLOSED 5.12.2 OPEN the packing leakoff drain valve to the plastic container (1/4" SS Whitey Valve - not tagged) for the desired charging pump. , 5.12.3 Time the packing leakoff for at least one minute. 5.12.4 Determine the approximate quantity of water by the markings on the container. 5.12.5 IE the leakoff quantity is > 0.5 gpm, THEN issue a Work Order. Visually try to determine which cylinder (s) is (are) leaking.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES
?Q,; W 5M ;G M$ TITLE NUMBER:
jh jh f LETDOWN, CHARGING, AND C12.1 REV: y!$@E% I 44d SEAL WATER INJECTION j7 f@7g;,, p,% if y- Secti- $,Q-5 , Page 39 of 40 i
$ IE the leakoff quantity is < 0..: gpm, THEN packing dous ggg,gpl lyggy; y
n t warrant replacement at this time. 5.12.6 CLOSE the packing leakoff drain valve to the plastic j container (1/4" SS Whitey Valve - not tagged) for the desired {
,. charging pump. l 5.12.7 OPEN the packing leakoff valve to the NARDT for the desired charging pump:
VC-15-51 [2VC-15-51],11 [21] CHG PMP DRAIN TO NARDT VALVE OPEN DB VC-15-53 [2VC-15-53],12 [22] CHG PMP DRAIN TO NARDT VALVE OPEN OB VC-15-55 [2VC-15-55],13 [23] CHG PMP DRAIN TO NARDT VALVE OPEN 5.12.8 IE any leakoff water accumulated in the plastic container, THEN drain it to the nearby floor drain. 6.0 ATTACHMENTS NONE
7.0 REFERENCES
7.1 Developmental References 7.1.1 Flow Diagrams: XH-1-38, Chemical and Volume Control System XH-1-39, Chemical and Volume Control System XH-1001-4, Chemical and Volume Control System XH-1001-5, Chemical and Volume Control System 7.1.2 Logic Diagram NF-40784, Chemical and Volume Control System l l t.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES NUMBER:
$ $qq 5$hh:
title
- h. .y g w$ LETDOWN, CHARGING, AND -
C12.1 4!MlM REV: y@y% ej@NiENH SEAL WATER INJECTION ' j7 WQ A , b"Ugg ti,djb ;j^1 l Page 40 of 40 7.2 Imolementing References 7.2.1 C12.1 AOP4, Alternate Letdown Flowpaths 7.2.2 F3-2, Classification of Emergencies 7.2.3 C3, Reactor Coolant Pumps 7.2.4 C12-1 [C12-5), Chemical and Volume Control Charging, Letdown and Seal Water 7.2.5 C12.5, Boron Concentration Control i 7.2.6 C7, Reactor Control System i l l l l l i
1 41493@$ JOB PERFORMANCE MEASURE gire1.0/9J 3 01Emra da741 WORKSHEET !.$gg$@$$$ SC 1 TASK TITLE: Review Prepared Isolation For Approval ! JPM NUMBER: ADMIN-2 Rev. O RELATED PRA None l INFORMATION (SEE PITC 2.3): , TASK NUMBER: 1190120301 K/A NUMBERS: 2.1.23 ; APPLICABLE METHOD OF TESTING: Simulato Performance: Actual Performance: Evaluation Location: Turbine Building: Auxiliary Building: Simulator Control Room: Other Anywhere Time for Completion: 15 Minutes TASK APPLICABILITY: SRO: RO: NLO: (Check all that apply) PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: APPROVED BY: DATE: Resp Grp: O Page 1 of 4 Assoc Ref: PITC TP 3.7
I
)
I l Review Prepared Isolation For Approvel l ADMIN-2 Rev. 0 l ) Operator: (SROI ROINLO) l j Evaluator: l
~ Date:
1 READ TO THE OPERATOR l I
' I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS:
. Unit 1 is in Cold Shutdown. . Essential CC loads are being supplied by Unit 2. . 11 CC Surge Tank is being taken out of service for maintenance, leaving it isolated and vented to atmosphere through MV-32088,"11 CC Surge Tank Vent".
1 I 1 INITIATING CUES:
. The SS directs you to review, per SAWI 3.10.0 section 6.10.3.b, the prepared isolation for the 11 CC Surge Tank.
PITCO-089 Page 2 of 4 Rev 5 10/98 , i l
l R: view Prepared Isolation For Approval l ADMIN-2 Rev. 0 l JPM PERFORMANCE INFORMATION ! Required Materials: Completed Isolation for 11 CC Surge Tank with one required manual . valve left off of the isolation. ! NF-39245-1. General
References:
5AWI 3.10.0, NF-39245-1 Task Standards: Isolation for 11 CC Surge Tar.k reviewed and valve CC-30-11 found to be required for addition to the isolation. Start Time:
.NOT.E.,iWiiiiis.60idingi,fEfaIUIitBE v ~. n uisti,B%s'siid.s~~EininiUiiW%.i,s,iE,n ng
~
x- , 109 prompting.theTexamineenTMcAll cues"are"oni, . . == n .k t doo Wen he~exsr actionsF [i : [knarisdk$si0liiglENA lNf$nhatiod(y[e[dEEItiAnhiriesjMRkaMAMUidd!!Nbdil6dd i
$0TEiCM6al siipiiWEiarliid Wisiiriht" 0516sillis"jisif666556sitsEh066sBFinshiftdWM
[fi36eetMstahdAM foidaNYjhiisai$i$ksShidsMINNiiMNM[6IlypMhddndi4M Performance Step: By using controlled plant drawings or performing a plant walkdown or both, Critical X (S-1) verify that the isolation is correct and adequate to ensure the protection of l plant personnel and equipment. Standard: Isolation reviewed and valve CC-30-11 found to be required for addition to the isolation. i Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: The candidate should report to the SS that, "a discrepancy was found in that CC-30-11 needs to added to the isolatian." At this point, inform the candidate that, "this JPM is complete." Stop Time: PITCQ-089 Page 3 of 4 Rev 5 10/98
TURNOVER SHEET INITIAL CONDITIONS:
. Unit 1 is in Cold Shutdown . Essential CC loads are being supplied by Unit 2. . 11 CC Surge Tank is being taken out of service for maintenance, leaving it isolated and vented to atmosphere through MV-32088,"11 CC Surge Tank Vent".
INITIATING CUES:
. The SS directs you to review, per SAW13.10.0 section 6.10.3.b, the prepared isolation for the 11 CC Surge Tank. -
l l PITCQ-089 Page 4 of 4 Rev 5 10/98
p: IIgolation Ids' 99-00026 v1 Status: DRAFT
Title:
~ REPAIR LEAKING CC' SURGE TANK I.L ~A2cc.Wrk' Doc: Oid: 135375
.Ir sted For:
PrGpared by: R:vicwed by:
- Equipment: Isolated:
-Equipment: 012-012,. CC SURGE TANK
-Alt-Id: .012-012 '
1
' System: CC - COMPONENT' COOLING Unit: 1 l Func. Sys: CC - COMPONENT COOLING {
Location: Bldg: Auxiliary' Building 1 Floor: ELEVATION 755 l Room:: J Remarks:- 1 Icolation: Tnatructions: ISOLATE 11 CC SURGE TANK; LEAVE VENT PATH OPEN Slocking/ Locking. Devices Removed?
'[-] CV-Air Supply Tag (s):
(-l:] Fire Protection Vlv Position Tag (s)
-[ ] Fuse Plugs. Installed R3ctoration:
. Instructions:
In3 tall: Blocking / Locking Devices '(per 5ACD3.10) [1 ].CV Air Supply Tag (s)
.[ JtFire~ Protection Viv Position Tag (s) 3
(.-] Fuse Plugs _ Returned to. Control Room l ['.] Partial -Restoration Attachment.(PING 1072)' .i' [ ] TemporaryJRestoration Attachment-(PING 7471)
=- -Tags,------------------------------------------------------------------------
Tcg* l' . . Type: HOLD Size: LARGE Handwheel. IV: N Status: NEW ; Equipment::CC-30-12, 11 CC RECIRC TO SURGE TANK !
' Alt Id: ._
l System: CC -LCOMPONENT COOLING. Unit: 1 l Func. Sys: CC -> COMPONENT COOLING ccation':1 Bldg:' Auxiliary Building-
' Floor: ELEVATION 703 '
Room: > Remarks: ABOVE-11 CC PUMP l l l
m eee This equipmsnt is not found in the Champs Equipment Master List Trg Pos: CLOSED
'Mrm Pos: OPEN emarks:
CSDS: IV: No: Tcg: 2 Type: HOLD Size: LARGE Handwheel IV: N Status: NEW Equipment: CC-19-1, 11 CC SURGE TANK OUTLET Alt Id:
. System: CC - COMPONENT COOLING Unit: 1 Func. Sys: CC - COMPONENT COOLING Location: Bldg: Auxiliary. Building Floor: ELEVATION ~755 Room:
Remarks:
*** This equipment is not found in the Champ,s Equipment Master List
.TEg Pos:-CLOSED Norm Pos: OPEN Remarks:
CSDS: IV: No: 55 3 , Type: HOLD Size: LARGE Handwheel IV: N Status: NEW Equipment: CV-31432, 11 CC-SURGE TANK MAKEUP WATER CV HANDWHEEL , Alt Id: ! System: CC - COMPONENT COOLING Unit: 1 ) Func. Sys: CC - COMPONENT. COOLING Location: Bldg: Auxiliary Building Floor: ELEVATION 765 I Room:'- Remarks:
*** This equipment is not found in the Champs Equipment Master List tag Pos: CLOStD Norm Pos: OPEN Remarks: LOCAL OPERATOR CLOSED l
CSDS: ; IV:'No: I Tags 4. Type: HOLD- Size: LARGE Handwheel IV: N Status: NEW Equipment:'MV-32088,- 11 CC SURGE TANK VENT Alt Id: System:'CC -- COMPONENT COOLING Unit: 1
'mc . Sys: CC - COMPONENT COOLING l ocation:' Bldg: Auxiliary Building Floor: ELEVATION 755 Room: .
l Remarks: VENT PATH
*** This equipm:nt is not found in the Champs Equipment Master List
-Tcg Pos: OPEN "onn Pos: OPEN
.emarks:
CSDS: IV: 'No: T gs 5- Type: SECURE Size: SMALL IV: N Status: NEW Equipment: MV-32088, 11 CC SURGE TANK VENT Alt'Id: System: CC - COMPONENT COOLING Unit: 1 Func. Sys: CC - COMPONENT' COOLING Location: . Bldg: Auxiliary Building Floor: ELEVATION 735 Room: Remarks: CONTROL ROOM
*** This equipment is not found in the Champ,s Equipment Master List . Tag Pos: NEUTRAL Norm Pos: NEUTRAL Remarks: VENT PATH CSDS:
IV: No:- TL 6 . Type: SECURE Size: LARGE Test Dead IV: N Status: NEW Equipment: BKR 1N1-Z3, SPLY BKR FOR MV-32088 11 CC SURGE TNK VENT
-Alt Id: 193-8 System: CC. - COMPONENT COOLING Unit: 1 Func. Sys:'CC - COMPONENT COOLING ' Location: Bldg: Auxiliary Building Floor: ELEVATION 755 Room:
Remarks:
*** This equipment is not found in the Champs Equipment Master List Tcg' Pos: OFF . Norm Pos: ON Remarks. 1 I
CSDS: ; Tsot Dead: "
.IV: No:
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.:(9&iM D J JOB PERFORMANCE MEASURE d68hlI9f91 l
7 [d$d$ WORKSHEET p if3)d M R@ TASK TITLE: Prepare For Entry into A Locked High Radiation Area JPM NUMBER: ADMIN-3 Rev. 0 , RELATED PRA None 1 INFORMATION l (SEE PITC 2.3): TASK NUMBER: 1190100301 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Sim'ulate Performance: Actual Performance: Evaluation Location: Turbine Building: Auxiliary Building: Simulator. Control Room: Other Time for Completion: 20 Minutes TASK APPLICAB' JTY: SRO: RO: NLO: @ (Check all that apply) ,, PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: APPROVED BY: DATE: Resp Grp: O Page 1 of 7 Assoc Ref: PITC TP 3.7
I l Prepare For Entry into A Locked High Radiation Ar:2 l ADMIN-3 R:v. 0 l Operator: (SRO / RO / NLO) Evaluator: _. Date: READ TO THE OPERATOR l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.' INITIAL CONDITIONS: o Water leakage has been reported in the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area. INITIATING CUES: o The SS directs you to investigate and determine the source of leakage. 1 l 1 t l PITCQ-089 Page 2 of 7 Rev 5 10/98 l
l Prepara For Entry into A Locked High Radittion Arca l ADMIN-3 Rev. 0 l w JPM PERFORMANCE INFORMATION Required Materials: None. General
References:
F2 Task Standards: Required preparations made for entry into and the location indicated for the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area. Start Time: m , NdTEiyW_ r m.~ hen - d o.. pro,Ei.r,ing,t' Eval _f_ -
,_7,#he.--
. m..
t exa m,-,__,,mb-.m_. issrm,-. c sd, y,gy to av,o 9 nm i
$w@bwarrant ce,m p.ro, m, ptin,.. ~. ,
receiving,am,in,ua,or, g n.~the.n:,e.x-#eem
- n ~ Typ' c,a,lly
_theJrd, m ,n .._. d.e_d whm.m nn cues,'are'o,.~ly Cues to.mus m en .n.~.m -~ nn e,the4xa..,m ormatiodi4dhe: exam,inee,lpoksX,asksfor.theIndication)2bi; n.,onsydcijm.#,
~ nc .
n -. - . . ,, , . n. iNO,TEs,C,r,tti_ sc cal 's oF,
%gdimsjt the,tep_s~aren,ma,,rk,e.di_sith ~w -, ~ - na e-m - , ,
an 'T.n! below,,ith_o' . . .,,,_ , _
,n,
. jtandaMlotanyylitical;stej[shallss, bit]hfa,d,u_m,RthlOJEWddshs,Wd$aM
- y ~
Performance Step: - Obtain the Locked High Radiation Area key. Critical X (S-1) Standard: Locked High Radiation Area key obtained. I TEUAl % $$ihiNM 9 IY"3NIE a % k di k_ M m M iy %z m e $,lk,slI65EI65MF vomam asw. T k 5 SIS $ 7 3 s;.n s aA mm.m a, m ago. _ffico mm % % ,a s a w a m~a m m www-c... wasmusamimg
;E.va n r gy. wm 997y x lu,alo,r, Cue:us;m ngKey,is.;oMv wemv vemn ma ained.7,ppan;3smgm mapaqm;p tMdni.hsi!dadanmatWGMGEMimdmaEEMsdaaiLWadAs#MEWisadMMasn&p%p4mwqu,ggg gmpgggma;ww MM Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 3 of 7 Rev 5 10/98
l Prepara For Entry into A Locked High Radiation Area l ADMIN-3 Rsv. 0 l Performance Step: At Access Control, determine the RWP for Locked High Radiation Areas. Critical Standard: RWP 11 determined to be the RWP for Locked High Radiation Areas (Barrel Yard - Hot Drum Storage Area). l
,Eva,Us,t_or T Note:m, s,,,7_pn.
....m ._. ._ , . . .
eg e.,, ,,m, m ,. wu uMiMan M Mawwwa:asm;ask i Th_e:can,dida,te may &MMtekawwk RpSfo,ra,_pplic_ab,le RWP,.5 awa& apn N y ,AE e y m .m e.m,m, 3 m - y -,,. a ator E,v._, w Ew m am e lum,mrdu-,m,w e.krmmm np sdy- wo m,_d p aske aen, ir,_iform candida,wie;th at ,mp#RWPMqis.th e' app ableL RWP."r.r-
. _. li,c,odamegammu, ,
n M Performance: SATISFACTORY UNSATISFACTORY Comments: Pe2ormance Step: Review the RWP for entry conditions and requirements. Critical X (S-2) Standard: RWP conditions and requirements reviewed and the following determined:
- 1. Dose rates need to be known or survey meter has to be used to survey 1 the area. !
- 2. Continuous RPS coverage is required for entry.
- 3. A pre-job briefing is required to review dose rates and allowable dose. l
- 4. Stay time has been converted to your individual dosimeter Dose Alarm.
- 5. TLD and dosimeter required for entry with Dose Rate Alarm set at 5000 mR/hr and Dose Alarm set at 100 mrem.
- 6. Normal Full Suit-up required unless authorized less by RPS.
, , _ . . . _ ~ . . , , ,. _ _ . . , _ _ , , , _. .__m... _, .Ev.alua_ tor No._ y.,m,t,e,:$m W/*Can,dida,_te'm,. a_y:'us oo_k,tto c eterm ,=._ine.'if, dose,ra,tes~areT ji&&gsi6M&Magdigurrently,knowDAe!
r 4 #m survey m _ _:mapi_n_1b,.___l
-m .. -
r.may;consialtWith;RPA,Eg~ ; Ah,nhim
'w- Evil 6AkiECUsIZh%59fsildifd/I6f6&hTaHalditiWi(f6Ghii6fB6iiis7Eiss"dNip5K5d'Afilia?
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- = - ~ -
9 M, nyn -A dae , 4 la Anfran wjo,the=; ce area.: A s. m , & 2 ,, Performance: SATISFACTORY UNSATISFACTORY Comments: PITCQ-089 Page 4 of 7 Rev 5 10/98
l Prepara For Entry into A Locked High Radiation Area l ADMIN-3 Rav. 0 l Performance Step: Request coverage and pre-job brief from RPG. Critical X (S-2) Standard: RPS coverage assigned and pre-job brief completed. m m.~ - -
.c
, Evaluator . Nc, t pre m ont uousL m,
!cowawNote~@pwMr%%=-w&aayFghsaa&w pp w.ge wp ww a cWahnau ummyyA,,t,:as'RPS_to o# %g- w m siinEMsggMMWcoverage ws e m, m. ,-,,
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following,; a f.,o.ta,tions:fpm z ,., m.n attach,e n specific. mi W over;
. + -
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u MM;.g 3 , .
, s,., .
.at the BarrelYardEHot~DrumL gA e
Wam ,/ w;A,a's",,as%w% , w Cgga m: eww m survey; e,:ww map Area;w m e n% awilllie posted loc _ ally ~for,c--ww
. rates e are M42.e, low, able dose ume reviewed for;thejob will mhe'20,urrent m.in Jmdose n m m w ,e ann wn R&
'a ~
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/ m EhMsMsM Ahasentjo,the area for,c_ontinuous;coveragen ; Mh > y, ag:g ni Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Obtain electronic dosimeter and log-in on the Access Control Computer Critical X (S-2) System. Standard: Dosimeter obtained and Access C : Computer System logged-in on.
.w.,,. .-. , .- .n ,n+, n--. - .- .n .na w EvaluatorNots:~S . .ames%wwC
.la Candidate'sh,ould l_og,WL in on t M a. s ;-an nhe standard RWP for~operat, o MJ _ au Mn ii;; Ma anna 1.
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m Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 - Page 5 of 7 Rev 5 10/98
l Prepara For Entry into A Locked High Radiation Arca l ADMIN-3 R v. 0 l Performance Step: At the Barrel Yard - Hot Drum Storage Area entry gait, remove the lock and Critical X (S-2) open the gait. Standard: Barrel Yard - Hot Drum Storage Area entry gait lock simulated reme W and location of Locked High Radiation Area indicated. EE 0 mum 6fAE@YlyE MTlii[di6didits*need]661Fiddidsis"fEW"B6EslindVHBf6iue"@f pfR@ C.
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ss ywdg;jp A, h aaM!se "",, w %n &ag[within;ls:This"d/o =u.,erf Qwfwn. a ~ ..vn may be"p , m -med su ; .m,ap.-as a, - p 7v m . m s reference.,an r po!nbng tA.,the;a.m,grea; m g m a g,. , g g g;g ; a %
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s ::c ... . ..-,.a , e.- ..- .....m. . -:- -. : :. .,. c-m ,,rn.....e ,i,., -..---...-y,., Cuen , NF c When ~the candidats indicates',that'he/she wou;ld rsm,;,q .ove Glock onf ,. 4
!Esaluator,gf
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<p=..a.ns w,mms e m vn- ha :ggEadiat, wn locati.on is;all,te ion vmn Are.ac nm ~ n.xnnuw ted.h amas,,nsEdgng ii Performance: SATISFACTORY UNSATISFACTORY Comments:
i
. Terminating Cues: When the location of the Locked High Radiation Area within the Barrel Yard
- Hot Drum Storage Area has been indicated, inform the candidate that, "this JPM is complete."
Stop Time: PITCQ-089 Page 6 of 7 Rev 5 10/98 l
)
TURNOVER SHEET -INITIAL CONDITIONS: o Water leakage has been reported in the Locked High Radiation Area within the Barrel Yard - Hot Drum Storage Area. INITIATING CUES: o The SS directs you to investigate and determine the source of leakage. I PITCO-089 Page 7 of 7 Rev 5 10/98
BM I JOB PERFORMANCE MEASURE sMiift/9{ M WORKSHEET $[M$fAE$$ 3F TASK TITLE: Initiate Emergency Local Evacuation JPM NUMBER: ADMIN 4S Rev. 0 l RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 0850110101 l j K/A NUMBERS: 2.1.23 1 APPLICABLE METHOD OF TESTING: l Simulate Performance: Actual Performance: Evaluation Location: Turbine Building: Auxiliary Building: 1 Simulator- Control Room: l Other: i Time for Completion: 5 Minutes l TASK APPLICABILITY: SRO: RO: NLO: i (Check all that apply) l PREPARED BY: Mark J Jones DATE: 3/24/99 REVIEWED BY: DATE: APPROVED BY: DATE: l l l Resp Grp: O Page 1 of 7 Assoc Ref: PITC TP 3.7 i l l l
l Initiata Emergency Local Evacuation l ADMIN 4S R:v. 0 l I Operator: (SRO / RO / NLO) ; Evaluator: Date: READ TO THE OPERATOR I will explain the initit.1 conditions, which step (s) to simulate or discuss, and provide initiating cues. l When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: ! o A steamline break from Unit 2 has occurred in the Auxiliary Building. o CAM alarms and fire alarms have been received, which indicate that steam is causing a hazardous atmosphere inside the Auxiliary Building. INITIATING CUES: l o The SS directs you to initiate a local evacuation of the Auxiliary Building due to a steamline break ! per F3-9, Section 7.2. o Report completion to the SS. l l PITCQ-089 Page 2 of 7 Rev 5 10/98 l L _
l Initiata Emergency Local Evacuation l ADMIN-4S Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
F3-9 Task Standards: Local evacuation of the Auxiliary Building initiated by actuation of the evacuation alarm and announcement over the public address system.
' Start Time:
HDTEiWhiiiWhi6GlaiiiYiiiiGif6EDU3ENeiiisi35iliiid7EEifi~6sG iienas Ty iestis.20sss,eshipbNnik.v=E.n w~p-, W@nprompshs:tn n,senstmation(i.elthelexamineeJooks"otasksf6ttik w~ n - - ~n ~nrv isa n n.,iM5is n i EwtmwarrantreceivingLthejnf i ehdicati sQsd,
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NOTE _iC.O. U_c a. I.,,, . w tho' __, _ _st.e. p_nu, mb, l . b, MnmeetLthst_eP_s ar,e'e_n,_arked_ wit,h_a, e standardfotanysri.ticaljtepjhall
,,,n .
.n result n,"X,"iti.o.
lo,., J y inf,ai!GMMthisy@d,,e.rK id_n,.nie l Performance Step: Determine the appropriate assembly area for accountability. Critical X (S-1) Standard: Access Control HP Office determined to be the appropriate area for accountability for evacuation of the Auxiliary Building. l Performance: SATISFACTORY UNSATISFACTORY Comments: , 4 Performance Step: Sound the evacuation alarm. Critical X (S-1) Standard: Evacuation alarm sounded by momentarily placing the EVACUATION ALARM switch to the "ON" position. Performance: SATISFACTORY UNSATISFACTORY Comments: ._ PITCO-089 Page 3 of 7 Rev 5 10/98
l Initiata Emergency Local Evacuation l ADMIN-4S Rsv. 0 l Performance Step: Announce over the public address system the location of the problem and Critical X (S-1) any evacuation instructions. Standard: The following announced over the public address system:
" Attention, all plant personnel. There is a steamline break occurring in the Auxiliary Building. All personnel should evacuate from the Auxiliary Building and go to the Access Control HP Office for accountability. Stay clear of the Auxiliary Building until further notified."
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Repeat the message to ensure that all personnel are informed. Critical X (S-1) Standard: The following announced over the public address system:
" Attention, all plant personnel. There is a steamline break occurring in the Auxiliary Building. All personnel should evacuate from the Auxiliary Building and go to the Access Control HP Office for accountability. Stay clear of the Auxiliary Building until further notified."
Performance: SATISFACTORY UNSATISFACTORY Comments: ! Terminating Cues: The candidate should report to the SS that, "F3-9 step 7.2.1 is complete." At this point, inform the candidate that, "this JPM is complete." Stop Time: ___ PITCQ-089 Page 4 of 7 Rev 5 10/98
r I initiatt Emergency Local Evacuation l ADMIN-4S R v. 0 l I SIMULATOR SETUP l Instructor Guide: ( o initialize the simulator to any stable IC. o Place the simulator in "RUN". i l 1 l l PITCQ-089 Page 5 of 7 Rev 5 10/98 I
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F-TURNOVER SHEET INITLAL CONDmONS: l o A steam line break has occurred in the Auxiliary Building. o CAM alarms and fire alarms have been received, which indicate that steam is causing a hazardous atmosphere inside the Auxiliary Building. INITIATING CUES: o The SS directs you to initiate a local evacuation of the Auxiliary Building due to a steam line break per F3-9, Section 7.2. o The SS directs you to report when you have completed F3-9, Section 7.2. PITCQ-089 Page 7 of 7 Rev5 10/98
\
4 INITIAL SUBMITTAL OF THE WALKTHROUGH JPMS FOR THE PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 i l l l l i l i
. J
3
.iTrit+ b 1 1: JOB PERFORMANCE MEASURE t?dpl98
,[Mdd[#[ WORKSHEET Be$s@N5M$
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TASK TITLE: Withdraw Shutdown Bank B l l JPM NUMBER: SIMUL-1 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 0010180101 l K/A NUMBERS: 2.1.23 ' APPLICABLE METHOD OF TESTING: Simulate Performance: Actual Ferformance: I 1 l Evaluation Location: Turbine Building: Auxiliary Building: Simulator: Control Room: Other: I Time for Completion: 5 Minutes TASK APPLICABILITY: SRO: RO: NLO: (Check all that apply) PREPARED BY: Mark J Jones DATE: 3/25/99 REVIEWED BY: DATE: APPROVED BY: DATE: Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
l l Withdraw Shutdown Bank B l SIMUL-1 R::v. 0 l Operator: (SRO / RO / NLO) Evaluator: Date: READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: e RCS heatup is in progress per 1C1.2. o As directed by 1C1.2 step 5.1.7.H, shutdown banks are being withdrawn per 1C5. o Shutdown bank A has been fully withdrawn. o initial N31 and N32 countrate prior to Shutdown Bank A withdrawal was 500 cps. INITIATING CUES: o The SS directs you to fully withdraw shutdown bank B per 1C5 beginning at step 5.2.6. j o Report completion to the SS. PITCO-089 Page 2 of 8 Rev 5 10/98 L J
l l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l JPM PERFORMANCE INFORMATION Required Matenals: None J General
References:
1C1.2,1CS Task Standards: Shutdown bank B fully withdrawn to 228 steps. Start Time: _ y __, ,,_
-s rov ing r must rc
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_A_ M ; m' m:m.s , I 1 l Performance Step: Position CS-46290, ROD BANK SELECTOR, to the "SBB" position. Critical X (S-1) 4 1 Standard: CS-46280 placed in the "SBB" position. Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 Page 3 of 8 Rev 5 10/98
l l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l Performance Step: Pull CS-46281, IN-HOLD-OUT lever, to the "OUT' position. Verify the Critical X (S-2) digital OUT direction lamp is LIT. Standard: CS-46281 held in the "OUT' position and digital OUT direction lamp is verified LIT. [EUal65tMNoN?[0E g7 $T$ddh6al jisrt'bf;tliis;stidis!!nidingCSy281 in tis?OUT6positidnN umaamasarih-maomAmmanw.w . en muaa.m uu au_ . .a 4 me ; m Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Verify shutdown bank B group 1 step counter indicates the withdrawal Critical steps. Standard: Shutdown bank B group 1 step counter verified to be indicating the withdrawal steps. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Verify the control rods in shutdown bank B are moving on the Rod Position Critical Indication System indicators. Standard: Shutdown bank B rods are verified to be moving as indicated on the Rod Position Indication System. Performance: SATISFACTORY UNSATISFACTORY Comments: l l PITCO-089 Page 4 of 8 Rev 5 10/98 i
1 l Withdraw Shutdown Bank B l SIMUL-1 Rev. 0 l . I 1 1 Performance Step: Withdraw shutdown bank B rods to 228 steps. I Critical X (S-3) Standard: Shutdown bank B rods are withdrawn to 228 steps, then CS-46281, IN-HOLD-OUT lever, is released. LE#aldsi6FN6teins cami:A n h asea, PWYTindflil6Albait'of s aw acw h mewee dthlistsiilil6 m,eme,msmc WlitxnanMY6dit6"228's@sh gs;,m Agn a '77 I l I Performance: SATISFACTORY UNSATISFACTORY l 1 Comments: 1 Terminating Cues: The candidate should report to the SS that, " shutdown bank B has been fully withdrawn." At this point, inform the candidate that, "this JPM is complete." l l Stop Time: 1 1 I PITCO-089 Page 5 of 8 Rev 5 10/98
l Withdraw Shutdown Bank B l SIMUL-1 R;v. 0 l , SIMULATOR SETUP l Instructor Guide: ) i o initialize the simulator to IC-5. o Place the simulator in "RUN". o Fully insert shutdown bank B. o Place CS-46280, Rod Bank Selector, to the "SBA" position. o Place the simulator in " FREEZE". o When the candidate is ready, place the simulator in "RUN". I l i PITCO-089 Page 6 of 8 Rev 5 - 10/98
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i TURNOVER SHEET l lNITIAL CONDITIONS: l c RCS heatup is in progress per 1C1.2. I l o As directed by 1C1.2 step 5.1.7.H, shutdown banks are being withdrawn per 1C5. o Shutdown bank A has been fully withdrawn. o initial N31 and N32 countrate prior to Shutdown Bank A withd'wal was 500 cps. l INITIATING CUES: o The SS directs you to fully withcraw shutdown bank B per 1C5 beginning at step 5.2.6. o Report completion to the SS. l l l l i l l PITCO-089 Page 8 of 8 Rev 5 10/98 l-A
l JPM:1 Operator: JPM QUESTION (AnswerSheet) QUESTION 1 System: CRD
Subject:
- l Startup Reset Switch Response K/A & Rating: 001K402 3.8/3.8 Given the following Unit 1 conditions:
-Reactor Power is 100% MOC.
-Rods are at the normal position.
- The RO inadvertently places the ' Rod Control Startup' switch to
_.. Question:; STARTUP. The RO then places the ' Bank Selector' switch to MANUAL and places the 'IN-HOLD-OUT' switch to the OUT position. When rod motion STARTS, what will the Bank Overlap Unit (counter) ! , indicate ( 3M Bank A = 128 ( Answer: Bank B = 128 Bank C =.128 ! Total = 384 ! B5 Rev 2 Refemnce: 1CS, Sect 5.3, P. 6, Rev 4 j l Reference Material Use: - l Yes @ No O l Pedigree: . l New ' CANDIDATES RESPONSE: SAT: UNSAT: I l l 1 2
f , JPM: 1' OPerator: JPM QUESTION (Answer Sheet) l l QUESTION 2 System: CRD
Subject:
- l Rod Insertion Limits K/A & Rating: 001A302 3.7/3.6 Unit 2 is at 70% power.
Question: By how much (in rod steps) will the Rod insertion Limit change if power is reduced tc 35%? Answer: 84 +/-5 Reference *- - Technical Specification Core Operating Limits Report, Unit 2 Cycle 18, Fig 4 Curve Book, Fig C1-8 l Reference Material Use: l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: l l l I
1 JPM QUESTION 2 JPM:1 Unit 2 is at 70% power. By how much (in rod steps) will the Rod insertion Limit change if power is reduced to 35%7 l l J
JPM QUESTION 1 i JPM:1 Given the following Unit 1 conditions:
-Reactor Power is 100% MOC.
-Rods are at the normal position.
The RO inadvertently places the ' Rod Control Startup' switch to STARTUP. The RO then places the ' Bank Selector' switch to MANUAL and places the 'lN-HOLD-OUT' switch to the OUT position. When rod motion STARTS, what will the Bank Overlap Unit (counter) indicate i
)
I 1 i i
j T@'M. @ 2 JOB PERFORMANCE MEASURE gi m526iM0/gt innMl:23 WORKSHEET fpMMk TASK TITLE: Alternate In-Service RHR Loops JPM NUMBER: SIMUL-2 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 005.ATI.18 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Simulate Performance: Actual Performance: Evaluation Location: Turbine Bu;lding: Auxiliary Building: Simulator: Control Room: Other: Time for Completion: 11 Minutes i TAOK APPLICABILITY: SRO: RO: NLO- > (Check all that apply) l l PREPARED BY: Mark J Jcnes ,_ DATE: 3/25/99 REVIEWED BY: DATE: l i APPROVED BY: DATE: Resp Grp: O Page 1 of 11 Assoc Ref: PITC TP 3.7
g l Alternat7 In-Service RHR Loops l SIMUL-2 R:v. 0 l ' Operator: (SRO / RO / NLO) Evaluater: Date: READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. i When you complete the task successfully, the objective for this job performance measure will be ! satisfied. INITIAL CONDITIONS: o RCS is in Cold Shutdown at 130 *F. o 12 RHR pump is running. l INITIATING CUES: o The SS directs you to shift from 12 RHR pump and heat exchanger in service to 11 RHR pump and heat exchanger in service and place 12 RHR pump and heat exchanger in standby per 1C15 section 5.3. o Report completion to the SS. i PITCO-089 Page 2 of 11 Rev 5 10/98
l Attemats in-Service RHR Loops l SIMUL-2 Rev. 0 l ; s JPM PERFORMANCE INFORMATION Required Materials: None General
References:
1C15 Task Standards: 11 RHR pump and heat exchanger in service,12 RHR pump stopped. Start Time: w,,n c n n.. , ..
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Performance Step: Start the standby CC pump. Critical J Standard: Both CC pumps verified running. l 7"'+tTi&2q .', ~
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5 Wild UtsisMdwfMNOMSid$!$$1d@MdW.kh@bd$14N!biSE,S11 $$g/8dA a dSiEUM!bdSSDMNS$1 air.O,: i _ f c 1 ileIa d/2 i iM.h- dub.: ) .-.. Vrs dUldii . Performance: SATISFACTORY UNSATISFACTORY Comments: l l l i i PITCO-089 Page 3 of 11 Rev 5 10/98 l 1
I l l l Attemata in-Service RHR Loops l SIMUL-2 Rr,v. 0 l Performance Step: Open the standby RHR HX CC inlet valve. Critical l I Standard: 11 RHR HX CC inlet valve MV-32093 opened by placing CS-46023 in the OPEN position; red light lit, green light extinguished. Performance: SATISFACTORY UNSATISFACTORY l l Comments: i Performance Step: Verify CC flow through the standby RHR HX. j Critical l l Standard: 11 RHR HX CC flow verified using 4102002 (11 RSDL HX CC INLT Flow) and 4102001 (11 RSDL HX CC OUTL Flow). I l asamenman mi! 3CDT6@AtAEfd issfi6iiidtNiiEsd52d00'IsidB60"giMEPF7F"$$7!T7a
$valus6fM$i@sie$EI$sucGaminasemen:suswnnadh2isi:!!asaxhsmagadebidi Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify the standby RHR HX outlet flow control valve is closed. Critical Standard: 11 RHR HX outlet flow control valve CV-31235 verified closed by observing 100% output on 1HC-624. l Perfonnance: SATISFACTORY UNSATISFACTORY l l Comments: __ l PITCO-089 Page 4 of 11 Rev 5 10/98 I J
F l. [ l Alternata In-Service RHR Loops l SIMUL-2 Rsv. 0 l Performance Step: Verify the RHR HX inlet and outlet crossover valves are open. Critical i Standard: Aux Building Operator requested to verify RH-2-3, RH-2-4, RH-2-5, and RH-2-6 are open. a ~. . .
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a n. .. va WF STh ,b,o,,oth,o,per e ator,wiRac
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. .a 2_5.Fand RlL12!.6 g a"*N"t"m"" ^am""a"g""u" ope"ng"u",u_i
~m;g""w" .a""g' Performance: SATISFACTORY UNSATISFACTORY Comrnents:
Performance Step: Start the standby RHR pump. Cdtical X (S-1) Standard: 11 RHR pump started by momentarily placing CS-46134 in the START position; red light lit, green light extinguished.
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mp,%m .o yaction
==nwn=xwwwylarm is required for.tlus unle=ss s,ig=s=nof cavitatio=n.
ns sis.n o w ,ste ex.mnd i
+ne .m a,.
M:u
-e~q m& , m.a mc
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- n. w ndidateuw.n + yinot.s.
may;orma. top s.~wn+n at this nt andreviewthe:Ala+rmF wn
. _ _A r. _ m m *o h_ _G mWRe,sp> o_nse Procedure.
m wnw w.nwmns iontu_ _Ing_o_n_f_am_il.iari_ty._.with.t_h._is:co_ndit_. Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-08; Page 5 of 11 Rev 5 10/98
j Alternata In-Service RHR Loops l SIMUL-2 Rnv. 0 l l Performance Step: Verify CV-31237,11/12 RHR BYPASS FLOW, maintains the desired total Cr'tical RHR flow. Standard: Total RHR Ilow verified to be approximately 2000 gpm by observing 1FI-626. Performance: SATISFACTORY UNSATISFACTORY Commente: __
~
1 Performance Step: Open oncoming RHR HX outlet flow control valve 5%. Critical l l Standard: 11 RHR HX outlet flow control valve CV-31235 opened 5% by adjusting 1HC424 to 95% output. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Verify the oncoming RHR HX function by observing RHR HX outlet Critical temperature,1Tl422 (local) is reading lower than 1TI-630, RCS HOT LEGS TO RHR (red pen). Standard: Aux Building Operator requested to report 11 RHR HX outlet temperature as indicated on 1TI-622 and this temperature then verified to be lower than RCS Hot Legs to RC' temperature from the red pen on 1TR-630.
, . _ ~ -,, y .m.-- ,,
_,_,ysm'tempera ,m u ,, _ y. _ m.. 7 .
., , tu,,r,as e irid.,,.~s,,yd on;1T1422ish ,_,=.-m6u_ld belPML LEvaluator,
- Note:W9Mya w 11RHRLHXcutlet on mm ww mmr ica m-~ M s
mme a;, e es ,w%W y r, - repolted, +annmg=me as so v=alue c- Minhtly yg lowe,rM- an mS RCmHot v m.x nww # Leg to RHRm - J." J h ucu w attempediituregggg, a;s46=g qw rwg.gigh,% wg;s , ma sg c
. < . . _ . ~ . . . m= ~ ..- - ,
m,_ .m. .....,m., _ , , , ._ . , _ . ... iEv,a,luator,C,ue:P
, ,mr ,
?,, M. a yins, Aux
,n_Bdilding, 'Operatoir,,'f11?RHR1HX,ciutlet temperature'as,Fw-me,.- . . . . . _c.-~.- m .s -- . .
we& 3khenLuw ME$hdi $%_onjTl422 ism %%ng-,.,r ygM'Lun,t, L, O7 l iTa ? C g ' Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 Page 6 of 11 Rev 5 10/98
i 1 l Alternats in-Service RHR Loops l SIMUL-2 Rav. 0 l l Performance Step: Gradually shift RHR cooling to the oncoming RHR HX by opening the outlet Cdtical X (S-2) flow control valve while simultaneously cloeirg the outlet flow control valve for the offgoing heat exchanger. Observe CV-31237,11/12 RHR BYPASS FLOW, maintains the desired RCS temperature. l 1 I Standard: 11 RHR HX outlet flow control valve CV-31235 is opened by lowering the l output on 1HC-624 while 12 RHR HX outlet flow control valve CV-31236 is l simultaneously closed by raising the output on 1HC425. During this l operation, total RHR flow is maintained at approximately 2000 gpm as l indicated on 1Fl426. [ IE9EfuiiEN6fsISETI*MRHWdisi6 narEssmandi4emmaammesimscansanes@wuK ainhaA nN7VIC Ell 6tiffl6WiliBGid'tidisppi6Mfiat&ly"2000 gp#na meh ! Performance: SATISFACTORY UNSATISFACTORY ? 1 ! Comments: l l l Performance Step: When the offgoing RHR HX ot2iet flow control valve is closed, then verify Critical the oncoming heat exchanger is maintaining the desire RCS temperature. l 1 l , Standard: When 12 RHR HX outlet flow control valve CV-31236 is closed, verifies RCS temperature is maintained within approximately 5 F of starting temperature as indicated on 1TR-630. 1 I Performance: SATISFACTORY UNSATISFACTORY Comments: i Performance Step: Stop the offgoing RHR pump. j Cdtical X (S-3) Standard: 12 RHR pump stopped by mornentarily placing CS-46185 in the STOP position; green light lit, red light extinguished. Performance: SATISFACTORY UNSATISFACTORY Comments: l PITCO-089 Page 7 of 11 Rev 5 10/98 j
)
J l Alternata In-Service RHR Loops l SIMUL-2 Rcv. O ] l Performance Step: Verify CV-31237,11/12 RHR BYPASS FLOW, maintains the desired total ) Critical RHR flow. l l 1 Standard: Total RHR flow verified to be approximately 2000 gpm by observing 1 FI- ' 626.
- - -- , . _ . , - . , _ . . _ , .~.. - . .. . luator
- Eys - - Note:FD~", > " a RHR&c .,. . sered' total flowishould be approximately+2000'gpm.W_.- =.W' ?'
ie m suk2m s;a u m :'11 r!!!saa s!we mus m u nsa m u d e s em e s s nasa m m ? s!" Performa n.r: SATISFACTORY UNSATISFACTORY Comments: Performance Step: If it is desired to stop one CC pump, then perform the following: Critical Standard: Both CC pumps left running. I
. .s.m z,. w-LEvalu_9 tor Cu,_e:g,g,a m Malf:aske -,.,d_
ero,.port
... that -,r " itis-ssise+d md- - -
to'l~ea~ve ve-e~ both"'~CC pumps' running. n a u s m w s h : m a n a t h a n ,u m ^ m a E scsna m asas a;ma m a daez m l Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: The candidate should to the SS that,"12 RHR pump and heat exchanger are in service, and 11 RHR pump is stopped. At this point, inform the candidate that, "this JPM is complete." Stop Time: PITCO-089 Page 8 of 11 Rev 5 10/96
l Alternata In-Service RHR Loops l SIMUL-2 Rev. O l SIMULATOR SETUP instructor Guide:
. Initialize the simulator to 10-2.
. . Place the simulator in "RUN".
. Ensure CV-31237.11/12 RHR BYPASS FLOW, is in " AUTO" and maintaining total RHR flow at 2000 gpm.
. Ensure ERCS screen RH1 is updated with correct valve positions as follows:
. Select ERCS display RH1 on SDCON-5.
. Press F2 "D2VU".
. Enter the following valve positions:
. 32164 OPEN
. 32165 OPEN
. 32230 OPEN
. 32231 OPEN
. 32084 CLOSED
. 32085 CLOSED
. 31235 CLOSED
. 31236 OPEN
. 32064 CLOSED
. 32065 CLOSED
. 32066 OPEN
. 31237 OPEN
. 32234 CLOSED
. RH-2-5 OPEN
. RH-24 OPEN
. RH-2-3 OPEN
. Rii-2-4 OPEN
. Save by pressing F4.
o Change ERCS RH1 screen setpoints to "RH1 Active" as folkrus:
. Select ERCS display RH1 on SDCON-5.
. Press F2 "D2VU". 3
. Press F5 two times to move ERCS field to Alarm Setpoints.
. Press F2 to toggle to RH1 Active.
. Press F4 to save.
. Press CANC.
o Select RH1 dispiay and verify RH1 setpoints active, o Place the simulator in " FREEZE". o When the candidate is ready, place the simulator in "RUN". l l l i PITCO-089 Page 9 of 11 Rev 5 10/98 l l I
i l 8 9
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T I A P l
l TURNOVER SHEET l l
. INITIAL CONDITIONS: ~o RCS is in Cold Shutdown at 130 F.
1 o 12 RHR pump is running. INITIATING CUES: 1 o The SS directs you to shift from 12 RHR pump and heat exchanger in service to 11 RHR pump and I heat exchanger in ouvice and place 12 RHR pump and heat exchanger in standby per 1C15 section 5.3. o Report completion to the SS. l j i PITCQ-089 Page 11 of 11 Rev 5 10/98 l
{ JPM: 2 Operaton JPM QUESTION (AnswerSheet). QUESTION 1 System: RHR .
Subject:
l Cooldown Limitations K/A & Rating: 005A101 3.5/3.6 During a plant cooldown on Unit 1, the following RCS parameters were recorded: Time T-cold Loop pressure 0000 547 2230 0015 536 1900
~ Question'-
0045 504 1490 0100 488 1400 0115 467 1092 0130 444 720 0145 421 365 What (if any) limitations have been exceeded? Answer: Temp / pressure not in the normal cooldown zone at 0145 (<50Deg Subcooled).
Reference:
Figure C1-3B Reference Material Use:' l Yes @ No O l Pedigree: -l New CANDIDATES RESPONSE: SAT: UNSAT: 1 1 I i l
)
JPM:2 ;JPM QUESTION OPeraton [(Answer Sheet) QUESTION 2 System: RHR
Subject:
- l Refueling Cavity Fill / Drain K/A & Rating: 005K109 3.6/3.9 You are the RO assigned to fill the refueling pool prior to refueling with the following conditions:
1 11 RHR pump and HX are providing shutdown cooling l 12 RHR pump is in standby RWST levelis 75% ; While filling the refueling cavity using 11 RHR pump, you observe Question: RWST level drop and refueling cavity level increase at the expected ; rate. When the task is nearly complete, you notice: l RWST levelis 18% and stable l Refueling cavity level is 752' and stable All equipment is operating as expected There are no equipment failures or misalignments Why has level stopped changing in both containment and the RWST?
' Answer: RWST head is less than RCS head.
Reference:
C 4.1 rev. #7 page 32 Reference Material Use: el Yes 3 No O l' Pedigree: c - l New CANDIDATES RESPONSE: SAT: UNSAT:
)
JPM QUESTION 2 JPM:2 You are the RO assigned to fill the refueling pool prior to refueling with the following conditions: 11 RHR pump and HX are providing shutdown cooling 12 RHR pump is in standby RWST levelis 75% While filling the refueling cavity using 11 RHR pump, you observe RWST level drop and refueling cavity level increase at the expected rate. When the task is nearly complete, you notice: RWST level is 18% and stable Refueling cavity level is 752' and stable All equipment is operating as expected There are no equipment failures or misalignments Why has level stopped changing in both containment and the RWST? i
JPM QUESTION 1 JPM:2 During a plant cooldown on Unit 1, the following RCS parameters were recorded: Time T-cold Loop pressure 0000 547 2230 0015 536 1900 l 0030 520 1500 1 0045 504 1490 0100 488 1400 0115 -467 1092 0130 444 720 0145 421 365 What (if any) limitations have been exceeded? I l l l l 1 4
'M f. ::isH' Fib JOB PERFORMANCE MEASURE (R7g .1 %: : 24f: n s1% < - . n r. m.N._E:"z a L. WORKSHEET M P,Psm. *E &z::
TASK TITLE: Manual Makeup To The RWST JPM NUMBER: SIMUL-3 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 004.ATI.13 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Simulate Pedormance: Actual Performance: I Evaluation Location: Turbine Building: Auxiliary Building: I S:mulator: Control Room: Other. l Time for Completion: 8 Minutes l TASK APPLICABILITY: SRO: @ RO: 2 NLO: l (Check all that apply) l PREPARED BY: Mark J Jones DATE: 3/25/99 REVIEWED BY: DATE: APPROVED BY: DATE: l l Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7 l l J
l Manual Makeup To The RWST l SIMUL-3 R:v. 0 l 1
)
l Operator: (SRO / RO / NLO) Evaluator: l Date: READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: o .11 RWSTlevelindicates 70%. o Unit 1 is at 100% . ;wer. o No equipment OOS. o- Present RWST boron concentration is 2650 ppm. INITIATING CUES: l' o The SS directs you to increase RWST level to 75% per C12.5 section 5.5. o Report completion to the SS. l PITCQ@9 Page 2 of 8 Rev 5 10/98
l_ Manual Makeup To The RWST l SIMUL-3 Rsv. 0 l JPM PERFORMANCE INFORMATION Required Materials: None General
References:
C12.5 Task Standards: RWST level increased as indicated by makeup integrators counting up. Start Time: m.- mm = ,um . n - - - - r w% , a_ m .m w._-
,w. m. pato.m: r C,ues .110th,e,'
m xaminseicars e .u,__., must be exercised t6.avol, - d,.- w:.,e"
% _ STypically[r%m gm m . . -
f~##M g ; e wh.en t dyd. ,z he ,.- ee
!EE$$k,,iMddhsk.._ mal IMUkNkIN[examin.o_'s'a NMblM)1b
- .nm.m._ --.m. m ,.mm. .- s.~ ,- -- m ar XM
._, i -.mw,Ws.
.y e.,be. l wo.
u' : _ _ ~., ., . . _ . . ' n. u... -m _mb. e,,.-- m.,-..,,m. rnFail.u.. re, toa= pana ' .~ h ..
.cg.i. ~.--
1ri f.. align. 6...f
. - th. .i..s 2 MA ,_Ya- C~~
JPMM,wn l Performance Step: Using C12.5 Figure 1, Blended Flow Nomograph, estimate the setting for Critical HC-110, BORIC ACID FLOW CONT, to obtain the desired blended flow concentration. Standard: HC-110 setting determined to be 65% (i S%). MidlUMEUEMI55@uf57+$3$TNE"MMENMIEM>,, jdw
~
mauu]Ql--+lS!W A m..am~,hw9F e c mue _ -. %r Ws@wsks w ij$wa n au .u . - ~m ~ f.e;went i -:f( p u/fsw a @wsuu@wa%:M%=% i
~ ,
s Mj. . o ., , AM,"-
- mo :=:o nb.K.a:@m,,f$lE@il n -
Wi..: t.." %w at e 1 4
.1 ,
Performance: SATISFACTORY UNSATISFACTORY Comments: PITCQ-089 Page 3 of 8 Rev 5 10/98 l
I-l Manual Makeup To The RWST l SIMUL-3 Rev. 0 l l Performance Step: Verify the boric acid and reactor makeup flow controllers are in " AUTO". Critical Standard: HC-110 and PC-111 are verified in " AUTO". Performance: SATISFACTORY UNSATISFACTORY l Comrnents: Performance Step: Place CS-46300, MAKEUP MODE SELECTOR, in " MANUAL". Criticai X (S-1) Standard: CS46300 placed in " MANUAL"; CS-46457 green light lit, red light extinguished. 1 Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: To add makeup to 11 RWST, OPEN the following valves: Cdtical X (S-1) VC-11-59, MANUAL MAKEUP HDR ISOL. SI-17-1, BLENDER TO RWST. Standard: Aux Building Operator requested to open VC-11-59 and Sl-17-1. EG0a@N5Mk P " 1 Th{68bih operstbf'wiIl[act]as XUs Building Operatdfioidden Sid721. ' ild$$h 6hi g giVCi11i59 is not modeldd .oi1Lthe simulator " > EfalustsicaeT ,' ' - / (Th~e b6oth"operst6r willl rep 6rt as Aux'Bhilding Ogssrat6rinst?'VC-11-:-
?,,m3& 159 ahdfSI-17-1 sre opsn."? ~ '
~ ' ' ~ " ~
Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 Page 4 of 8 Rev 5 10/98
l Manual Makeup To The RWST l SIMUL-3 Rev. 0 l l Performance St6p: Set HC-110, BORIC ACID FLOW CONT, to the setting previously Critical determined. Standard: HC-110 set to approximately G5%. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Set batch integrators 1YlC110 and 1YlC111 near their maximum settings. Critical X (S-1) Standard: Boric acid and reactor makeup water batch integrators,1YlC110 and 1YlC111, set near maximum.
$Esalua%
[# HNnMEl , iNote;[ NETOgnulirtorj5s/ sit [ldE@sEsISidf@t
- ,[satisfikwhen'tl1elinteghatorslarelse abovebro@
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Momentarily place CS-46457, BORIC ACID MAKEUP, to " START", to Critical X (S-2) initiate manual makeup. Standard: CS 46457 momentarily placed to " STAR r'; red light lit, green light j extinguished. l Performance: SATISFACTORY UNSATISFACTORY Comments: i Terminating Cues: When the m akeup integrators begin counting up, indicating flow, inform the candidate that, "this JPM is complete." Stop Time: PITCO-089 Page 5 of 8 Rev 5 10/98 L
l Manual Makeup To The RWST l SIMUL-3 R*.v. 0 l SIMULATOR SETUP instructor Guide: o initialize the simulator to IC-10. o Enter remote to adjust RWST level to 70%. (Relative Order 0) o When the candidate is ready, place the simulator in "RUN". o When directed during JPM performance, enter remote to open SI-17-1. (Relative Order 1) J j
)
l l I PITCQ-089 Page 6 of 8 Rev 5 10/98
1li l 8 9
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0 0 1
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TURNOVER SHEET INITIAL CONDITIONS:
- 11 RWSTlevelindicates 70%.
i e' Unit 1 is at 100% power. l e _ No equipment OOS. e Present RWST boron concentration is 2650 ppm. l 1 I INITIATING CUES:
. The SS directs you to increase RWST level to 75% per C12.5 section 5.5. . Report completion to the SS.
l J l i I l l l PITCO-089 - Page 8 of 8 Rev 5 10/98 i
]
I~ i JPM:3 Operator: JPM QUESTION (AnswerSheet) _. l QUESTION 1 System: CVCS
Subject:
l Tech Spec For RWST K/A & Rating: 2.1.23 3.4/4.0 In preparation for RCS heat up following a refueling, the following l plant conditions are observed: l
- 11 BAST at 12.3 weight /% concentration Question'*
~
^ '***'*
- 11 BAST temp is 172*F
- RWST at 2606 ppm boron
- RWST level at 66%
Can the RCS exceed 200*F? Why or why not? r Answer,* RWST does not meet the minimum volume of 200,000 gallons, which l corresponds to 68% level. ! Referenco: i Tech. Spec. 3.3.A.1.a and the Tank Book page 73 Reference Material Use: - l Yes No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: i l l l l
JPM: Operator: JPM QUESTION f(Answer Sheet). ,0UESTION 2 System: - CVCS
Subject:
{ VCT Level Control K/A & Rating: 004K412 3.1/3.4 You are performing a cooldown on Unit 1, which requires significant l RCS make up via the CVCS system when the following sequence occurs:
-A Manual make-up using the DILUM mode is completed
-The MAKEUP MODE SELECTOR is placed in " AUTO" Question: -The BORIC ACID MAKEUP CONTROL switch is NOT taken to
" START".
-No other operator action is taken while the cooldown continues.
Describe the sequence of events that occur over the next hour, with respect to the VCT level and any associated control functions. VCT level will decrease to the auto make up setpoint (17%), but make up i Answer:' will not start. Level will decrease to the lo-lo level (2 to 4%), the VCT outlet will close and the RWST to charging pump suction will open. Refemnce: B-12A pages 14 - 19 Reference Material Use:" l Yes @ No O l Pedigree: l New _ CANDIDATES RESPONSE: SAT: UNSAT:
)
- r. ,
p, JPM QUESTION 2 JPM:3 l You are performing a cooldown on Unit 1, which requires significant RCS make up via the CVCS system when the following sequence occurs:
-A Manual make-up using the DILUTE mode is completed
-The MAKEUP MODE SELECTOR is placed in " AUTO"
-The BORIC ACID MAKEUP CONTROL switch is NOT taken to
" START".
-No other operator action is taken while the cooldown continues.
Describe thw sequence of events that occur over the next hour, with respect to the VCT level and any associated control functions. i 1 I
e JPM QUESTION 1 JPM:3 in preparation for RCS heat up following a refueling, the following plant conditions are observed: l - 11 BAST at 12.3 weight /% concentration {
- 11 BAST level at 65% i
- 11 BAST temp is f,TF
- RWST at 2606 ppm boron
- RWST level at 66%
Can the RCS exceed 200*F? Why or why not? I ( l
Lg 9i1 JOB PERFORMANCE MEASURE 8
!% $@# @R 3$ WORKSHEET Be%g$mps SAs h TASK TITLE: Transfer 1R-11/12 Sample Discharge From Containment To Aux Bldg Stack JPM NUMBER: SIMUL-4 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3):
TASK NUMBER: 073.ATI.01 K/A NUMBERS: 2.1.23 APPLICABLE I AETHOD OF TESTING: Simulate Performance: Actual Performance: @ Evaluation Location: Turbine Building: Auxiliary Building: Simulator. @ Control Room: Other. i Time for Completion: 2 Minutes ! TASK APPLICABILITY: SRO: @ RO: NLO: (Check all that apply) 1 i l PREPARED BY: Mark J Jones DATE: 3/25/99 l REVIEWED BY: DATE: 1 APPROVED BY: DATE: l Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7 I J
r-l Transfer 1R-11/12 Sample DischarDe From Containrnent To Aux B]do Stackl SIMUL-4 R v. 0 l Operator: (SRO / ROINLO) Evaluator: Date: READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance reeasure will be satisfied. INITIAL CONDITIONS: e 1 R-11/12 sample discharge is aligned to the Containment
. ~ Containment pressure is approaching 0.7 psig.
INITIATING CUES: The SS directs you to transfer 1R-11/12 sample discharge from the Containment to the Aux Building stack per C11 section 5.1.
. Report completion to the SS.
PITCQ-089 Page 2 of 8 Rev 5 10/98
l ) l Transfer 1R-11/12 Sample Discharge From Containment To Aux Bldg Stack l SIMUL-4 R v.0 l JPM PERFORMANCE INFORMATION Required Materials: None l General
References:
C11 l Task Standards: 1R-11/12 sample discharge aligned to the Aux Building stack. Start Time: y -
- w. 4
.~l,uator ,NOTyEMWh_enp,r_ov,i, - Eva d ing-. to th_e.. -- ~~ ~~..- . b. ex..e.
examineetcaremust . is~e,d erc to,,a_ void m,m,,! 7 R QMrsdid;arNinM#hpisal . , Cues';iyhAnsl Md$andidWeiernW1nrennatl6stiKniklakoinffpfosidad usenensei66saiREsks:WWindicatishWM M'tlEens$in55'E% _ -.y.__, m -,mo g
.N . OT.E:-- -. msm ._,i- ,_m,,_,_ked,w.
v.itic..a .-:are.m_ a,,r . . ith
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.. , wthe vnance num -jFa e E$$Rshg,tM.
ilis
.g#tandarllf6(snpyritidall step %zN.s.,,._m.m...m m~. .
,_,....,, b.,e,r;m.-...,lu,re s.-...-..- . . .
sse
#( W ;iN l Performance Step: Verify S103, SAMPLE SELECTOR switch, located on 1R-11 drawer in the Cridcis "CONTAIN" position.
Standard: S103 verified in the "CONTAIN" position. i 4 i Performance: SATISFACTORY UNSATISFACTORY Comments: 4 1 l I I l PITCQ-089 Page 3 of 8 Rev 5 10/98 1 l
4 1
)
l Transfer 1R-11/12 Sample Discharge From Containment To Aux Bldg Stack l SIMUL-4 R::v. 0 l Performance Step: CLOSE SV-33786, VENT SAMPLE RETURN by depressing S107, R-11/12 Critical X (S-1) DISCHARGE TO CONTAINMENT, until the yellow light on the switch is OFF. Standard: SV-33786 closed by depressing S107; yellow light extinguished.
- 7. .-. . . _ _ . _ . _ . _ . , _ , , . . _ . .y. , _ , m . _ _ .
EvalustorNoteOA N ...' ilf both"S107 and S108'are~ depressed the,,. _. ens and thei a uw
%..,mm,~m.. v. w%yt m.m;4 a p.u.. m.pm.e.p_s._o..n_lo.w.
'o._n..e. va_lve.. c._a.n.._ tie._0..e= w~ly _a.,;,,u
. . t.e;m mxm m a m =~ ~ ; u
.u_ e.~.m. ,hg .mm h .._ _
P_e..n. _e.d.._.,,a_ _e.h, ._ti._
~
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Immediately CPEN SV-33785, VENT SAMPLE RETURN, by depressing Critical X (S-2) S108, R-11/12 DISCHARGE TO AUX STACK, until red light on the switch is ON. Standard: SV-33785 opened by depressing S108; red light lit.
. ~ . . . - - . _. . ,. ,.-. ._ ~.
.. ~. .. ~.-n Evaluato+r;Not,e:,P , & ':lf b,oth i
+.v ~ . -S107/and S108 %.re,d,ep_resse,d. ithen'.rieltherlv,alve"op,e,ns and thek lo>,.w j.owM. ~ly;o~net
..x . - - ~ - . . - .. .
Midn s di'/di %Cg apump trip,.n.-s on ~.~ caq~$e pene o. ~d.pt .e,dggAti;m-.- +-~ 4 l Performance: SATISFACTORY _ UNSATISFACTORY Comments: I l I 1 I 1 I I l PITCO-089 Page 4 of 8 Rev 5 10/98
)
r l I i l Transfer 1R-11/12 Simpla Dischargefrom Containment To Aux Bldg Stack l SIMUL-4 Rev. 0 l I " Performance Step: When 1R-11,12 sample discharge is returned to Aux Bldg, then OPEN RD-Critical 5-2,1R-11/12 RAD MON SAMPLE INLET TEST. I ! Standard: Aux Building Operator requested to open RD-5-2. ! 1 i G. stus.t..oi.N6tiilEWWR6612..rliin. 6G. .iiod, eled, ON,.'.si.s"s.inidist6.
, - . <s. i m. . 2 . - -er m. .r- .. . o . -:
MT A f/S, m , ~.;jrME. 4%,5 m .:m d.dKN Mil.1: syhhMMidEil1 h3d u .i':.s.aidilt $rikddLS'E.did jddddd!$12?i!bddh1SdiUEid $lidCifE!) iLd - jd AjdI[ibidd:d$ilkAO:hs'ij3mid;$lijshsdOd! b::d EIlfd!d D$ klaNYar,M2/.kiM!d w!dlid!gi c-g . m, - ,7 . sy.w--- c , . g 4. ._s e. . y .m yq, , ,r, rEv.xalua, tor,Cu,ys.gg,j y p , ,g,.. .. e:7 .2%Myr,.r Re as' Aux Building Ope:rato%,n.n. ...r "RD 6;2 'is ope, n." - m p. M.4p,. gg- O l" wane!wam% M.,g,g. ms!M Muaemm.h .usamam,assmthm a:!;im!N ? ;w ir . t,3 me.m cm,;., as Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: The candidate should report to the SS that, "1R-11/12 sample discharge has been transferred to the Aux Building stack." At this point, inform the candidate that, "this JPM is complete." Stop Time:
)
l 1 PITCO-089 Page 5 of 8 Rev 5 10/98 i
p l Transfer 1R-11/12 Sample Discharge From Containment To Aux Bldg Stack l SIMUL-4 R:v. 0 l SIMULATOR SETUP l Instructor Guide:
+ initialize the simulator to IC-10.
Enter override to cause Containment Pressure indicator (PI-4127901) to indicate = 5 psig. (Relative Order 0) Ensure light bulbs for sample discharge to Aux Building Stack ai,d Containment Building are good.
. Ensure 1R-11/12 suction is not isolated (by a SI).
. When the candidate is ready, place the simulator in "RUN".
I t l l l 4 t PITCO-089 Page 6 of 8 Rev 5 10/98
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8 [l 9
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0 0 1 e u R e 4- r I 5 u0 9 v L U m7 2 e P1 4 R M I t nI S eP - l mr no t i aac t ni od n CI ~ P U T E . k c S 8
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f o o m O 7 d T e i B A g a x L P P u U T A M o M N T I C t n S 1 0 e 9 7 m 2 i n 1 4 t a n o C O . A m D o r R F V e O g r a h c is D C 1 l e 0 H p C m M a I S S 2 1
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1 1 0 9 r 8 e 0-f - s n Q C U ar T T I P l
[;; 1 L TURNOVER SHEET INITIAL CONDITIONS:
. 1R-11/12 sample discharge is aligned to the Containment.
. Containment pressure is approaching 0.7 psig.
t l INITIATING CUES:
. . The SS directs you to transfer 1R-11/12 sample discharge from the Containment to the Aux Building stack per C11 section 5.1.
. Report completion to the SS.
l l PITCQ-089 Page 8 of 8 Rev 5 10/98
.JPM: 4 Operator: .
. LPM QUESTION (Answer Sheel)
QUESTION 1_ System: I Rad Monitors
Subject:
- - l Liquid Release Rad Monitor Malfunction K/A & Ratin,g: 073K301 3.6/4.2 Unit 1 is at power with the following conditions:
-121 ADT monitor tank is ready for release.
-R-18 background count rate is 5,500 cpm.
Questio'n: In preparation for releasing 121 ADT monitor tank to the river, the CHECK SOURCE button is depressed on R-18 and the count rate is 30,000 cpm. What, if anything, must be done regarding radition monitors to release 121 ADT MonitorTank to the river? Answer-
- Have HPs bug R-18 in the monthly bug position and verify Monthly Bug Point reading minus background is within 3 E+4 and 8 E44. _.
Reference:
C21.1-5.1; 121 ADT Monitor Tank Release pp. 6-7. Reference Material Use: lYes@ No l Pedigree: .lNew CANDIDATES RESPONSE: SAT: UNSAT: I i
JPM: 4 Operator: JPM QUESTION (AnswerSheet) l l QUESTION 2 System: ' Rad Monitors
Subject:
- l Rad Monitor Downscale Failure K/A & Rating: 073A202 2.7/3.2 Given the following Unit 1 plant conditions:
-Containment inservice Purge is in service
-Fuel Handling is in progress Question:
-All raditiation monitors are in service '
l 1R-11 fails downscale and must be removed from service. What ! action, if any must be taken? j Answer: Terminate fuel handling operation. l
Reference:
^^
Dd Reference Material Use: l Yes N No O l Pedig7el: l New __ l CANDIDATES RESPONSE: SAT: UNSAT: l l 1 1
t JPM QUESTION 2 JPM:4 Given the following Unit 1 plant conditions:
-Containment inservice Purge is in service
-Fuel Handling is in progress
-All raditlation monitors are in service 1R-11 fails downscale and must be removed from service. What action, if any must be taken?
1 l d
l JPM QUESTION 1 L JPM:4 l Unit 1 is at power with the following conditions:
-121 ADT monitor tank is ready for release.
-R-18 background count rate is 5,500 cpm.
In preparation for releasing 121 ADT monitor tank to the river, the CHECK SOURCE button is depressed on R-18 and the count rate is 30,000 cpm. ! What, if anything, must be done regarding radition monitors to release 121 ADT MonitorTank to the river? l i t
U
'm JOB PERFORMANCE MEASURE l
1 . WORKSHEET $ jig l@@$$s Bs!@ $$ TASK TITLE: Respond To A RCP Thermal Barrier Hx Leak JPM NUMBER: SIMUL-5 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 008.ATI.11 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Simulate Performance: G Actual Performance: Evaluation Location: Tuitine Building: Auxiliary Building: O Simulator Control Room: Other Time for Completion: 8 Minutes 1 TASK APPLICABILITY: SRO: RO: NLO: 1 (Check all that apply) l l PREPARED BY: Mark J Jones DATE: 3/26/99 REVIEWED BY: DATE: !
- t l APPROVED BY
- DATE: l l
l l Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7 1
n:- l Respond To A RCP Thermal Bamer Hx Leak l SIMUL-5 Ray. 0 l Operator: (SRO / RO / NLO) l Evaluator: 1-Date: READ TO THE OPERATOR l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.- INITIAL CONDITIONS: o Unit 1 is at 100% power. o Annunciator 470220109, HI RADIATION TRAIN A PANEL ALARM has just actuated. I l INITIATING CUES: o The SS directs you to respond to the alarm per the appropriate Alarm Response Procedure. i I l i l l l l PITCQ-089 Page 2 of 8 Rev 5 10/98 l l l
l R:spond To A RCP Thermal Berrier Hx Leak l SIMUL-5 R:v. O I JPM PERFORMANCE INFORMATION Required Materials: None General
References:
C47022, C47047, Cid AOP2 Task Standards: 11 CC Surge Tank vent valve closed and 11 RCP Thermal Barrier Hx
!solated.
Start Time: _. _ m,.
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._~2 o~,,- , ,_.,_ .e_'exerc e JE 1 prompting"ths,exahilhesET picall9 j[hwarrantiopsivinM}M#rbsiiM:(in; cues"ah,ar,rune i snip pioirided?wherin"daminei'sectinish Dis}narfildseMW)[iski3afssdhdijstinhj$M3 porescnWihss ersmarkenweiWX9sioMWsrinidasstes%Wrwe:NiiisEEP teidenetMstandar@MusMisast4jsalllressitifs18in($%1sippiWMsensdagsj Performance Step: Determine the initiating alarm and respond to the alarm as specified in Critical C47047, TRAIN A RADIATION MONITORING SYSTEM ALARM RESPONSE PROCEDURES.
Standard: R-39 determined to be the alarming rad monitor and C47047 transitioned to. w .-~x~ n. uEva.w
~luato~r.N~oie:r ys.This~.s_tep isv.-- - w wd;in~D,47022.e. g - n a.. o,n,an.x ni~o edna mA3jsdislse i, sprocsdur,e[$prescriben 0(rathe {$iNorni..c n n from,may not_re.. fer: . s N.
thisfactis memoryJ2131bdys Performance: SATISFACTORY UNSATISFACTORY Comments: l 1 i l PITCQ-089 Page 3 of 8 Rev 5 10/98
- l R:spond To A RCP Thermal Barri r Hx Leak l SIMUL-5 Rev. 0 l Performance Step: Close 11 Component Cooling Surge Tank Vent valve MV-32088. Critical X (S-1) Standard: 11 CC Surge Tank Vent valve MV-32088 closed by placing CS-46024 in the CLOSE position; green light lit, red light extinguished.
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. 1 Em.a. .n. ..u.. .al..l.y~tuwwuwus%,g
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w ;. , ,, [EQa' l 6aI#s0Q $$666%Ad@idateji$&s%tiiel5S't65i(65/ihi is)l6516g di&3{CQ ; 3 31/% vi,M { wdngEagsnsd,SurgsiTank
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,w w m me te acimovded, umu V rWValys MV42088/then'
#ging.6wm-m p o up.s , .^91deNe6stinirepeat 1s repo.Axwasmagshubew .s %m- a ,m a )
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Refer to appropriate actions as described in C14 AOP2, LEAKAGE INTO Critical THE COMPONENT COOLING SYSTEM. Standard: C14 AOP2 transitioned to. 1 Performance: SATISFACTORY UNSATISFACTORY ! Comments: l PITCQ-089 Page 4 of 8 Rev 5 10/98
l l l R:spond To A RCP Thermal Barrier Hx Leak l SIMUL-5 Rev. 0 l Performance Step: Check radiation monitor R-39. High radiation indicates contaminated water Critical leakage into the Component Cooling System. Refer to Section C4 AOP1, Reactor Coolant Leak, for manual actions in the case of a reactor coolant leak into the Component Cooling System. Refer to Table 1 for other possible sources of contaminated water. Standard: C4 AOP1 referred to and/or SS informed that it needs to be implemented for RCS Leak and Table 1 reviewed for possible leak sources. ) 1 1
'>[f ? :f jy@l W j @ @@j%y[ @ @ @ @ (pp @ tu %O@f 3
- un-aamMuwaw.-amu amun nunnam. aua ,~ , ,, w wwu~ me l Performance: SATISFACTORY UNSATISFACTORY l
Comments: 1 l Performance Step: Check RCP CC outlet flow and temperatures. If flow or temperature is ' Critical X (S-2) higher than nomial, then CLOSE the affected RCP thermal barrier heat exchanger CC retum valve. Standard: 11 RCP CC outlet flow (F1-4127601) and temperatures (TI-4127602) determined to be higher than normal and 11 RCP THERM BARRIER CLNT OUTL valve CV-31245 closed by placing CS-46022 in the CLOSE position; green light lit, red light extinguished. Performance: SATISFACTORY UNSATISFACTORY Comments: ' Terminating Cues: When the candidate closes CV-31245, inform the candidate that, "this JPM is complete." Stop Time: l l 1 PITCO-089 Page 5 of 8 Rev 5 10/98
l Respond To A RCP Thermal Barrier Hx Leak l SIMUL-5 R:v. 0 l SIMULATOR SETUP instructor Guide: Initialize the simulator to 1C-10. t Enter overrides to fail auto closure of CC Surge Tank Vent. (Relative Onfer0) Enter malfunction to cause 40 gpm leak in 11 RCP Thermal Barrier Heat Exchanger. (Relative Order 0)
. When the candidate is ready, place the simulator in "RUN".
When the candidate places CS-46024 for 11 CC Surge Tank Vent valve MV-32088 in the CLOSE position, remove the overrides to fail auto closure. (Relative Order 1) I I i i l i PITCQ-089 Page 6 of 8 Rev 5 10/98
lll IJ
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TURNOVER SHEET INITIAL CONDITIONS:
. Unit 1 is at 100% power.
Annunciator 47022-0109, HI RADIATION TRAIN A PANEL ALARM has just actuated. INITIATING CUES: The SS directs you to respond to the alarm per the appropriate Alarm Response Procedure. i PITCQ-089 Page 8 of 8 Rev 5 10/98
)
JPM:5 OPerator: JPM QUESTION l (AnswerSheet) QUESTION 1 System: CC
Subject:
- : l Actions For Leak On CC To RCP K/A & Rating: 015AK302 3.1/3.1 Unit 2 is at 100% power and all systems normal, when the following occur: g,g. . -21 CC Surge Tank Level begins lowering
-CC flow from 22 RCP indicates 80 gpm
-22 RCP motor bearing temperatures are increasing What actions are required in response to these conditions?
Trip the reactor Answer: Stop 21 and 22 RCP's isolate 21 and 22 RCP component cooling supply and return. l
Reference:
2C14.AOP1 pp. 4-5; Rev. 4 l Reference' Material Use:? ..l Yes No l Pedigree:- l New CANDIDATES RESPONSE: SAT: UNSAT: i I l l l
JPM:5J JPM QUESTION OPoraton
- (Answer Sheet)
QUESTION 2 System: CC
Subject:
l Expected Response Of Surge Tank K/A & Rating: 008K402 2.9/2.7 Given the following conditions:
-Both units are in a normal 100% power lineup gg,,g -No CC transfer is in progress A 25 gpm leak out of the CC system occurs. Assuming no operator action, what automatic actions will occur with respect to both unit's CC systems?
Both 11 and 21 CC Surge Tank levels will decrease and alarm at the low Answer,' level set point, resulting in opening of their respective auto makeup valve. Levels will oscillate between normal level and the low level alarm setpoint as the makeup valves open and close. 1C14 AOP1 Pgs. 2 and 3 Reference': C47020:0203 NF-39245-1 Reference Material Use: l Yes @D No O l Pedigree: .{New CANDIDATES RESPONSE: SAT: UNSAT:
JPM QUESTION 2 JPM:5 Given the following conditions:
-Both units are in a normal 100% power lineup
-No CC transfer is in progress A 25 gpm leak out of the CC system occurs. Assuming no operator action, what automatic actions will occur with respect to both unit's CC systems?
l l l i i I l
7 JPM QUESTION 1 JPM:5 Unit 2 is at 100% power and all systems normal, when the following occur:
-21 CC Surge Tank Level begins lowering
)~ -CC flow from 22 RCP Indicates 80 gpm
-22 RCP motor bearing temperatures are increasing i
What actions are required in response to these conditions? l l l l I I 1 l l 1 l I
M !? JOB PERFORMANCE MEASURE Re !i k 3$$'d@d .[ WORKSHEET $$$@sg$$p/g 1 l l TASK TITLE: Depressurize The RCS Following A Steamline Break JPM NUMBER: SIMUL-6 Rev. O i 1 RELATED PRA None INFORMATION (SEE PITC 2.3): ; I TASK NUMBER: 301.ATI.19 , 1 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: ! Simulate Performance: Actual Performance: Evaluation Location: Turbine Building: Auxiliary Building: ; Simulator. Control Room: Other Time for Completion: 6 Minutes TASK APPLICABILITY: SRO: RO: @ NLO: (Check all that apply) PREPARED BY: Mark J Jones DATE: 3/26/99 REVIEWED BY: DATE: APPROVED BY: DATE: Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
n-l Depressurize The RCS Following A Steamline Break l SIMUL-6 Rt.v. 0 l L Operator: (SRO / RO / NLO) l' Evaluator: Date: I READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.' INITIAL CONDITIONS:
. Both SGs are depressurizing slowly in an uncontiolled manner.
Uncontrolled depressurization of both SGs actions have been completed including 1E-0,1E-2, and 1ECA-2.1 through step 34.
. Letdown has been established per C12.1.
INITIATING CUES: The SS directs you to continue actions per 1ECA-2.1, starting at step 35. i 1 l L l l l PITCQ-089 Page 2 of 8 Rev 5 10/98 t l l- )
1 l Depressuriza The RCS Following A St::rmline Break l SIMUL-6 Rnv. 0 l JPM PERFORMANCE INFORMATION Required Materials: None 1 General
References:
1 E-0,1 E-2,1 ECA-2.1 l Task Standards: RCS oressure reduced to less than 400 psig using Auxiliary Spray. l Start Time:
%j$yE%yit [C @ y @ M E95&i l
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p$$d$d[Mstrant l recelyirsi thn)nf6tonti6Ei[(Ck$5jiins@sjhcNdisNaskd; _m _ . . , _ . . _Cr NOTEi;. ,,iti, cal steps,a. ,...,.k..remar ed;w_ ith,'a,n#Xib,,e_lowthe, _ _ _ _ ,._ _ ,,.,,,,,_..,,ilur,e number #Fa to_ ,?!_ ,
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i Performance Step: Check RCS Pressure - LESS THAN 400 PSIG. l Critical Standard: RCS pressure checked and determined to be greater than 400 psig. Performance: SATISFACTORY UNSATISFACTORY l Comments: Performance Step: Determine that auxiliary spray is to be used to depressurize the RCS. Critical l- Standard: Normal spray determined to not be available due to RCPs being secured. Auxiliary spray determined to be available since letdown is in service. Performance: SATISFACTORY UNSATISFACTORY Comments: PITCQ-089 Page 3 of 8 Rev 5 10/98
m l Depressuriza The RCS Following A St:::mline Break l SIMUL-6 Rcv. 0 l Performance Step: Depressurize RCS using suxiliary spray, Critical X (S-1) Standard: 1. CV-31329, AUX PRZR SPRAY FROM REGEN HX, opened by momentarily placing CS-46295 to "OPEN"; red light lit, green light extinguished.
- 2. CV-31328, REGEN HX CHG LINE OUTL, closed by momentarily placing CS-46296 to "CLOSE"; green light lit, red light extinguished.
yg , _.2g . . _ m _. ,_ n ats mayg djd_st ch,_arg,..(' y, va.lda..,tk_No~te 44; gy,Ca,_did.._.m. an ng pump l speed ._d._ch., _argmg;
. , _. ,fl.o,_w. -_controls m . .. .
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- s 3=s Perfonnance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: When RCS is reduced to less than 400 psig, stop depressurization. Critical X (S-2) Standard: 1. CV-31328, REGEN HX CHG LINE OUTL, opened by momentarily placing CS-46296 to "OPEN"; red light lit, green light extinguished.
- 2. CV-31329, AUX PRZR SPRAY FROM REGEN HX, closed by momentarily placing CS-46295 to "CLOSE"; green light lit, red light extinguished. .
1 lEvaldstoiNbGinGdffCindid55A insliiftdf8WEidii$diIpriofid~decrsisirid BEla@20)F[ J ' n ?wne bcooling.amm %mMm"M W %L m u.y.mm 'W u.. ,x, A umam wemmsu mm1 ' uamusmam , Performance: SATISFACTORY UNSATISFACTORY 4 Comments: 1 i i PITCO-089 Page 4 of 8 Rev 5 10/98 j
F. l Deprassurize The RCS Following A Stiamline Break l SIMUL-6 Ray. 0 l Performance Step: Retum to Step 34. l Critical Standard: Step 35 completed and step 34 returned to. l l Performance: SATISFACTORY UNSATISFACTORY _ Comments: Terminating Cues: When the RCS is depressurized to less than 400 psig and the candidate indicates that he/she is retuming to step 34, inform the candidate that, "this ; JPM is complete." Stop Time: - l
)
)
PITCQ-089 Page 5 of 8 Rev 5 10/98
p I-l Depressurize The RCS Following A Steamline Break l SIMUL-6 R:v. 0 l I SIMULATOR SETUP instructor Guide: o initialize the simulator to IC-10. l o Enter malfunctions to cause a 5% steam line break, outside containment, on both A and B SGs. (Relative Order 0) o Enter malfunctions to cause 1R breakers to fail to close, preventing Bus 11 and 12 transfer. l . (Relative Order 0) l o Place the simulator in "RUN". e Trip reactor and initiate SI. o Perform E-0 and ECA-2.1 steps 1 through 34. o Er.sure the following conditions are established: l . Letdown is in service l
. RCPs are secured l . Pressurizer heaters are secured
. RCS pressure is greater than 400 psig.
l o Place the simulator in " FREEZE". o When the candidate is ready, place the simulator in "RUN" l l i I l l I I l ! PITCO-089 Page 6 of 8 Rev 5 10/98 i
_ l 8 9
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l C C l R Oma t o to 5 6- e e r l s l s v L wt t s i a a i e U pp F F R RuU r r M t k k I 2 ne B B S 1 R R l e m 1 1 nn i i 1 2 LtaV nI 1 s 1 s S o S u u 3 MCM B B ll P _ U _ T E ll S 8 R 0 1 f o O 7 T e g A ll a L P . U . M I B 2 A B 2 2 0 0 0 S S D D M E E - k a _ e r lIll B e i l n F F F m L L L a A A A t e M MM S A g i n w A l o 1 7 7 0 0 o l 0 S D D F E S M M M E I h I C I S S S R e h T t r O 9 O O 8 u s 0-s e r Q p C e T I D P l
TURNOVER SHEET INITIAL CONDITIONS: . ' Both SGs are depressurizing slowly in an uncontrolled manner. = Uncontrolled depressurization of both SGs actions have been completed including 1 E-0,1E-2, and 1ECA-2.1 through step 34. . Letdown has been established per C12.1. INITIATING CUES: . The SS directs you to continue actions per 1ECA-2.1, starting at step 35. I i i l PITCQ-089 Page 8 of 8 Rev 5 10/98
i a. JPM: 6 OPeraton JPM QUESTION (AnswerSheet) QUESTION 1 l System: ressunzer E#ed MeaWng Pressudzer Safety On
Subject:
Pressure Control PRT K/A & Rating: 008AA108 3.8/3.8 Given the following unit 2 conditions:
-RCS daily leak rate surveillance results in leakage of 2 gpm. l
-Unit 2 charging pump leakage is .025 gpm l Question: -Unit 2 pressurizer safety valve is determined to be leeking. 1
-The PRT level has increased from 72.5% to 76% over 7 hours.
The SS asks you to determine what portion of the total leakage is unidentified leakage. The PRT level increase is approximately 200 gallons in 7 hours.
, 200 gallons in 7 hours (420 min) equals approximately .475 gpm.
Add .025 gpm charging leakage . Leaves 1.5 gpm (+/- 0.1) gpm unidentified. l
Reference:
Tank book tab 70 Reference Material Use: l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: I 1 l l l l f
l l
\
l JPM:6 JPM QUESTION OPeraton (AnswerSheet) QUESTION 2 Pressurizer Relationship Between Charging, Auxiliary System:
Subject:
Pressure Control Spray, And The Pressurizer K/A'& Rating: 004K117 3.4/3.4 Given the following Unit 1 conditions: l -Letdown isolated l -12 charging pump in service
-PRZR Pressure is 435 psig Question: -Loop T hots are 380*F
-Loop T colds are 378*F
-VCT temperature 111*F
-PRT temperature 79'F l
Can Aux Spray be used to reduce RCS pressure? Why or why not? No, PRZR pressure corresponds to about 456*F - 111*F VCT temperature
#"***" (345'F) would exceed Tech Spec 3.1.B.2.b limit of 320*F. i Steam Tables
Reference:
T.S. 3.1.B.2.b 1C1.3 Limitation 4.1.5 Reference Material Use: -l Yes O No l Pedigree: l New I l CANDIDATES RESPONSE: SAT: UNSAT: ____
I; i JPM O'JESTION 2
'JPM:6 Given the following Unit 1 conditions:
-Letdown isolated l
-12 charging pump in service l -PRZR Pressure is 435 psig
-Loop T hots are 380'F ,
l -Loop T colds are 378'F l
-VCT temperature 111*F
-PRT temperature 79'F i
Can Aux Spray be used to reduce RCS pressure? Why or why not? 4 l I 1 l l
~
l JPM QUESTION 1 L .JPM:6 Given the following unit 2 conditions: RCS daily leak rate surveillance results in leakage of 2 gpm.
-Unit 2 charging pump leakage is .025 gpm ,
-Unit 2 pressurizer safety valve is determined to be leaking.
-The PRT level has increased from 72.5% to 76% over 7 hours.
The SS asks you to determine what portion of the total leakage is unidentified leakage. l i
i
~
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l JOB PERFORMANCE MEASURE [L.~P ,x$ J WORKSHEET RWWEN!M#d# ) l TASK TITLE: Respond To High Containment Pressure (Manual Containment Spray initiation) I JPM NUMBER: SIMUL-7 Rev. O l l RELATED PRA None ! l lNFORMATION l (SEE PITC 2.3): TASK NUMBER: 0260050101 l K/A NUMBERS: 2.1.23 l l l APPLICABLE METHOD OF TESTING: 1 i Simulate Performance: Actual Performance: Evaluation Location: Turbine Building: O Auxiliary Building: l Simulator @ Control Room: Other. I Time for Completion: 7 Minutes TASK APPLICABILITY: SRO: RO: @ NLO: 0 (Check all that apply) 1 PREPARED BY: Mark J Jones DATE: 3/26/99 l REVIEWED BY: DATE: APPROVED BY: DATE: l Resp Grp: O Page 1 of 8 Assoc Ref: PITC TP 3.7
l Responsd To High Containment Pressure (Manual Containment Sprcy initiation) l SIMUL-7 R v. 0 l Operator:' (SRO / RO / NLO) Evaluator: Date: READ TO THE OPERATOR 1 will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: o Steamline break inside containment has occurred. o 1 E 0 has been performed, and transition to 1E-2 was directed. o The SM detects an orange path in containment. INITIATING CUES: o The SS directs you to respond to the orange path in containment per 1FR-Z.1. o Report completion to the SS. PITCO-089 Page 2 of 8 Rev 5 10/98
l Responsd To High Containment Pr=sure (Minu:1 Containment Spr y initiction) l SIMUL-7 R v. 0 l JPM PERFORMANCE INFORMATION 1 i Required Materials: None General
References:
1FR Z.1 Task Standards: Containment spray pumps running with proper valve alignment. Start Time: a m,n w,+, e ma n g-w ~c n mm me cyyysyyggyny m mmw an u L xapp
.~.; c - v'actio~nst y- ~ e exami s hbi $1bh _ .h b...,~ hk h f N, k khk hk [hl neem .
nn, , , . - e. w. ere. wwithan a.w~E~ tie ~ low.tN,aam
- o. . numb +e,re Faliu:n,re: tow,tg
,Ag!ws! "" **um W s . .
P me ~ + - p. WOteM@;tne ' kE2!ssi ,, -_
~ . >,,,EY.. . m M- ".* .m._.,Fwtg.-
f00" ME.~ . ...)S, ..b"a4@W,2!hs1hkeit,is Perfonnance Step: Verify Containment isolation Valves CLOSED. Critical Standard: All " Containment Isolation" lights on panel 44104 verified lit except for personnel and maintenance airlock doors and auxiliary feedwater isolation valves. Performance: SATISFACTORY UNSATISFACTORY Comments: i i i PITCO-089 Page 3 of 8 Rev5 10/98 i
)
r-l Responsd To High Containment Prcssuro (M:nual Containment Spray initiation) l SIMUL-7 Rev. 0 l l l Performance Step: Check containment spray - ACTUATED. Critical i Standard: Containment Spray Actuated alarm,47019:0103, verified lit. 5faldai6EN66IiEiW3hMTW5roceduriEduti6iiiT hst t ifd ECAdM lossW Ehiefgency C661anF QNy yshouldbebi
@MyglQLs@MfT@$RMdUthtidni$s.Eshd.
unan -m n s ;~- .
$Mhnsuddh+Mit@:.operatediasjirecited bp;that p~roced~ure5t 22R; J2id n imM~
a ,d y l I a;ausAunGL&wMmm. p6fthatM1EC441lha5Ln6f lEstuatdCUsiF?QFTliasilsa@m;Audinian beer nnannsg a m_ iinipleribedtsd$aaml,mW d Performance: SATISFACTORY UNSATISFACTORY l Comments: 1 < l l l l Performance Step: Check containment spray pump - RUNNING, if not start. Critical X (S-1) Standard: Containment spray pumps determined to not be running and then started by momentarily placing CS-46008 and CS-46009 to " START'; red lights lit, i I green lights extinguished. i' Performance: SATISFACTORY UNSATISFACTORY Comments: l Performance Step: Check containment spray system valves - PROPER EMERGENCY Critical ALIGNMENT (containment spray pump discharge valves MV-32103 and MV-32105). Standard: MV-32103 and MV-32105 red indicating lights 44007 and 44008 verified lit. Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 Page 4 of 8 Rev 5 10/98 l
1 l R:.sponsd To High Containment Pressura (Manual Containment Spray initiation) l SIMUL-7 Rnv. 0 l l Performance Step:
~
Check containment spray system valves - PROPER EMERGENCY l Critical X (S-2) ALIGNMENT (containment spray pump suctions from caustic standpipe CV-l 31941 and CV-31938). 1 Standard: CV-31941 and CV-31938 opened by momentarily placing CS-46124 and CS-46125 to "OPEN"; red lights lit, green lights extinguished.
;EsaldatMNoteW EThkseYalses will hAve td t%dpenid"manuAllyW # >f g <" A a +._ sa. a.aa , .a.muwu . . . u;m.axmm=:m1.wau:.: .ha.w..,zhw Performance: SATISFACTORY UNSATISFACTORY Comments:
Termina:Ing Cues: When the containment spray pump discharge valves are verified open, inform the candidate that, "this JPM is complete." Stop Time: i 1 l l l l l l t 1 l PITCQ-089 Page 5 of 8 Rev 5 10/98 l
l Responsd To High Containment Prassura (Manual Containment Sprcy Initiation) l SIMUL-7 R5v. 0 l SIMULATOR SETUP Instructor Guide: , o initialize the simulator to IC-10. o Enter malfunctions to defeat auto start of containment spray pumps. (Relative Order 0) o Enter malfunctions to fail auto opening of caustic addition valves. (Relative Order 0) o Enter malfunction to cause a 100% steamline break, inside containment, on 'B' SG. (Relative Order 0) o Place the simulator in "RUN". o Perform E-0. o 'Nhen containment pressure peaks (about 18 psig), enter malfunction to cause a 100% steamline break, inside containment, on 'A' SG. (Relat/ve Order 1) o Ensure 200 gpm AFW flow to SGs such that there is no red path on Heat Sink. o When containment pressure is above 23 psig and orange path is indicated in containment, place the simulator in " FREEZE". o When the candidate is ready, place the simulator in "RUN". i l l PITCO-089 Page 6 of 8 Rev 5 10/98
- l 8 llll 9
/
0 0 - 1 8 e i t 3 1 4 df df e e o 9 9 i s o ios - R t u 1 3 1 3 nma nm 7- A V
- I e
I a 5 V- r re e e L t o C C ut r ut r v U s v v t s pp t s pp e R l V n RuUt i uU i ia V n R IM F t - S 2 d d p ed pd e 12 n e I n e 1 1 AO AO m e m co co enn l p m it t i t ti i nn i i Pn s ls s s LtaV LtaV nIS S nIS ui ul i S o S a aa a a o CS CF CF MCM MCM t llll llll P
)
U n T i o E ll t ia t S 8 i i.
. R 0 0 0 0
f o y a O 1 1 7 r p T e S A ll g a t L P n U e m n M I B 3 A 2 B 2 B 1 A 1 0 ia t S 0 S 0 S S 0 S 0 S n C C C M M o C l a u n a M ( F F F F F e L L L L L r A A A A A s u M M M M M s e r P l1ll t n e m 1 1 1 A 1 A 1 in 0 S 0 S 0 S 0 S 0 a C C C S t n M M M M M o I S I S I S M M C I S I S h ig H $ d 0 0 0 0 I 9 s 8 n 0-o p b Q s C e T R I P l
F' TURNOVER SHEET 1 INITIAL CONDITIONS: o Steamline break inside containment has occurred. o 1E-0 has been performed, and transition to 1E-2 was directed. o The SM detects an orange path in containment. INITIATING CUES: o The SS directs you to respond to the orange path in containment per 1FR-Z.1. o Report completion to the SS. 1 PITCQ-089 Page 8 of 8 Rev 5 10/98 l l 1
JPM: 7 - jPWQUESTION OPerator: (AnswerSheet) QUESTION 1 System: CS
Subject:
l Heat Removal Capability (w/CFUs) K/A & Rating: (W)E14K2.2 3.4/3.8 Unit 1 is in Hot Shut Down, in preparation for cooldown prior to refueling with the following conditions.
- 11 Containment Spray Pump is OOS for a PM
- The RCS is borated to Cold SD A loss of bus 12 trips 12 RCP, causing an abrupt RCS pressure Question: in rease. This results in a design basis LOCA and the following conditions:
-Containment pressure is 21 psig and increasing.
-All four CFUs are tripped on overload.
-Containment Spray is manually actuated.
Explain how and why you expect containment pressure to respond over the next 15 minutes. swen Containment pressure will continue to increase at a slower rate. One CS ump cannot remove enough heat to reduce pressure in the short term.
Reference:
TS 3.3 bases page B 3.3-3 Reference Material Use: l Yes Z No O l Pedigree: 'l New CANDIDATES RESPONSE: SAT: UNSAT:
r JPM:7- :ypy_ QUESTION 'OPerator: 1
. (Answer Shect)^ '
l l QUESTION 2 System: CS
Subject:
Failure Of Caustic Addition During LOCA I K/A & Rating: 026A205 3.7/4.1 j Following a large break LOCA resulting in fuel failure, the RO notes j that the Caustic Standpipe level is not decreasing after Containment Spray actuation. Question:: What affect does the steady Caustic Standpipe level have on E Co, inment conditions? swer; Co' iment pH will be lower than expected (which will result in higher air ; iodine concentrations and increased probability for corrosion). U' 3 1 6.4.3.2
'Refem- B-18D page 8 l
Reference Material Use:V j Yes No l Pedigree: -:l New 1 OANDIDATES RESPONSE: SAT: UNSAT: l 1 l I l l l~ l
possu mmemp a ss i n m JPM QUESTION 2 JPM:7 Following a large break LOCA resulting in fuel failure, the RO notes that tne Caustic Standpipe level is not decreasing after Containment Spray actuation. What affect does the steady Caustic Standpipo level have on Containment conditions? \
JPM QUESTION 1 JPM:7 Unit 1 is in Hot Shut Down, in preparation for cooldown prior to refueling with the following conditions.
- 11 Containment Spray Pump is OOS for a PM
- The RCS is borated to Cold SD A loss of bus 12 trips 12 RCP, causing an abrupt RCS pressure increase. This results in a design basis LOCA and the following conditions:
-Containment pressure is 21 psig and increasing.
-All four CFUs are tripped on overload.
-Containment Spray is manually actuated.
Explain how and why you expect containment pressure to respond over the next 15 minutes.
l JToMA ' JOB PERFORMANCE MEASURE 3e916Mj(g@ s , l m, . WORKSHEET *:: m g y: m z m memacum TASK TITLE: Emergency Starting Of 122 Diesel Fire Pump JPM NUMBER: PLANT-8 Rev. O RELATED PRA PRA important Event INFORMATION (SEE PITC 2.3): TASK NUMBER: 086.ATI.12 / 086.ATI.14 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: J Simulate Performance: Actual Performanco: Evaluation Location: Turbine Building: C Auxiliary Building: Simulator. Control Room: Other Screenhouse Time for Completion: 10 Minutes TASK APPLICABILITY: SRO: @ RO: NLO: @ (Check all that apply) PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: i APPROVED BY: DATE: i l l Resp Grp: O Page 1 of 9 Assoc Ref: PITC TP 3.7 i 4
l Emergency Starting Of 122 Diesel Fire Pump l PLANT-8 R:v. 0 l Operator: (SROI RO / NLO) l l Evaluator: ' Date: ~ READ TO THE OPERATOR I will expla;n the initial conditions, which step (s) to simula'.e or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: o The Unit 1 SS has ordered the Control Room to be evacuated per F5 Appendix B. o You have reported to the Screenhouse. o Using PI-11082, you have discovered header pressure is O psig and that 122 Diesel Fire Pump is not runnirg. INITIATING CUES: l o The Unit 1 SS directs you to manually start the 122 Diesel Fire Pump per F5 Appendix B, Attachment L o Report completion to the Unit 1 SS. 1 l I PITCQ-089 Page 2 of 9 Rev 5 10/98 i
l Emeroency Starting Of 122 Diesel Fira Pump l PLANT-8 R:v. 0 l ! JPM PERFORMANCE INFORMATION Required Materials: Copy of F5 Appendix B, Attachment L General
References:
F5 Appendix B Task Standards: 122 Diesel Fire Pump is running. Start Time:
,.m _ . .m
_ ... _. __ , Whe,n,,,_ . NOTE: a da ust m xerc b7@o e- providi,ng it
#Ev.l.g..im6,r4,u,es,.~,,6yM,s..
e ,,, m _, avo . on Mpromptingth,w e am~ine,%4%4 ex e .,,,,,_ b,e:e
--m % wo
-.,is,. s~dj6m,.,i,d jare;only providedwhen ee wm t wuwwy y.,ically s cue QEhwarfarthceiving;ttiejnfonhatl6MidthbaiblMidoksMsks fetthelindl@ti6n)M2:
m ew w n on, n n--nn, m nn . e ~ w n -
;, 'are' W ith an?X%elowt,h,m 7.
m.aem, e ~m , ncem , n. .u... mb.ne.rHF_,ai_l,ur,e. , e m
.m -- ~ y4
_r_d._ __t._hy'_tical4s_tep,'s_hh._~ll ,res.~Q..l_t'in i_l2,a%9fallsr s maam _ _ . . . . . . . _ .. _m _ . . _m Performance Step: At panel 136-2, place DSL FIRE PMP 121 OIL STG TK Pump local Critical AUTO / REMOTE / LOCAL control switch CS-19081 in " AUTO". Standard: CS-19081 is placed in the " AUTO" position. s . Evsl.uator m,,,h to,,,,. ,m . . - o :w modr ._nm'li36
.. ,_ y,, ,m-ane 2,1s,o,n th,e n,,o,,rt,h wall b~eliind th,e D.iese , l Fire P_umpa , < E e -
sanmassmMaanmedimemme *ms&TsMimedena&&a# mamsme sl fiKths % wam aau w c e n wausaamas{CiS@9 fEp&l6atdr[Kasi5?%$ a w wmuumMm%UTdy6Eiti6iM@fyyPD , yysfF m, e .mm Q?W Performance: SATISFACTORY UNSATISFACTORY Comments: l l I-i l l PITCQ-089 Page 3 of 9 Rev 5 10/98 l t
l Emergancy Starting Of 122 Di sel Fira Pump l PLANT-8 Rsv. O J Performance Step: Ensure the Battery Charger Control switch is in "ON". Critical Standard: Battery Charger Control switch checked in "ON". [EialGaf6EDUiiii[P5QQWBiffidyClisrg&FC66trbiiMi6tiflilii"ON"P inaemikaah,a sa As JeemAw!saainC;ii naw %M[@b o.Aa6hh6@WWO Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Depress and release the RESET pushbutton CS-70394-04 located inside of Critical the diesel control cabinet. Standard: CS-70394-04 depressed and released.
, m ,_. . - .,_ m.,
valua. W_,,Cu,_e:n x. . m ' and_rele,.,. ase _._, d_, _,, yn.n._ _, . y2K M2K;' , , _Res,. ...,yet push _ button h_as;b_e_en,mde__, , o 1 iL Y ;;X:m% MwanxmcmLCMk niin.W@dawd%?lky W Performance: SATISFACTORY UNSATISFACTORY Comments: I Performance Step: Tum local 5-position selector switch CS-70394-01 to " MAN-A" or " MAN-B". l Critical Standard: CS-70394-01 turned to " MAN-A" or " MAN-B".
. .- . - . . ..c . -.
w s,, , ,
.EV, .r,;
alu_ato. e: C,,d. .~a, ,,d pos. . . . n:. ", I ,w.
,C. S-70394. 41 is~i ir,i (selecte,. _itio-. sin.N A,or,"M,AN,-B",,).,c;g,.,,
ai4di w- ) 2 mv *. Z,/ i i ' i
< ma <, i ' c m4 r? 61 .xJ ZEs. r 14 ' u ,% em e m iLA- Odd h u Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 4 of 9 Rev 5 10/98
l Emergency Starting Of 122 Dirsel Fira Pump l PLANT-8 Rev. 0 l Performance Step: Depress START pushbutton CS 70394-02 to crank engine. Critical Standard: CS-7039442 is depressed for no longer than 30 seconds.
!.Evalua_to.m _.._,,,ygr Note:W AW @Th_e e_n., n atter . ntinuously_ ;e s$$$515$$Nd6I5bi!fN15$gi_ne'is_'n_ot , ie_s c_o. . _ .1Rthah to,be,c_ra_nk,e,d,,o,,_~o_neiset'of M bn84 $ d $N M gi d dd h m =r .. , , a , ,a , . u. g, , n , , ,. ,Evalua+n wmg% w> ten ~gine torCue:gg d,o .es'not, crank.m.wn gwec y c ~m EC i ~ ' a,3na 26 % . N i w A m :1 d;yFvl n , M:bd.C, &r<& ,t. m ,. ' Clyt-::.
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Tum local 5-position selector switch to the opposite MANUAL position of the Critical position selected previously. I Standard: CS-7039441 turned to opposite " MAN-A" or " MAN-B" of the position selected previously. y. u M_._ ._, - .,403_ 7 . . - - -
,,_,y., , . .
Eva., ,n. -,_
,~~,, luato.+r C,_e:b x&+ Cm,CS,bendh,64,41Is,i,in. se on:fM,
_l_ecie,, d R,u7..,m. Jor"P. A,Nm" -B 2.,w. 0 4,:t .7
.m urawsve eemw M-a u:;&td m a
,m w.
- ux idida.cnaitwwg:n "
u _wn .nn;n n=n - n'J uiwgeGim!!ndiaWdhw.wnenxukehninw n. ? 4 n,wnhiinwe%Ranuit.a+nm - wAs~ s Performance: SATISFACTORY UNSATISFACTORY Comments: l l 1 1 PITCO-089 Page 5 of 9 Rev 5 10/98
l Emergency Starting Of 122 Diesel Firo Pump l PLANT-8 Rsv. 0 l Performance Step: Depress START pushbutton CS-70394-02 to crank engine. Critical Standard: CS-70394-02 is depressed for no longer than 30 seconds. r rank,_ed,o_n_o,. .m . __ne set of -. t . contin.._ (Eval ..,, .vNote,:h,m,, uator . ,. , Th.i. . ...,_in,,, R eng e-,is_'n_o.z..,t,o ,b_e,,c_ t ba,te,ri_es'.m, uousl .., ,,_ m j p6p. @. Q.a ni L awQ6f M....g5f. W.. N. ..s.e. M.- W-..a? W a9 I ?+.I.J. j, M, , W yn,, a.w . M%N - _aa - u ,w f
,, I
,.r,o 9 ,,..s- -
, , , e.g . .s .., y g i ,
; E.,,lu. ,.,e- n.,r ,.. 4v e ,va ator, mCue;pm
. t En,uiwsw..u, w.m.na.ow, .. me apw.p:,%yw, ,,. , egspe;does ,1 not> crank.m. w e, m _ ' u a ,.
u,a.m a m m mum w ae b a a.; a m me m ma_ ,,,,s.. -...m acy, . .- Perfonnance: SATISFACTORY UNSATISFACTORY Comments: Perfonnance Step: Determine if an Emergency situation exists. Critical Standard: Emergency situation determined to exist.
._ ,, , ..... ~._,_ . ,_ m. , ,'
,Evalua
. . , . . ..LC ,,_.___._..d._......_._._.,.._...
k,uha+w.n,toru,u,e:h.
+ e ndi.imm@nA!auws,t.rWWWM. n ..
..n#@m. ,. .fvunb 1,_22 D...,ies t "M6%idH,WmWMmliik&,,ai,el,ngn.ta _.~. -
FireLPu.- w ' ,S& T.
" M US.n! .be,,_'sta.._ rte, .he.
i g'u,ninad3HHhnIOinMu,e.~'
,w6M, n to,.n. .l,p c, ,om_
n.'t. h,,eLfir.nn bat h.r/W!a-
.n ek W+,e
- dWMWG' iv- it Wm40Mda..F .t i' ' :P Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCO-089 Page 6 of 9 Rev 5 10/98
l J l Emergency Starting Of 122 Diesel Firo Pump l PLANT-8 Rcv. 0 l l Performance Step: Turn the Manual Override Knob fully clockwise to bypass the electric ! Critical X (S-1) solenoid control and permit fuel flow. I Standard: Manual Override Knob turned fully clockwise.
.y. mr .
,,_ m m,m.m.
9w VGy h,m, tor R,o,,ts,w: ~,,,_l k,n. o eEv alua 1
. e manua b,is,m_"a small ye, llow,,Imob_on th.i.,, south,
. id, e. .of th_en ", .
's 1 L DW
$._@id.s$sa#andMmd_d?u @idiN_ibc.s_i.s_d..id. _,_ib_.d._51sN"$._f_tM..._Y.d_ fib _ !
e - - . w . n m mm mm m- wsr-we-ww , r m lwor uat Cue:rpng@p,wy.mwmmy wManualOvem e w *cdw. e Knob is fully clocN.,uqisev oy em -, m m.m pwww 1
- Eva ENe . p 7 m m pr %e y ,
J snW G0KMe0.iG@inid UGs,9%HiME G 1 m, J-'M - def 4 i+< A oi HMMiWW5 sn - Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: OPEN cooling line bypass valve to the heat exchanger FP-121-3. l Critic' X (S-2) Standard: FP-121-3 opened. 4
- pu In 4
"'[W'V'Lr', N.e,.. wM W.. . . n
- ,1a t nr.
,,jia;. .- 4 4 .t'<'-' n
, 3gn 5 . . - i n. i . . y n : t- i m& ..
W % r+ ,9 %M..vM;m 1
- -%.lu,a,)ts.,
u a a m , %ep;C' wym mowg i' us: FP"";12'+1' 'i ,3o,pe,n
+ 18"s
. eeve M b S,.
&,m:ve& ... W+ 9,i_ %,, m o -
W;a' , 3"'9 $ r.6 s? %h + d!YGai!~ Qgr%mMW@Lill2MibbW i i s
,v 2 -
,n kiii.M5 Oduhn \0nLhhMbMHik..nM ^ , AR'c' ?!%gNh h%: 4tO> L v&kk - dK r D NUkid?iUS% e < m2HiiM ddl k:khis\% O Performance: SATISFACTORY UNSATISFACTORY Comments:
PITCQ-089 Page 7 of 9 Rev 5 10/98
)
1 l Emergency Starting Of 122 Di:sel Firo Pump l PLANT-8 Rsv. 0 l i Performance Step: Lift CONTACTOR A START LEVER to the Emergency Start. I Critical X (S-3) Standard: Contactor A Start Lever lifted to the Emergency Start.
- z. . .- . . , _ . . ., .
_.....m. . r rE n~ . _ .. _ . . t._ _ -, g ,. 4Th,,A, ,Contacto,r A,.. . Starttever
.,. ._. . .. m._is,,.l _. ..,..,,. _ , _. ,h_e 'n,,o,,i,th_ side of th,,e_'e, ng~in
> ~.~ luator gpgunNo e:WW+ wa-n .
~ ,g ,ocated on
, m -.t ~~ e .- - x
$ Ud!Nb .id f ' ' ; , _ nee..N~Qidg6+0!${$6ssisdss,gg ., g!jy($2$~ij$$$ijffsejiy@,{ygg, ,,iy
- m, s.~ -. m- ,,, ,__. - .-,,..,,_____y,..,, ,,..,
ar U , & W122 Die.,~,.
,E,v,a,. lu, o.to,.md, ,u, e:.,,,,.. ,
- sel ire "F._P, ump,, start,s?;p' ~ .1 , , 4 4 A g C &, wg,,.,,, , '
WasammaaxsEnsuaximum;;e,waws;mame a w ms;wma,a;gm sia;m.ssww I Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: The candidate should report to the Unit 1 SS that, "122 Diesel Fire Pump is - running." At this point, inform the candidate that, "this JPM is complete." Stop Time: I l PITCQ-089 Page 8 of 9 Rev 5 10/98
TURNOVER SHEET INITIAL CONDITIONS:
. The Unit 1 SS has ordered the Control Room to be evacuated per F5 Appendix B. . You have reported to tha Screenhouse. . Using PI-11082, you have discovered header pressure is O psig and that 122 Diesel Fire Pump is not running.
INITIATING CUES:
. The Unit 1 SS directs you to manually start the 122 Diesel Fire Pump per F5 Appendix B, Attachment L. . Report completion to the Unit 1 SS.
r I l l PITCO-089 Page 9 of 9 Rev 5 10/98
\
PRAIRIE ISLANo NUCLEAR GENERATING PLANT NORTHERN STATES POWER CoMPAW PLANT SAFETY PROCEDURES 1~ TITLE: NUMBER: CONTROL ROOM EVACUATION (FIRE) F5 Appendix B l
' 'Section REV: 19 , t 1}
Page 1 of 3 ATTACHMENT L - LOCAL STARTING & STOPPING OF 122 DIESEL DRIVEN FIRE PUMP l cCAllTIOll:} AVOID PUMP!NG AGAINST A DEAD HEAD FOR MORE l l THAN 5 MINUTES. A. Starting 122 Diesel Fire Pump Manually
- 1. At panel 136-2 (north wall behind Diesel Fire Pump), place DSL FIRE PMP 121 OIL STG TK Pump local
- AUTO / REMOTE / LOCAL control switch CS-19081 in " AUTO".
- 2. Ensure the Battery Charger Control switch is in "ON".
- 3. Depress AND release the RESET pushbutton CS-70394-04 located inside of the diesel control cabinet.
- 4. Turn local 5-position selector switch CS-70394-01 to " MAN-A" OR " MAN-B". -
i
' C (J T/ O tl,5 ? WHEN STARTING 122 DIESEL FIRE PUMP MANUALLY,1;LQ 5
mi p 3, NO_I CRANK THE DIESEL ON ONE SET OF BATTERIES f,-
, ,t ';
CONTINUOUSLY FOR LONGER THAN 30 SECONDS.
- 5. Depress START pushbutton CS-70394-02 to crank engine.
Release the pushbutton when the diesel starts.
- 6. IE the engine fails to start within 20 seconds, or If the engine fails to crank, THEN turn the local 5-position switch to the opposite MANUAL position of the position selected in Step 4.
above AND repeat Step 5.
- 7. lE engine fails to start in either " MAN-A" OR " MAN-B" position AND it is required for an emergency situation, THEN continue with Step 8.
Page 55 of 102
m 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY PLANT SAFETY PROCEDURES ( - TITLE: NUMBER: f CONTROL ROOM EVACUATION (FIRE) F5 Appendix B
. [ISec' tion y g REV: 19 1
1 Page 2 of 3 l ATTACHMENT L - LOCAL STARTING & STOPPING OF 122 DIESEL DRIVEN FIRE PUMP (Continued)
,.#*}
"A, IN in case f failure f the DDFP control panel, the diesel may l
$wn, UTE*${\t'*
,l' M ' . j, u
be started by using engine mounted controls. The shut-down solenoid valve manual override knob la j(Rdd ti90[b.J.Jfpainted }g' Wyellow ANQ is located on the solenoid valve. The s i
? NOTE:O
- knob faces the oil filter. The solenoid valve is mounted on ;
$ $ ~ [ 0 I ',., top of the fuel pump. the fuel pump is located to the left of '
%QM yWjp the oil filter.
- 8. Turn the Manual Override Knob fully clockwise to bypass the electric solenoid control and permit fuel flow.
- 9. OPEN cooling line bypass valve to the heat exchanger FP-121 -3.
-y ans
;4w,4: 4 h , ' ,q - 4 The emergency start magnetic switches, labeled CONTACTOR A START LEVER and CONTACTOR B START pMU
; NOTE; t.,by$ JF- LEVER, are located on the north side of the engine, i
' ' ' ~
between the battery cable conduit support and the engine
., f _ block.
.n_ w , , -
w-
- ~ . . . .
3CAUTIONi@.. DO.NOT CRANK THE DIESEL ON ONE SET OF BATTERIES M nr, p G Q,.;i,W mM h n, ia CONTINUOUSLY FOR LONGER THAN 30 SECONDS. ;
- 10. Lift CONTACTOR A START LEVER to the Emergency Start .
- 11. lE engine fails to start within 20 seconds, THEN lift CONTACTOR B START .
l Page 56 of 102
PRAIRIE ISLAND NUCLEAR GENERATING PLANT N8RTHERN STATES POWER COMPANY PLANT SAFETv PROCEDURES "E TITLE: NUMRER: CONTROL ROOM EVACUATION (FIRE) F5 Appendix B
; Section- REV: 19 Page 3 of 3 ATTACHMENT L - LOCAL STARTING & STOPPING OF 122 DIESEL DRIVEN FIRE PUMP (Continued)
B. Stoppina 122 Diesel Fire Pumo NOhE*,'_' All w 122 Diesel Fire Pump to operate at a minimum flow
. for 3 to 5 minutes before stopping the dh.sel engine.
- 1. E the pressure is less than 95 psig AND no emerg'ency stop is necessary, THEN, allow the diesel to run until pressure is above 100 psig.
WOTE.h.: ' [; The OFF position is also used to lock controls out of 94 - service.
- 2. Place the local 5-position selector switch CS-70394-01 in
" AUTO".
- 3. E required THEN CLOSE MV-32134 using pushbutton PB-19035.
- 4. E required, THEN CLOSE FP-30-4,122 DD FP DISCH TO TEST HDR.
C. Stooping Dieselfire Pumo When Started by Engine Mounted Controls NdTE' ~ Th* ' " "'"9 Step will return the shutdown valve to electric solenold control.
- 1. Turn the Manual Override Knob fully counterclockwise to isoiate fuel to the engine.
- 2. CLOSE cooling line bypass valve to the heat exchanger FP-121-3.
Page 57 of 102
JPM:8 Operator: JPM ' QUESTION (Answer Sheet) i QUESTION 1 System: Interlocks That Protect The Turbine Fire Protection
Subject:
Generator Exciter KIA & Rating: 086K407 2.5/2.8 A fire has occurred in the Unit 1 turbine generator exciter. The turbine bearing pre-action valve (PA-14) has opened. Exciter bearing i ne 244 is in alarm. Question: What operator action (s) is(are) required to establish water flow l through the sprinkler system? a) Deenergize the exciter (open the field breaker)
' Answer' b) Open FP-134-1, Exciter Bearing Fire Protection Manual Valve Reference, F-5 App. A, Zone 24, Rev 5 C31, 5.11, P. 52, Rev 23 i Reference Material Use: - l Yes @ No O l Pedigree: - l New CANDIDATES RESPONSE: SAT: UNSAT:
4 l j l J
f I l JPM:8 Operator:
.JPM QUESTION (AnswerSheet).
QUESTION 2 System: Fire Protection Subjact: Action For Fire in The Plant (PRA I Important Event) KIA & Rating: 2.4.27 3.0/3.5 l A fire alarm in Zone 19 has occurred. The Reactor Head Vent System contains PRA important equipment and is affected by a fire in this Question: l What action (s) must be taken to reduce the probability of core damage? Open Panel 11, Ckt 18 and Panel 16, Ckt 18. (Deenergizes Panels 191 Answer: and 162 respectively) This is done to deenergize Reactor Head Vent Solenoid power. Refme,* F5 App. A, Zone 19, P.2, Rev 5 F5 App. D, P. 39 & 40, Rev 4 Reference Material Use: l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: i l l
b JPM QUESTION 2 JPM:8 A fire alarm in Zone 19 has occurred. The Reactor Head Vent System contains PRA important equipment and is affected by a fire in this zone. I What action (s) must be taken to reduce the probability of core damage? l l l
)
l l l l l l l l
JPM QUESTION 1 JPM:8 A fire has occurred in the Unit 1 turbine generator exciter. The turbine bearing pre- j action valve (PA-14) has opened. Exciter bearing Zone 24-9 is in alarm. What operator action (s) is(are) required to establish water flow through the sprinkler system? l l l i l
r 3 i' OR SHEET - . . I l TASK TITLE: Vent Containment Using Post LOCA Vent System JPM NUMBER: PLANT-9 Rev. O l I RELATED PRA None INFORMATION j (SEE PITC 2.3). j TASK NUMBER: 024.ATI.04 KIA NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: Simulate Performance: Actual Performance: l Evaluation Location: Turbine Building: O Auxiliary Building: @ Simulator: Control Roont Other l Time for Completion: 6 Minutes ) TASK APPLICABILITY: SRO: RO: @ NLO: @ (Check all that apply) ; PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: APPROVED BY: DATE: l Resp Grp: O Page 1 of 6 Assoc Ref: PITC TP 3.7
p 1 l l Vent Containment Using Post LOCA Vent System l PLANT-9 Rav. 0 l l l Operator: (SRO / RO / NLO) ! Evaluator: Date: l READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be ; satisfied. I l INITIAL CONDITIONS: l o Unit 1 is at power and containment pressure is at 1.3 psig. o Communications with the Control Room have been established. INITIATING CUES-o The Unit 1 SS directs you to vent Unit 1 containment using the post LOCA vent system (Train A 11 l only) per C19.4, beginning at step 5.1.5. o Report completion to the Unit 1 SS. PITCQ-089 Page 2 of 6 Rev 5 10/98
1 [ Vent Containment Using Post LOCA Vent System l PLANT-9 Rev. 0 l 1 JPM PERFORMANCE INFORMATION Required Materials: Copy of C19.4, Section 5.1. General
References:
C19.4 Task Standards: Train A 11 post LOCA vent simulated in service to vent containment pressure. Start Time: NOTWW6iirii.mm ymy um% siiiMaih. m. DMNGiMED0iismen w wwe= t6WA56thi@*$asiWukiWessicisWd w v.e se M!1 Wisidia psy p ' ti uw the'examineesTyp~ically;;wdhe~m n cues'are only provided whe%'xwm examinee n the examinee'e looks'a
.ww:actionsN ra%.~qq
. A . . .
w vwing tHmh~nfo,..rm,a._ tion.(i.e .- w.. wuww
- - - -. - . _ .. or-was. ks ev ~emf.-.rt.o..ah.I annn.y,~m_d.,
dicat
. ..e~.n.. -.. . .ko-)
j-- ~1 & St rm. zen 7 e.1 g *g5g-'s ljaqbp ; W?ty; sa re -ea t'.qpe; *c yt r c up jgg. ph yM4MjQq.1g}gn ingMtg v. Sm. g 4 l Wje.---H 'are,y'gleggko ggy tg--ma edwith'gq6ge an eX" be"+ow l thelk M)q 9g1'tg3pqhtteglperformancIS._,e si,1M.ep number.t Fali]ure
%q q%gR - g - -.wag_ g... ~. g g..._ g g -g g g ggyg g.Jgu yswsu,g3
.-, ..- ..- ~ _ . . . . . - - . . ~ . ..
e m-4, Performance Step: Remove the control switch cover lock for MV-32271 Train A 11 Post LOCA Critical X (S-1) Hydrogen Control Vent Isolation (Key 222). Standard: CS-70905-01 cover lock removed.
, , , m, .- ,_ m, , . . - , - - . . y
-wm N %me. TN_stJ PM -is~p,er. R l- c EU,s,,,u,s,t.orh,o_ter_%g_ndMleA95'Jlevatio, a ~. o ~ -n v + n.
formed nun from th,e;H,yd~r endelEbbi
,Ev,,a.ld,stor n
C,u~e:m_-c;- , n,,CS-70905%- Icover
~ _,lo,ck is,u . removed, , , , - , nn , , , .
m- c- e,, M wam M &wde Law es C m m m;m eie+M.; %m#R MAsedda MsWe Performance: SATISFACTORY UNSATISFACTORY l Comments: , 1 PITCQ-089 Page 3 of 6 Rev 5 10/98 i
1 l Vent Containment Using Post LOCA Vent System l PLANT-9 R3v. 0 l l l Performance Step: OPEN MV-32271 Train A 11 Po.st LOCA Hydrogen Control Vent isolation. Critical X (S-1) i Standard: MV-32271 opened using CS-7090541. ) m m, . m . . . , _ ....m . m
;E,m valu_atord, ote:3 _ %.
, ., , qNT .he c_andid_ ate.... i
_may.dm. __. . _u.s-,,_i,r.e, men ._._t f.o....m._hs
, o- ,- 4 .-. .scuss.~the- ,..wa mo . ,W. _,_mran . s , ii
. a_ ca.- . l.s uw'. c. ' - am. this~v.a....l_~veLwithm
- m _. ._
in'one min,,u_te fol~l. . _ _ _ . _.__ ac.,. ...c. _ ..._ide_~nt/a n... g_an..... a.m._WcC U., 4 lEy51ustMC0e:QS x umm aw m WMR5dIi66 amua(lEiffessli6hfestiN6EisIAdfdEM$5257R[Tf7
. .hgasegasmseammm Aht,s,g,s , M7 Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Remove Train A Hydrogen Post LOCA Panel cage ccver lock (Key 222). I Critical X (S-2) Standard: Train A Hydrogen Post LOCA Panel cage cover lock removed. y .~. . ,. - m ,m ~ m omm m . em . _ . _ .
~Evaluato_. r %y Tr~a,n s A S. ,m ,ydrogen.< m s'.~ P ck remove s
su w o. Cue:y
,n ,- yA v
L
.,. -- w we,ea. m ww n.:Post
< w, vue wen.LOCA.7_anel s s em,ancag,e
,,wM%dk.a,ak saw uum coverlo e mUa.a_-.cm, en v m.v:~u m-
~,_d.4 us
' N +A mm ,+ m.r,.
.a .n..
Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Tum the Foxboro Air Switch (CS-28252), to the " MAX" position to align the Critical X (S-2) large flow control office. Standard: CS-28242 turned to the " MAX" position. m . -- ~ . -. -
. ~ lua..torCu,e:> .
. .,-~ .. ,- m,_ , -,
Eva KCS;28242 is inthe, l ' MAX",._i,ti.._,m. pos oniEO?' E, o~ , V, ; '~ g a;&. a ~ : wa '%u a w .a n a % & ,, u n . sw s ,,x a, n, Performance: SATISFACTORY UNSATISFACTORY Comments: PITCO-089 Page 4 of 6 Rev 5 10/98
l Vent Containment Using Post LOCA Vent Syst:m l PLANT-9 Rav. 0 l Performance Step: Increase the pressure setting on the manual Foxboro Air Controller ML-l Critical _ X (S-3) 28124 to 10-15 psig to open CV-31923. Standard: ML-28124 setting increased to 10-15 psig. i ! Evaluator [ Cue (if. - ',4 'JMCE2812 a m2nwa;m .in L _ ,cnmand4[pressdrel15Bidaf6Elrsid(13lpsis.$
'J " N a .;a a.1 l ru;
@ iauhM 1
l
- m. n _sm= ,. em ,_
l Performance: SATISFACTORY UNSATISFACTORY 1 1 Comments: 1 1 Terminating Cues: When the foxboro air controller is simulated being set at 10 to 15 psig, , inform the candidate that, "this JPM is complete." l l l Stop Time: l l 1 l l PITCO 089 Page 5 of 6 Rev 5 10/98 1 l
TURNOVER SHEET INITIAL CONDITIONS: o Unit 1 is at power and containment pressure is at 1.3 psig. e Communications with the Control Room have been established. 1 INITIATING CUES: o The Unit 1 SS directs you to vent Unit 1 containment using the post LOCA vent system (Train A 11 only) per C19.4, beginning at step 5.1.5. o Report completion to the Unit 1 SS. 4 i l I I PITCO-089 Page 6 of 6 Rev 5 10/98 l t
l l PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN CTATES POWER COMPANY OPERATING PROCEDURES
~ l l g TITLE NUMBER:
l '
- C19.4 POST LOCA VENT SYSTEM DEPRESSURIZING THE REV:
12 g ;secuorij CONTAINMENT VESSEL Page 1 of 7 TABLE OF CONTENTS 1.0 PURPOSE . . . . . . . . . . . . .......... ............. .. ...... . 2 2.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . ....................... 2 3.0 PR EC AUTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 LI M ITATI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 l 5.0 PROCEDURES.............................................. 3 5.1 S t a rt u p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5.2 S h ut d own . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 6. 0 ATTAC H M E N TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
7.0 REFERENCES
.............................................. 7 7.1 Developmental References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 7.2 Implementing References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 CONTINUOUS USE
- Continuous use of procedure required.
- Read each step prior to performing.
I
- Mark off steps as they are completed. -
- Procedure SHALL be at the work location.
. /7 0.C. REVIEW DATE:
REVIEWED BY: ff h DATE: // /3 APPROVED BY: DATE: r-
//[
i V L
3 7 l-l PRAIRIE lsLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: C19.4 [i POST LOCA VENT SYSTEM
^
REV: DEPRESSURIZING THE 12 TsscuoM CONTAINMENT VESSEL p ,g i 1.0 PURPOSE This section describes the operation of the Post LOCA Hydrogen Control System for controlling the positive pressure within the Containment Vessel. It is used to reduce the containment pressure prior to placing either the Containment Purge System or the Containment in-Service Purge System in use or when Containment Vessel pressure exceeds = 1.3 psig, on ERCS Computer point 1U1000A. The Containment Vessel pressure is vented to the respective units shield building stack. The 1-R-11/12 (2-R11/12] sample selector switch is left in the CONTAINMENT position in order to be conservative and to account for the low recirculation in the shield building stacks with only the Shield Building Ventilation fans running. This procedure may be used alone or in conjunction with the Containment Purge System (C19.2) or the Containment In-Service Purge System (C19.2). The Unit 2 numbers appear in brackets. Post LOCA Control for Unit 1 is on the Unit 2 side of the Aux Bldg, and Unit 2 Post LOCA Controlis on Unit 1 side of the Aux Bldg. 2.0 PREREQUISITES i 2.1 If a short term containment release has not occurred since the unit was last placed into cold shutdown, a pre-release sample and a Containment Pre-release Authorization SHALL be completed and approved by the Duty Chemist. 2.2 A minimum of 2 channels of Radiation Monitors for each unit to be purged (1-R-12 and l 1-R-22 or 2-R-12 and 2-R-22). I 3.0 PRECAUTIONS 3.1 If at any time Containment isolation is required, CLOSE all Post LOCA valves j immediately. I 3.2 Terminate the release if at any time 1-R-12 [2-R-12] or 1-R-22 [2-R-22] become inoperable. 4.0 J IMITATIONS i 4.1 An operator, with a radio, SHALL be available in the Aux Bldg during the depressurization to ensure Containment Isolation can be completed within 1 minute of a Containment Isolation Signal. 4.2 If Containment Vessel pressure is greater than 2 psig, refer to T.S.3.6.l. l ,
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES 7,7tg NuuseR: POST LOCA VENT SYSTEM C19.4 REV: DEPRESSURIZING THE 12 LSectiAn < CONTAINMENT VESSEL p,g , 3 ,, 7 5.0 PROCEDUREr 5.1 Startup 5.1.1 IE necessary, THEN request a sample and Containment f Pre-release Authorization from the Duty Chemist. . 5.1.2 The Shift Supervisor SHALL verify that the Post LOCA purge is allowed and verify that the 1-R-12 [2-R-12] and 1-R-22 [2-R-22] setpoints are at or below the calculated setpoints on the Containment Pre-release Authorization. .
'/'
5.1.3 IE using a Containment Pre-release Authorization, THEN log the initial containment pressure and date on the last page. 7
.M _
5.1.4 Start either the Train A Shield Building Ventilation Fan or the Train B Shield Building Ventilation Fan for Unit 1 [2]. Both Shield Building Ventilation Fans can be run if it is desired, but l only one fan is required. Log the time and the number of vent j fans started on the Containment Pre-release Authorization AtlQ notify the Duty Chemist. , [CNhTION!? TO ASSURE PROPER ADMINISTRATIVE CONTROL OF MV-32271 [MV-32290] WHILE OPEN, THE FOLLOWING E REQUIREMENTS SHALL BE SATISFIED: q
- 1. AN OPERATOR SHALL BE DESIGNATED TO HAVE THE 6 M RESPONSIBILITY FOR CLOSING WITHIN ONE MINUTE
> FOLLOWING AN ACCIDENT.
- 2. CONSTANT COMMUNICATION SHALL BE ESTABLISHED BETWEEN THIS OPERATOR AND THE
, . CONTROL ROOM TO FACILITATE DIRE 70N.
i
- 3. AN EVALUATION OF EXPECTED ENVIRONMENTAL CONDITIONS, FOLLOWING AN ACCIDENT, SHALL BE MADE TO VERIFY ACCESSIBILITY. l l
5.1.5 Remove the control switch cover lock for MV-32271 l [MV-32290] Train A 11 [21] Post LOCA Hydrogen Control Vent isolation (Key 222). 5.1.6 OPEN MV-32271 [MV-32290] Train A 11 [21] Post LOCA . Hydrogen Control Vent isolation. l l
)
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES N ' TITLE NUMBER:
@ POST LOCA VENT SYSTEM C19.4 REV; DEPRESSURIZING THE 12
, cSecuoni CONTAINMENT VESSEL Page 4 of 7 5.1.7 Remove Train A Hydrogen Post LOCA Panel cage cover lock (Key 222).
5.1.8 Turn the Foxboro Air Switch (CS-28242 [CS-28244]), to the
" MAX" position to align the large flow control orifice.
[CMhTIOMD TO ASSURE PROPER ADMINISTRATIVE CONTROL OF CV-31923 (CV-31924] WHILE OPEN, THE FOLLOWING REQUIREMENTS SHALL BE SATISFIED:
- 1. AN OPERATOR SHALL BE DESIGNATED TO HAVE THE
/n W e RESPONSIBILITY FOR CLOSING WITHIN ONE MINUTE FOLLOWING AN ACCIDENT.
^
- 2. CONSTANT COMMUNICATION SHALL BE
'^'
, ESTABLISHED BETWEEN THIS OPERATOR AND THE CONTROL ROOM TO FACILITATE DIRECTION.
e': <
- 3. AN EVALUATION OF EXPECTED ENVIRONMENTAL
^
s $ji CONDITIONS, FOLLOWING AN ACCIDENT, SHALL BE
,x 3> MADE TO VERIFY ACCESSIBILITY 5.1.9 increase the pressure setting on the manual Foxboro Air Controller ML-28124 [ML-28170] to 10-15 psig to open CV-31923 [CV-31924].
S.CM. . UTI. ON..h. , TO ASSURE PROPER ADMINISTRATIVE CONTROL OF t MV-32273 [MV-32292] WHILE OPEN, THE FOLLOWING M > M- REQUIREMENTS SHALL BE SATISFIED:
^
, 1. AN OPERATOR SHALL BE DESIGNATED TO HAVE THE RESPONSIBILITY FOR CLOSING WITHIN ONE MINUTE FOLLOWING AN ACCIDENT.
- 2. CONSTANT COMMUNICATION SHALL BE s
.c > ESTABLISHED BETWEEN THIS OPERATOR AND THE p'
"~
CONTROL ROOM T ~) FACILITATE DIRECTION.
- 3. AN EVALUATION OF EXPECTED ENVIRONMENTAL CONDITIONS, FOLLOWING AN ACCIDENT, SHALL BE MADE TO VERIFY ACCESSIBILITY.
I I 5.1.10 Remove the control switch cover lock for MV-32273 I [MV-32292] Train B 12 [22] Post LOCA Hydrogen Control Vent I isolation (Key 222). ! l l I
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: A POST LOCA VENT SYSTEM C19.4 DEPRESSURIZING THE REV: 12 ES suoni CONTAINMENT VESSEL p,,, 3 ,, 7 5.1.11 OPEN MV-32273 [MV-32292] Train B 12 [22] Post LOCA Hydrogen Control Vent Isolation. 5.1.12 Remove Train B Hydrogen Post LOCA Panel cage cover lock (Key 222). 5.1.13 Turn the Foxboro Air Switch CS-28243 [CS-28245]'to the
" MAX" position to align the large flow control orifice.
iCAl/TIOAI.h '
~ ' ' '
TO ASSURE PROPER ADMINISTRATIVE CONTROL OF CV-31929 [CV-31930] WHILE OPEN, THE FOLLOWING REQUIREMENTS SHALL BE SATISFIED:
* ~ '
m ,
- 1. AN OPERATOR SHALL BE DESIGNATED TO HAVE THE RESPONSIBILITY FOR CLOSING WITHIN ONE MINUTE pg "
FOLLOWING AN ACCIDENT.
,xm
- 2. CONSTANT COMMUNICATION SHALL BE ESTABLISHED BETWEEN THIS OPERATOR AND THE CONTROL ROOM TO FACILITATE DIRECTION.
s J g 3. AN EVALUATION OF EXPECTED ENVIRONMENTAL CONDITIONS. FOLLOWING AN ACCIDENT, SHALL BE MADE TO VERIFY ACCESSIBILITY. 5.1.14 increase the pressure setting on the Foxboro Air Controller ML-28126 [ML-28172] to 10-15 psig to open CV-31929 [CV-31930]. 5.1.15 WHEN the Containment Pressure is less than 0.5 psig,IBEN terminate the depressurization by proceeding with Step 5.2.1. 5.2 Shutdown 5.2.1 CLOSE MV-32271 [MV-32290] Train A 11 [21] Post LOCA Hydrogen Control Vent isolation. 5.2.2 CLOSE MV-32273 [MV-32292] Train B 12 [22] Post LOCA Hydrogen Control Vent isolation. 5.2.3 Decrease the pressure setting on the Manual Foxboro Air Controller ML-28124 [ML-28170] to the Minimum Setting to close CV-31923 [CV-31924].
PRAtRIE IS' 4ND NUCLEAR GENERAL *NG PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: e '$ POST LOCA VENT SYSTEM C19.4 DEPRESSURIZING THE REV: im. 12
? section? CONTAINMENT VESSEL p,,, , ,, 7 5.2.4 Decrease the pressure setting on the Manual Foxboro Air Controller ML-28126 [ML-28172] to the Minimum Setting to close CV-31929 [CV-31930].
5.2.5 Install the control switch cover lock for MV-32271 [MV-32290], Train A 11 [21] Post LO^% Hydrogen Control Vent isolation. 5.2.6 Install the control switcli cover lock for MV-32273 [MV-32292], Train B 12 [22] Post LOCA Hydrogen Control Vent isolation. 5.2.7 Install Train A Post LOCA Panel cage cover lock. 5.2.8 Install Train B Post LOCA Panel cage cover lock.. 5.2.9 STOP the Shield Building Ventilation Train that was started in Step 5.1.4. 5.2.10 Fifi in the Containment Pre-release Authorization as to the final containment pressure, date and time the Shield Building Ventilation was stopped M notify the Duty Chemist. 5.2.11 Verify the Shield Building Ventilation System is in a " STANDBY" status. 5.2.12 Independent Verification that MV-32271 [MV-32290], Train A 11 [21] Post LOCA Hydrogen Control Vent Isolation is CLOSED M control switch cover lock installed. 5.2.13 Independent Verification that MV-32273 [MV-32292], Train B 12 [22] Post LOCA Hydrogen Control Vent isolation is CLOSED E control switch cover lock installed. 5.2.14 Independent Verification that CV-31923 [CV-31924], Train A 11 [21] Post LOCA 2H Vent Press CV is CLOSED E Train A Post LOCA cage cover is CLOSED with lock installed. 5.2.15 Independent Verification that CV-31929 [CV-31930], Train B 12 [22] Post LOCA H 2 Vent Press CV is CLOSED E Train B Post LOCA cage cover is CLOSED with lock installed.
]
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURg l
'^y
- TITLE NUMBER:
' ' POST LOCA VENT SYSTEM C19.4 REV: DEPRESSURIZING THE 12
~ tsections CONTAINMENT VESSEL p,, 7 y 7 5.2.16 1E the containment purge release is to continue using either the Containment Purge System or the Containment in-Service Purge System, THEN complete the purge release in accordance with C10.2. Otherwise, sign the Containment ,
Pre-release Authorization AND return it to the Duty Chemist. 6.0
- ATTACHMENTS NONE
7.0 REFERENCES
7.1 Developmental References 7.1.1 Logic Diagram NF-40776, Containment Hydrogen Control System 7.1.2 Flow Diagram NF-39251, Post LOCA Hydrogen Control System 7.2 Imolementing References 7.2.1 Technical Specification T.S.3.6.l. l d l
JPM: 9 Operator:. JPM QUESTION
- (AnswerSheet)
QUESTION 1 Systemt. Post LOCAVent
Subject:
Inservice Purge Response To SFP High l Radiation K/A'& Rating:. 029K403 3.2/3.5 The following Unit 1 plant conditions exist initially:
- Plant in Refueling Shut Down
- Fuel movement in progress in Containment & Spent Fuel Pool
- ( - Spent Fuel Pool normal ventilation in service Question'1 : - Containment inservice Purge in service The top nozzle separates from a spent fuel element on the SFP crane and R-25 is in high alarm What is the affect (if any) on Sent Fuel Pool ventilation?
121 SFP normal supply and exhaust fans stop, Answer:- 121 Spent Fuel and in-Service Purge exhaust fan continues to run (discharge to Unit 1 exhaust stack). B-11, Pg. 33, Table B11-1 C47047 for R-25
Reference:
NF-40757-1 Drawing SFP-004 Reference Material Use: "l Yes @ No O l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: l i
JPM: 9 Operator: JPM QUESTION
.(Answer Sheet)
QUESTION 2 Systera: " " "
Subject:
Sources Of Hydrogen in Containment C K/A & Rating: 028K503 2.9/3.6 Question-*
" "'" E * * *I9 " **I* ^' * * "'" * ***"I"**
Hydrogen production? Answer: Zirc Water reaction, radiolitic decomposition of water, corrosion of metals
Reference:
Tech Spec basis 3.6 page B.3.6-2 Reference Material Use: l Yes O No @ l Pedigree: l New CANDIDATES RESPONSE: SAT: UNSAT: l l 1
i l JPM QUESTION 2 l ! JPM:9 Following a design Basis LOCA, what are the three sources of Hydrogen production? l l l l l l l l l l l l l
JPM QUESTION 1 JPM:9 The following Unit 1 plant conditions exist initially:
- Plant in Refueling Shut'Down
- Fuel movement in progress in Containment & Spent Fuel Pool
- Spent Fuel Pool normal ventilation in service
- Containment inservice Purge in service The top nozzle separates from a spent fuel element on the SFP crane and R-25 is in high alarm What is the affect (if any) on Sent Fuel Pool ventilation?
I i
q w T; RED ^ JOB PERFORMANCE MEASURE LReyg(n10p
%N6T$ N WORKSHEET MY$4@@5fN i
TASK TITLE: Transfer Unit 2 480v Busses To Their Altemate Supply JPM NUMBER: PLANT-10 Rev. O RELATED PRA None INFORMATION (SEE PITC 2.3): TASK NUMBER: 062.ATI.32 K/A NUMBERS: 2.1.23 APPLICABLE METHOD OF TESTING: 1 Simulate Performance: Actual Performance: l Evaluation Location: Turbine Building: O Auxiliary Building: Simulator Control Room: Other: SBO Building Time for Completion: 7 Minutes TASK APPLICABILITY: SRO: RO: NLO- ' (Check all that apply) PREPARED BY: Mark J Jones DATE: 3/29/99 REVIEWED BY: DATE: APPROVED BY: DATE: Resp Grp: O Page 1 of 9 Assoc Ref: PITC TP 3.7
l Transfer Unit 2 480v Busses To Their Altemato Supply l PLANT-10 R;v. 0 l Operator: (SRO / RO / NLO) Evaluator: Date: 3 READ TO THE OPERATOR I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: o - Unit 2 is in Cold Shutdown. o Bus 26 needs to be isolated for a PM. INITIATING CUES: o The Control Room Operator directs you to transfer busses 221 and 222 to their alternate supply using 2C20.6, Sections 5.15 and 5.17 respectively. o Report completion to the Control Room Operator. l l l i l l PITCO-089 Page 2 of 9 Rev 5 10/98
l Transfer Unit 2 480v Busses To Their Alternata Supply l PLANT-10 Rev. 0 l JPM PERFORMANCE INFORMATION Required Materials: Copy of 2C20.6, Sections 5.15 and 5.17 marked up as follows: Steps 5.15.1 through 5.15.7 compieted Steps 5.17.2 through 5.17.6 completed. General
References:
2C20.6 Task Standards: Busses 221 and 222 transferred to their alternate supply. Start Time: ne. ,,, ,,r.n g, n m a 1
.roGidingf u raOTw ;!W,h.en,'pw.ma .
est n~ex n . - m m m,,,n exe
.- nn,eetca,re:mu.st, m." exam.~inee m g actionin<
M mg.
> prompting t,he exa m.mm mineeR.n call # mm%.w,ly
~n cues'areon proVid . the m m,, v _receivin~g,,en rn,
_ thel._ n n
._ _on _et _ _mm-n n vnn~n,nnex jorasks
_ neefor.the.. _.oo. u _ _ _a n)m cation tb .s? 3
.~ . . ~ - . -
i 1 um OTEin~ . tic.ste_ps _al_ . _,m -~ . _ _. nce _ w-. :num e _ __6'_r$Fsil_ure_to; m&_ i Nsdnfpeet; m. n.,'are mark _edWit~h a_nf, X7.tielo_w th_e l h g .~fMhw i n Atanda_._ w.e
. . y, _lj tica c.n ~itesult pi un(nl ure3 tiid@n- g sk Performance Step: Rack BKR 221 A, BUS 221 SOURCE FROM 22A XFMR, to the Critical " CONNECT' position per C20.6-1.
Standard: Safety equipment (Fireman's Coat Hard Hat with Face Shield, Gloves) obtained and BKR 221 A racked to the " CONNECT' position.
, v n >. n -,c , ,nmnann an,w .~ .w
- me Mp~Rackinga aker n'a"se=mn t,s =a .,n na the'can
,,_di e ih .ica et.
untor N n wwww"parate t ust have w!- ;sm set :w & x~. nt1s . mu ~d
~ m.be.a worn'and
~u wmeme + thel + ,
Whers O&en w , , mn, wy'y h x x ,4,4merme e.a e .. n-re p., m;a;n v mugypue gym nm:s > wmg -,_ *A > b$$.b1Mi((bk bb hi.1 $[,, Id!T$ M . . . . . dbbbib bbEN $'b $$bbbd$h gjigggpWWWBKR221A"is'_ INTR"CONm. W%g$M9M " "x_",
- m. ...- n_. e._,n;a;_mm.a _um guy;y4 a mm;a m $5,iftI66fo $x $m, m _M,g
.. ., .m .. m ma ~ ,_
1 l Performance: SATISFACTORY UNSATISFACTORY l Comments: I l PITCO-089 Page 3 of 9 Rev 5 10/98
I 1 ( l Transfer Unit 2 480v Busses To Their Altarnats Supply l PLANT-10 Rev. 0 l Performance Step: Verify 7300426,22A XFMR 480V POTENTIAL IL Green, is ON. Critical Standard: 7300426 green light on bus 221 and 222 control panel verified on.
,a awu g.;gFEvsluiddCusiiWWW%7300426ficenli wn.wwghm;uxan n.auiw w.~wue.u~;w n naw n. wa.o
.x .x ht1s gamn ONNWMWN n mm.n..naw y Wid ~ v 1 Sx Mv.%W
,mman,n - g C
-~.. a a v. m._a s _ . . .
I 1 1 1 Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: Place CS-7300407, BKR 221M BUS 221 SOURCE FROM 221M XFMR, in Critical X (S-1) "OPEN". Standard: CS-7300407 placed in "OPEN".
,E,valuator.._ m .. . m -
- m. , _
,chesk,ed. . _,. -..,in . ~. n.m .. ~ .Lthe follow g are;i dica _ted/ob_ served:, , a, _ . ,,,
kh c0 ;C_ue:e kYbhNnk F , m$:_0fkY,22YhN$hhhhf5 hNcnL .x
;y -L mg , m.a.w zw ,: . ,mem.~7300409/ Bus 2,21Voltme.t.er%. dic.,ht.e.,s w...7n ; +.yw. g .T W ug(M
- ~.- ~ , . -
$ - 0 g-vo,.ltst
- ~ . -
W. , W e .. >, 1 Hea:t sa@F % : 'Q,emwnh.sgf_jQf.._
# M sP CWannunciator"47524 9 s ,M igg"e,ggtiMP,70206lBss M W 221[480,Volth C W M 9 %,A9 ,; A i 4 .% ,m 44aw,% o m . _ .. . # wm # , ym m.. ,
Performance: SATISFACTORY UNSATISFACTORY Comments: i 1 4 1 I PITCQ-089 Page 4 of 9 Rev 5 10/98
1 l Transfer Unit 2 480v Busses To Their Alternats Supply l PLANT-10 Rev. 0 l Performance Step: Place CS-7300410, BKR 221 A BUS 221 SOURCE FROM 22A XFMR, in Critical X (S-2) "CLOSE". 1 I l l Standard: CS-7300410 placed in "CLOSE". 1 l Mil 0at6FCuiiRMS -4 fMstisB12Ad[$si6tl6M5dsisirsliditsBI6tiisN*ddM--@M,y, U meNWW o nW dq PMW4 w1,,Q, Bl&221A'16mEs;.%~ CLOS E,D,~77%f-
%~ r --
f dica .
.J p %~%m,m+ aMyMM e a[,p,7300411;7300412land:
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s ate i -~ %.20, 3 amps um
~W
~ - .~m
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~
y ~ M%4., m &<.30 7+#%r 0409/ Bus"221_sVoltme_t_erf.ind._icat_es"47 m ~
- m -
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~
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# ps4mmimin auwmww the CR;annunciat q#x 4 ~.m u%a#wempmmue anw= aFromTrans~fonner.=p"r47524:0506;-Bus'221!
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~
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- ,di65t6E41923022480V' s , ww w ~ i._s._O,
<nsbus tsdindleatss$70%w ; n 1221 avoltsu,,g~m ne mggdgagga,gmywgegugggga l
I l Performance: SATISFACTORY UNSATISFACTORY 1 Comments: I Performance Step: Rack BKR 221 M to the " DISCONNECT' position per C20.6-1. Critical Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 221M racked to the " DISCONNECT' position.
-_ , - . _ -,n n ~ .._. n ,. ..
,9;1 <
w Evaluat r. Nots:$+&s,adw.ww&:. n.w ,~,.bn. w w .an na,maaw .xn n .jO we m cx s,afetyLeq _ ,btaining -emnus u wn a~ww& ipmentLwas
. x nonnevaluated l~ame%a,,a,ma mma,.nadk previously?,,,7.w&xaa e,w~waww .rn i
r ! c.. v .,%. _ - y,y --w. - . . . ,, nm,.,., - - - - - y n, y,,, .,ms. yo gym . m lev,aluator;C,ue:s .n.w .i-,,4a M.7 ,
,BKR'22.1,M,is~ in+the;'DISCON . i N W,.,,-
mes um -an m.umaraan.x-m uammama
~~ musuksaNECT, mw" :
mwouposition.
.- =a-m um m.werech Am,a ,,,.
wm
-,,W~,ha Perfe mance: SATISFACTORY UNSATISFACTORY Comments: ;
i l
. PITCQ-089 Page 5 of 9 Rev 5 10/98
r l Transfer Unit 2 480v Busses To Their Alt:rnato Supply l PLANT-10 Rav. 0 l Performance Step: Rack BKR 222A, BUS 222 SOURCE FROM 22A XFMR, to the Critical " CONNECT' position per C20.6-1. i Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 222A racked to the " CONNECT" position. 7 w n n. myypenWO.btaini.
, Evaluator N~ote:yp,p . .c w
. . ..'fe.f ng sa y~n. t equ ipm~e~n~w~a,s n .
e~vayus.,ted na revious p.v .- lyhyyn,n,7 l awimww n, l Ah2asmash.Jwammeshkaues.shsmssmanawaseaam!ssis fm.sma.x:w.m-
,EGildai6FC655FICM l TBkk2224iiih~tha?dONNECM'p6sitio6$zt@.nma:MYWJMyF1"?E a
~ u. -r u &u suura~ me u am m.wamu w w .n..aw.u.u & , a.u mr pa w w w.m ,.n u ge.w n ..w s . w.x.u 5.-. m.wam,uL
,r e m e w:stmaAu nu,m k s' s.,.- wwanu.6mwaxnak:m Performance: SATISFACTORY UNSATISFACTORY i
Comments: i I I l Performance Step: Verify 7300426, 22A XFMR 480V POTENTIAL IL Green, is ON. Critical j Standard: 7300426 green light on bus 221 and 222 control panel verified on. !
\
- m- -~. m -F wng e;mmet i
t
- EValuatob.p .. u. .oe: w ~
c wer7300426 green l.7e'. ig :lurONo.m s yqu,W9&Jg9? wwma.wmenpm.:nem'nw xx JMd)Md.dLS6ndndidg;eiMahilidassmehddsdlsNid!idshIshe?%ww!!Aassibm!&CCO6dsdGCEddsMshd dbh had A
)
Performance: SATISFACTORY UNSATISFACTORY Comments: l l l PITCO-089 Page 6 of 9 Rev 5 10/98 1 1
l Transfer Unit 2 480v Busses To Their Alternato Supply l PLANT-10 Rev. 0 l Performance Step: Place CS-7300419, BKR 222M BUS 222 SOURCE FROM 222M XFMR, in Critical X (S-1) "OPEN". Standard: CS-7300419 placed in "OPEN" W W
, _' _..~,._,l Cue _p;,%@
y m g m:; ,mmwM w " PEvaluator ., ,_,,,li_che_c,,k_ed,,' the follo,_ing _are in,_di_cated/,ob,s,_er,,_ed:_@__W-_,, v ',a
, m,- o ,
w a m. a m,- mmmew #em - - .w M,0 2,eww,as.3 N. w@w y Bkr.1222.M_~ind,w icat_es O_PE,Ny ., yngpgp3e
., , ww. .. n .
c oltsMis?i. 4 300421EB6si222
, . gD$M,, .m%,, y@dn~the.CRran,%,m.mVoltns,tsriindicht y .
- m. % m - _ --
m +
,fM,& yy -@A~2% n.mpeUndervoltage c g;'x. tor 4 m.
.,,a, y %w P, o We nun :B e -
, n .w n a w cia g aan wg ,s 222,480Voltr.,_ ,
mm_ i ew o.Ae.~ m,a,a,,, , < as ~ 9-,m, Jm.,.,, m,-,,.~ .-,m.._.. ...
- m. s O_Nw.,..,3, .,.,, , m, a, ,.u , ,m ,2_.
..m.,
e -a.m ,m ,. .,x Performance: SATISFACTORY UNSATISFACTORY Ccmments: ! Performance Step: Place CS-7300422, BKR 222A BUS 222 SOURCE FROM 22A XFMR, in Critical X (S-2) "CLOSE". Standard: CS-7300422 is placed in "CLOSE". c wwam w n. w m- w a
.Ev,a a
aluan~ tor,h,~ue,mm,g;mi~fj-h~ecknythe w n ie ed . g followin,_:are
~w r - ~ indicated /ob_ d: r,serve,nnnm~m mng ,
~
as wp - mq P r, A.ym , . s CLO eam _H . .w~w@+M.,; ,22.,2 ind~i,.c,424fand ,I,,B. k,s..m _.- 73004254ach"indi
.w m c m s. p=e,gm , am.m
. . ,g an g,~ g , e +
Epydu$$2.5_46SS.
.- 2,m20 _?ar.m.,.hpsh #, 1 7._3,00,4_23E_7300,221&olthie_ tert,ind_icates'470 m v
-~ - __, ,
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m-J's e3Aso&mm VW4?Nwmh.m NiMt a o m ,q,. 30,,0, 421fB,w n,~ r us' m .,-%,m,,s ..,_.,.-,,,,~,-m_o,~m,r.## u ,, < + E in Asriudbla n 7 05 , e v , ger%s , , T @<ME. u W,an.the'CRlna n nn 3ds+.e.t6f4.u. r.n 52442,wlB6,s'222 w m , s:
, 1
' . w , & ~s,Undervo.
-- m ltag,e - ~,Cle a_r.t -
..m., _ . . -
a,,
- Po.m- M m- a
, 7J J%u, Min th,e'C.R..h.w,nnnnc_iato,r747524 -#u Transformer 22A" Closed!is ONTOgr z% ~.0505tB_us'222 um m m m m JMF, rom' M ','
M
@ K S, Nfh ,i@M
-m s, ,em
%dMMDIU$liEsnEliU3d@55UVIMsS2 ValtissWi n,c M w#
mmA Y $.$e :- e,.~- ~, m mem - Wm
~ ,
MA4;u Q.susM),A,OM,;.d s m1 4,. .> Ms%;;&d;J.,idjap!LM,ukv._o,lt. , L- W4'
- s. "Qd;;;&,M"""%'" Es!#GAdaEJJ;LiL; WJid,OiGMLa' .
N e
' Sids L;;iJha',Jh.di.;2sma6 Performance: SATISFACTORY UNSATISFACTORY Comments: _.
PITCO-089 Page 7 of 9 Rev 5 10/98
L l Trcnsf:r Unit 2 480v Busses To Their Altamata Supply l PLANT-10 Rev. 0 l I 1 i Performance Step: Rack BKR 222M to the " DISCONNECT' position per C20.6-1. j Critical l Standard: Safety equipment (Fireman's Coat, Hard Hat with Face Shield, Gloves) obtained and BKR 222M racked to the " DISCONNECT' position. Eyilsat6 [awaaw&oti[ffMiffd6fii6iR[dif5ify61isr6ihf9;isl5yiisafe'djissiB0ily3 ";", >s + *' ' +[
- a. wanmuu,mmxw;mwwrw w w.mm m ,.
IEyilyj%en@hsChi '7IMBKR ~ f"", " ~ [ [ "E T
&#m 4 a a m2f2MVl6Vi}DISdDNNECT'@
a 2 ea m .h r 4 INN 3id ~ m 1 Performance: SATISFACTORY UNSATISFACTORY Comnysnts: Terminating Cues: The candidate should report to the Control Room Operator that, " busses 221 and 222 have been transferred to their altemate supply." The candidate may also indicate that he/she would inform the control room that they need to continue monitoring bus loading on ERCS. At this point, inform the candidate that, "this JPM is complete." Stop Time: l l 1 i l l PITCO-089 Page 8 of 9 Rev 5 10/98
7... i TURNOVER SHEET INITIAL CONDITIONS: o Unit 2 is in Cold Shutdown o Bus 26 needs to be isolated for a PM. INITIATING CUES: o The Control Room Operator directs you to transfer busses 221 and 222 to their alternate supply using 2C20.6, Sections 5.15 and 5.17 respectively. o Report completion to the Control Room Operator. PlTCO-089 Page 9 of 9 Rev 5 10/98
r , PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: l 2C20.6 l i C Section i UNIT 2 - 480V SYSTEM REw 7 Page 24 of 35 5.15 Transfer of 480V Bus 221 from BKR 221M to BKR 221 A CAUT/ONN THE SAFEGUARD BUS TRANSFER IS A DEAD BUS 6 p. e TFiANSFER. FOR THE 480V BUS TO BE TRANSFERRED, M.. O JM@W'i;M THE ASSOCIATED INSTRUMENT INVERTERS MUST HAVE fiFFm >MW DC POWER AVAILABLE AND THE RESPECTIVE l t6~WMgggg3d3 M $ $gg INVERTER.3 INSTRUMENT BUSES MUST BE POWERED FR
$ff :h SINCE BUS 221 WILL BE DE-ENERGlZED, OPERATIONS -
Qi 7;f AND ENGINEERING SHOULD REVIEW THE LOAD LIST Z'5 j$kpg PRIOR TO TRANSFER FOR ANY LOAD THAT WOULD AFFECT THE UNIT IF DE-ENERGlZED. w:e %g
*,mn '
y 5.15.1 Verify MV-32033,2 TURB LOOP B CLG WTR HDR MV, CLOSED _03 E the valve must remain OPEN, THEN turn 4 OFF BKR 2A2-B5 AND enter 72 hour Cooling Water LCO in l accordance with T.S.3.3.D.2.b. / l I 5.15.2 Verify MV-32038, CLG WTR DUMP MV, CLOSED. l
, f, _ i 5.15.3 Verify MV-32329, LOOP A/B CLG WTR RTRN HDR XOVR MV B, OPEN.
'6' 5.15.4 Install Secure Cards per Safety Card Stock Isolation 2C20.6-1.
'f~ :
hh7[?YY,E The following steps are performed to ensure load is
$MkMNJ controlled on the alternate feeds.
5.15.5 Using the ERCS computer, record the load amps for Bus 221 as follows: Bus 221 amperes O 2Y8021A
\
5.15.6 Verify the Bus 221 amps are less than or equal to 900 amps.
' E greater than 900 amps,' first verify all transferable MCC's are transferred to Unit 1 per 1C20.6 (MCC 1 AB2), THEN secure Unit 2 Train A equipment until proper loading can be achieved.
f
?RAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATCS POWER COMPANY OPERATING PROCEDURES #MMgga m's " " '"'
2c20.s N 2 - 480V SYSTEM nev: hk! hk 7
=u
. ugwwy;g7lg.g Page 25 of 35 5.15.7 Notify SS that if any new Train A equipment is to be started, or MCC's transferred then loading on Bus 221 must be controlled to 900 amps. ERCS point 2Y8022A has been set up to alarm at 800 and 900 amps. [/ j
'(/ SS At Bus 221: )
i 5.15.8 Rack BKR 221 A, BUS 221 SOURCE FROM 22A XFMR to the " CONNECT" position per C20.6-1. J l At Bus 221 & 222 Control Panel (In D5/D6 Bldg): - ( l 5.15.9 Verify 7300426,22A XFMR 480V POTENTIAL IL Green, is ON. 5.15.10 Place CS-7300407, BKR 221M BUS 221 SOURCE FROM 221M XFMR, in *OPEN." A. Verify BKR 221M indicates OPEN. B. Verify 7300409, BUS 221 VOLTMETER, indicates 0 volts. C. Verify annunciator 47524-0206, BUS 221480 VOLT UNDERVOLTAGE, alarms. 5.15.11 Place CS-7300410, BKR 221 A BUS 221 SOURCE FROM 22A XFMR, in "CLOSE." A. Verify BKR 221 A indicates CLOSED. B. Verify 7300411,7300412,7300413, each indicate less than 900 amps. C. Verify 7300409, BUS 221 VOLTMETER, indicates 420 to l 505 volts. - D. Verify annunciator 47524-0206, BUS 221480 VOLT UNDERVOLTAGE, clears. i E. Verify annunciator 47524-0506, BUS 221 BKR 221 A ALT SOURCE FROM TRANSFORMER 22A CLOSED, alarms.
I l 1 { PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMcER:
' . v4 2C20.6 1
./'., ;,. C.w,:v;M.
.2%) UNIT 2 - 480V SYSTEM nev: 7
, %cti6n@ fig v : '- ' ' ' Page 26 Of 35 F. Verify 4192302,480V BUS 221 VOLTMETER, indicates 420 to 505 volts. )
5.15.12 Rack BKR 221M to the " DISCONNECT" position per C20.6-1. 1 l 5.15.13 Continue monitoring Bus 221 loading using the alternate { feed point on ERCS to control load below 900 amps. J 221 A point ID is 2Y8022A. l l l l l 1 l l
p t PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBE"U 2C20.6 UNIT 2 - 480V SYSTEM REv: 7 Section : Page 29 of 35 l 5.17- Transfer of 480V Bus 222 from BKR 222M to BKR 222A l ! $. . . THE SAFEGUARD BUS TRANSFER IS A DEAD BUS ' l CAUTION
,; Xq :r' [C!g TRANSFER. FOR THE 480V BUS TO BE TRANSFERRED, 9 0 013 Y.@ h THE ASSOCIATED INSTRUMENT INVERTERS MUST HAVE h M NNNN?f Q JU. DC POWER AVAILABLE AND THE RESPECTIVE -
"utu mM ME INSTRUMENT BUSES MUST BE POWERED FROM THE
! INVERTER.
lM$ {GjW0kQA'.ykI ~h 33 l @$IBMfe%y AND SINCE BUS 222 WILL BE DE-ENERGlZED, OPERATIONS ..
@s$
C ' ;;TNg$yijygd? PRIOR ENGINEERING SHOULD REVIEW THE LOAD LIST gg .ieTO TRANSFER FOR ANY LOAD THAT WOULD
.]% gjj' AFFECT THE UNIT iF DE-ENERGlZED.
l At Bus 222: 5.17.1 Rack BKR 222A, BUS 222 SOURCE FROM 22A XFMR to 1 the " CONNECT" position per C20.6-1. i 1 5.17.2 ' Check Unit 2 Pressurizer Heater Group B (MCC 2R1) supplied from BKR 271 or transfer per the appropriate
- section of this procedure. , -
5.17.3 Install Secure Cards per Safety Card Stock Isolation 2C20.6-2. , The following steps are performed to ensure load is j nod 2l[d!$$:2
' aw+;.4 i
, o.m.a ;- g controlled on the alternate feeds.
1 5.17.4 Using the ERCS computer, record the load amps for Bus 222 ] ' as follows: Bus 222 amperes b 2Y8023A 5.17.5 Verify the Bus 222 amps are less than or equal to 600 amps. 1E greater than 600 amps, first verify all transferable MCC's ! are transferred to Unit 1 per 1C20.6 (MCC's 1T2 and 1MA2), THEN secure Unit 2 Train A equipment until proper _ loading ~. l can be achieved. . 5.17.6 Notify US that if any new Train A equipment is to be started, or MCC's transferred then loading on Bus 222 must be controlled to 600 amps. ERCS point 2Y8024A has been set l up to alarm at 500 and 600 amps.
'(/ SS
1
' PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY OPERATING PROCEDURES TITLE NUMBER: i 2C20.6 Cv Section .
, UNIT 2 - 480V SYSTEM ney:
7 l
)
l Page 30 of 35 At Bus 221 & 222 Control Panel (In DS/D6 Bldg): i 5.17.7 Verify 7300426,22A XFMR 480V POTENTIAL lL Green, is ON. 5.17.8 Place CS-7300419, BKR 222M BUS 222 SOURCE FROM 222M XFMR, in "OPEN." l
. A. Verify BKR 222M indicates OPEN. --
B. Verify 7300421, BUS 222 VOLTMETER, indicates 0 volts. . C. Verify annunciator 47524-0205, BUS 222 480 VOLT UNDERVOLTAGE, alarms. 5.17.9 Place CS-7300422, BKR 222A BUS 222 SOURCE FROM 22A XFMR, in "CLOSE." A. Verify BKR 222A indicates CLOSED. 1 B. Verify 7300423,7300424,7300425, each indicate less j than 600 amps. ) 1 C. Verify 7300421, BUS 222 VOLTMETER, indicates 420 to 505 volts. D. - Verify annunciator 47524-0205, BUS 222 480 VOLT l UNDERVOLTAGE, clears. E. Verify annunciator 47524-0505, BUS 222 BKR 222A ALT , SOURCE FROM TRANSFORMER 22A CLOSED, alarms. - H F. Verify 4192303,480V BUS 222 VOLTMETER, indicates 420 to 505 volts. 5.17.10 Rack BKR 222M to the " DISCONNECT" position per C20.6-1. 5.17.11 Continue monitoring Bus 222 loading using the alternate feed point on ERCS to control load below 600 amps. 222A point ID is 2Y8024A. - J
JPM: 10 Operaton
^
JPM ' QUESTION (AnswerSheet). QUESTION 1 System:: AC Electrical
Subject:
l Operaticnal Limits For Diesel Generator K/A & Rating: 062K102 4.1/4.4 With both units in a normal full power lineup, the 480V breaker for 21, D-5 Diesel Room Normal Mode Vent Fan trips open. Question: What affect (if any) does this failure have on D-5 operability? Answer: No effect, this fan is not required for D-5 operability. 2C20.7 page 6
Reference:
C18.1 page 19 Reference Material Use: l Yes @ No O l Pedigree: -lNew CANDIDATES RESPONSE: SAT: UNSAT: l l l l j
JPM: 10 Operator: JPM QUESTION (Answer Sheet)' QUESTION 2 System:L AC Electrical
Subject:
' l Effect Of SI Actuation On Either Unit l KIA & Rating: 062A401 3.3/3.1 l Given a normal full power system alignment, in the event of a Sl on
! Question: Unit 1, which 480V loads on train B would you expect to see rejected and restored? 122 Station Air Compressor,12 and 14 FCU's,122 Control Room Chiller, swen: 122 Control Room Chilled Water Pump
Reference:
B 20.5 Table B 20.5-3 page 16 Reference Material Use: IYes@ No ] l Pedigree: 'lNew CANDIDATES RESPONSE: SAT: UNSAT: l
r-JPM QUESTION 2 JPM:10 Given a normal full power system alignment, in the event of a Si on Unit 1, which 480V loads on train B would you expect to see rejected and restored?
P JPM QUESTION 1 JPM:10 I With both units in a normal full power lineup, the 480V breaker for 21, D-5 Diesel Room Normal Mode Vent Fan trips open. l What affect (if any) does this failure have on D-S operability? l I
l INITIAL SUBMITTAL OF THE SCENARIOS FOR THE i l
- PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 i
I i l f P'
i l SCENARIO USAGE MATRIX (Indicates, by Scenario Number, Number of Evolution Types per Candidate) Q.),,jirqlN if , - RO1 RO 2 RO3 REACTIVITY 1 2 3 NORMAL 2,2 3,3 1 INSTRUMENT 1,1,2 2,3,3 3,1 COMPONENT 1,2 2,2,3,3 3,1,1 ' MAJOR 1,2 2,3.3 3,3,1 RO1 RO 2 RO3 REACTIVITY 1 2 4
~l NORMAL 2,2 4 1 l lNSTRUMENT 1,1,2 2,4 1,4 l COMPONENT 1,2 2,2,4,4,4 1,1,4,4,4 l MAJOR 1,2 2,4,4 1,4,4
- m. . : .a., #.-- RO1 RO 2 RO 3 REACTIVITY 2 3 4 NORMAL 4 2,2 3,3 INSTRUMENT 2,4 2,3 3,3,4 COMPONENT 2,2,4,4,4 2,2,3 3,3,4,4,4 MAJOR 2,4,4 2,3,3 3,3,4,4
_ _ _1
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I File Number: 99-01
Title:
Load Reduction; FRV failure; PRZR Rev: 0 Level Inst. Failure; BATP Trip; Loss of l Feed;IR Undercompensation ) i Lesson Plan: NRC Exam Duration: 2 hours l Author: Jim Lash . Approved by: Date: 1 OBJECTIVES:
- 1. Diagnose and respond to a FRV failing to manual per C47011:0305.
- 2. Perform a load decrease per C1.4.
- 3. Diagnose and respond to failure of controlling PRZR level channel low per C51.
- 4. Diagnose and respond to a loss of normal boration due to a BATP trip per C47015:0403.
- 5. Diagnose and respond to a loss of Bus 12 resulting in a loss of main feedwater and reactor trip per E-0.
- 6. Diagnose and respond to failure of main steam header pressure instrument high and a failed open steam dump per E-0.
- 7. . Diagnose and respond to loss of feed to both SGs per FR-H.1.
- 8. Diagnose and respond to under-compensated IR NIS per ES-0.1 RELATED LER's, SER's, SOER's, etc.:
. ERTF 96-12; Inadvertently cut cable feeding 21 BATP ERTF 93-04; Unit 1 Rx Trip caused by Bus 12 86 Lockout LER 93-05; Unit 1 Rx Trip due to loss of RCP caused by inadvertent relay operation RELATED PRA INFORMATION (See PITC 2.3):
Initiatina Event with Core Damaae Freauency: Loss of Main Feedwater (4.4%) Important Components: 12 MD AFW Pump Important Operator Actions with Task Number: Restore MFW following Rx Trip; CRO 311.006.06.01 Page 1 of 17 - L a
Title:
Lead Reduction; FRV failure; PRZR Lcv:1 Inst. Fcilure; BATP Trip; Lcc3 of F:cd;IR Underacmpenxti:n SCENARIO OVERVIEW Initial Conditions:
. Current power is 89%.
. Shutdown is in progress due to 11 SG tube leakage (Technical Specification 3.1.C.2.e) of approximately 5 gpm.
. Action is in progress IAW C4 AOP2 (Action Level 2) at step 2.7.9 to have the Unit shutdown in the next 4 hours.
. Unit 2 is operating at 100% power. l
. 12 MD AFW Pump is OOS due to grounds. Expected time OOS is at least 24 hours.
12 Boric Acid Transfer Pump is OOS for preventative maintenance. The pump is expected to be released to service in the next 2 hours. I Seauence of Events: Event 1: FRV Fails to Manual
. During the power reduction,12 SG level control fails to MANUAL.
Manually control feed to 12 SG to maintain proper level per C47015:0403 Event 2: Load Reduction
. Continue load reduction per C1.4.
Event 3: Controlling Pressurizer Level Channel Fails Low i~ollowing at least a 5% power reduction, the controlling Pressurizer level channel fails low. Charging pump speed increases, PRZR heaters deenergize, and letdown isolates. Take manual control of charging pump speed & select a new controlling channel
. Restore letdown per C12.1 Return charging pump speed to automatic.
Event 4: BATP Trip During a boration, the only operable (11) Boric Acid Transfer Pump will trip.
. The crew will be required to evaluate RCS boration during shutdown.
Page 2 of 17 \
71M
Title:
Load Reduction; FRV failure; PRZR L;v:1 In t. .. F llure; BATP Trip; Loss of Feed;IR .. - M , . Undercompenxti:n mW -G QWs
. Alternates include swapping Charging Pump suction to RWST or using another BAST.
Event 5: Loss of Bus 12 / Loss of Feedwater
. A loss of bus 12 will cause a loss of 12 MFP and 12 RCP and a reactor trip. . A feedwater isolation will occur at 554 *F. . When the TD AFW pump starts it will overspeed and all feedwater will be lost. . After steam dump control is taken to the pressure control mode, the Main Steam header pressure instrument will fail high and one steam dump valve will stick open. . The crew must take action to stop the steam release by shutting the MSIVs. . Entry into FR-H.1 will be required to handle the loss of heat sink now that SG levels are less than 50%. . Action should be taken to establish MFW by resetting the feedwater isolation (this is a PRA significant task).
Event 6: IR Undercompensation
. At approximately 15 minutes following the reactor trip, the crew will be required to determine Source Range NIS failed to re-energize due to undercompensation of IR NIS channel N35.
. Manually reenergize the Source Range NIS.
. Scenario ends when stable plant conditions are established per step 15 of ES-0.1.
+ Critical Tasks
> Manually isolate steam dumps from the control room before an entry into an Integrity orange path or ECA-2.1 is required.
> Estab!ish feed flow to at least one SG before RCS feed and bleed is required.
PRE-EXERCISE BRIEF
- 1. Follow NUREG-1021 Appendix E; Part E Page 3 of 17
Titis: Lcad Reductirn; FRV failura; PRZR Lev:1 In:t. "! Failure; BATP Trip; Loco cf Feed;1R Undercompen2cti:n
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I INSTRUCTOR GUIDE l
- 1. Initialize to IC-21 and verify the following conditions: ;
- a. RCS boron display = 818 ppm.
- b. MOC Al displayed.
- c. Bank D step counters at 186, all others 228.
- d. All charts advanced and cleared of previcus trends.
- e. ERCS is on-line and functional with alarms acknowledged / cleared.
1
- 2. Insert the following pre-existing conditions (Relaf/ve order of 0) '
- a. 11 SG tube leak of about 5 gpm
- b. N35 Undercompensation l
- 3. Perform the following- .
1
- a. Place 12 BATP to pullout and hang a secure card. j
- b. Place 12 MDAFW pump from service as follows !
Place 12 MDAFW pump in pullout and attach a secure card. j Place 12 MDAFW pump in MANUAL and attach a secure card. i
- c. Place Rods in MANUAL
- d. Run the Valve Position Limiter down and then just off the limit i l
- 4. Arrange the following information:
- a. Take the simulator out of Freeze and place XT24 on one ERCS screen.
Place QuickPlot "TAVTREF" on SDCON4. Allow the olots to develoo,
- b. Cat i Vent opening sheet reflects no logged openings.
- c. Log books are open to a blank page.
1 l d. C1.4 consumable is the same revision as the book and signed off through Section 5.2.7. The Valve Position Limiter has been run down to present , load per C1.4 Precautions. l
- e. Make a copy of C4 AOP2 "SG Tube Leak" and sign off appropriate steps through step 2.7.9 (transition from step 2.4.1) including Attachment A. l
- f. Update and print and LCO log with the following information:
t 11 SG 3.1.C.2.e 1HR SG tube leakage 30 min. ago j 12 AFW 3.4.B.2.b 72 HR CM Ground on motor Today 0100 pump I Page 4 of 17
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t Tit ls: Lecd Reduction; FRV failure; PRZR Lev;l In t. 9m/MU ID y Fciture; BATP Trip; L0ca cf Fc:d; IR !
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- 5. Conduct shift turnover
- a. Use the shift turnover sheet provided and provide the following information:
Current power is 89%. Load decrease per C1.4 at step 5.2.8. Shutdown is in progress due to 11 SG tube leakage (Technical Specification 3.1.C.2.e) of approximately 5 gpm discovered about 2 hours ago. Action is in progress IAW C4 AOP2 (Action Level 2) at step 2.7.9 to I have the Unit shutdown in the next 4 hours. SG leakage is being monitored using XT24. 12 MD AFW Pump is OOS due to grounds. The expected time OOS i is at least 24 hours. 12 Boric Acid Transfer Pump is OOS for preventative maintenance. The pump is expected to be released to service in the next 2 hours. Unit 2 is operating at 100% power.
- b. Allow 3-5 minutes for control board familiarization. I
- 6. At the discretion of the chief examiner insert failure of 12 SG FRV (Relative order oi1).
- a. If asked to locally investigate 12 FRV, report that you don't see any problems with the valve or valve controller. ;
- b. If asked to investigate 12 FRV, as the engineer or I&C, report that you will initiate a work order to investigate the failure. l
- 7. At the discretion of the chief examiner (following the required power change),
insert pressurizer level channel failure low (Relative order of 2).
- a. If directed, trip the bistable (Relative order of 3),
- b. Perform IV of the bistable tripping and generate work orders as directed.
- 8. At the discretion of the chief examiner insert failure of 11 Boric Acid Transfer !
Pump. (Relative order of 4) This will remain unnoticed until the next baration is performed. I
- a. if asked to investigate, report that the breaker is tripped (MCC 1 L1 535) and the motor is hot to the touch.
Page 5 of 17 1 w i
Titla: Lcad R:ducti:n; FRV frilura; PRZR Lev;l Inst. Fcilure; BATP Trip; Lees cf F=d;IR i Und:rc mp:nrti n
- b. If asked, as an electrician or system engineer, report that you will l investigate and write a work order.
l l
- c. If asked to restore 12 BATP, report that you will check its status. Later report that the pump will be available in 1 hour. The Work Control Center will handle closing the work package and clearing the isolation. l 9.
At the discretion of the chief examiner insert Bus 12 lockout (Relat/ve order of 5)
- a. When 11 TD AFW pump starts, then enter an overspeed trip on the pump.
(Relative Orderof 6)
- b. If asked to investigate, report that the 86 lockout has actuated and a 51G flag is present.
1
- 10. Reactor Trip and Loss of Heat Sink EOPs a
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- a. One minute after Steam Dump is placed in the Steam Pressure mode, fail PT-484 high (Relative order of 7) to cause all steam dumps will open AND THEN stick one steam dump open (Relative order of 8)
- b. If asked to isolate stuck open steam dump, then after 3 minutes insert remote and report that RS-6-1 is shut. (Relative order of 9)
- c. 11 TD AFW pump has overspeed and the trip throttle valve linkage has fallen apart. Maintenance reports that it will take at least 1 hour to fix.
- d. If asked, as the unit 2 RO, to cross-tie AFW from 21 MD AFW pump, explain that you are using the pump and it is not available at this time.
- 11. At the discretion of the chief examiner, (SR instruments reset) place the simulator in FREEZE.
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Title:
Lead Reduction; FRV failure; PRZR Lcv:1 In:t. Frilure; BATP Trip; Leca of Feed;IR Und::rcompennstirn __ Name: Position: Lead RO Date:
=-
"O*JBENdtNede!MMWWEWrasM:!ssWM 1rdcM Number?W NMKA Valuer @
FRV Failure to Manual Time S/U Position Expected Response Feedwater Control Fail to Manual Alarm (C47011-0305) Lead . Manually control 12 NR SG level within 5% of band per Figure C1-39. (39% to 49%) SS/ Lead e inform System Engineer and l&C to investigate
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3"~:~44WehilliM$dlif4M?$210cN!!@ts&i%Ws%c9ffM Comments: Page 8 of 17 l L..
r I
Title:
Load Reducti::n; FRV failure; PRZR LGv:1 In:t. ' E y it i 14.1 F ilure; BATP Trip; Le23 cf F;;d;IR ee y R e .. Y'i
~'
Und:rc mpenrti:n . DEM45R1!EhMEvi6t.Descriptionskf@WWMAird!PS$ fiinKALNurnbe'rlW ftwKA'Valuen& Load Reduction Time S/U Position Expected Response Perform actions IAW C1.4: SS . Power reduction directed by SS. Lead . Raise Load Limiter Lead . Lead observe turbine and generatorlimits per C1.4 i RO . Commence boration RO . When Tave shows a decrease, Then reduces turbine load by setting the SETTER and depressing GO RO . Rods may be placed in MANUAL REval66torNotliPA@673@$4!1s@4cdM%Mapet%MI*@!@Mgg75mWyw%AmammtagMfuglW Comments: l l l 1 l l l l Page 9 of 17 j
Titix Load Reduction; FRV failura; PRZR LSv:1Iriit.' s Fillure; BATP Trip; Leca cf Ford;IR Und:rcampenxtian _.
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Pressurizer level transmitter failure 000 028 EA1.08 5.7/3.8 ) i Time S/U Position Expected Response l C61.3 Pressurizer Level 1L428 - Low ' RO e Take manual control of the charging pump speed to maintain level at program. RO
- Select position 2-1 on pressurizer level control selector switch.
RO e Restore pressurizer heaters for normal operation. The switches for heaters which were ON must be taken to OFF for 3 to 12 reconds to reset the anti-pumping feature. RO e Retum charging pump back to auto. RO e Switch pressurizer level recorder to another channel. Lead /RO e inform SS to refer to T.S.3.5 (6 hr LCO for B/S tripping). Lead /RO . Trip and independently verify bistables. , Lead /RO . Initiate work order on the failed channel. Lead e Make appropriate log entries. RO C12.1 Restoring Letdown e Place letdown temp CV in MANUAL at 50%. e Place letdown press CV in MANUAL at 50%.
- Establish sufficient (at least 15 gpm) charging flow through the regen HX. I e Open a 40 gpm orifice isolation valve while adjucting the letdown press CV so letdown press does NOT reach 600 psig.
- Retum letdown temp and press control to AUTO.
-M 255EliiSifLihj5$5Inldid MdISM55dEEENU3 Comments:
Page 10 of 17 L
Titis: L":ad R: duction; FRV failura; PRZR L; val in:t. Fcilure; BATP Trip; Lo3a cf Feed;IR W E fi f W H
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e 9 UndIrctmpen2rti:n i h :6. - R.4 MiMgSMii#pMl3EEfentDescription$iMinii%:$t%Bi$$@i;@ @nKKNumber;M P !MKA"ValueWas Boric Acid Pump Trip Time S/U Position Expected Response Boric Acid Deviation Alarm C470154403 RO . Places makeup controller to OFF RO . Continue load reduction using rods and/or swap charging pump suction to RWST.
-Open MV-32060 RWST Supply
.Close MV-32061 VCT Supply
! u . 9 M?wm smew adihn.enNCggesgumM5iWmA%yywamis di M ni,Mn M R! . $diNthse Comments:
j l l Page 11 of 17
Titis: Lead Reduction; FRV failure; PRZR Lcvsl inst. Fcilure; BATP Trip; 1.oss of Feed;IR Und:rc:mpenxti:n w n. -3E4ct1_-WW@tionWSdEA#He@:;idiUE ?BKA'NuhitMG& iiknKA ValuM@: Bus 12 Lockout / Reactor Trip Time S/U Position Expected Response E 0 Reactor Trip or Safety injection RO . Verify reactor trip. - Rx Trip Bkrs; Flux; Rod positions Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized. RO . Check if Siis required
--SG Pressure >500 psig
-PRZR Pressure >1815 psig
--PRZR Level >5%
-Subcooling >20*F
-Containment Pressure <4 psig SS . Transition to ES-0.1 RE61Dit5BNoGLEsiMGi!3J&sur.iMa5ms$$semifmashmytWimege!!*smetermissimis Comments:
Page 12 of 17
Lead Reduction; FRV failure; PRZR Lcv:1 In:t. ' '-Title: Fcilure; BATP Trip; Lcca of F::d;IR - i j Und:rcompensatirn . . l
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Mi%KAVi0uetch Main Steam Line Header Pressure Instr. Failure High and Stuck open Steam Dump. Time l S/U Position l Expected Response ] ES-0.1; Reactor Trip Recovery SS . Announce " Unit 1 ReactorTrip" Lead . Place steam dump in ' Steam Pressure" mode. Lead . Notify TBO to isolate MSRs. Lead . Check cooling water pressure A & B >75 psig RO e Check RCS Tm controlling at 547"F Lead . Stop dumping steam by either (crMcal task)':
-Shut both MSIVs l
-Call Aux Operator to isolate Steam Dump by shutting RS-6-1 l C47012:0602; 12 RC Loop Low Flow ;
RO e Shut 'B' PRZR Spray Valve (CV-31225) l l
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Comments: Page 13 of 17 I
- _ J
~ "Tille: Load Reductirn; FRV failure; PRZR Lev 1 Irr.t. -
Fcilure; BATP Trip; L ca cf F::d; IR Und:rcompenrti:;n '- - ipiE3ET.EE@s2Etz ==s-7-3GGE %.W2059ff- m EMi2N(imber56 ENKAiVailuegre loss of Feed / Loss of Heat Sink Time S/U Position l Expected Response i FR-H.1; Loss of Heat Sink RO/ Lead . Verify secondary heat sink is required.
-RCS pressure > SG pressure
--RCS Hot Leg >350*F RO/ Lead . Check for secondar to bleed and feed.' y heat sink, if none stop RCPs and skip directly Lead . Attempt to restore AFW flow:
- Attempt to cross-connect AFW from unit 2. l
- Dispatch operator to locally restore AFW.
- Stop 11 RCP.
. Attempt to restore main FW flow.
RO - Reset Sl i Lead -Investigate lockout on bus 12. Lead - Check FW Containment isolation Valves open Lead - Depress all four FW lsolation reset pushbuttons i Lead - Determine 11 MFP available l Lead - Open FCV Bypass valve 5 Lead - Establish at least 200 gpm (1x10 tbm/hr) flow (criticaltask') Lead . Check SG levels: SS - If flow adequate and levels increasing, transition to ES-0.1
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-; < ! E ie Comments:
L /eh-m= Ebhk i l l Page 14 of 17
Titis: Lead Roduction; FRV failure; PRZR L; val in2t. .. Fcilure; BATP Trip; Losa cf Fred;IR l Und:rc:mprnxti:n i 1
.3PE_ _ _ E - ==d _ __':#E5F'lHfWO N M K N6htbar h ;M;LKAValue%#
Reactor Trip Recovery 4 Time S/U Position Expected Response ES-0.1 Reactor Trip Recovery 4 Lead Check FWstatus l -Reduce Main FRV demand to zero l -Verify FW flow >200 gpm'
- l. RO . Verify all control rods fully inserted l RO . Check PRZR level trending to 21%
RO C12.1 Restoring Letdown (if necessary)
. Place letdown temp CV in MANUAL at 50%.
]
j . Place letdown press CV in MANUAL at 50%. 1 . Establish sufficient (at least 15 gpm) charging flow through the regen HX. l . Open a 40 gpm orifice isolation valve while adjusting the letdown press CV so letdown press does NOT reach S00 psig.
. Retum letdown temp and press control to AUTO.
ES-0.1 Reactor Trip Recovery (cont.) RO . Check PRZR pressure trending to 2235 psig Lead . Control FW flow to establish 10 to 40% SG NR level Lead . Verify off-site power available
-identify lockout on bus 12 and does not restore power to it.
-Verify auto action of C47005-0102 .
Breakers 12-4 and 12-1 open 12 RCP and MFP tripped Refers to C20.5 AOP3 Lead- . Open Turbine HP drains using CS-46392 C3; RCP Start RO . Verify support conditions for RCP start
. Start 11 RCP Oil Lift Pump
. Start 11 RCP
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Titb: Lead R:ducti:n; FRV failure; PRZR Lsv;l init. ' ^
.. : >: TlM; "' '
')
Fciture; BATP Trip; Loca of F :d; IR fr W W :i d' Tsl Und rc mpensitien . ' 4 . ~ . ' . 3 .e % .. ' t QiiS$ltftSi*g$sdivdHt9discriptionWimn4WEi#R!:A 229 ##1,KANumberE os!KAValueI2w Intermediate Range Under-compensation Time S/U Position Expected Response ES-0.1; Reactor Trip Recovery (cont.) RO e Check IR fluxless than 5 x 10'" amps RO . Manually energize SR detectors by placing both SR Reset / Block switches in RESET RO . Transfer NIS recorder to SR N31 and N32
; 9 4 !4 Comments:
Page 16 of 17
CHAMPS FORM KTF-D 2
' RETENTION:' 7 DAYS DATE:
l UNIT 1 LPEO / PEO TURNOVER l TIME N(1800-0600) SFGDS EQUIP OOS/LCO'S 1 212 AFW PUMP AS OF TODAY AT 0100 DUE TO A GROUND 2 311 SG TUBE LEAKAGE AT 715 GPD 3 : RAD MONS 005: ANNUNC'S 005: OUTSTANDING SP' S t FIRE DET/ PROT EQUIP IMPAIRMENT: OTHER EQUIP OOS / STATUS: 1 : 12 BATP FOR PM 2 3 : l 4 : \ 5 : 6 : 7 : 8 : 9 : 10 : 11 : 12 : 13 : 14 : 15 : j 16 : l 17 : I MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE: l 1 : 2 3 : 4 : 5 : OPERATIONAL PLANS FOR COMING SHIFT: 1 : MONITOR LEAKAGE USING XT24 2 : SHUTDOWN PER C1.4 3 : 4 : _ NEW PROCEDURES / INSTRUCTIONS: 1 : C4 AOP2 ATTACHMENT A COMPLETE 2 : 3 : , WATCHSTANDERS LPEO: LASH PEO JONES LPEO RELIEVED BY: TIME: DATE: PEO RELIEVED BY: TIME: DATE: CB WALKDOWN --> LPEO: TIME:
--> PEO : TIME: _
M6WiaSh$lhdDlht3dalb690lWGuideR98Wa%l f File Number: 9942
Title:
Load increase; PRZR Pressure instr. l Rev: 0 Failure; Loss of Generator Cooling; Dropped Rod; Faulted SG Lesson Plan: NRC Exam Duration: 2 hours 3 l Author: Jim Lash Approved by: Date: l OBJECTIVES: 1
- 1. Perform secondary lineup for power operation por C1.2.
j
- 2. Perform a load increase per C1.4.
- 3. Diagnose and take corrective actions for a high failure of pressurizer pressure control;ing channel per C51.
- 4. Diagnore and respond to a reduction in Main Generator hydrogen cooling per C47007.0401.
- 5. Diagnose and respond to a dropped control rod per C5 AOP4 and E-0.
l
- 6. Diagnose and respond to a failure of a main steamline isolation and an l
MSlV failure to close per E-0. I
- 7. Diagnose and respond to a failure of one train of Safety injection to actuate and a trip of one SI pump per E-0.
- 8. Diagnose and respond to a failed open SG Code Safety valve per E-2, j E-1, and ES-0.2.
l RELATED LER's, SER's, SOER's, etc.: LER 96-01; Main Steam Safety found outside 1% tolerance LER 97-08; Unit 1 Reactor Trip caused by electrical ground in Rod Control system RELATED PRA INFORMATION (See PITC 2.3): l Important Components: 12 Si pump D1 Diesel Generator i L Page 1 of 16
Title:
Lead increase; PRZR Prescura In:tr. Fcilura; 3.9 iJ Lecc of Gener: tor Cooling; Dr:pped Rod; " Faulted SG , SCENARIO OVERVIEW Initial Conditions: . Current power is 15% and has been held there for 20 minutes. . Unit startup is continuing with power increase to 100% power. . Action is in progress IAW 1C1.2 siep 5.6.23. All actions required in 1C1.2 have been completed with the exception of 5.6.23 (Electrical lineup) and 5.6.24 (Steam Dump alignment), which are to be performed following turnover. Power ascension will continue IAW 101.4. . Unit 2 is operating at 100% power. . PORV PCV-430 has been leaking-by and is isolated. . The 12 BATP is OOS for preventative maintenance. The pump is expected to be released to service in the next 2 hours. . D1 is in the process of being restored to service following repair of leak on the Jacket Coolant system Seouence of Events: Event 1- Load increase . Following shift turnover, the crew will continue the power ascension to the next plateau. The crew will complete the remaining actions of 1C1.2 . Transition to and continue per 1C1.4. Event 2: Controlling Pressurizer Pressure channel fails high . Instrument failure causes sprays to open. The RO needs to take manual control of pressure to stop the pressure reduction. . Follow C51 to take the channel out of service. Event 3: Loss of Hydrogen Cooling . Temperature sensor for Main Generator hydrogen cooling fails low causing the ! control valve CV-31360 to close. . Hydrogen temperature will increase and alarm (C47007:0401) 4 Manual operation of the Hydrogen Temperature Controller restores hydrogen to its normal temperature range. Page 2 of 1C l
Title:
Lead incrzse: PRZR Pr;ccure in:tr. Fcilure; #F;Iffal@iac#.99L2r,eh1s Le:c cf Gen:rct:r Cooling; Dr:pped Rod; +- Faulted SG m*mestev:n0p$$g IRESNiM3? us e e if NO operator action is taken a generator fault trip will be initiated on high temperature. Event 4: Rod Drop
. A periphery control rod (J-10), will drop resulting in a Power Range negative rate trip on one of the operab') N1 channels. . The crew is expected to manually trip the reactor per C5 AOP4. . The actions of E-0 should be initiated.
Event 5: Faulted SG l
. A Code Safety Valve on 12 SG fails open resulting in depressurization of the l secondary system.
Si is actuated (automatic or manual)
. Train A equipment fails ta respond to the "S" signal and must be manucIly operated. . The 12 S1 Pump trips on its start, so the operator is expected to ensure the 11 SI l Pump is manually started.
1
. When a steamline isolation is generated, the MSIV doesn't close.
]
. Actions of E-0 should be continued and transition should be made to E-2. I
. Upon completion of actions E-2 for isolation of the 12 SG transition is made to E-1. I 1
. Scenario ends following evaluation for termination of Si at step 12 of E-1 or using the information page and ES-0.1.
I l
+ Critical Tasks
> Establish flow from at least one high-head ECCS pump (11 S1 Pump) prior to transitioning out of E-0.
l
> lsolate AFW to a faulted SG before transition out of E-2.
, i l PRE-EXERCISE BRIEF 1 Follow NUREG-1021 Appendix E; Part E l l l i I l Page 3 of 16
Title:
Lead increase; PR NIS Frilure; Lcoo of Generator Cooling; Dropped Rod; Fculted SG M I
.M {
1 INSTRUCTOR GUIDE
- 1. Initialize to IC-16 and verify the following conditions:
- a. RCS boron display = 1154 ppm.
- b. MOC Al displayed.
- c. Bank D step counters at 105, all others 228
- d. All charts advanced and cleared of previous trends.
- e. _ ERCS is on-line and functional with alarms acknowledged / cleared.
- 2. Perform the following:
- a. Transfer busses 11 through 14 from the M to the R source.
l
- b. Place Steam Dump in Steam Pressure mode. ;
- c. Open Turbine HP Drains using CS-46392 )
- d. Remove 12 BATP from service by placing it in pullout and attaching a l secure card. !
l
- 3. Remove D1 from service as follows: )
- a. Place D1 control switch in pullout and attach a secure card. I
- b. Place D1 output breaker control switch in pullout and attach a secure card.
- c. Place Di . speed control to lower until the governor ready lights extinguish.
- d. Place "D1 Out of Service" signs on the control board at various locations.
- 4. Remove PORV PCV-431C from service as follows:
- a. Close PORV block valve, MV-32196, and attach secure card.
- b. Place a Work Order sticker next to PCV-430.
- c. Place an information tag on the control switch stating PCV-430 leaking.
- 5. Insert the following pre-existing conditions (Relative order of 0)
- a. Failure of MSIVs to auto isolate
- b. Failure of 'A' Train Si to actuate
- c. 12 Si pump trips when started. l
- d. 12 SG safety opens when reactor trip switch is operated.
- 6. Arrange the following information:
- a. Cat i Vent opening sheet reflects no logged openings.
- b. Log books are open to a blank page.
l Page 4 of 16
Ldad increrse; PR NIS F;ilure; Los3 cf ::5--- ~
Title:
Gen:rztor Cooling; Dropped Rod; Fculted SG MM _;
- c. C1.2 consumable is the same revision as the book and signed off through Section 5.6.22.
Attachment 'C' filled out with 1) 30; 2) 30 and 60; 3) 30; 4) 100; 5) 100 and 0.85 Sign off SPs as NA or complete at the end of C1.2.
- d. Update and print and LCO log with the following information:
< Ms @$ @ Gyf7,"4 iComponenti STimel EReas'ons F y 1 , y L e (Datefodl MiTS NbbsfM SLimits 2CodeW viDescription" s 9 Tini 50 '
D1 3.7.B.1 7 days CM Jacket Coolant leak Yeste' day 1200
- 7. Conduct shift turnover
- a. Use the shift turnover sheet provided and piovide the following information:
l Current power is 15% and has been held there for 40 minutes. ' Unit startup is continuing with power increase to 100% power. Action is in progress IAW 101.2 step 5.3.23. All actions required in 1C1.2 have been completed with the exception of 5.6.23 (Electrical lineup) and 5.6.24 (Steam Dump alignment), which are to be performed following turnover. , 1 l a) Power ascension will continue IAW 1C1.4. b) Fuel is preconditioned to 100% power with Bank D at 218 steps from a trip on May 13. PORV PCV-430 has been leaking-by and is isolated. The 12 BATP is OOS for preventative maintenance. The pump is expected to be released to service in the next 2 hours. D1 is in the process of being restored to service following repair of leak on the Jacket Coolant system Unit 2 is operating at 100% power.
- b. Allow 3-5 minutes for control board familiarization.
- 8. During the load increase Page 5 of 16
Title:
Lead increro; PR NIS Fcilur0; Los3 of G:nerctor Cooling; Dr:pped Rod; Fculted SG
'f@ o if Ti:.W.f]
i Gl sky in 1,3
- a. Open MSR lsolations as directed (Relative order of 1)
- b. If called concerning starting the HDT pump, ask the CR to wait until you get l
some sample results on the secondary.
- 9. At the discretion of the chief examiner insert pressurizer pressure instrument failure high (Relative order of 2)
- a. Trip bistables upon request (Relative Order of 3).
i
- 10. At the discretion of the chief examiner (following the required power change),
insert the Generator Hydrogen temperature sensor failure downscale (Relative order of 4) l I
- a. If asked to investigate, report that you will initiate a work order.
1
- 11. At the discretion of the chief examiner drop a control rod (Relative order of 5)
- a. When the reactor is tripped, then ensure that 12 SG safety fails open. I
- b. Open the CL orifice bypass as requested (Relative order of 6) i
- c. If asked to investigate the lockout on 12 SI pump, report that the pump tripped on overcurrent.
- 12. At the discretion of the chief examiner place the simulator in FREEZE.
l l l l l Page 6 of 16
Title:
Load incre:se; PR NIS Fcilure; Less of ;1 % K jef. T T }
'..f]
C:norctor Cooling; Dropped Rod; Fculted SG i j . ? .il A 1 lJ 1 .3 Name: Position: SM SS Lead RO Date:
+ a pgI , ? Event Description F" M ?HF ' ' " ' '
~ 3KA' Number #9 '
iKA Valuem
- Load increase Time S/U Position Expected Response C1.2; Unit 1 Startup Lead . Transfer non-safeguards busses from 1R to 1M (1M breakers held for at least 1 second while observing ammeters)
Lead . Transfer Steam Dump to Tavg. mode C1.4; Unit 1 Power Operation Lead . Notify Duty Chemist Lead /SS . Verify Thermal Power Monitor is on NIS RO . Verify all PRZR heaters ON Lead . Carry forward turbine loading rate from C1.2. Lead . Raise / verify Load Limiter to 100% Lead /SS . Verify ITC negative and place turbine control in imp in RO . Dilute using Alt. Dilute RO . When Tavg increases, then depress GO on turbine Lead . Direct outplant actions for load increase eEvaluctorNoter e 4
' r.a? 4 't2 , t 1 ' " +
!NfWM e < um W, Mit% o '
N N,i* Comments: i Page 7 of 16
1 L i
,emqs ' Wh 4 Event Descriptionn , - , ,# 4 - 6 mi KA Numbere
- N KA Value i! .
Pressurizer Pressure Failure High , Time S/U Position Expected Responsa j C61.3 Pressurizer Pressure 1P 431 - High l RO . Place pressurizer pressure controller in MANUAL and stabilize pressure. RO
- Select 2-1 on channel seledor switch.
l RO
- Retum pressure control to AUTO.
l RO . Select another channel on the pressurizer pressure recorder. SS
- Refer to T.S.3.5 (6 hr LCO for B/S tripping).
Crew . Identify and refer to T.S. 3.10.J if pressure <2205 psig. Lead /RO . Trip and independently verify bistables. ; Lead . Initiate work order on the failed channel. Lead . Make appropriate log entries. eEvalsetWNotere w frNtcNe M!n a & 1m ' ' " > smit '
' " u MW am n M Comments:
Page 8 of 16 i
I = - Lcad incrers;; PR NIS Frilure; Lcca of 5 2fgp
Title:
l i 0:nerat:r Cooling; Dropped R:d; Fculted SG . . . . l:&% i i
, w :: Event Description t m i:( 3 KA Numberm KA Value; j Loss of Generator Hydrogen Cooling J
l Time SIU Position Expected Response ' l C47007:0401; Generator or Exciter Gas Hi Temp 1 Lead . Determine source of alarm using recorder 47027 information Tags 001 to 009 and O29 to 031 Lead . Check hydrogen pressure Lead . Increase cooling water flow by taking CV-31360 to manual and open. Lead . Initiate a Work Order Lead . Make Log entry J Evaluator Notew ' > > , s: , +!E , i hn * , - 'e > > >>i,- , 1 Comments: l l l l l Page 9 of 16
Title:
Lead incre se; PR N!S Fcilure; Loc;)cf l Gin:r .t:r Cooling; Drcpped Rod; Fculted SG . l
., %r - > ;! Event DescriptionWW , ' 4 xe :sKA Numbere ; KA Value+.
Rod Drop i 1 Time S/U Position Expected Response C5 AOP4; Dropped RCA RO . Identify that a rod has dropped. RO . Manually initiates a reador trip.' 8 Evaluator Note:2R T"'""CW '3W M ,s-%.ngw:.S,,.E.,;M;m
..; . Qii elm 8.. 38 v.-. a r eo .3 gi b;hmmp%%
u mW f-!D U .h-.dhs!OiN'.r$+%+ OE5!!E ,.'Y t w dw'S!hu i <O. FAL N"35@WimmsW"
'lsf3 ueQ3ny
\I2,r,N,N,,9#d,wq:$b[5ish:!$,3m,ppsy,s,-
%, ,s is , ,
, .: Ar 4 W mitur. tv l JU9.:ImmediateActionXEF;%q$,A nin w ~- gsg@m .,.,a- p rg e- m .4t
_mt a -
,, m. , ,, < gj.a 3
. . . . r -
3
~
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,4 ,
fgg@npfg!%.
;m m, ,-w , .,e4Qgjgl4g,
. , , ;d.c 4<-
w ,n 8;Q,3;r 'g;:ie Comments: Page 10 of 16
)
Title:
Lead incre:C ; PR NIS Fcilure; Leco cf "
"~ ~"2 F GIntrcter Cooling; Dropped Rod; Fculted SG MW 4 Event Descriptiona >r, . - t ,, ' a KA Numbera r KA Valuem Reactor Trip Time S/U Position Expected Response E-0 Immediate Actions RO . Verifies reactor tripped Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized.
RO . Check St actuated Status Light or Si First Out ON RO . Actuates Siif required (any of the following)
-SG Pressure <500 psig
-PRZR Pressure <1815 psig
-PRZR Level <5%
-Subcooling <20*F
-Containment Pressure >4 psig TEvaluator, Note:MJ ll Mein >,Jfim b 4 v' alg ' C '.Erf sijalfg! ' ,,in!;!im
- HT / o 1 4
' * " ' ?,6p;ft;:-[',;i; gyp i yp{ , V!n. i i, r:;yFj!, g;![ *i a"
' t
'@rf;jylr,]jfptyp{,yyy *
>, ,i Comments:
i l l l l i l Page 11 of 16
c i l
' ' ~
l
Title:
Load increrse; PR NIS F11!ure; Los3 of - Gener; tor CoolingtDropped Rod; Faulted SG ;
)
{ i m wegevP 9EventDescriptionpe wrW+%% : m eMA l6mbers a m -! KA Valuee l Reactor Trip (cont.) l i Time S/U Position Expected Response E 4 continued Lead . Verifies component alignment Lead . Verify Train B ESF actuated Lead . Start 11 Si pump (criticaltask)' t Lead . Align Train A components per SI Active Panel 1 Lead . Intiates Containment Isolation signal for Train 'A' ; 1 RO . Closes 'B' MSIV. Crew . Verifies Air to Containment valves open Lead /RO e Closes MV-32115 (CC to SFP Cooling) SS
- Ensures communication with NRC is established w/i 1 hour Lead /RO . Opens turbine HP drains l
Lead /RO e Directs Outplant to stop TB roof exhausters aad isolate the MSR's SS . Ensure Auto-Action Guide is implemented l Lead /RO . Place SD in " Steam Pressure" mode Lead /RO e Maintains >200 gpm total AFW flow unless *B" SG level is >10% Lead /RO . Closes 'A' MSIV if needed to control cooldown RO e Vertifies RCP seal injection 6 to 10 gpm l Crew . Diagnoses a Faulted SG and transition to E-2 l lEvggggy M L,3;MNg%g%es jj;j;ggg n.ine;WaimgM' r ? ' sh), fwfygg;ggggggggy;;;g_ g N W93p%%w :cy QM
%ditEstablishLilowfrom vnMe2WCW N Orm?&2atisast:ddsssnm f n3M MMMWMSff!@% o T'"eno$dgHead'ECCS
@ 8 !M p Comments:
i i l l Page 12 of 16
l
Title:
Load increase; PR NIS Frilure; Loss of . Generat:r Cooling .; Dropped Rod; Fculted SG . l
* ' " : Event Description
, mS C " cKA'Numberf 3 KA Value s '
Faulted SG Time S/U Position Expected Response l E-2; Faut *ed S3 Isolation I i Lead . Verify 12 MSIV closed ' Lead . Verify 11 SG intact Lead . Identify 12 SG as faulted Lead . Verify Main Feed to 12 SG isolated Lead . Isolate AFW to 12 SG (criticaltask)' Lead . Close steam supply from 12 SG to TD AFW; MV-32017 Lead . Verify 12 SG PORV closed Lead . Verify 12 SG blowdown isolation valves closed Lead . Check CST levels > 5000 gallons Lead . Initiate SG samples SS . Transition to E-1 b f' i hhi%ik, kN!hIN!NSIbNbNk$bh0 [' hiI h k eid bf d f E h hbi!Id$ NIN[b $ N h!i MuSWEW@iM{EM&sM# vyyyppppywgy mmr c7pg ypeygyweg B !$i!!iM E es g@y;t!io% stas3 @iuE29%;p1 H Comments: 1 Page 13 of 16
' ' ' ~ ~ ' "' '
Title:
Load incre:se; PR NIS Fcilure; Los3 of . Generator Cooling; Dropped Rod; Fculted SG .,
. L,s .
as , sw , 9 Event Descriptioni '
, W & .m 9 2KA' Numbers :.KA Value ;!
Si Termination' Time S/U Position Expected Response ES 0.2; Si Termination Lead . Reset SI Lead . Reset Cl Lead . Verify IA to containment RO e Verify charging flow established Lead /RO . Stop both RHR pumps Lead /RO . Stop 11 Si pump Lead /RO . Close BAST suction valves MV-32081 and MV-32082 Crew e Verify Si flow is not required.
- EvaluatorNote;gna gg ft E xa stg$j$lhe;<gg stiijs
;;:Ph @
w am us . gpA sg , 3..s ,Qpngis o pm,. .
. , ..gS q@q mq.;j r+
y ...n a4q.;;r 7 " at.eu -w,g/ , ., g. se
%yp;; :
@4:g
. Wi?T.
o.w 11,f;v;pgr c
" p
,-m
-~ a;y.t.
.2 is. ,., base.d'up.o. , . mf
.,s
, w p w ac- ; , r
@p., o ira,nsition.to.ES -m 0.yNDY5p&NdMUiWM c. ,ormation P. a,pee.y~,.n, m s ofu E" 1, +p<ufWrhie,,m
.. -1in,e;s,j,.
t,h, iy ., g-; ,;.g m; , tjgg.n. .,n,%ek W
*r EUsW. !' - $$ I34 Nr,' 4 inn. . . :ZIS6 4:, c" r a 4ih + " >M$
_ gdgI-! el I [dMr D' ~ did Di V Comments: Page 14 of 16
] _
jj e t a i H p k l b c o V L V 7LE l I o s s s er p d oi S H to U t s s I I n i g n P B C o A o se l s P i r s S S o F s a R e o s n R T r t p c P Pr s s s s C 0 R V ia
- t i y Z T T e 1 O
r R R re
.I M i p p T r i r S T T M S 1# fe I
r T T 2 C t y R P T e O A A T O Z Z P R R o P r o 2 H n J d o L C P P L L e R U x t f fo lu D B C a A G G C R R c
' p S 5 6 8- 7 7 J 1 i e e m - 0 0 1 1 1 I f u F
- A B ru ru u G 7 1
7 1 7 1 7 1 I 3 4 4 3 4-3 4-3 4 4 3 o s p p 3 E
.U l i
l i a a a a I l i l i P S 2 S S S S
- - - 4 C C T T T C C C C
- - s o w 1
/
1 F F FF S 1 R R R R F I I P P P P L D 1
, Ii ~
E V _ d _ o _ R d e _ p P I p R o r y T . D r X a R g m 9' n m i l o u A S o -
% N N N N 0 P P P P P P N 1 ' t u
0 E E E E 0 I I I I I I E f n
" p A 0 1
P P P P O O O O 5 2 R R R R R R T T T T T T P O n t o i n i o a r r n o a . e t P n a e l u _ G A B B 7B 4 5 6 7 G f m 2 2 6 .A S l l 1 l 2 0 1 0 2 0 0 2 3 2 2 2 1 2 2 7 5 0 0 o i S 0 0 P O IO S P P R P 4 0 i i S S S S 1 i 2 X 2 2 P P P P P P 1 1 1 1 0 G 0 1 L _ s R R R S MMMM R R R R R R R E D s M R C o L e r l u i a E E E E R E E E E E e E F F F F F F F L L L L L L T T T T V T T T T T i F F T O O O O O O O O O O O L L O S A A A A A A M M MM S M M M M MM A A M I M MM M M M E E E E Y E E E E EE M M E N R R R R S R R R R R R R R P e s a A A A A 3A A A A A A A A A eG I O 0 1 P P P P 0 2 2 2 1 0 0 0 3 0 3 3 0 0 0 3 0 0 3 3 0 3 3 0 0 0 0 3 3 4 0 2 0 2 O crS R R R R 1 S S 5 S S S P P P P P P P G D L 1 h M M M R R R R R R R E R nd MMM M M M M M M M M M M M M C S S S S S M M M MM ie t I I I I I I I I I M dl I S I I S S S S I I S S I I S S I S I S S I S S I S au oa LF e it c f EP 0 0 0 O 0 O 1 1 1 1 2 3 3 3 3 3 3 4 5 6 i T O
l i CHAMPS FORM KTF-D 2 1 RETENTION: 7 DAYS DATE- ! UNIT 1 LPEO / W,0 TURNOVER TIME:N (*AB00-0600) l , SFGDS EQUIP OOS/LCO'S: ; 1 :PORV PCV-430 LEAKING AT 2 GPM- ISOLATED l 2 :01 EDG (REPAIRED) 3 : RAD MONS 005: ANNUNC'S 005: l l J OUTSTANDING SP' S : FIRE DET/ PROT EQUIP IMPAIRIENT: ] PATHS FROM THE GRID DUE IN 4 HOURS OTHER EQUIP 008 / STATUS: 1 212 BATP FOR PM 2 : 3 : 4 : 5 : 6 : ; 7 : I 8 : i 9 : I 10 : 11 : 12 13 : 14 : 15 : I 16 : 17 : MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE:- i 1 :D1 EDG RESTORATION IN PROGRESS 2 : J 3 : 4 : i j 5 : l OPERATIONAL PIANS FOR COMING SHIFT: 1 : CONTINUE WITH C1.2 AND LOAD INCREASE PER C1.4 TO 100% POWEB (<.85%/ MIN) 2 : 3 : 4 : l NEW PROCEDURES / INSTRUCTIONS. i 1 FUEL PRECONDITIONED TO 218 STEPS AND 100% - MAY 11, 1999 ! 2 ' :ITC VERIFIED TO BE NEGATIVE BY NUCS ! 3 : I I WATCHSTANDERS LPEO: LASH PEO: JONES LPEO RELIEVED BY: , TIME: DATE: PEO RELIEVED BY: TIME: DATE: CB WALKDOWN --> LPEO: TIME: _
--> PEO TIME:
1 1
]
l PPUP 1 Simulator Ex9 rcis: nuid1?W WWl File Number: 99-03
Title:
Load increase; Loss of Charging Flow; Rev: 0 Tavg Failure High; Loss of Vacuum; Turbine Valve Failures; ATWS; SG Pressure instr. Fail High; SGTR Lesson Plan: NRC Exam Duration: 2 hours Author: Jim Lash Approveo oy: Date: OBJECTIVES:
- 1. Start a second feedwater pump per C28.2.
- 2. Perform a load increase per C1.4.
- 3. Diagnose and respond to loss of air to a charging pump per C47015 and C12.1.
- 4. Diagnose and respond to a Two instrument failure high per C51.
- 5. Diagnose and respond to trip of running Gland Steam Condenser Air Exhauster that results in decreasing vacuum per C47008 and C29.
- 6. Diagnose and respond to sequential closure of MSR Intercept valves per l C23 AOP2. l l
- 7. Diagnose and respond to a failure of the reactor to trip per E-0.
- 8. Diagnose and respond to a SG pressure instrument failure high resulting in a SG PORV opening per C47011 or E-0.
- 9. Diagnose and respond to a SGTR per E-0 and E-3.
l RELATED LER's, SER's, SOER's, etc.: None RELATED PRA INFORMATION (See PITC 2.3): i Initiatina Event with Core Damaae Freauency: SGTR (7.1%) j important Components: Reactor Protection System 11 TD AFW Pump Important Operator Actions: CRO 301.004.06.01; Cooldown and Depressurize from SGTR Before Overfill (E-3) Page 1 of 19
Title:
Load increrse; Less of Ch:rging Flow; Tcvg Frilure High; Lcca of Vccuum; Turbine Vciva "M i Z i l Failures; A1WS; SG Pressure instr. Fall High; SGTR g SCENARIO OVERVIEW Initial Conditions:
. The scenario will begin at 50% power with two Condensate Pumps, two Heater Drain Pumps, and one Feedwater Pump running. . Out-plant actions have been completed to support starting a second MFP. . Following turnover the crew will start the MFP and continue the power ascension Seouence of Events:
Event 1: Load increase
. Per C1.4. + Stan a second MFP per C28.2 Event 2: Loss of Charging Flow . Mechanical blockage in air supply line results in the running Charging Pump speed reducing to minimum.
o The crew will be required to start another Charging Pump to restore normal charging and seal injection flow and maintain Pressurizer level. Event 3: Tavg Failure high
. A Tcow RTD fails. . Control rods automatically insert, requiring operator to take manual control. _ . Charging pump speed increases, requiring operator to take manual control. l . The affected channel is defeated and control systems are restored to automatic. ! . Protective bistables are tripped to satisfy Tech. Specs per C51.
Event 4: Loss of Gland Steam Condenser Vacuum j
. The running Gland Steam Condenser Air Exhauster trips. . Due to the reduction in air removal from the gland seal system, gland steam ,
l condenser vacuum decreases.
. The crew will respond by swapping to the attemate Gland Steam Condenser Air I Exhauster per C29.
Event 5: Intercept Valve Closures I
. One MSR Intercept valve will close. . The crew will respond to turbine drains indications and alarms and direct the Turbine l Building Operator to investigate.
Page 2 of 19 i
Title:
Load incr: ass; Loss of Charging Flow; Tcvg Failure High; Loss of VEcuum; Turbine Vciva
. M 69 Failures; ATWS; SG Prtc;ure in:tr. F ll High; NS'y.., L I SGTR Y/.c2$ 1
. The crew will determine a MSR Intercept valve has failed closed due to EH fluid Ic3 at actuator and perform actions of C23 AOP2. . A second MSR Intercept valve will fail closed, requiring a reactor trip. Eveni6: ATWS 1 l . The reactor trip breakers will fail to open and the crew will need to actuate the new DSS /AMSAC system to trio the unit. Event 7: SG Pressure Instrument Failure with Opening PORV e Following opening of the reactor trip breakers,12 SG PORV opens due to failure of the associated pressure channel input. l . The crew will be required to take the Controller to MANUAL and shut the PORV when SG pressure is below the normal opening setpoint of 1050 psig. . Upon completion of actions of FR-S.1, transition should be made to E-0. . Si is NOT expected to have actuated or be required, so at step 4 of E-0 transition is made to ES-0.1 Event 8: SGTR . Upon transition to ES-0.1 a SGTR occurs in 12 SG (over a 4-minute period). . The crew should transition to E-0 and perform the actions beginning with step 1. . At step 20 of E-0, transition is made to E-3. . The scenario ends following depressurization of RCS to minimize break flow. , + CriticalTasks
> Insert negative reactivity by either inserting control rods, establishing RCS boration; or directing local trip of the reactor prior to FR-S.1 Step 6. > lsolate feed flow irito and steam flow from ruptured SG before entry to ECA-3.1 is I required. > Establish and maintain RCS temperature to establish adequate subcooling to preclude transition into ECA-3.1 and without causing an extreme challenge to the i Suberiticality and/or Integrity CSFs. I I
PRE-F.XERCISE BRIEF
- 1. Follow NUREG-1021 Appendix E; Part E 4
i Page 3 of 19 ! l
Title:
Load incresco; Lcss of Chrrging Flow; Tcvg MIDW'ETMK% Fillure High; Leca of V cuum; Turbino V lva T f." .' ~ N V M E T Y I Fcilure2; ATWS; SG Pre 2 cure in:tr. Fcil High; 57 ~ . NN f SGTR JAM M*N W M INSTRUCTOR GUIDE I
- 1. Initialize to IC-19 and verify the following conditions:
- a. RCS boron display = 1141 ppm.
- b. MOC Al displayed. ,
- c. Bank D step counters at 177, all others 228.
- d. All charts advanced and cleared of previous trends.
- e. ERCS is on-line and functional with alarms acknowledged / cleared.
- 2. Insert the following pre-existing conditions (Relative order of 0)
- a. Mechanical Failure of Reactor Trip Breakers
- b. PT-449 failure low and bistables tripped
- c. Increase FW Pump casing temperatures
- 3. Establish the following conditions:
- a. Place a "l&C Channel in Calibration" placard near channel PT-449.
- b. Remove 11 TDAFW pump from service as follows Place 11 TDAFW pump in pullout and attach a secure card.
- Place 11 TDAFW pump in MANUAL and attach a secure card.
- c. Place a 2dorifice in service. Start 12 Pump in MAN; place 11 in AUTO. l
- d. Establish 1 MFP,2 Condensate pumps, and 2 HDT pumps running.
- 4. Arrange the following information:
- a. Cat i Vent opening sheet reflects no logged openings.
- b. Log books are open to a blank page.
- c. C1.4 consumable is the same revision as the book and signed off through Section 5.1.18.D.
- d. Place Current Value of 1U2026AH on an ERCS display.
- e. Update and print and LCO log with the following information:
TS: Time' Reason. , _ . ,.._ ,. ' LComNneht' ' LNumbes JLimit iCodet ? Description ' Date and Times 11 AFW 3.4.8.2.b 72 HR CM Oilleak on oil cooler Today 0100 pump j i l Page 4 of 19
]
Title:
Load increr.se; Less of Chrrging Ficw; Tcvg Frilure High; Loss of Vccuum; Turbine Valva TN!i W 7 K"75 y,, e j;fNE/ [jfhM;
' Db_M..fj Failures; ATWS; SG Pressure Instr. Fall High; . ...
SGTR
- 5. Conduct shift turnover
- a. Use the shift turnover sheet provided and provide the following information:
Current power is 50% with a load increase in progress. Ready to l start a second MFP at C1.4 step 5.1.20.E. 11 TD AFW Pump is OOS due to governor problems. The expected time OOS is at least 24 hours. l - I&C is performing a calibration of pressurizer pressure channel l PT-449 (Yellow) which is expected to be completed within 1 hour. 1 Unit 2 is shutdown.
- b. Allow 3-5 minutes for control board familiarization.
- 6. When requested, provide support for starting a second MFP.
- 7. At the discretion of the chief examiner insert loss of air to 12 running charging ]
pump. (Relative order of1) l
- a. After the Aux. Bldg. Operator has been directed to investigate the pump, report that there is an air leak coming from the speed controller for the 12 charging pump.
- b. If maintenance is contacted regarding 12 charging pump, report that it you will initiate a work order. Estimated time for repair is about 2 hours.
- 8. When charging has been restored AND one charging pump is in AUTO, _T_h_e_q at the discretion of the chief examiner insert yellow channel Tem failure high.
(Relative orderof 2)
- a. Trip bistables upon request (Relative Order of 3).
- 9. At the discretion of the chief examiner enter failure of gland steam air exhauster and resulting lowering of gland steam condenser vacuum. (Relative order of 4)
- a. If asked to investigate, report that the gland steam condenser air exhauster has tripped.
- b. As directed, report dampers positioned per C29.
l Page 5 of 19
Title:
Load increase; Loss of Charging Fl w; Tcvg
' Failure High; Los3 of Vacuum; Turbine Vciva Failures; A1WS; SG Precture in;tr. Fall High; SGTR 10c At the discretion of the chief examiner fail one turbine intercept valve closed (Relative orderof 5) a.' if asked to investigate, report that there is a small EH fluid leak at the actuator for CV-31167
- b. At the discretion of the chief examiner fail a 2d intercept veJve closed.
(Relative orderof 6)
- 11. When a reactor trip using DSS is performed, then perform the following:
1
- a. Insert PT-478; SG pressure instrument failure high (Relative order of 7)
)
- 12. During E-0:
- a. If asked, locally open the reactor trip break 3rs one minute after being directed. (Relative order of 8)
- b. When the crew transitions to ES-0.1, Then insert SGTR on 12 SG (Relative orderof 9)
- 13. During E-3:
- a. Wait a couple of minutes and report that a cation column frisk of 12 SG reveals activity above background.
- b. After containment isolation is reset, wait 5 minutes and report that a frisk of the SG sample bottle shows elevated activity in 12 SG. No elevated activity in 11 SG.
- 14. At the discretion of the chief examiner (Sl pumps off), place the simulator in FREEZE.
Page 6 of 19
r-
)
Title:
L".ad increase; Loss of Ch:rging Flow; T5g-Fciture High; Loss of Vacuum; Turbine Vciva Failures; ATWS; SG Pressure instr. Fall High; SGTR l Name: Position: SM SS Lead RO 1 l Date:
- MW is eo PEvent DescriptionWHe4 > h rm mKA Numbere w KA Value Wm Start 2"" MFP Time S/U Position Expected Response Lead C28.2; Start a Second MFP (Section S.6)
. PlaceNerify CV-31875 Recirc to Open Position
. ERCS GRPDIS "OP6" to observe temperatures e Otart 12 MFP (Switch held until Recirc valve open and permissive ON) l l
. Evaluator Note:: ' ail . i nisaw -
na > ( > > aid s i .. aun ',m .u a a Comments: i l l Page 7 of 19
i l l l
Title:
Load increrse; Less of Charging F12w; Tcvg Failure High; Lecc of Vacuum; Turbina V::lva "fidiOT7WJ f.;';
$$siil;jfI;i{.J.;1h -
l Failures; ATWS; SG Pressure instr. Fall High; '4R*"R7%W 77 % A SGTR $$5 Y 3"M N @l P % $ 4
.; grm , t ' vm it Event Description? 4' 'e:' s & W KA Numbere '
o KA Value$ ' ( Load increase Time S/U Position Expected Response C1.4 Load increase RO . Dilution started ] RO . When Tavg shows an increase, turbine place in GO l l tEvaluatorNote:m " > w e e:! +++ -- ' em > >~te m: " "
- em" m rsn Comments:
I 1 i i l l l
)
l l l, l l l l l 1 I 1 l 1 i l Page 8 of 19 1 , j
n Titix Lead incrama; Leco cf Chaging Flaw; Tcvg Q glgg Frilura High; Leco of Vrcuum: Turbina Vcivs 4 Failures; ATWS; SG Pressure instr. Fall High; Q# SGTR . Vd*EM[b:fh,[4-:' I
- m. , agy;0rnh nEvent Descriptiontip% 4 '
nw aWM KA Numbere 4 e ~ KA Values - Loss of Air to Running Charging Pump Time S/U Position Expected Response C12.1 and/or C12.1 AOP1 l RO . Determine 12 charging pump low speed. RO e Stop 12 charging pump. RO e Start 13 charging pump. RO . Adjust seat injection flow to between 6 and 10 gpm per pump. RO . Place running charging pump in AUTO. Lead . Make appropriate log entries 2: Evaluator Note:D ' '
'e ' '"N > ' d> 'Pt f Comments:
l l J l Page 9 of 19 1
F Tit l3: Lead incre:se; Lecs of Chrrging Fitw; T&vg Fcilure High; Les of Vccuum; Turbina Vtivs Failures; ATWS; SG Prt: cure instr. Fall High; a.
.? ,"
. A nGF@"
' f?
M(iFM M t: A3PJ:jf;g60 SGTR E N D:i$ $F $ .['*s N
. 74 .e,i mmum Qa;. Event Descdotionmin W ' 's rMMM BG KA'NumberuF @ IKA Value2 %
Te Channel Failure High Time S/U Posifs. Expected Response C51.4 Tavo Loop 1 A 1T 404 - High RO . Place charging pump in MANUAL and maintain pressurizer level. RO . Select Yellow channel on Two defeat switch and pull out. RO e Retum rod control to AUTO, RO e Retum charging pump speed to AUTO. SS e Refer to T.S.3.5 (6 hr LCO for B/S tripping). RO/ Lead
- Trip and independently verify bistables.
RO/ Lead e initiate work order on the failed channel. Lead
- Make appropriate log entries.
" Evaluator. Notes 'E '
'. 'W ,< 71 > ">
- RE m ;'i
- Comments:
l Page 10 of 19
Title:
Load increra; Loss of Chirging Flow; Tcvg . n L. g -l T- Q p j ; Fcilure High; Lo"3 of Vccuum; Turbina Vciva .. ..f y. .r.- '! '7.y.. ye Fcitures; ATWS; SG Prerura Instr. Fall High; .l- fC .:. 1. ff . ( SGTR l-7 "~~"r"~"* '7t0 M + Jcww aM Event DescriptionV,- ,Ju > , em wu. miKA Number!2 o f KA Valuef - Loss of Gland Steam Condenser Time S/U Position Expected Response C47008 and C29; Swap Gland Steam Air Exhausters Lead . Start Standby G.S. Air Exhauster Lead . Direct TBO to Open B Damper and Shut A Damper Lead . Direct Electrician to investigate and repair Lead . Make appropriate log entries t Evaltiator. Note:? 6 Pmm"? >v ' U" me 4"N 'A m 4- %i > ,b & >'1 Comments: 1 l l i i l l l l Page 11 of 19
Title:
Load incre:se; Loss of Chirging Fisw; Tcvg Failure High; Lcca of Vccuum; Turbine Vciva
.Jj% n
- ? i . L..1:'r a
- nd Q' f:g/g 'J
~"
Failures; ATWS; SG Pressure instr. Fall High; 7 'I T; ^ SGTR Sf5 * .':Mb 92sM
- , ' * * ' + " - Event Descriptioneee ,
e ? KA Numberb " " dKAValue:s s Intercept Valve Failure Time S/U Position Expected Response C23 AOP2; Malfunction of Turbine EH Control System (1" Valve) Lead . Identify Intercept valve closed Lead . Direct TBO to investigate Lead . Inform crew of 70% power limitation C23 AOP2; Malfunction of Turbine EH Control System (2" Valve) Lead . Identify 2 intercept valves closed on one turbine and need to trip Rx and Turbine REvaluator Note:t te ' ' ' ' " '"
" " ' ;"* " nA" " + , " PcMie Comments:
1
)
i l i l; 1 I I Page 12 of 19 j
F
Title:
Lead incre:se; Less of Chrrging Fl:w; Tsv9 a h m-
.r ~ m.a n . w .t, n ,-7 Fcilure High; Lc2a of V2:uum; furbine Vciva L ~.c - :twN.g;:J
. ,. .2. .
Failures; ATWS; SG Pressure Instr. Fall High; i? . i W 1,0 SGTR YA Y E %1 s 41# 1
" ' - @> @ Event Descrigion 9 ~ em 1 W KA Number? s KA Value e ..
Reactor Trip / ATWS
~
( Time l S/U Position Expected Response E-0; Reactor Trip er Safety injection RO . Attempt to trip unit using Rx Trip Switches RO/ Lead . Trip unit using DSS switch (crMcaf)' RO . Verify reactor power less than 5% Lead . Verify turbine trip - both turt>ine Stop Valves Closed f 1 Lead . Verify safeguards buses 15 & 16 energized. ; RO . ' Check if Siis required
-SG Pressure >500 psig
-PRZR Pressure >1815 psig
-PRZR Lwel >5%
-Sul, cooling >20*F
-Containment Pressure <4 psig i
SS . Transition to ES-0.1 if no Si required. Continue in ES-0.1 until Si is required. 1
'rJ Evaluator q 35 y.4 W W yr MNoterwwiXE$nt..pt?ti p;g T @jWgjg!gWE#>JMey%gfdq'7 >i% p wWWajiWisP* f1lit!! .!yp kugiisgp-/!@?g;W 7...
Nnfid [tnhhNtiNNE $y!.jj0%(PQyy]htbbINtiorhfNirhdlkh h hitN didsN b h M bl hhstdhiskih "" i.gy < ge y loca, ~ w yg g a. pge ; F,R-S.1 l' trip ofitseisactor m.. .. prior'to g,. . ; y Step 67 %$5%
; y a,pp, m . m, ;g,.-
' T9P t < 'Ti
. zqy a. .._$c. ,! 4 ->;'~'
;gg. , . -
gm3i l 7. Comments: Page 13 of 19
~
-t.
Title:
Load incrense; Leco of Ch:rging Fitw; Tcvg -[.
;l P. 'f,f %,. ,;pf JR '
j Fcilure High; Lcca of Vccuum; Turbine Valva .;~ Q F W ".JLD.; R, Frilure3; ATWS; SG Pr;ccurs in:tr. Fall High; .C:Tl ???".M?M'.- SGTR E5E wMENFddE.M i x; c Event DescriptionW" "m 9> r KA'Nambera %' r ! KA Valuev- l SG Pressure Instrument Failure High l Time S/U Position Expected Response C47011 I I Lead /RO . Identify and inform crew of open PORV { Lead /RO . Shut PORV by taking PORV controller to Manual Lead . Control SG Pressure manually "EvaluatorNoten$m me 1 amOWG unM*WW w/**4 f OM @wv' '"Neo" " ' " ' es & Comments: l 1 l 1 l 1 l i i l Page 14 of 19
Title:
Lead increzco; Less of Ch:rging Fl w; Tcvg i RW of life c; a Failure High; Lo23 of Vccuum; Turbina Velvs hij :if ll W .I a wh 4; Q&l Tyy Fcilures; ATWS; SG Pr:scure in:tr. Fril High; u7 (L l SGTR Nnt i N emktm1Na Eveert Descriptione'*" > " ' "4 P: mW KA'Numbert " J KA Value t*
- SGTR; St Required or Actuated 1
1 I Time S/U Position Expected Response RO/ Lead . Si actuated Automatically or Manually i SS . E-0 Re-entered E-0; Reactor Trip or Safety injection RO . Verify Reactor Tripped Lead . Verify turbine trip- both turt>ine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized. RO . Verify Si actuated Status Light ON Lead . Verifies component alignment l Lead . Closes MV-32115 (CC to SFP Cooling) SS . Ensures communication with NRC is established w/i 1 hour Lead . Opens turt>lne HP drains Lead . Directs Outplant to stop the TB roof exhausters and isolate the l MSR's SS . Ensure Auto-Action Guide is implemented Lead . Place SD in
- Steam Pressure" mode Lead . Maintains >200 gpm total AFW flow unless "A" SG level is >10%
RO . Verifies RCP seal cooling Crew . Diagnoses a Ruptured SG and transition to E-3 ibEvaluatorNoter > C ' <. , - *e' > 4+AM s >> r MWs N a e. M Comments: Page 15 of 19
r i
Title:
Lead increrse; Lcss of Ch:rging Flew; Tcvg J 9 47%.s % . Fcilure High; Losa of Vacuum; Turbina Vciva : 1 .7 ~ ~1 :Qf C1 Fcilure0; ATWS; SG Prescure in2tr. Fcil High; e .: . . .i ; y ;g,7 +. q g. .-; l g +,g. p.
..,.,,..a
... ..,c , . , . .
l i 1
,9WM @@MEventDescriptionWcWN m% eKA NumberM wmKA ValueW l l ,
l Steam Generator Tube Rupture I I Time S/U Position Expected Response E-3; SGTR l RO/ Lead . Identify 12 SG as ruptured. Lead . Isolate flow from 12 SG. (Critical Task)'
- Close steam supply to TD AFW pump.
- Close MSIV.
-(SG PORV closed eariier) !
Lead e isolate feed flow to 12 SG when NR is >10%. (Critical Task)' l Lead /RO . Reset St. Lead /RO e Reset Cl. Lead . Initiate RCS cooldown (Critical Task)2
- Determine required CETC temperature.
- Cooldown at maximum rate using condenser steam dump.8A i
- Maintain CETC temperature once desired value is attained.
AEvalu,ator.Notem '.-
, %im ~FMM % fy3 W W "i@eWigym owwr : g i
c~ .s y.yjw. j , dp
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,,,1
, qN 0: Q1 .-l flow;to!an;...... .lM!.d@4 $;, tin 4,mwpW/M;W d steam flowfmmy;.;;Lm$dL,AYGf ghfQgM.h4., mw[@MS SUVAiWbds hiM O m
m x H.~4.,a;. n a @ ?.~% m. .., MP - _D sm t!Q i W W,mm%_V
#.@--a%.m,s c.~,m M M W M h.$_?9 %, an C.,hF -,ts?il Ms '2J.1stablish a..,,m-nd maintaixn an - RC.S. tusta., , ciu. d,e'transitionD i,intd ECM. 391! uadd with.
- 6. t causin._chal g an' extreme.orswere temp _e~rature,.,to_
p .; y agggggg .lenge to th,,e, In0.to
'~an e_ estab,._lish,ade.
n apt 3 1 _ egg w f
, 73 q pt g ;;g g % - 3p;;;;7 y g g g g y y y m g g y,r,g g d/ orc, q>g.
gg q
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,y ,- y g & ug g,e ,,,ga r, , -m,- , , , eg 7,y p Comments:
m i Page 16 of 19 . 1
Title:
Load incre:se; Loss of Ch:rglag Flow; Tcvg .. s .g . 3 A i Cr: t.j-Fcilure High; Loss of Vccuum; Turbine V:lva '* : dis # fg[Q.g j Qdy.L Fcilures; ATWS; SG Prerure Instr. Fcil High; SGTR A o; e%UA w smmwEventDescriptionMcm wwnnu % KANumberm enKAValuem Steam Generator Tube Rupture (continued) Time S/U Position Expected Response E-3 (continued) RO/ Lead . Stop RHR pumps. RO . Establish maximum charging flow from RWST. RO . Tum all pressurizer heaters OFF. RO . Depressurize the RCS using normal spray at the maximum rate until either:
- RCS press < SG press and PZR level > 5%.
- PZR level >70%.
- Subcooling <20 F.
RO . Verify RCS pressure increasing. Crew . Verify Si termination criteria are met. Lead e Stop SI pumps'
- mem gnw; rm?Ps33r3 3psMgapay;;;sG?rinP .emsig Mgytil:
esisi p* e ti y muw . uwwwuc w CEvaluator. ) , M ANUgki 3 jr3$dP; ., Ud '" 4Note:n, ammu Y;37%IjM$p;%.n g lgE![Qf , awhshg[h;fh3 np!Weimat/[fidjO,fj;hM!.ll3l ifAft0r 81 pump p gy,qy are
'ny.: stopped!attbeldiscretion'of the Chief Examiner /the.. scenario;may be te v
3 g 9 5 % ; ;g g g y g g;g g y g g a g ? g ,4 b y g g e ve gy,a Comments: l l l i l Page 17 of 19 l
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o CHAMPS FORM KTF-D 2 RETENTION: 7 DAY 3 DATE: l UNIT 1 LPEO / PEO TURNOVER l TIME:N(1800-0600) SFGDS EQUIP OOS/LCO'8:
-1 :11 TD AFW PUMP DUE TO GOVERNOR PROBLEM - EXPECT 24 HOURS FOR REPAIR 2 :PT-449 FOR CAL 3 :
RAD MONS 008: ANNUNC'S OOS: OUTSTANDING SP'S: FIRE DET/ PROT EQUIP IMPAIRMENT: OTHER EQUIP OOS / STATUS: 1 : 2 : 3 : 4 5 : 6 : 7 : 8 : 9 : 10 : 11 : 12 : 13 : 14 : 15 : 16 : 17 : MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE: 1 : 2 : 3 : 4 : 5 : OPERATIONAL PLANS FOR COMING SHIFT: 1 : START A SECOND MFP PER C1.4 AND CONTINUE LOAD INCREASE 2 l 3 : j 4 : l NEW PROCEDURES / INSTRUCTIONS: 1 : 2 : 3 : WATCHSTANDERS LPEO: JONES PEO: LASH LPEO RELIEVED BY: TIME: DATE: PEO RELIEVED BY: TIME: DATE: CB WALKDOWN --> LPEO: TIME:
--> FEO : TIME:
l9 - imul' tor Exerci:. 'uld~ W "sl File Number: 99-04
Title:
Coastdown; inadvertent Boration; Loss i Rev: 0 of CC; Load Reduction; Leaking PRZR PORV; RCP Trip; Loss of All A.C.; SBLOCA > Lesson Plan: NRC Exam Duration: 2 hours Author: Jim Lash Approved by: Date: OBJECTIVES:
- 1. Diagnose and respond to failure of the letdown temperature contioller and subsequent boration per C47015:0408.
- 2. Diagnose and respond to loss of component cooling per C47020-0101.
- 3. Perform a load reduction per C1.4.
- 4. Diagnose and respond to a leaking pressurizer PORV per C47012:0506.
- 5. Diagnose and respond to a RCP trip and subsequent reactor trip per E-0.
- 6. Diagnose and respond to a loss of all AC power with failure of D1 to automatically start per ECA-0.0.
- 7. Diagnose and respond to failure of AFW to start and a subsequent flow indication failure per ECA-0.0 and C47.
- 8. Diagnose and respond to small break LOCA per E-0, E-1, and ES-1.1.
RELATED LER's, SER's, SOER's, etc.: LER 96-12; LOP to Unit 2 and Degraded Power to Unit 1 -Rx Trips on Both Units RELATED PRA INFORMATION (See PITC 2.3): Initiatina Event with Core Damaae Frecuency: Loss of All A.C. (34.2%) SBLOCA (1.3%) Important Components: 11 & 12 CC Pumps D1 & D2 Diesel Generators Page 1 of 16
Title:
Crtdown; inadvIrt:nt Borctien; Lo2a cf , Load Reduction; Leaking PRZR PORV; RCP Trip; Loss of All A.C.; SBLOCA SCENARIO OVERVIEW Initial Conditions:
. The scenario will begin at 96% power in coastdown to the scheduled refueling outage . D2 out of service . Pressurizer pressure, Yellow channel (PT-449) is being calibrated Seouence of Events:
Event 1: CVCS Letdown Temperature Control Problem
. The CVCS letdown temperature controller for TCV-130 fails to 68% in AUTO, resulting in hotter than normal letdown flow stream (135 F+). . This should result in boration of the RCS as the hotter water picks up boron from the demineralizers. . The crew is expected to diagnose as RCS temperature begins to drop faster than expected. . The Tave limits for Coastdown curve C1-29 is violated requiring the crew to reduce power to return to the normal operation region. . The crew can take manual control and adjust to restore normal letdown temperature of 110*F per C1.4.
Event 2: oss of CC
. The running (12) CC Pump trips and the 11 CC Pump fails to start. . The crew will start the standby CC pump and monitor RCP bearing temperatures. . -if any of these reaches 200 F, the crew should trip the reactor and then stop the affected RCP(s).
.. Due to the failure of the CC pumps, T.S. 3.0.C is invoked and a shutdown required. Event 3: Load Reduction
. Per C1.4.
Event 4: Pressurizer PORV Leak-by 4
. One PRZR PORV leaks by . The crew will need to diagnose which PORV is leaking and isolate the leakage. . Adhere to T.S. 3.1 for a leaking PORV.
Event 5: RCP Trip
. 11 RCP trips due to failure in the lower bearing. !
Page 2 of 16 I
Titis: C ::tdswn;inidvirt:nt B:rctirn; Leca cf CC; ' WWiw Lead Reducti:n; Lc: king PRZR PORV; RCP wmm Trip; Loss of All A.C.; SBLOCA -
.. $7
- The crew will perform the actions of E-0 and transition to ES-0.1 based on SI NOT actuated nor required.
Event 6: Loss of All Safeguards A.C. / AFW Flow Failures . Following transition to ES-0.1, a loss of offsite power occurs. Unit 1 experiences a loss of all AC power due to the unavailability of D2 and failure of D1 automatically start, and unavailability of unit cross-ties (Unit 2 failures). . ECA-0.0 is entered. . The crew is expected to manually start 11 TD AFW pump and maintain at least 200 gpm flow to the SGs. The flow indicator to the 12 SG has failed low requiring controlling 200 gpm to 11 SG or calling the Aux Bldg Operator to get flow indication locally. . The flow to 12 SG may be throttled and adjusted based on SG level trend. The 200 gpm flow is required until at least 10% level is reached in either SG. . Bus 15 can be energized by manually starting D1. . Once bus 15 is verified energized, the crew will transition back to ES-0.1. Event 7: RCP Seal Failure / SBLOCA . Due to the loss of cooling during the loss of all AC,11 RCP has a SBLOCA via the pump seals.
- The crew should recognize the decreasing RCS pressure and PRZR level, and manually initiate SI.
. The crew will transition to E-1 at step 21 of E-0. . The scenario ends at step 24 of E-1 when it is determined that transition should be made to ES-1.1. + Critical Tasks
> Establish the minimum required AFW flow rate to the SGs on a loss of all AC before SG dryout occurs. > Energize at least one AC Emergency Bus so that transition to ECA-0.2 is not required upon completion of ECA-0.0.
PRE-EXERCISE BRIEF
- 1. Follow NUREG-1021 Appendix E; Part E Page 3 of 16
l'
Title:
Cacctdown; inrdv:rtnt Boritinn; Lo23 cf , L:ad Reducti:n; Leaking PRZR PORV; RCP , Trip; Leca of All A.C.; SBLOCA INSTRUCTOR GUIDE l
- 1. Initialize to IC-17 and verify the following conditions:
- a. RCS boron display = 0 ppm.
- b. CDC Al displayed.
- c. All step counters at 228.
- d. All charts advanced and cleared of previous trends.
- e. ERCS is on-line and functional with alarms acknowledged / cleared.
- 2. Insert the following pre-existing conditions (Relative order of 0)
- a. 11 CC Pump fails to auto start
- b. D1 Fails to auto start.
- c. TD AFW flow to 12 SG indicator failed low, i
- d. TD AFW Pump Fails to Auto start.
- e. PT-449 failure low.
- 3. Remove the following equipment from service:
- a. Place a Channel In Calibration placard near channel PT-449.
. b. D2 DG as follows Place D2 control switch in pullout and attach a secure card. l Place D2 output breaker control switch in pullout and attach a secure card.
Place D2 speed control to lower until the governor ready lights extinguish. Place D2 "Out of Service" signs on the CB at various locations.
- 4. Arrange the following information:
- a. Cat i Vent opening sheet reflects no logged openings.
- b. Log books are open to a blank page,
- c. ERCS " COAST" displayed in CR.
- d. Place a copy of PT-449 calibration procedure on the desk
- e. Update and print and LCO log with the following information:
... < - MS^^ WW LReasont o e W "
?- . ' 'eP 10$ ISM. ,, sib IEbrslOb 50 8 Y'CodsI ad$ DEN *IhAl$bMN INb"N*EbkiNY D2 3.7.B.1 7 days CM Jacket Coolant Leak. , Today 0100 1
Page 4 of 16
1 Titis: Csmtd:wn; intdv:rtInt Borcti:n; Les3 cf CC; Lead R:ducti:n; Leaking PRZR PORV; RCP Trip; Loss of All A.C.; SBLOCA .
- 5. Conduct shift turnover
- a. Use the shift tumover sheet provided and provide the following information:
Plant is in coastdown operation I D2 is OOS due to a jacket water coolant leak. Work is complete and ! the diesel is being restored to service. l&C is perfomiing a calibration of pressurizer pressure channel
' PT-449 (Yellow) which is expected to be completed within 1 hour.
Unit 2 is operating at 100% power.
- b. Allow 3-5 minutes for control board familiarization.
NOTE:. 1 . lThe boration of the.RCS needs to be.' monitored closely and may need to c be re entered.9 When manual action is taken to 'r educe letdown - item'peraturef _ th !!D
! stop increasing boron co'ncentrations
- 6. At the discretion of the chief examiner insert failure of CVCS letdown temperature controller (Relative order of1). Ensure RCS boron slowly increases and use remote function to change it about .5 ppm / minute. (Relative order of 2) l
- a. When the crew takes manual control of TCV-145 and reduces letodwn I temperature, then stop the boration. (Relative order of 3)
- 7. At the discretion of the chief examiner (after power change), insert lockout of 12 l CC pump (11 CC pump will fail to auto start). (Relative order of 4) !
- a. If asked to investigate 12 CC pump, report that the motor feels very hot.
4
- b. If asked to check the breaker, repod that there is a 50-51C relay picked up.
- c. If asked to investigate why 11 CC pump didn't auto start, tell them you will look into it.
- d. If contacted, call in as the Shift Manager (preferably after the crew has recognized the Tech Spec on the CC pumps) and inform the SS that management has considered the plant equipment problems and direct that a unit shutdown to start the refueling shutdown be commenced immediately.
Page 5 of 16 j
Title:
Coa:tdown; in:dv:rt:nt Bortti:n; Lcc3 of CC; 'T7M - T ^ N S - 1 I Lcad Reduction; Leaking PRZR PORV; RCP Y * ~ Or YW X l Trip; Loss of All A.C.; SBLOCA D$$MMTh l 1 i 8.
^
At the discretion of the chief examiner insert leaking pressurizer PORV (Relative orderof 5). NOTE: If the crew elects to trip the unit, be prepared to insert RCP trip._ l
- 9. At the discretion of the chief examiner insert RCP trip (Relative order of 6) l
- 10. Following the transition to ES-0.1, insert the loss of off-site power (Relative order of 7)
- a. If asked to investigate D1, report that there is no apparent cause for the start failure.
- b. If asked, inform the crew that there is no Si on unit 2.
- c. If asked to locally check AFW flow to 12 SG, report flow from simulator on screen "SIMFWO8"
- d. If asked,12 MD AFW pump is nee (ed on unit 2 and is not available.
- e. If requested to evaluate aligning 480V buses 121 and 122 to unit 2, report that an engineering evaluation will be performed.
- 11. When the crew transitions from ECA-0.0 to ES-0.1, Then simulate the seal package failures on both RCPs (Relative order of 8).
- a. When directed, shut RCP seal injection throttle valves.
(Relative Orderof 9)
- b. When directed, shut RCP CC return valves, (Relative Orderof 10)
- 12. At the discretion of the chief examiner place the simulator in FREEZE.
l l 1 l l l l Page 6 of 16
i t
\
Title:
Cortdown; in:dy;rt:nt Borcti:n; Lces cf CC; Pie 4. m-
* .. J1 l L!ad Reduction; Leaking PRZR PORV; RCP Tri : Loss of All A.C.; SBLOCA T O. P.. h.T, ., '.iT27;*
- n. a E..... . ..H.au A%m._. .:. .....'*u..um.'._d.
Name: - Position: SM SS Lead RO Date:
"' as e Event Description 9 >-
KA Number e ' st KA Value# n Boration due to CVCS temperature failure Time S/U Position Expected Response l Figure C1-29; Tave Restrictions During Coastdown RO/ Lead . Reduce load to get in operating region of C1-29 RO . Control Delta I within band Lead /SS . Contact chemist RO . Take manual control of TCV-145 and increase CC flow to Letdown 1 HX i t Evaluator Note: m
@ tj%}f]ii[ y'
-' ,a
, , @ 'h [w4 i$ @ y ', r
~ - > >
..l,'
e s ,
*w
,, "[h, [s.M f dNNiyj[ j$h'%is l '
, .gf f p W4 4T6e Sant may not.;e'ntettheyell6Wlzons:oflcuse CF29llf theWeW;ishnickt6Msb6dd3Ta@s
, L,MTref deviation alarm lmay alert the crew to a problemi ~ G. gf'$
,4 m '
m ,3 ... c - r' y , m, , "J"'u +w fib & KOrf O ;psW % jy
'1 Comments: '
l l 1 I l l l 1 ! Page 7 of 16 2
Title:
Coa tdown;inrdv;rt:nt Bor; tion; Lom of CC; R. r ti o O . rf?,. .. ., . a Load Reduction; L cking PRZR PORV; RCP Trip Loss of All A.C.; SBLOCA i-f.;e JQ.. o e V r.: N' ^hg/.] .y.f; l l e e,, a Event Descriptionn , > W Eu , im KA'Numbera , o KA Value? Loss of Component Cooling Time S/U Position Expected Response C47020:0102; 12 CC Pump Lockout Lead . Start 11 CC pump. Lead . Notify electrical department SS . Refer to T.S.3.3.C for LCO. SS . Declare 1 hour LCO per T.S.3.0.C since 2 CC pumps are inoperable. C47015:0408; Letdown Flow Hi Temp RO . Verify letdown divert CV-31204 to VCT. RO . Verify letdown HX Outlet temp drops on 1T130 RO . When letdown temp is < 130*F, then place CV-31204 to Dernin
. Evaluator Note:,
,2 W ?"n ,,
4 i
, . . . ' " + i, ; S .
Comments: i l l l l l l l Page 8 of 16 t j
~
Title:
Coa tdown; inady;rtent Boration; Los3 of CC; . T'T W T ^
- 4,z.. -
Load Reduction; Leaking PRZR PORV; RCP r,. . - - ~ 4,T ' ~-Y w.. s M Trip; Loss of All A.C.; SBLOCA p. i.c.i.c 2]cr < j,n' o , m , iu ml Event Description @s e>> e W> w
- 9 KA' Number c , '
- KA Value ?.
Load Decrease Time S/U Position Expected Response C1.4
. Lead . Notify Nudear Engineering Lead . Notify Duty Chemist Lead /SS . Notify Power Marketer RO . Tum on all pressurizer heaters RO . Depress GO on turbine SS . Change ERCS TPM to NIS
, Evaluator Noter"
> ' imw> mW ww:, w o", *,w> '
mm r 2 ' > 1 ee Comments: Page 9 of 16
Title:
Coa:tdown; inadv2rt:nt Bor; tion; Lo22 of CC; Load Reduction; Leaking PRZR PORV; RCP Trip; LCc3 of All A.C.; S!LOCA
,', # 0 n e r w : Event Description-t M&c Qw e , Bio : ss KA Numberb n E KA Valueun PRZR PORV Leak-by Time S/U Position Expected Response C47012:0506 PORV Relief Line Hi Temp RO . Verify relief line temperature high and RCS Pressure low.
Lead . Isolate PORVs one at a time to determine leaking valve by obr.erving reliefline temperature j RO . Leave PCV-431C isolated (MV-32195 closed) l SS . Refer to T.S.3.1.A.2.c for LCO. SS . Verify PORV isolated within 1 hour (MV-32195 closed) tEvaluator.NoteNa ' * * . , W x: a w w ,f / ' " s w !M s n w 4
= /* w >:n , , ., s Comments:
)
l Page 10 of 16
1 i
Title:
C ctdown;in dv.::rt:nt Borction; Lrca of CC; r N i 9 i n 'i: m .L 1 l Load Reduction; Leaking PRZR PORV; RCP ^
~ . . . h,AE ....._&
W J', _, Tri : Lc23 of All A.C.; SBLOCA _. J, . ' ..Q,J. oo ' G+Ne x. Event Description s Av, ,& m m , ,m se,;KA Numbera u KA Valuem a RCP Trip / Reactor Trip Time S/U Position Expected Response E-0; Reactor Trip or Safety injection RO . Verify reactor tripped Lead . Verify turbine trip - both turbine Stop Valves Closed Lead . Verify safeguards buses 15 & 16 energized. RO . Check if Siis required
-SG Pressure >500 psig
-PRZR Pressure >1815 psig
-PRZR Level >5%
Subcooling >20'F
-Containment Pressure <4 psig SS . Transition to ES-0.1.
J Evaluator Note:: > "m < om'N '4+ 9% M e
- M+M&~ M + +% % M ww awip e W M +
Comments: l l 1 Page 11 of 16 a
F.
Title:
Coa:tdown; inadv:rt:nt Bor tion; Lo33 of CC; Lead Reducti*n; Leaking PRZR PORV; RCP Trip: Los3 of All A.C.; SBLOCA .. I i
. .%9,9,me.MEvent DescriptionWw+em
- em e sKA Number + - we KA Value w*
Loss of All AC Power 1 Time S/tJ Position Expected Response ECA-0.0; Loss of All Safeguards AC Power SS . Enter ECA-0.0; Loss of All Safeguards AC Power i RO . Verify RCS is isolated. RO . Start 11 TD AFW Pump and verify AFW flow > 200 gpm. (critical)' { l - Pump Seledor taken to Manual l - Pump Started
- Pump Seledor switch retumed to Auto to reinstate low discharge pressure trips.
i SS . Announce Rx trip, notify SEC, establish communications with NRC within 1 hour. i Lead . Check CL header pressures > 25 psig. ) Lead . Unable to energize bus 16 from unit 1 source and D2 l Lead . Start D1 and energize bus 15 (critical)* SS . Retum to procedure and step in effect Lead . ReMad 11 CC Pump Transition to E 4/ES-0.1 SS . Direct implementation of 1C20.5 AOP2. RO e Check if Siis actuated or required SS . Transition to ES-0.1
.'1EvaluatorNote:L fe o4ga P, N E g i: w%M4 3h e dks w -E , x.up4 ] # ]y. . _ g
+
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m.r.mw.M,in. m .h. W;E.s e.. m m m.m@h. b.1P REstathshthe"m ir loss'of a u gqqqwn?mnepurn wrequired"AFW,
< nmm a dma~"o?m4pmq)93 flow,; rate n to w om ~nwthemywwww SGs o_n wnwmm, a.. wg,ll AC before SG ;
I w ,. m. p . m m ,,
> p gr%w - ~ a n ;.,, .O .a, gm g S Et ua,.f "" ; na.n%j %(g . Dy1 N 4 y"n prx', %,u%a M s;3 w ., 9;; w '
i d, . 7We ;paJ , ! :;gg 4 , ,.,x
, 4 a m ..w
+ + v.-
'(20 !$cEnergize;st least,one;AC Emerge,ncypus so that on.1 tra ECA4.2'is:not required1uporG; W
' UCoinpleson'of m ECA4.0D mg%.: 3 V"WNE a v: wewOd %m NRM
;Wn%@WeiWWe M'WW'um p: 9,, -- a vm.%,rm%1 ~ ,
m r, at , s muss.t L b .; 1 Comments: l 1 l l 1 l \ l l l l l Page 12 of 16
.Y
Title:
Coastd:wn; inady;rtnt Bor; tion; Lecc of CC; M Qf-5 ] M;g' y Lead R: duction; Leaking PRZR PORV; RCP 4 IWei+ m: Trip; Lcca of All A.C.; SBLOCA ! W#@W EfE ' $ ] e ' L ' '; o ;: Event DescriptionW UM Jn i aKA Numbero a n 1KAValue: .. Loss of RCP seals and SBLOCA l Time S/U Position Expected Response C3 AOP2 Loss of Seal Cooling RO e Close MV-32166 Seal Water Retum isolation Valve E-0 (cont.) SS . Re-enter E-0 at Step 1, upon Sl. Crew . Confirm reactor and turbine trips Lead . Verify bus 15 energized and C20.5 AOP2 implemented. Lead . Verify component alignment. l
- Start 11 CC Pump
- Assign Attachment G for containment isolation to outplant SS . Announce Rx trip and SI, notify SEC. !
Lead . Close MV-32115. SS . Ensure communication with NRC is established within 1 hour. Lead . Open turbir'e HP drains. Lead . Direct outplant to stop the TB roof exhausters and isolate the MSR's per Att. J. Lead . Maintain >200 gpm total AFW flow and 900 psig discharge. SS . Implement Auto Action guide, Table EO-1. Lead . Place steam dump in
- Steam Pressure" mode.
Crew . Do NOT restore cooling to Thermal Barrier HX l Crew . Diagnose LOCA and transition to E-1. l l t Evalustor Noter +' . * ' m* "1 !' 'm " " N
- Comments. j i
Page 13 of 16
1 Titim C cctdown;in:dv:rtInt B r;ti:n; Leca cf CC; RI ^ A4s "^ { f Load Reductirn; Leaking PRZR PORV; RCP l Trip; Loss cf All A.C.; SBLOCA Q ) ks-i 1-
, , Twam - , a Event Descriptione m 4
.ti m 1 uw e KA Numbers s:N KA Valueim SBLOCA i i
Time S/U Position Expected Response E-1: Loss of Reactor or Secondary Coolant Lead . Maintain >200 gpm FW flow to SG until NR level > 105 Then maintain 10-50% NR level. Reset Si and Cl. ' Lead
- RO + Check if SI termination criteria are met.
i Lead /RO + Stop RHR pumps J
- Lead /SS
. Verifies Aux Bldg radiation is normal Lead . Aligns FCU radiation monitors: i
-Direct AB to open RD-4-8 and 2RD-4-2.
-Verifies SV-33384 and 33907 are open (rad monitor panel area) l SS . Transitions to ES-1.1.'
4
)
AEvalustorNote:n
, , ; ' , xtnen Acs:a MN * :, r,. 3 1 A q
', . ' 3G yg:iw % y ~, m > h hymqq;,!@irmn%g, th y ??w t o' o _.r e m u.;n#ggIjh"iaing p n , 7 tgp r g 34%,;.A 3pg;a.gggjq o'may,tdterminatedg;k
$dindhe scenar;i.. pme:
7:p ..g upon trans y up)g;,itio;;;ts gg Ai % g.gpg 3p%,195% 2 m p, GWik 2' i t M en ~ Wer ' ntt ifL
.ESM' W (E!W?:r;if ' 42!gigt
. t SmMensq t "' PiuMMOM Comments:
!l I
i 1 1 I i 1 l Page 14 of 16 j
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7 CHAMPS MRM KTF-D 2 i RETENTION: 7 DAYS DATE: l UNIT 1 LPEO / PEO TURNOVER 3 l TIME:N(1800-0600) SFGDS EQUIP OOS/LCO'8: 1 :D2 FOR JACKET COOLANT LEAK 2 :PT-449 FOR CALIBRATION 3 : RAD MONS 008: ANNUNC' 8: OOS: OUTSTANDING SP' 5: FIRE DET/ PROT EQUIP IMPAIRMENT: OTHER EQUIP OOS / STATUS: 1 : 2 : 3 : 4 : 5 : 6 : 7 : 8 : 9 10 : 11 : 12 : 13 : 14 : 15 : 16 : 17 : MAJOR EQUIPMENT REPAIRED /RETURNLff FO SERVICE: 1 : 2 : 3 : 4 : 5 : OPERATIONAL PLANS FOR COMING SHIFT: 1 : CONTINUE COASTDOWN OPS 2 : 3 : 4 : NEW PROCEDURES / INSTRUCTIONS: 1 : 2 : 3 : WATCHSTANDERS LPEO: LASH PEO: JONES LPEO RELIEVED BY: TIME: DATE: PEO RELIEVED BY: TIME: DATE: CB WALKDOWN --> LPEO: TIME:
--> PEO : _ TIME:
l 1 l l l l
.l'
.t.
INITIAL SUBMITTAL OF THE WRITTEN EXAMINATION FOR THE PRAIRIE ISLAND EXAMINATION THE WEEK OF MAY 17,1999 l- 1 i i i l I l l I l i i i l l l 1 1 l, ' .I .' \ s ! f 4 l ! l ( '. !
l 1999 PrairieIslandNRCExam RO Cognitive Level and Question Sources N hkihbk Application 11 hhNMlhMhh FacHy Exam Bank 34 13 I Compr9hension I 49 NRC Exam Bank 15 6 Memory 40 Previous Two 9 5 NRC Exams __ New 42 TOTALS 100 100 24 66% New or Signifcantly Modified l l f March 31,1999 (Submittal)
Q==* lam Topict l Overtime limits The following is the work schedule for a licensed Reactor Operator on day shift: 5/12 - 8 hours as Lead i 5/13 - 8 hours as RO and 2 hours holdover. l 5/14 - 8 hours as RO . 5/15 - 8 hours as Lead and 8 hours holdover as Lead 5/16 - 8 hours as RO 5/17 - scheduled 8 hours as RO 5/18 - scheduled 8 hours as Lead At the end of the shift on 5/16, the SS asks the individual if he could stay over 2 additional hours as RO. Which of the following describes the applicable guideline for continuing work? The individual...
. a. can continue work without any restrictions.
' b. will exceed the limit for working in a 24-hour period and must have the approval of the SS,
- c. will exceed the limit for working in a 48-hour period and must have the approval of the GSPO.
- d. will exceed the lirrit for working in a 7-day period by the end of the period.
Ams: - l c l Exam Level: lR I Connitive Level: I Comtwehension l Explanation The limits are 16 in a 24-hour period; 24 hours in a 48-hour penod and 84 hours in a 7 day period. The operator of Amewer'- would exceed the 24 hour in 48-hour period limit since on 5/15 and 5/16 the operator reaches the 24 hours worked level. To exceed sny OT limits, the authonzation of PM or designee (including SM and NGS) is required. In any 24 hour period the maximum time worked is 16 hours. In the 7 day period total time based only on remaining scheduled work is 66 hours. Tier: l Generic Knowledge and Abilities l RO Gmup: l1 l SRO Gesup: l1 l System / Evolution Number: - GENERI System / Evolution
Title:
[ C ,_ Casesory: l2.1 l Conduct of Operations KA: i2.1.1 l Knowledge of conduct of operations requirements. I'*3 Value: l 3.7 - l SRO Value: l3.8 l CFR: I 41.10 /45.13 Reference. Reference Number. Reference Section Page Numbeds) Revision learn. Ob] Plant Operatson 5AWI 3.15.0 6.2.10,6.4.2 6-7 4 Plant Operatson P91501A14 II.C.4 11-12 2 1.a Questlos Source . New Question Modification Method Question Source Comments: l Material Required for Examination: _. i Page1 .\
Question Tople: l Turnoverlos resiew
- For the current week, a NRC-licensed operator is assigned to administrative duties NOT associated with the l on-duty shift. On Tuesday day shift, the operator was required to fill the position of Unit 1 RO for 6 hours of the shift due to illness of the assigned RO. The following week on Thursday evening, the operator assumed the position of Unit 1 Lead at turnover.
What is the requirement for this operator in reviewing the Unit 1 Reactor Log? The operator must review the Unit 1 Reactor Log...
- a. since Sunday of the current week.
- b. for the past 7 days.
- c. since Tuesday of the previous week.
- d. for the past 15 days.
Ans: Ic l Exam level: lR I Connitive Level: l Comprehension l Explanation As soon as possible after assuming the duty, the operator will review handwritten logs for changes that have ofAnswer taken place since last assigned to the watch station, up to 15 days. The Lead and RO are required to review the appropriate Unit Reactor Log. Since the Log was last reviewed on Tuesday of the presious week, it will need to be reviewed sina that time. The other times are typical requirements for resiew of associated material, including the maximum expected penod for review of the Logs. Tier: l Genenc Knowledge and Abilities l RO Group: l1 l SRO Group: l1 System / Evolution Number: GENERI System / Evolution
Title:
C Catemory: l2.1 l Conduct of Operations KA: l2.1.3 l Knowledge of shift turnover practices. ILT Value: l3.0 l SRO Value: l3.4 l CFR: l 41.10 / 45.13 Refenwace Reference Number Reference Section Page Number (s) Revision learn. l Obj i Shift Orgamzauon, SWI O-2 6.3.4 11 40 Operauon & Turnover l- Records andlAss P91501A12 II.A.3.a 9 2 2 l Question Souste NRC Exam Bank Question Modification Significantly Modified !- Method Question sourte Comments: l Material Required for Emannisation: i l l 1 Page 2
Questlos Tople-t l Power limits Which of the following describes the requirements concerning operation at the maximum allowable steady-Mate full-power level as defined by the Unit Operating License?
- a. Power may exceed 100% for a short duration but at NO time will exceed 102%. The average power for an eight hour shift is to be 100% or less.
- b. Average power may exceed 100% for an eight hour shift, but at NO time will exceed 102%.
- c. Power exceeding 100% requires a power reduction only if projected average power for the eight hour shift exceeds 100%.
- d. Average power for an eight hour shift is to be 102% power or less. If power exceeds 102%, then power must be reduced to 100% orless.
Ans: Ia l Exam 14 vel: lR I Coanitive Isvel: l Memory l Explanation As given by procedure direction. B. is the best &=8=* but
, the word " average" makes it incorrect ofAnswer Tier: l Generic Knowledge and Abilities l RO Group: l1 l SRO Group: l1 System / Evolution Number: GENERI System / Evolution
Title:
C Catenory: l2.1 l Conduct of Operations KA: l 2.1.10 l Knowledge of conditions and limitations in the facility license. R1Value: l2.7 l SRO Value: l3.9 l CFR: l 43.1/ 45.13
.eference Reference Number Reference Section Page Numbeds) Revision 14arn.
Ob] UNIT 1 POWER ICl.4 4.11 4 14 OPERATION 4 Cl.4/C1.6 Review P8197L 007 II.D 8 5 2 Work Rules and SWI O 1 6.7.2 7,8 ! Philosophy... Question Souste Facility Exam Bank Question Modification Method Ouestion Source Comments: 1 Material Required for Examination: Page3
1 l ! Question Topict l Communications Which of the following describes the correct usage of repeat back when directing an APEO in the field to wfonn valve manipulations? The APEO should... j
~
- a. Jprovide verbatim repeat back of orders.
- b. repeat back paraphrasing the orders to ensure the message was understood.
- c. repeat back only that portion of the orders that are NOT completely understood. )
- d. repeat back the orders only if the directions were provided over the phone or Plant Page system.
Ams: Ib l Exam Level: lR I Comaltivelevel: l Memory l Esplanation 'Ihe receiver SHALL ar*nawledge receipt by a paraphrased repeat bedc. Verbatim repetition is NOT desired ofAnswer sine:c this may not in<licare understanding of directions. The repeat back is desired in all forms of verbal communication including face-t> face communication. The entire nwenare or direction should be repeated. Tiert l Generic Knowledge and Abilitics l RO Gresp: l1 l SRO Gesup: l1 Systesa/Evolutlos Number: GENERI System / Evolution
Title:
C Catenary: l2.1 l Conduct of Operations KA: l 2.1.17 l Ability to make accurate, clear and concise verbal reports. FO Value: l3.5 -l SRO Value: l3.6 I CFR: l 45.12 / 45.13
.eference Refertace Number Reference Section Page Number (s) Revision Imara.
Obj Operauon Section 5AW13.15.6 6.14.c 1 0 Coaununications Communications P91501All8 V.B.2.c 12 1 1,4 Q==tlam Soorte Facility Exam Bank Q=atta= Modifientia= Method Ouestion Soorte Comments: 1 Material Regulard for ; Examination: l I Page 4
c. Ommelam Topict l Method for Independent Verification Safety tagging is being performed for MV-32086, Emergency Boration to Charging Pump Suction valve, to j msure the valve remains closed for isolation purposes. 1 f What is the normal preferred method for performing Independent Verification for this valve?
- a. Check the position indication lights prior to the MCC power being removed.
- b. Locally manually operate the valve hendwheelin the closed direction.
- c. Loully check valve stem position.
- d. Check for NO system flow after starting a Boric Acid Transfer Pump.
Ans: Ia l Exam IAvel: lR _ l Commitive Level: 1 Memory l Expla==*iam Motor Q= ='d Valve position is normally verified using remote light indication. Other means of position ofAnswer verificanian such as observing local indications or stem position is allowed. However globe valve position is the most difficult to determine and some do NOT have local position indication. ' Functional testing such as a check for flow is more appropriate for venfying return to normal IV. Most MOVs are NOT manually operated closed due to potential for damage when opening, and seguire specific direction and permission for manual operation.
'Iler: l Genene Knowledae and Abilities l RO Group: l1 l SRO Group: l1 Systent/Evolutlos Number: GENERI System / Evolution
Title:
C Catenory: i2.1 l Conduct ofOperations KA: l 2.1.29 l Knowledge of how to conduct and verify valve lineups.
# Value: l3.4 l SRO Value: l3.3 l CFR: l 41.10 / 45.1/ 45.12 Itaference Reference Numiber Reference Section Page Numbeds) Revision learn.
Ob] Control And Q= =*iaa Of 5AWI 3.10.0 6.10.14.d.1 30-32 8 Plant Es4M j Methods Of Performing 5AWI 3.10.1 6.3.1 7 7 Ir '- -- - '-- : Verification Control / Operation of Plant P9150L 024 V.F.1 24 4 Equip Questba Sourte New Questka Modification Method Questlos Source Conaments: I Matedal Required for Examlastlos: Page 5 j [,
1 1 1 Ouestlos Topic: I Surveillaace forTech Specs i Which of the following sets of data from SP 1001 or SP 2001; Unit Daily Logs, v*ould require action per Tech. Spec ~ Limiting Conditions for Operation?
- a. 121 UNIT 1 DSL GEN STG TNK- 12200 GAL 122 UNIT 1 DSL GEN STG TNK - 13700 GAL i
.123 UNIT 1 DSL GEN STG TNK - 13800 GAL
-124 UNf:~ l DSL GEN STG TNK - 12475 GAL' l l
- b. 121 CL PMP OIL STG TK- 10650 GAL !
122 CL PMP OIL STG TK - 10700 GAL All 4 Unit I diesel generator storage tanks total- 52000 GAL
- c. 21 D5 FUEL OIL STG TANK - 25100 GAL 23 D5 FUEL OIL STG TANK- 24900 GAL l 22 D6 FUEL OIL STG TANK - 26100 GAL .
24 D6 FUEL OIL STG TANK - 21000 GAL with a sample resu!ts making the tara: out-of-service.
- d. ~ 21 D5 FUEL OIL STG TANK- 17450 GAL 23 D5 FUEL OIL STG TANK- 17100 GAL !
'22 D6 FUEL OIL STG TANK- 16650 GAL
- 24 D6 FUEL OIL STG TA'E - 21000 GAL Ans: Id l Exam level: lR ! Connitivelevel: l Comprehension l
' ppImation The operability requirements are Unit 1 - 70000 total available gal. AND 51000 for the Dl/D2 DGs and 19000 ofAnswer for the CL pump; Unit 2 75000 available gals for D5/D6 DGs. Distractor with one tank OOS, still has requirM 75,000 gallons, Tier: l Generic Knowledge and Abilities l RO Group: l1 l SRO Grtep: l1 System / Evolution Number: GENERI System / Evolution
Title:
C Category: l2.2 l Equipment Control - KA: l 2.2.12 l Knowledge of surveillance promdures-RO Value: l 3.0 - l SRO Value: l3.4 l CFR: l 41.10 / 45.13 Reference Reference Number Reference Section Page Numberts) Revision I4 ara. Ob] Auxiliary Electrical Systems Tecimical 3.7.A.5 110 Specifications SurveiDance Prc, gram P9150L-016 - IV.D.4 11-12 1 3 Questson Soun:e New Question Modification Method E Question Source Cosaments: l Matedal Required for Examelastion:
- 6 1
l
f I i Question Topict l Thermal Overload . 1 1 The RO has been directed to initiate an Emergency Boration in response to an ATWS condition. When the
' witch for MV-32086, Emergency Boration to Charging Pump Suction valve, vas taken to OPEN, dual .ndication was received and then both position indicating lights went out. An APEO dispatched to the MCC for the valve reports NO unusual conditions except it appears the thermal overload device on the breaker is tripped. ;
What direction should be provided to the APEO concerning the Thermal Overload? The APEO should...
- a. complete a Work Order for troubleshooting the Thermal Overload device.
- b. obtain Electrical Department assistance before attempting to reset the Thermal Overload device,
- c. initiate Safety Tagging to complete the Out-of-Service for the valve.
- d. depress the Thermal Overload RESET pushbutton ONE time to allow valve operation.
Ans: Id l Eram Level: lR l Cognitive Level: l Comprehension l Explanation If the a Thermal Overload protection has operated and a RESET pushbutton is provided external to the MCC, in ofAnswer the event that operation of the equipment is critical, the device may be reset one time by qualified personnel. In this case when Emergency boration is required, it is considered critical that the Emergency Boration valve be operated. Normally a Work Order should be initiated AND the electrical department contacted for any trip of a thermal overload device and subsequent reset. Safety Tagging is NOT warranted in this situation for resetting Thermal Overload dedce.
,ler: l Generic Knowledge and Abilities l RO Group: l1 l SRO Group: I1 System / Evolution Number: GENERI System / Evolution
Title:
C Category: l2.2 l Equipment Control KA: l 2.2.24 l Ability to analyze the affect of maintenance activities on LCO status. R13 Value: l2.6 l SRO Value: l3.8 l CFR: l 43.2 / 45.13 Reference Reference Number Reference Section Page Number (s) Revision Learn. Ob] CONTROL AND 5 AWI 3.10.0 6.9.5.c 19 8 OPERATION OF PLANT EQUIPhETT Control / Operation of Plant P9150L-024 II.E.3.d.2) 12-13 0 1 Equipment Question Source New Question Modification Method Question Source Comments: l Matedal Required for Examination: Page 7
Ouestlos Toole: I RO Fuel Handling r-eihility l L Which of the following is NOT a rerponsibility of the Fuel Handling Operator in the Control Room during l movement of fuel?
- a. Maintain the 1/M Plot during fuel loading in the core following total off-load.
I b. Sign off the Fuel Transfer Log following relocation for each fuel assembly.
- c. Provide concurrence for lowering the manipulator crane onto any fuel assembly.
- d. Monitoring RCS temperatures every 15 minutes if RHR is stopped.
Amst Id l Exam level: lR l Connitive level: l Memory l Explanation ' lie RCS :- - ;+ =- s is logged and plotted HOURLY egantless of RHR condition. The Control Room operator ofAnswer will inspect the source range count rate and recorders AND gives approval prior to unlatching from an assembly added to the core. The operator will then calculate AND plot the new data for the 1/M plot. 'Ibe Control Room operator is responsible for updatmg aM sign off of the Control Room Fuel Transfer Iag following each fuel movement. The Control Room Operator SHALL concur with the movement before the manipulator crane is lowered onto any fuel adly (along with other movements). Tier: l Generic Knowledge and Abilities l RO Group: I1 l SRO Group: 11 System / Evolution Number: GENERI System / Evolution
Title:
C Catenary: 12.2 l Fe@~ Control KA: 2.2.30 Knowledge of RO duties in the control room dunng fuel handling such as alarms imm fuel handhng area, communication with fuel storage facility, s>Wems operated from the control room in support of fueling operations. and supporting instrumentation. RO Value: l3.5 l SRO Value: l3.3 l CFR: l 45.12 Reference Refertece Number Reference Section Page Number (s) Revision Laara. , Ob] REACTOR REFUELING D5.2 6.26, 7.1.5 & 6 12-13 23 OPERATIONS DUTIES AND SW1O-41 6.1.6 3 5 RESPONSIBILITIES OF FUEL HANDLING PERSONNEL 4 Plant & ShiA Orennwatian P91501A04 III.d & e Il-12 3 W Source New Question Modification Method Questice Source Comments: l ,,,
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Material Required for Examination: p Page 8
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