ML12342A288

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2012 Palisades Nuclear Plant Initial License Examination Administrative Files
ML12342A288
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/01/2012
From: Walton R
NRC/RGN-III/DRS/OLB
To:
Nuclear Management Co
Shared Package
ML11354A190 List:
References
ES-401, ES-403-1
Download: ML12342A288 (29)
v • d • e


Text

{{#Wiki_filter:2012 PALISADES NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE FILES

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Palisades Date of Exam: October 12th, 2012 Exam Level: RO I2?J SRO I2?J Initials Item Description abc

1.

Clean answer sheets copied before grading

2.

Answer key changes and question deletions justified and documented

3.

Applicants' scores checked for addition errors {reviewers spot check >25% of examinations}

4.

Grading for all borderline cases (80% +/- 2% overall and 70 or 80, as applicable,.:!: 4% on the SRO-only) reviewed in detail

5.

All other failing examinations checked to ensure that grades are justified

6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Date

a. Author 10/15/2012
b. Facility Reviewer(*)

10/15/2012

c. NRC Chief Examiner(*}

H{&[20\\1,

d. NRC Supervisor(*)

'{Lp;. (*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Page 5 of 5

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Pa\\v;c(de5 5{-(i~o~ Date of Examination: Oc~.. -zo~Z-Developed by: Written - Facility ~ NRC 0 /I Operating - Facility ~ NRCD Target Chief Date'" Task Description (Reference) Examiners Initials -180

1.

Examination administration date confirmed (C.1.a; C.2.aand b) jlJ1tJ -120

2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

.[4&) -120

3.

Facility contact briefed on security and other requirements (C.2.c) fo¥cJ -120

4.

Corporate notification letter sent (C.2.d) M) [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] X {-75}

6.

Integrated examination outIine(s) due, including Forms ES-201-2, ES-201-3, !~~W ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d) 1\\~\\,1 {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)} ~~~ {-45}

8.

Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable). supporting documentation (including Forms ~\\J ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6. and any Form ES-201-3 updates), and reference materials due (C.1.e, f. g and h; C.3.d)

9.

Preliminary license applications (NRC Form 398's) due (C.1.I; C.2.g; -30 f(VtW ES-202) -14

10. Final license applications due and Form ES-201-4 prepared (C.l.I; C.2.!;

ES-202) 0lw -14

11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

~\\lW -14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

R~W -7

13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

R'AW -7

14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent r:PJ (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed Q\\\\.\\.J with facility licensee (C.3.k)

-7

16. Approved scenarios. job performance measures, and questions

~W distributed to NRC examiners (C.3.i)

  • Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by case basis in coordination with the facility licensee.

[Applies only) {Does not apply} to examinations prepared by the NRC. ES-201, Page 25 of 28

ES-501 Post-Examination Check Sheet Form ES*501*1 Post*Examination Check Sheet Facility: pQ1\\<5~AeS Date of Examination: Ot>ro~ 2-0\\2 Task Description Date Complete

1.

Facility written exam comments or graded exams received and verified complete to/ \\6" rzo\\ 7

2.

Facility written exam comments reviewed and incorporated and NRC grading completed, if necessary 't 1712-0\\2.

3.

Operating tests graded by NRC examiners 'D }2-{., Ib Dt2

4.

NRC chief examiner review of operating test and written exam grading completed \\\\ 1"1IZ011

5.

Responsible supervisor review completed III!s-J ;A)I'L

6.

Management (licensing official) review completed \\\\ / )S- ) 2£:1:2.

7.

License and denial letters mailed \\,!lb)70\\1

8.

Facility notified of results \\1 ) I <) ) 20\\1

9.

Examination report issued (refer to NRC MC 0612)

10.

Reference material returned after final resolution of any appeals ~14 ES-501, Page 23 of 25

ES-201 reement Form ES*201*3

1.

Pre-Examination rJ tJc.:f: I J.f.ad C:;c.f. K.fe., ZOrz-I I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of..JURe 25th -.11 !Iv 6th, ~g11 tf as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until comp/etion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination tJCrf. / ~f.",I'I) t)c-t 8{ 2.o'L To the best of my knowledge, I did not divulge ~ny unauthorized persons any information concerning the NRC licensing examinations administered during the week( s) of JUlie 25th dulv 6th, 2011. rom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE I RESPONSIBILITY

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V<=?1 c-L oJP~ ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 10/1/12 and 10/8/12 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations andlor an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 10/1/12 and 10/8/12. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE 1RESPONSIBILITY

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I '? CL\\\\s ~"<.S N\\lcmu. P\\~ ES-201 Examination Security Agreement Form ES-201-3

1.

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

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE ~:~c~~~~~ r; ~~~~ ~~~~ ~--tt= ~~ '~if~I~;

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NOTES: ES-201! Page 27 of 28

Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway ~Entergy Covert, MI 49043 Otto W. Gustafson Licensing Manager PNP 2012-095 October 22,2012 NUREG 1021 Regional Administrator U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 ATTN: Janet Kweiser

Subject:

Initial License Examination Comments Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Dear Sir:

In accordance with NUREG 1021, ES-402, Entergy Nuclear Operations is submitting comments on the initial license examination administered at the Palisades Nuclear Plant during October 2012. Attachment 1 contains the required i,nformation. Please contact Jeff Iliff at (269) 764-2974 if you have any questions regarding this submittal. This letter contains no new commitments and no revisions to existing commitments. : Palisades Initial License Examination Comments CC R. Keith Walton, Region III, USNRC Project Manager, Palisades, USNRC (w/o attachment) Resident Inspector, Palisades, USNRC (w/o attachment) Document Control Desk, USNRC (w/o attachment) OCT 242012

ATTACHMENT 1 PALISADES INITIAL LICENSE EXAMINATION COMMENTS 8 Pages Follow

Attachment #1 Comments on Palisades 2012 NRC Written Examination There were three comments regarding the 2012 NRC Written Exam. The comments are for Questions 4,14 and 33 and are from Tim Ishmael (Docket 055-32866): Comment #1: Question #4 is not valid. There is not enough information in the stem to correctly answer the question. The student needs to know the value of Primary Coolant System temperature and they must have a copy of EOP Supplement 1, "Pressure Temperature Limit Curves," to determine the correct criteria for securing the last two PCPs. Question: Which one of the following correctly completes the statement below? Per EOP-4.0, "Loss of Coolant Accident Recovery," the indication that the Control Room team uses to determine when to trip the last two Primary Coolant Pumps (PCPs) is (1) and the reason for tripping all PCPs under these conditions is to (2)

a. (1) Primary Coolant System (PCS) subcooling less than 25°F (2) prevent damaging a PCP
b. (1) PCS subcooling less than 25°F (2) minimize PCS inventory loss
c. (1) Pressurizer (PZR) pressure less than minimum for PCP operation (2) prevent damaging a PCP
d. (1) PZR pressure less than minimum for PCP operation (2) minimize PCS inventory loss Correct Answer: 'B' Facility Position: The facility agrees with Mr. Ishmael that question #4 is not valid and has no correct answer because there is not enough information in the stem for the applicant to correctly answer the question. EOP-4.0, "Loss of Coolant Accident Recovery," steps 6 and 8 require Primary Coolant Pumps (PCPs) be monitored and secured during a LOCA if any of the following three conditions are met: (1) Pressurizer Pressure lowers to less than 1300 psia (first two PCPs only) (2) PCS subcooling lowers to less than 25°F and (3) PCP operating limits are not met per EOP Supplement 1, "Pressure and Temperature Limit Curves." With PCS temperature above 500°F, the 25°F subcooling criteria applies. If PCS temperature is less than 500°F, the minimum pressure for PCP operation criteria applies. Furthermore, even if PCS temperature was supplied in the stem, the student would need the curve supplied from EOP Supplement 1 as a reference to determine the correct criteria to apply because knowing the point at which minimum pressure for pump operation becomes more limiting (500°F) is not required knowledge. Based on these issues, the Facility recommends that Question #4 be removed from the exam.

References:

EOP-4.0 steps 6 and 8 EOP Supplement 1

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP-4.0 Revision 21 Page 9 of 113 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS NOTE: P-50A and P-50B shall not be operated simultaneously when Te is less than 300°F. 1£ PZR pressure lowers to less than 1300 psia AND SIAS is initiated, THEN PERFORM BOTH of the following:

a. ENSURE one PCP is stopped in each loop.
b. LE PCS is less than 25°F subcooled, THEN ENSURE ALL PCPs stopped.
7.

WHEN PCS temperature lowers, THEN ENSURE PCPs configured as follows: PCSTe MAXIMUM OPERATING PCPs 3 2 CONTINGENCY ACTIONS 1£ PCPs are operating, THEN VERIFY PCP operating limits are satisfied. Refer to EOP Supplement 1. 8.1. STOP PCPs which do NOT satisfy PCP operating limits. © =Continuously applicable step ~= Hold Point

Pressure and Temperature Limit Curves 2500 U 200 of SubcooliDg Curve

(Use lowest operable temperature)

-I 2250

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Attachment #1 Comments on Palisades 2012 NRC Written Examination Comment #2: Question #14 is not valid. There is no correct answer because there is information in the stem that conflicts with all correct answers. If Preferred AC Bus, Y 40, is de-energized it is not possible for EK-1342 to be alarming. Question: Given the following with the Plant at full power: A manual Reactor trip occurs in response to a Steam Line Break inside Containment During the transient, Y 40, Preferred AC Bus, de-energizes Pressurizer pressure is 1725 psia and lowering slowly Containment pressure is 4.2 psig and rising The following alarms annunciate: o EK-1126, CIS INITIATED o EK-1342, SAFETY INJ INITIATED Which one of the following describes the action(s) required, if any, based on the above conditions for the Right Channel of Containment Spray and Safety Injection?

a. Containment Spray and Safety Injection must be manually initiated.
b. Containment Spray must be manually initiated only.
c. Safety Injection must be manually initiated only.
d. No actions required; Containment Spray and Safety Injection will automatically initiate.

Answer: 'A' Facility Position: The Facility agrees with Mr. Ishmael that there is no correct answer because of conflicting information given in the stem of the question. EK-1342, "SAFETY INJ INITIATED" alarm and a loss of Y 40, Preferred AC Bus, cannot exist at the same time. EK-,1342 actuates when both trains of Safety Injection actuate via SIS Relays SIS-1 and SIS-6 (see PID E-17 sheets 3 and 4). If Y40 is de-energized, then SIS-6 relay will not actuate because relay 5P-8 does not have power. If SIS-6 relay does not actuate, EK-1342 will not alarm because both trains must receive an actuation signal. If the applicant sees that EK-1342 is alarming in the stem he or she would believe that the Safety Injection Equipment actuated and 'B' would be the correct answer. Therefore, the presence of EK-1342 in the stem makes this question operationally invalid and no answers are correct. The Facility proposes that Question #14 be removed from the exam.

References:

ARP-7, window 42 E-Prints E-17, sheets 3 and 4

PALISADES NUCLEAR PLANT Proc No ARP-8 ALARM AND RESPONSE PROCEDURE Revision 71 Page 42 of79 TITLE: SAFEGUARDS SAFETY INJECTION AND ISOLATION SCHEME -13 (EC-13) 37 43 49 55 61 67 73 38 44 50 56 62 68 74 39 45 51 57 63 69 75 40 46 52 58 64 70 76 41 47 53 59 65 71 77 l3Jl 48 54 60 66 72 78 Sensor: Trip Setpoints: Coincident closure of contacts Alternate None Indication: OPERATOR ACTION: IF valid SIAS, THEN: o TRIP Reactor. o REFER TO EOP-I.O. FOLLOW UP ACTION: RESET SIAS per SOP-3, Attachment 4,"SIAS Reset Criteria and Repositioning SIAS Equipment." POSITION equipment per SOP-3, Attachment 4, "SIAS Reset Criteria and Repositioning SIAS Equipment."

REFERENCES:

EOP-l.O, "Standard Post-Trip Actions" SOP-3, "Safety Injection and Shutdown Cooling System"

Attachment #1 Comments on Palisades 2012 NRC Written Examination Comment #3: Question #33 has two correct answers. Choices 'A' and 'B' are both correct because the Quench Tank makeup supply can be lined up from P-79A1B, Primary System Makeup Transfer Pumps, per pro~edure RWSO-1, Transfer of Water from Primary Makeup Storage Tank (T-81) for T-90 Loads." Question: Which one of the following correctly completes the statement below describing the minimum required level and source of makeup water for T-73, Quench Tank? The Quench Tank is maintained at a minimum water level of (1) by adding makeup water using (2)

a. (1) 70%

(2) P-90A or P-90B, Primary Makeup Tank Pumps

b. (1) 70%

(2) P-79A or P-79B, Primary System Makeup Transfer Pumps

c. (1) 40%

(2) P*90A or P-90B

d. (1) 40%

(2) P-79A or P-79B Correct Answer: 'A' Facility Position: The facility agrees with Mr. Ishmael that question #33 has two correct answers ('A' and 'B'). The Quench Tank is normally supplied makeup water from P-90AlB, Primary Makeup Tank Pumps, but is capable of being supplied by P-79A1B, Primary System Makeup Transfer Pumps, per procedure RWSO-1, "Transfer of Water from Primary Makeup Storage Tank (T-81) for T-90 Loads." This procedure has been performed recently (August 2011) while the P-90AlB pumps were out of service. Both P-90A and P-90B have been cautioned tagged "OFF" since June of 2010 due to a leaking boric acid flow path to the SIRW Tank (WO# 228532). The pumps were left off until required to be used for makeup. Also, P-90A was out of service from May 2012 until September 2012 due to a failed seal. Based on the combination of the problems the Plant has experienced with P-90AlB and the fact that P-79A1B is capable of, and routinely is, used to supply P-90AlB loads, it is easy to understand why 3 of 11 applicants selected 'B' as the correct answer. The Facility proposes that both 'A' and 'B' be considered correct for Question #33.

References:

RWSO-1 W0228532 P&ID for Makeup Water System

Date: 10/19/2012 Time: 02:06:09 PM 8 ~ 6 S 4 ] H m " " '-'C' m "" " "'" d 119 0.; r ~ ',et ~ ~ ~-e:!ER ens;.,a-!'" te:f'i~I!R!iEP PSC-S5 P'tl. eafss"Rllea ref-55 til! ~~~ .l&LllllL c ~Cf1' ~.) ~~i 1..(" r:i~ I -L..,---' E E j j if '~~:'ro ~,.;. ~UO~~"'i"io SJ o D 1-

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Procedure No RWSO-1 Revision 7 Effective Date 8/30/07 PALISADES NUCLEAR PLANT SPECIAL OPERA riNG PROCEDURE TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T -90 LOADS Approved: RLTucker I 8/30/07

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Procedure Sponsor Date New Procedure/R~vision Summary: Revision 7 Specific Changes Deleted the section and steps pertaining to transfer of T-81 to T-90. This process is contained in SOP-26 and spool piece RSP-DMW5200 is permanently installed. (PCR00868565) Changed the title of the procedure to remove the part concerning the transfer of T-81 to T-90.

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page i TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T -81) FOR T -90 LOADS Table of Contents 1.0 PURPOSE......................................................................................................................1

2.0 REFERENCES

...................................................... :........................................................ 1 2.1 SOURCE DOCUMENTS................................................................................1 2.2 REFERENCE DOCUMENTS.........................................................................1 3.0 PREREQUISITES..........................................................................................................1 3.1 GENERAL......................................................................................................1 3.2 SPECIAL NOTIFICATIONS...........................................................................1 4.0 PRECAUTIONS AND LIMITATIONS.............................................................................2 4.1 GENERAL......................................................................................................2 5.0 PROCEDURE.................................................................................................................2 5.1 PREREQUiSiTE.............................................................................................2 5.2 INITIAL VALVE ALIGNMENT........................................................................3 5.3 WATER TRANSFER FROM T -81 TO T -90 LOADS...................................... 5 5.4 RESTORATION.............................................................................................7 6.0 ACCEPTANCE CRITERIA.............................................................................................8 6.1 GENERAL......................................................................................................8 7.0 ATTACHMENTS AND RECORDS.................................................................................8 7.1 ATTACHMENTS............................................................................................8 7.2 RECORDS.....................................................................................................8 8.0 SPECIAL REVIEWS......................................................................................................8

PALISADES NUCLEAR PLANT Proc No RWSO*1 SPECIAL OPERATING PROCEDURE Revision 7 Page 1 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T*S1) FOR T -90 LOADS CONTINUOUS USE Procedure SHALL be at the work location. Read each step prior to performing. I-Mark off steps as they are completed. 1.0 PURPOSE 1.1 To provide instructions to transfer water from Primary Makeup Storage Tank (T-81) to Primary Makeup Storage Tank (T-90) loads when T-90 is not available.

2.0 REFERENCES

2.1 SOURCE DOCUMENTS 2.1.1 Letter Nuclear Licensing to NRC dated 07/08/80, response to IE Bulletin 80-10 2.1.2 Technical Specifications LCO 3.7.6 2.2 REFERENCE DOCUMENTS 2.2.1 NMC Fleet Procedure FP-E-MOD-03, "Temporary Modifications" 2.2.2 NMC Fleet Procedure FP-G-DOC-04, "Procedure Processing" 2.2.3 NMC Fleet Procedure FP-IH-CS-01, "Confined Space Entry" 2.2.4 System Operating Procedure SOP-2A, "Chemical and Volume Control System" 3.0 PREREQUISITES 3.1 GENERAL 3.1.1 T-81 sampled for acceptability prior to transfer to T-90 loads. 3.2 SPECIAL NOTIFICATIONS 3.2.1 Notify Mechanical Maintenance that support will be needed to install a blank plate (stainless steel, minimum 3/16" thickness) in place of RO-5201A. Work Order Number: I Operations Scheduler Date

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page 2 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T*81) FOR T *90 LOADS 4.0 PRECAUTIONS AND LIMITATIONS 4.1 GENERAL 4.1.1 MV-DMW705 and MV-DMW706, T-90 valves are located in T-90, Primary Makeup Storage Tank valve pit. The valve pit is a confined space. REFER TO FP-IH-CS-01, "Confined Space Entry." 4.1.2 The level in Tank T -81 is required to be maintained greater than 83% when in Mode 1, 2, 3, or 4 when a steam generator is relied upon for heat removal. (LCO 3.7.6) 4.1.3 When Tank T-81 is supplying T-90 Loads, the steps in SOP-2A, "Chemical and Volume Control System," requiring Pump 90 AlB operation (eg, PCS Dilutions and Blends) may be N/A'd. 5.0 PROCEDURE CONTINUOUS USE Procedure SHALL be at the work location. Read each step prior to performing. Mark off steps as they are completed. NOTE: Blank plate in place of RO-5201 A is installed at the end of Section 5.2. 5.1 PREREQUISITE 5.1.1 Ensure Work Order available for installation of a blank plate in place of RO-5201A SRO I Date I Time Work Order Number:

PALISADES NUCLEAR PLANT Proc No RWSO*1 SPECIAL OPERATING PROCEDURE Revision 7 Page 3 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T -81) FOR T-90 LOADS 5.2 INITIAL VALVE ALIGNMENT 5.2.1 ENSURE CLOSED spool piece RSP-DMW5200, PMU T-81 to T-90 transfer, isolation valves: MV-DMW712 MV-DMW713 5.2.2 ENSURE spool piece RSP-DrvJW5200 is installed. 5.2.3 ENSURE at least one Primary System Makeup Water filter aligned for operation by checking OPEN the inlet and outlet valves for the filter: __-.**~o

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'VALVE F'". F=-51 A .Vi,:.'. ;.. ' F",..5113 Inlet MV-PMU110 MV-PMU111 Outlet MV-PMU112 MV-PMU113 5.2.4 ENSURE P-79A and/or P-79B, Primary Makeup Transfer Pump in service. 5.2.5 ENSURE CLOSED MV-PMU114, E-26 Bypass. 5.2.6 STOP BOTH P-90A AND P-90B Primary Makeup Transfer Pumps. 5.2.7 OPEN the following breakers: 52-7937 P-90A 52-8037 P-90B 5.2.8 HANG a CAUTION TAG on the following breakers stating "Breakers Open Per RWSO-1": 52-7937 P-90A 52-8037 P-90B 5.2.9 ENSURE CLOSED MV-EHS11 0 to isolate steam supply to E-65. 5.2.10 ENSURE CLOSED the following valves: MV-DMW714 E-65 Outlet MV-DMW715 E-65 Inlet MV-DMW716 E-65 Bypass 5.2.11 ENSURE CLOSED MV-DMW146, Demin Water To T-88 Demileralizer. (Located at Spent Fuel Pool, North End)

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page 4 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T -90 LOADS 5.2.12 UNLOCK AND CLOSE MV-DMW705, T-90 valve. (Located in T-90 valve pit.) PenormedBy: ___________________________,__~--- Auxiliary Operator Verified By: ______________________,__-=-_ Auxiliary Operator 5.2.13 INSTALL a blank plate in place of RO-5201A as follows:

a.

OBTAIN SRO authorization to install a blank plate in place of RO-5201A., SRO Date

b.

INSTALL a blank plate in place of RO-5201A. Performed By: 1 -M~e-c~ha-n~i-ca~I~M~a~i-n-te-n-a-n-ce---------~D~a~t--e Verified By: ~~-:-:-~:::--__.,---_________,_______ Auxiliary Operator Date

c.

PLACE a Caution Tag on blank plate stating: "Blank plate installed in place of RO-5201A in accordance with RWSO-1." (component identification, RO-5201A may be used on caution tag)

d.

NOTIFY the SRO that the blank plate has been installed. Performed By: __________________________1_______ Auxiliary Operator Date 5.2.14 PROCEED to Section 5.3, "Water Transfer From T-81 to T-90 Loads," as directed by the SRO.

PALISADES NUCLEAR PLANT Proc No RWSO*1 SPECIAL OPERATING PROCEDURE Revision 7 Page 5 of8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T -90 LOADS 5.3 WATER TRANSFER FROM T-81 TO T-90 LOADS 5.3.1 OPEN MV-DMW505, Makeup Water Storage Tk Ht Exch E-65 Vent. 5.3.2 PLACE Caution Tag on MV-DMW505 stating, "RV-5203 is defeated, do not close." 5.3.3 UNLOCK AND CLOSE MV-DMW706, T-90 valve. (Located in T-90 valve pit.) Pe~ormedBy: ~__~~__________________I__~___ Auxiliary Operator Date Verified By: ______--,,_______________--.:..1_______ Auxiliary Operator Date 5.3.4 CLOSE the following valves: MV-DMW710, PMW Pump P-90A Discharge MV-DMW711, PMW Pump P-90B Discharge 5.3.5 ENSLIRE at least one primary makeup water filter aligned for operation by ENSURING OPEN the inlet and outlet valves for the filter: VALVE F-61A F-6.1'1B: ,,"c".;*,:..,.c.' Inlet MV-DMW718 MV-DMW720 Outlet MV-DMW717 MV-DMW719 5.3.6 OPEN MV-DMW716, E-65 Bypass. 5.3.7 To initiate water transfer from T-81 to T-90 loads, OPEN the following valves: MV-DMW712 Spool Piece, RSP-DMW5200 Isolation MV-DMW713 Spool Piece, RSP-DMW5200 Isolation 5.3.8 WHEN T-81 water is no longer necessary to supply T-90 loads, THEN CLOSE the following valves: MV-DMW712 Spool Piece, RSP-DMW5200 Isolation MV-DMW713 Spool Piece, RSP-DMW5200 Isolation 5.3.9 CLOSE MV-DMW716, E-65 Bypass.

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page 6 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T-90 LOADS 5.3.10 OBTAIN SRO authorization to remove blank plate and install RO-5201 A. Authorized By: _____-----------.-:.'--=---:- SRO Da~

a.

REMOVE Caution Tag from blank plate.

b.

REMOVE blank plate AND INSTALL RO-5201A. PerrormedBy: _______________~,_~___ Mechanical Maintenance Date Verified By: _______________~,_~--:-- Auxiliary Operator Date C. NOTIFY SRO that RO-5201A is installed. PerrormedBy:~~~___~_________'_~~ Auxiliary Operator Date 5.3.11 ENSURE CLOSED MV-DMW-565, T-90 drain. 5.3.12 OPEN AND LOCK, MV-DMW705, T-90 valve. PerrormedBy: ___~~~___________~,__~___ Auxiliary Operator Date Verified By: --:----:-:::--__=---:------------,---=---:- Auxiliary Operator Date 5.3.13 ENSURE OPEN the following valves: MV-DMW708, PMW Pump P-90A Suction MV-DMW709, PMW Pump P-90B Suction 5.3.14 OPEN the following valves: MV-DMW710, PMW Pump P-90A Discharge MV-DMW711, PMW Pump P-90B Discharge 5.3.15 ENSURE CLOSED MV-DMW-564, T-90 drain.

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page 7 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T -90 LOADS NOTE: Opening MV-DMW706 restores RV5203 back into service. 5.3.16 OPEN AND LOCK, MV-DMW706, T-90 valve. PenormedBy: __~~~__________________I__~___ Auxiliary Operator Date Verified By: I ~~~-=--~----------------~~ Auxiliary Operator Date 5.3.17 CLOSE MV-DMW505, Makeup Water Storage Tk Ht Exch E-65 Vent, AND REMOVE Caution Tag. 5.3.18 PROCEED to Section 5.4, "Restoration," when directed by the SRO. 5.4 RESTORATION 5.4.1 Align E65 Ht Hx as follows:

a.

OPEN MV-DMW714, E-65 Outlet.

b.

OPEN IVIV-DMW715, E-65 Inlet.

c.

IF required to support system operation, THEN OPEN MV-EHS110, E-65 Steam Supply.

d.

REMOVE CAUTION TAG from the following breakers: 52-7937, P-90A 52-8037, P-90B

e.

CLOSE the following breakers: 52-7937, P-90A 52-8037, P-90B

f.

START P-90A OR P-90B as directed by SRO.

PALISADES NUCLEAR PLANT Proc No RWSO-1 SPECIAL OPERATING PROCEDURE Revision 7 Page 8 of 8 TITLE: TRANSFER OF WATER FROM PRIMARY MAKEUP STORAGE TANK (T-81) FOR T -90 LOADS 6.0 ACCEPTANCE CRITERIA 6.1 GENERAL 6.1.1 Desired amount of water transferred from T -81 for T -90 Loads. 7.0 ATTACHMENTS AND RECORDS 7.1 ATTACHMENTS None 7.2 RECORDS Working copies of this procedure may be destroyed upon completion and SRO review. 8.0 SPECIAL REVIEWS 8.1 The scope of this procedure does include activities that require a 50.59 review per NMC Fleet Procedure FP-G-DOC-04, "Procedure Processing." Therefore, changes to this procedure require a 50.59 review. 8.2 This procedure implements a Temporary Modification. Technical changes to this procedure that affect this Temporary Modification require the generation or revision of Temporary Modification documentation per NMC Fleet Procedure FP-E-MOD-03, "Temporary Modifications."

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