Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5171999-08-25025 August 1999
Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A4961999-08-23023 August 1999
Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys.
ML18107A4671999-07-29029 July 1999
Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4601999-07-23023 July 1999
Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4241999-07-0202 July 1999
Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR
ML18107A3811999-06-10010 June 1999
Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3601999-06-0404 June 1999
Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML18107A2131999-04-14014 April 1999
Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431
ML18106B1591999-03-31031 March 1999
Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
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Proposed Tech Specs Re CR Emergency Air Conditioning Sys
ML18106B0641999-02-0808 February 1999
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ML18106B0611999-02-0808 February 1999
Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions.
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Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel
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Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys
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Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
ML18106A9231998-10-12012 October 1998
Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03
ML18106A9181998-10-12012 October 1998
Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10
ML18106A8941998-09-29029 September 1998
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ML18106A8781998-09-17017 September 1998
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ML18106A8371998-08-12012 August 1998
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ML18106A4241998-03-26026 March 1998
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ML18106A4291998-03-26026 March 1998
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ML18106A3921998-03-13013 March 1998
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ML18106A2141997-12-15015 December 1997
Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1961997-12-11011 December 1997
Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4
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Proposed Tech Specs Re Administrative & Editorial Corrections
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Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown
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Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing
ML18102B6391997-10-29029 October 1997
Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6491997-10-24024 October 1997
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ML18102B6461997-10-24024 October 1997
Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
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1999-09-10
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18102B6681997-10-0101 October 1997
Rev 8 to Inservice Testing Manual for Pumps & Valves Program.
ML18106A8291997-09-0404 September 1997
Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl
ML18102A7941997-01-21021 January 1997
Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem
ML18102A7931997-01-21021 January 1997
Event Classification Guide,Technical Basis, Salem Generating Station
ML18102A6661996-11-19019 November 1996
Rev 2 to Pse&G Simulation Facility Certification Program.
ML20115B7791996-07-0303 July 1996
Final Draft, Hope Creek Event Classification Guide, Sections 1-9
ML18101B1141995-11-14014 November 1995
Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML18101A7711995-05-11011 May 1995
Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan.
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML18101A6751995-02-16016 February 1995
Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
ML18101A6761995-02-16016 February 1995
Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response.
ML18101A5381995-01-27027 January 1995
Revised Salem Generating Station Event Classification Guide.
ML18101A2111994-08-17017 August 1994
Revised Salem Event Classification Guide.
ML18101A6771994-07-11011 July 1994
Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination.
ML20147B1601994-04-23023 April 1994
Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A8081994-01-0707 January 1994
Rev 30 to Salem Generating Station Event Classification Guide.
ML20147B1491993-11-0202 November 1993
Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A4201993-06-15015 June 1993
Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures.
ML18100A3771993-05-0505 May 1993
Rev 27 to Salem Generating Station Event Classification Guide.
ML18100A3661993-04-27027 April 1993
Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6
ML20147B1171993-04-13013 April 1993
Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML18096B2911993-02-10010 February 1993
Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18
ML20147B1021993-01-21021 January 1993
Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process
ML20135B6521992-12-29029 December 1992
Rev 0 to Loss of Overhead Annunciator Sys
ML20147B1371992-12-22022 December 1992
Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML18096A9601992-08-28028 August 1992
Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan.
ML18100A3151992-07-28028 July 1992
Rev 1 to Process Computer Maint & Mod Control Program.
ML18096B3191992-07-17017 July 1992
Rev 8 to Salem Nuclear Generating Station Odcm.
ML20147B1691992-05-0707 May 1992
Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications
ML18096A6791992-04-30030 April 1992
Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan.
ML18096A4421992-01-15015 January 1992
Rev 17 to Salem Generating Station Event Classification Guide
ML18096A3211991-10-0404 October 1991
Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18096A1431991-06-28028 June 1991
Rev 12 to Salem Generating Station Event Classification Guide.
ML18095A9661991-05-30030 May 1991
Artificial Island Salem Event Classification Guide, Rev 11
ML18096A1191991-05-28028 May 1991
Rev 2 to NFU-0039, Salem Reactor Physics Methods.
ML18095A9391991-05-16016 May 1991
Revised Replacement Pages to Facility Inservice Testing Program
1999-09-10
[Table view] |
Text
QUALIFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SAO INITIAL LICENSE OPERATIONS QUALIFICATION GUIDE AND IMPLEMENTATION PLAN APPROVAL PAGE PROGRAM: INITIAL LICENSE iRAINING REACTOR OPERATOR OR SENIOR REACTOR OPERATOR MODULE: NIA TITLE: REACTIVITY MANIPULATIONS DOCUMENTATION GUIDE REVISION: 2 PREPARED BY: DATE: q/'1/0i2 REVIEWED BY: DATE: rJ07
.. APPROVED BY: DATE: qIL11 L91 I
~ !
APPROVED BY: DATE: ~/4*!2l:
IMPLEMENTATION PLAN:
A minimun1 of five signature.'~ n:quircd lo ma:t lhc conditions for your litense. Si;nificant control mampulation methods contained in the tables allow for t\llO repeat penonna~es of the same method. The initial .;onditionl!
- associated with lhc PERFORMANCE STANDARD shall be entered in the "fNITIAL CONDITION" block prior to performing the manipulation. and entered in the "FINAL CONDITION" block at completion.
TRG CHAIRPERSON: ____ t}j"- -" "*ul~. ._ _. . e=~"--~------- DATE:W91 r- C1808260t25- 980810 -
PDR ADOCK 05000272 V PDR
*. ***----------"----------------- PAGE 1OF6 REVISION 2
QUALIFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SRO INITIAL LICENSE SECTION I Gl!NeRAL NAMF.:
CARD REACTMTY MANIPULATIONS TITLE DOCUMENTATION GUIDE OBJECTIVE This Guide 19 utilized to document the 10CFR55.31 (1) (I) requi,....,... for *significant manipulations at the c:ont~ which statu in part "Provid* evtdenc* that th* applicant, a ii trainee, has succeafully manlpulatad the controls of the facility for which a llcenA i5 sought. At
- minimum, five significant control manipulation* muat be performed which affect reactivity or power level."
REFERENCES
\. NUREG~1021, EXAMINER STANDARDS Z. 10CFR55 J. IN 97-67 TASK I. COMPLETE REQUIREMENTS Of= 10CFR55.31 {a) {5)
PAGE2 OF 6 REVISION 2
QUALIFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SRO INITIAL LICENSE SICTION 11 KNOWU!DGI! Rl!QUIRl!MENTS A. PREREQUISITES COURSES/QUALIFICATIONS Significant control manipulations must be supervised by a licensed operator. To Obmin credit for a given manipulation, you must be "at the controls.* Art SRO in tn11n1ng is not qualified to supervise a 519nifieant control manipulation, therefore no credit for supervision can be given. Satisfactcry completion af the fallowing items is required prior to performing ANY significant control manipulations.
SATISFACTORY COMPLETION OF STARTUP CERTIFICATION AS DESCRIBED IN TP*302.
SUPERVISOR* LICENSED OATE OPERATOR TRAINING YOUR NAME MUST APPEAR ON THE "MANIPULATION OF FACILllY CONTROLS" LETTER ISSUED BY THE MANAGER OF SALEM OPERATIONS.
SUPERVISOR *LICENSED DATE OPERATOR TRAINING B. PRE-EVOLUTION BRIEF Prior to performing ANY significant control manipulation. a pre-evolution bnef shall occur. At a minimum, this brief will cover the following:
- 1. Intent of the evolUtlon to be performed.
- 2. Precautions. prerequisrtes and initial conc:titions applicable to the evolution.
- 3. Termination criteria applicable to the evolution.
- 4. Identification of the Licensed Operator in charge of the evolution.
- 5. Arly knowledge items (such as the importance of doubling, indications of POAH. control
- charactanstics of the main turbine fer time of core life) important to the evolution.
The Licensed Operator in charge of the evolution will maintain constant surveillance of the trainee during the evolution. and terminate the evolution if plant conditions warrant C. POST -EVOLUTION OE-BRIEF At the completion of the evofution. the Licensed Operator in charge will formally relieve the trainee of the watcn ensuring positive comrot of the reactor and plant.
PAGE 3 OF 6
QUALIFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SRO INITIAL LICENSE
. I .
Cl "' . c * .. \'
METHOD PCRFORMANCE DA TE INITIAL FINAL LICENSED
. ** * . STANDARD . __ CONDlllQN CONDITION OPERATOR Ri;At."TOR WITH TME REACTOR IN MOOE 2 STARTUP OR LESS, A REACTOR STAATUP TO GREATER THo\N 2"' POWER.
WITH THE REACTOR IN MOOE 2 OR LESS, ~ REM:TOR STARTUP TO GREATER TMAH ~ POWER Pl.ANT WITH THE TURBINE AT 1800 STARTUP RPM OR LESS, SYNCHRONIZE THE GENERATOR AND RAISE LOAD TO A ~INM. ELECTRICAL OUTPUT OF GREATER THAN 120 MWe WlTH THE TURBINE AT 1800 RPM OR LESS. SYNCl<<ONIZE THE GENERATOR AHO RAISE I.CAD TO A FINAL El.£CTFUCAl OUTPUT OF GREATER THAN 120 MWe WITH THE REACTOR AT GREATER THAN~ POWER.
SHUTDOWN THE REACTOR TO MODE3 WITH THE REACTOR AT
. : GREATER THAN 2" POWER.
St-4UTOOWN THE REACTOR TO Mooe3 : !
WITM TME GENERATOR AT GREATER THAN 80 MWe.
SHUTDOWN TU"!INI!-
GENERATOR TO OFF-LINE WITH 11-IE GENERATOR AT GREATER THAfil IO MWe.
SHUTDOWN TURBINE*
GENERATOR TO OFF-LINE REACTOR WITH ROO CONTROL IH DOWN- MAHUAL, A REACTOR POWER POWER REDUCTION OF 5% OR MANEUVER* GREATER US1NG CONTROL ROD CONmOL INSERTION ONlY.
ROOS WfTH:ROO CONTROLtN
~~;A REACTOR POWER REDUC'TION OF 5,., OR GRMTER USING CONTROi. ROD INSERTION ONLY.
R~CTOR REACTOR POWeR REDUCTION DOWN- OF 5""' OR GFllEATER U5'NG POWER CVCS SORATION CONTROi.
MANEWER- ONLY.
SOAATION REACTOR POWER REDUCT N OF 5% OR GREATER USING CVC$ BOAATION CONTR~
ONLV.
F'AGE 4 OF 6 REVISION 2
QUALIFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SRO INITIAL LICENSE Q .. ~ " * . ..
- METHOD PERFORMANCE DATE INITIAL * .FINAL . LICCNSED
. * .
- STANDA~D * . CONDITION CONDITION OPERATOR PLANT !)OWN. GENERATOR OUTPUT POWER REOUCT10N av 51Ka UTILIZING MANEUVER* RE~NCe TURBINE INCREASE/DECREASE OR T\JRBINE JMNUAL CONTROL GENERATOR OUTPUT REDUCTION BY 5'41 UTILIZING REFERENCE INCREASE/DECREASE OR TURllNE fMNUAL CONTROL REACTOR UP* wn'H ROO CONTROL IN POWER MAN.UAL. REACTOR POWER PMNEUVER* FUSE OF 5% OR GREATER CONTROL USING CONTROL ROD ROOS WITHDRAWAL Y.
WITH ROD CONTROL IN l'MNUAL. REACTOR POWER RISE OF 5titt OR GAEATER USING CONTROL ROD WITHDRAWAL ONLY.
REACTOR UP* REACTOR POWER RISE OF 5%
POWER OR GREATER U$NG eves MANEUVER~ OILUTION CONTROi. ONLY.
DILUTION REACTOR POWER RI E OF 5%
.: OR GREATER USING CVCS DILUTION CONTROL ONLY.
~ '
GENERATOR OUTPUT RISE OY 5'41 UTILIZING REFERENCE INCREASE/DECREASE OR TURBINE MANUAL CONTROL GENERATOR OUTPUT RISE BY 5"' UTIUZING REFERENCE INCREASE/CECREASE OR TURBINE MANUAL CONTROL FEEOWATER WITH AT LEAST ONE SIG IN CONTROL IN MANUAL CONTROL , MAINTAIN MANUAL REQUIRED SIG LEVEL DURING A DURING Pl.ANT STARTUP FROM MOOE 2 STARTUP TO GREATER TMNI Z'tft REACTOR POWER.
wrl]t_AT LEAST NE SIG IN MAfiil~ CONT'ROI.. MAINTAIN REQUIRED SIG LEVeL DURING A.
P\ANT STARTUP FROM MODE 2 TO GREATER TMAN 2%
REACTOR POWER.
PAGE 5 OF 6 REV1SION 2
. ' QUAUFICATION GUIDE SIGNIFICANT CONTROL MANIPULATIONS FOR RO/SRO INITIAL LICENSE
~a {~* . '., . .. ~~
. e . . .
M[THOD P[RP:ORMANC[ DATE INITIAL FINAL . LICEN$EO STANDARD CONDITION . *coNDiTlo'N . . OPERATOR rEEDWATER WITH AT LEAST ONE SIG IN CONTAOLIN MANUAL CONTROL , MAINTAIN w.NUAL REQUIRED SIG LEVE1. DURING A DURING Pl.AHT*SHUTDOWN FROM SHUTDOWN GREATER TliAN 2% REACTOR
WJTH AT LEAST ON! SIG IN MANUAL CONTROL , MAINTAIN REQUIRED SIG LEVEL DURING A Pl.ANT SHUTDOWN FROM GREATER THAN 2" REACTOR POW!" TO MOD! 3.
FEEOWATER WITHATLEASTOfifESIG IN CONTROL IN MANUAL CONTROL , MAINTAIN MANUAL REQUIRED SIG LEVEL DURING A DURING A PLANT COWN POWER PL>NTDOWN MANE\JVER OF 6% OR CREATER POWER MAN EWER WITH AT LEAST ONE SIG IN MANUAL CON'mOL , MAINTAIN REQUIREC SIG l.2WL OURING A Pl.ANT DOWN POWER MANEUVER OF 5% OR GREATER FEEDWATER WITH AT LEAST ONE SIG IN
.. CONTROi.. iN MANUAL CONTROL. , MAINTAIN MANUAL REQUIRED GIG LEVEL DURING A ~ :
CURING A PLANT UP POWER MANEWER Pl.ANT UP OF KOR GREATER POWER MANEWER WITH AT LEAST ONE SIG IN MANUAL CONTROL, MAINTAIN REQUIRED SIG LEVEL DURING A Pt.ANT UP POWER PAANEUVER OF 5% OR GAEATER
- ' NC. TQ-TP .ZZ-0302 ATTACHMENT 1 (Page 3 of 3)
- Operational Experience and Modifications
- Pre-License Audit Examination (prepared and conducted by trainers other than the instructors who taught the course and given at the end of the module.
The trainee will spend a minimum of 13 weeks on-shift comprised of a minimum of 520 hrs of the operating experience module as extra person on shift in training for that position. During this time, the trainee shall be under the direct supervision of on-shift licensed personnel. Additionally, each trainee will be responsible for completing Checkout Cards performance items and system checkouts as scheduled. Sc;heduling of checkouts by NTC instructors should have the concurrence of the SNSS and should not impact trainee involvement in plant operations. The remainder of this module, will be divided between the classroom and the simulator. Satisfactory progress must be maintained by the trainee as stated in section 4.5.
MODULE IV~ NRC Examination Preparation (Duration 4 Weeks)
Prerequisites
- 1. Completion of the appropriate Salem or Hope Creek NEO program.
Topics The audit examination results are to be analyzed to identify any individual or generic weaknesses. The NRC Examination Preparation Module addresses these weaknesses prior to the NRC Examination. The contents of this module will be developed by the Lead Instructor - Salem or Hope Creek Replacement License Training, as appropriate, and will be approved by the Training Supervisor - Salem or Hope Creek License Operator Training, as appropriate.
Plant management should evaluate each candidate regarding these problem areas. This evaluation shall occur prior to subm_ission of the NRC license applicatiorF(Form NRC-398). It should ensure that performance problems have been corrected, and it shall re-establish the need for the candidate to perform license duties at the plant. Documentation of all Post-Audit training should be maintained with the course record.
NUCLEAR COMMON Re*; 0
QUALIFI!.TION CHECKOUT CARD (!ntinnation)
Hope Creek Senior Reactor Operator Training Program Hope Creek SRO ILT Operating Experience Hope Creek SRO QCC Name:~~~~~~~~~~~~~~~~-
QCC: NOH04IPl'SROG Action Code WATCHSTANDING ITEMS Given the assignment, COMPLETE a minimum of 13 weeks or 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> (which ever P is longer) with a minimum of 6 weeks at greater than 20% reactor power as an extra person on shift in the training program for the senior reactor operator position.
From To Shift Avg Date Time Date~ Time* ; Hours Pwr*** Crew: Operations Superintendent I I I I I I I I I I I I I I I I I I I I I I I I I I I I . .
I I I I I I I I I I I I I I I I I I I I I I I I .. *.
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Total hours/weeks On-Shift:
s:\hc_ops\taskrnu\hopqcard.mdb Page 13 of IS R~vision :::
