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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] |
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p uo og[9 UNITED STATES 4'
[ g NUCLEAR REGULATORY COMMISSION g
5 REGloN I
'o 8 475 ALLENDALE ROAD Y 8 KING oF PRUSSIA. PENNSYLVANIA 19406-1415 4, . . . . . ,o August 5, 1999 MEMORANDUM TO: PUBLIC FROM: Richard J. Conte, Chief Human Performance and d Emergency Preparedness Branch Division of Reactor Safety
SUBJECT:
HOPE CREEK APPEAL QUESTIONS The purpose of this memorandum is to docket in the PDR the licensee's technical response on facility design and operation for NRC staff questions related to individual operator . l exam appeals. Facility representatives indicated that there was no proprietary information in the attached, in accordance with 10 CFR 2.790. l
Attachment:
Licensee Response to Appeal Questions Docket No. 50-354 l
\/l 9908120043 990005 PDR ADOCK 05000354 /Y
^p' I y PDR //
~120007
F s ATTACHMENT LICENSEE RESPONSE TO APPEAL QUESTIONS To: Richard Conte - NRC Branch Chief i From: Harlan D. Hanson Jr. - Operations Superintendent
Subject:
Response to Request for Information on 1998 NRC License Exam Date: 07/08/99 The following is provided at your request regarding the 1998 License Examination if any of this information is unclear or stimulates further questions, please l feel free to contact me at 809-339-3005 at your convenience. Thank you for your help and support in resolving this matter.
-(1) SRO #22/RO # 23 Lesson plan 0301-000.00H-000027-16 Core Spray Objective 12.b. states: ,
"Given a labeled diagram / drawing of the Core Spray System controls / indication bezel, IAW the Core Spray Lesson Plan: '
- b. Assess plant conditions that will cause indicators to light or extinguish."
Page 23 of 53 of the lesson plan, paragraph 3.b. . states:
" the following white lights are provided on panel 10C618: One CSS Loop B high flow light, which illuminates when CSS Loop B flow exceeds the minimum flow valve closure setpoint of 775 gpm."
A drawing of the panel was not provided since the specific light was described in the question stem.
The CSS has a light that senses the "high flow" function, but this light is physically labeled as " Min Flow Bypass" on panels 10C617 and 10C618. The labels appear new (not yellowed with age as the others on the panel). The fact that the labels appear new was only identified several days prior to the administration of the written exam during a final readiness walk-down of the in-plant JPM's but after the exam had been delivered to the NRC. The Exam review team discussed this discrepancy between the Lesson Plan, the written exam and the actual plant configuration. Since the students were trained and had studied from the lesson plan and the description in the question stem supported the lesson plan A decision was made to leave the question 'as-is' based on the lesson plan.
There is only one flow related actuation signal in each Core Spray Subsystem that operates the loop min flow valve. The student should be capable of screening out distractors A & C based on the flow setpoint alone. Since distractors A&C would be screened out, this would also eliminate any confusion between the A & B Core Spray Loops. The remaining choices were related to B Core Spray Loop only.
This would leave a choice between answers B and D. Since the light was described as the "HIGH FLOW' light, the student should have been able to deduce that the light would come on with the condition indicated.
1 I
y I
2 The conditions of the stem have reactor pressure above the shutoff head of the Core Spray pumps.
The student should be able to recognize that the Core Spray loops would be in a low flow condition requiring the Min-Flow valves to be open. Since the loop flow would be below the HIGH FLOW'setpoint of 775 gpm, a high flow condition would not exist and the light in question would be extinguished. Based on the above, answer D is the only correct answer.
(3) SRO#72/RO#98 Based on system design, if the common air supply to the Fuel pool gate (s) catastrophically fails, check valves in the individual seal air supply tubing would prevent the other seals from deflating. See drawing M-53-1 sheet 2. For gate seal physical layout, HC.MD-FR.KE-0018(Q) page 14 of 15.
Likewise, if the common air supply was isolated and one gate seal had an air leak, then the remaining 3 seals would still remain inflated.
The question stem describes only one component failure. All other equipment is assumed to be working as designed.
Hope Creek station did experience a drain-down event from the closure of the V7068 valve as described in incident Report 94-082. However, this event was compounded by a pre-existing leak on at least one date seal, mis-operation of the seal isolation valves, and the apparent leak-through of the remaining check-valves.
Other considerations:
Normal water level in the Fuel Pool is 40 feet (25 feet above the top of active fuel in the fuel racks). The low level alarm setpoint is 3 inches below normal level. There are still 21 inches of water remaining above the Technical Specification minimum level of 23 feet when the FUEL POOL Hl/LO Level alarm annunciates.
(3) SROf86/RO#79 The question was intended for the student to recognize that a train isolation (manual or automatic) had taken place and that at least one of the train isolation valves had not reached the full closed position
. within the allowed 15 seconds. The close push button had not been (and does not need to be) pressed.
The push button was backlit blinking green.
The green closed light flashes (valve failure to close on command) only when:
- 1) there is a " train close command" to the train valves; and,
- 2) any of the associated valves are not full closed after 15 seconds have elapsed.. .
1
r
] ..'c 3
The " train close command" may come from 3 sources.
- 1) Pushing the green CLOSE push button for the in-service recombiner train.
- 2) If the " train shutdown" signalis received while up.t.in REMOTE. the train shutdown signal originates from any of the following signals:
l High recombiner temp - 900F Feedgas cooler condenser Hi outlet temp - 200F ;
ManualTrip '
Recombiner heaters off .
, 3) All associated local panel valve CLOSE push buttons are pressed while the train is in REMOTE The green blinking light will stop flashing and stay on continuously when all. associated valves reach full closed position.
1 Answer B is incorrect because NOT FULL OPEN limit switches are used for the similar red OPEN I push button blinking back-light scheme. j Answer C is incorrect because high flow is not a direct recombiner isolation signal.
Answer D is incorrect because high hydrogen concentration is not a direct recombiner isolation signal. Also, at least one of the valves must not ao fully closed after 15 seconds for the light to blink. Tha green blinking light does not necessarily indicate an automatic isolation signal by itself.
Therefore, answer A is the only con'ect answer.
(4) 99 SRO The student should be able to derive answer A based on several statements (described below) in the question stem and.a fundamental knowledge of the bases for those steps leamed from Objectives 5 and 6 of Lesson Plan 0302-000127-11, as well as global Terminal Objective # 3.
- 1) The stem only refers to one' room
- 2) The stem states the source of the water is from the fire suppression system, not a primary system discharging into the area l
- 3) The question limits the response to those actions reauired by EOP-103. Although HPCI may have {
been damaged by the fire and the operating crew would be consulting the ECG (Event Classification Guide) for additional required reports, it is clear that if the stem is adhered to, only 1 correct answer exists.
Therefore A is the only correct answer.
LP 0302-000127-11
r:
,..s 4
TERMINAL LEARNING OBJECTIVES:
Provided a scenario or plant / system status or previous plant condition, the trainee will be able to:
1.0 - Perform actions required to implement HC.OP-EO.ZZ-0103, for Secondary Containment Control. (14) 2.0 Recognize the entry condition (s) of HC.OP-EO.ZZ-0103, Reactor Building Ccntrol and utilize the flowchart to control reactor building parameters. (1-6) 3.0 Derive an expected actuation or continuation of the event based on basic knowledge presented during previous training. The trainee's response shall be consistent with and contain the essential elements identified on an answer key.
(1-6)
ENABLING LEARNING OBJECTIVES:
R5. Define the term " Maximum Safe Floor Level".
R6. Given any step in the procedure, describe the reason for performance of that step and/or expected system response to control manipulations prescribed by the step.
EOP Required Knowledge generally includes:
- 1) EOP Entry conditions.
- 2) Definition of specific terms used in the EOP's.
- 3) Bases behind Notes and Cautions.
- 4) General strategy of each leg of the EOP's.
- 5) Specific Lesson Plan Objectives for each EOP Lesson Plan.
CC:
Don Jackson Bud Havens Steve Thompson I file u: